ML20127M241

Insp Rept 50-285/85-11 on 850501-31.Violation Noted:Six Surveillance Tests Performed During Refueling Outage Ending in Jul 1984 Unaccounted for in Files,In Violation of Tech Spec 5.8.1

ML20127M241
Person / Time
Site:	Fort Calhoun
Issue date:	06/26/1985
From:	Harrell P, Martin L, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20127M213	List: ML20127M210 ML20127M224 ML20127M241
References
50-285-85-11, IEIN-84-06, IEIN-84-6, NUDOCS 8507010163
Download: ML20127M241 (11)

See also: IR 05000285/1985011

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection-Report: 50-285/85-11 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: May 1-31, 1985

Inspector: k andON

L. A. Yandell, Senior Resident Reactor Inspector,

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Fort Calhoun Station

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k4f. H5rrell, JCsident Reactor Inspector,

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Arkansas Nuclear One

Approved: [h h ~

L. E. Martin, S t1on Chief, Project Section A,

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Reactor Pro t Branch 2

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Inspection Summary

Inspection Conducted May 1-31, 1985 (50-285/85-11)

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Areas Inspected: _ Routine, unannounced inspection of. licensee's actions on

previous inspection findings, operational safety verification, surveillance

testing, surveillance program, maintenance activities,_ followup of

i IE Information Notices, and followup of LERs. The inspection involved 135

l' inspector-hours onsite by two NRC inspectors, of which 22 were offshift hours.

- Results

-Within the seven areas inspected, one violation was identified

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(failure to follow procedures paragraph 5).

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DETAILS

1. Persons Contacted

• R. L. Andrews, Division Manager, Nuclear Production

• • W. G. Gates, Manager, Fort Calhoun Station

• R. L. Jaworski, Section Manager, Technical Services

• T. J. McIvor, Manager, Technical Support

• J. K. Gasper, Manager, Administrative Services

• K. C. Hyde, Test Engineer

J. J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs

L. T. Kusek, Supervisor, Operations

M. R. Core, Supervisor, Maintenance

J. J. Fluehr, Supervisor, Station Training

C. J. Brunnert, Operations Supervisor, Quality Assurance (QA)

8. L. Saucier, Inspector, QA

L. H. Bnrcherding, Inspector, QA

• Denotes attendance at the May 17, 1985, exit interview.

• • Denotes attendance at the May 17 and June 10, 1985, exit interviews.

The NRC inspectors also talked with and interviewed other licensee

employees during the inspection. These employees included licensed and

unlicensed operators, craftsmen, engineers, and office personnel.

2. Licensee Action on Previous Inspection Findings

a. (Closed) Open Item 285/8217-01, " Housekeeping." The licensee failed

to include the controlled area of the plant in the Zone IV category.

The licensee has issued a revision to Administrative Procedure A-G-6,

" Housekeeping," to require that the controlled area of the plant be

kept in Zone IV. This item is considered closed.

b. (Closed) Open Item 285/8312-07, " Alternate Shutdown." The licensee

failed to list all valves required to be manipulated during alternate

shutdown operations. Emergency Operating Procedure (EOP) EP-24-A,

" Forced Evacuation of the Control Room Due to Fire," has been revised

to include HCV-2809A and HCV-28838 in the list of the valves to be ,

manipulated during cold shutdown. This item is considered closed.

c. (Closed) Open Item 285/8312-08, " Fuse Not Labeled." Repair

instructions for the raw water system provided in E0P EP-24-A,

require that the standby fuse in Switchgear 1A4, Unit 12 be pulled.

The licensee had not provided a label in Unit 12 to indicate which

was the standby fuse. The NRC inspector verified that the fuse has

been labeled and the label clearly indicates which is the stendby

fuse. This item is considered closed.

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d. (Closed) Open-Item 285/8312-09, " Incorrect Procedure." The licensee

issued E0P EP-24-A which incorrectly identified the conductors to be

jumpered for the repair of HCV-348. The licensee has issued a

revision to E0P EP-24-A to correctly identify the conductors to be

used. This item is considered closed.

e. (Closed) Open Item 8410-02, " Procedure Not Issued." The licensee had

failed to issue a procedure to implement 10 CFR Part 50, Appendix B,

Criterion XVI, Corrective Action. The licensee has issued Quality

Assurance Department Procedure, QADP-17, " Control of Deficiencies and

Corrective Action," to implement criterion XVI of Appendix B. The

NRC inspector reviewed the procedure and it appears that the

procedure effectively implements the requirements for corrective

action. This item is considered closed.

3. Operational Safety Verification

The NRC inspector performed activities as described below to ascertain

that the facility is being maintained in conformance with regulatory

requirements and that the licensee's management control system is

effectively discharging its responsibilities during power operation,

a. The NRC inspector made several control room observations to verify

proper shift manning, operator adherence to approved procedures,

adherence to selected Technical Specifications, and operability of

the reactor protective system and engineered safeguards equipment.

Selected logs, records, recorder traces, annunciators, panel

indications, and switch positions were reviewed to verify compliance

with regulatory requirements. The licensee's equipment control was

reviewed for proper implementation by reviewing maintenance order

status and the tag-out log, and by verifying selected safety-related

tag-outs. The NRC inspector observed several shift turnovers,

b. The NRC inspector toured the plant at various times to assess plant

and equipment conditions. The following items were observed during

these tours:

. general plant conditions

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vital area barriers not degraded or appropriately manned by

security personnel

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adherence to requirements of radiation work permits (RWPs)

. proper use of protective clothing and respirators

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plant housekeeping and cleanliness practices including fire

hazards and the control of combustible material

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work activities being performed in accordance with approved

activities

. physical security

. HP instrumentation is operable and calibrated

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c. The NRC inspector verified operability of the following

safety-related systems by performing a walkdown and switch

verification of the accessible portions of the system:

. High Pressure Safety Injection System per Checklist SI-1-CL-A

. Low Pressure Safety Injection System per Checklist SI-1-CL-B

. "A" and "B" Monitor Tank secured lineup per checklist contained

in Operating Procedure 01-WDL-3, Steps IV. A.18 and IV.B.18

. Plant Electrical Distribution per Checklists EE-1-CL-A and

EE-2-CL-A

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Nos. 1 and 2 Diesel Generator - Starting Air Systems per

Checklists DG-1-CL-A and DG-2-CL-A

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Nos.1 and 2 Diesel Generator - Fuel Oil System per

Checklists DG-1-CL-8 and DG-2-CL-B

d. The NRC inspector observed portions of Containment Purge 85023,

reviewed the discharge permit, and noted the following:

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the X/Q log was maintained, the readings were within limits, and

the shift supervisor review was performed

. the limiting X/Q was established ,

. VIAS was tested using RM 061

. the stack dewpoint and annubar readings were taken

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the tritium sampler was in place and the sample was taken

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the recommended release rate was established, and the actual

flow was lower than that authorized

. radioactivity analyses were performed

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the required effluent monitors and recorders were operational

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the required auxiliary building exhaust fans were operating

. OI-VA-1.Section IV.G was attached to the permit

. the initial reading of the stack flow integrator was noted on

the recorders

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the operations checklist to CMP 4.5 was complete and signed off

by the shift supervisor

. the permit was reviewed and signed off properly, and the

termination time was established

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e. The NRC inspector observed portions of Discharge Permit 85060 for "B"

Monitor Tank. The NRC inupector verified that a tank sample had been

taken and analyzed, that all radiological and chemical discharge

limits were satisfied in the discharge tunnel, that the operations

checklist was completed and signed off, that the maximum release rate

was established, and that the shift supervisor had signed off the

permit. The NRC inspector observed the discharge being secured from

AI-100 in the Auxiliary Building.

f. The NRC inspector attended the entrance and exit interviews of

licensee's Safety Audit and Review Committee (SARC) Audit No. 2-85

conducted the week of May 6th. This audit was conducted to

" determine whether commitments to the NRC and/or appropriate

corrective action to various problems are executed in a timely and

effective manner." It was noted that plant QA auditors were utilized

to address a substantial portion of the approved audit checklist.

The NRC inspector reviewed the checklist, observed the auditors

during the inspection, and discussed their observations with regard

to specific LERs, Operations Incidents Reports, and NRC inspection

reports.

No violations or deviations were identified.

4. Surveillance Testing

The NRC inspector witnessed portions of the following surveillance tests:

. ST-RM-1, F.2 (Monthly) Area Monitor Checks

. ST-RM-2, F.2 (Monthly) Process Monitor Checks

. ST-ISI-SI-1, F.1 (Quarterly) Safety Injection Valves Inservice

Testing

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ST-ISI-CVCS-3, F.1 (Quarterly) Chemical and Volume Control System

Pump Test

. ST-RPS-1, F.3 (Monthly) Power Range Safety Channels Test

. ST-CEA-1, F.4 (81-Weekly) Control Element Assembly Check

. ST-ESF-5, F.1 (Monthly) Automatic Load Sequencer Check

In the above surveillance tests, the NRC inspector verified where

applicable that:

. testing was scheduled in accordance with Technical Specification

requirements

. procedures were being followed

. calibrated test equipment was being used

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. qualified personnel were performing the tests

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limiting conditions for operation were being met

. test data were being accurately recorded

No violations or deviations were identified.

5. Surveillance Program

The NRC inspector reviewed the surveillance program to verify the program

is being conducted in accordance with approved procedures as required by

the Technical Specifications, inservice inspcction program for pumps and

valves, and the approved fire protection /p r eention program.

The review included the following verifications:

. .A' selected sample of surveillances required by the Technical

Specifications are being performed in accordance with properly

approved procedures.

. Surveillance tests for pumps and valves identified in the licensee's

approved inservice inspection (ISI) program are being performed in

accordance with approved procedures.

. The procedures used to perform Technical Specification and ISI

activities are technically adequate and are written so they can be

understood and used by the technicians performing the surveillance.

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Surveillances are being performed at the frequency required by the

Technical Specifications-and the ISI program.

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New or revised surveillance procedures are being issued, when

required, in response to recently issued Technical Specification

amendments.

. Surveillance procedures are written in a format that provides

prerequisites, acceptance criteria, and instructions for returning

systems or components to service.

. Completed surveillance tests are being filed and retained in a

records system in accordance with requirements.

During performance of the above reviews, the NRC inspector noted that

there were discrepancies in one of the surveillance tests. The

discrepancies were of a minor editorial nature. The licensee was notified

of the discrepancies and agreed to correct the procedure.

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The NRC inspector' reviewed the surveillance records completed during the

last refueling outage which ended in-July 1984. During a review of the

test records, the NRC inspector noted that six surveillance tests were not

in the: files. Upon notification by the NRC inspector of the missing

tests, the licensee initiated a search for the missing tests. The results

( -- of the search revealed that three tests had been inadvertently filed with

). the completed monthly surveillances instead of the refueling outage

l surveillance tests. One of the tests had not been reviewed by the

l performing group's supervisor, and two completed tests could not be

l located. The failure to account for completed surveillance tests in the

files is an apparent violation. (285/8511-01)

Based on the review of past NRC inspection reports and discussions with

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NRC personnel, the maintenance of all types of QA records has been a

j continuing problem for the licensee.

No other violations or deviations were identified.

6. Maintenance Activities

The NRC inspector witnessed portions of the work performed on the

following maintenance items:

a. Safety-Related Design Change Order (SRDCO) 85-7/MR-FC-84-29, "RPS

Dual Potentiometer Upgrade." The licensee experienced the failure of

three dual potentiometer modules as reported in LERs 83-05, 83-06,

and 83-07. An investigation was performed to determine the cause of

the failure (see NRC Inspection Report 50-285/84-04, paragraph 6.e) and

the ifcensee decided to replace all 36 modules in the reactor

protective system. The NRC inspector reviewed the work package and

noted the following:

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The Pre-Installation Modification Control Sheet (Form H) was

filled out properly, purchase order information was present, and

PRC approvals were obtained.

. The Engineering Evaluation and Assistance Request (Form A) was

completed and contained appropriate approval signatures.

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The Safety Evaluation (FC-154) was filled out and approved.

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The SRDC0 was filled out and approved by QA, Quality Control

(QC), and the plant manager.

. The PRC approved work procedure contained signed off

prerequisites, QC hold points, materials identification

information, applicable Technical Specification requirements,

and the approved drawing list.

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On separate occasions the NRC inspector observed the work performed

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on Channels A and C, verified that procedure signoffs were current,

and confirmed that appropriate jumper log entries were made. The NRC

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inspector observed portions of Calibration Procedure CP-A/APD after

work was complete on Channel A and Surveillance Test ST-RPS-12, F.2

to verify operability,

b. Maintenance Order (MO) 851270, " Charging Pump CH-1C." A packing leak

on the charging pump was identified by the operator who prepared the

M0. The NRC inspector verified that the M0 was properly signed off,

that Tag-Out 85-358 was assigned, and that the applicable Technical

Specification was referenced. The pump was repacked in accordance

with MP-CH-1, " Inspection and Repair of Charging Pumps." The NRC

inspector reviewed the work procedure and verified that initial

conditions were signed off, that RWP 125 was assigned to cover this

work, and that QC hold points were observed. Qualified craftsmen

were assigned to the task and the NRC inspector noted that purchasing

information was identified on the M0. Following repairs, the NRC

inspector observed performance of Surveillance Test ST-ISI-CVCS-3,

F.1, "CVCS Pump Test," to verify operability and noted that the MO

was signed off, the tags cleared, and the pump returned to service.

c. MO 851135, "No. 2 Diesel Generator." During performance of a

surveillance test the licensee determined that the voltage regulator

could not provide sufficient control to maintain the power factor

within operating limits. An approved PRC procedure was prepared to

cover this work and the NRC inspector noted that the shift supervisor

signoff was present, that procedure steps were signed off, and that

the safety analysis (FC-154) was completed and attached. Procedure

Change 1477u was processed and incorporated properly. The NRC

inspector observed the work in progress and verified that tags were

properly hung, that qualified craftsmen were assigned to the task and

that they exhibited safe work practices.

d. MO 851641, " Nuclear Instrumentation (NI)." The SIGMA meter

providing temperature indication on the NI detector well cooling

channel was in alarm. The MO was written to " calibrate or repair as

needed." The NRC inspector reviewed the M0 for proper approvals and

signoffs. Calibration Procedure CP-734A, " Nuclear Detector Well

Cooling Temperature," was performed and it was determined that the

meter movement was inoperable. The NRC inspector observed the

troubleshooting, installation of jumpers, and removal of the

instrument for repair. The NRC inspector reviewed the jumper log for

proper entries and verified that the tags were cleared correctly

after the instrument was reinstalled.

e. H0 851061, " Sampling System; PCV-2560." Valve PCV-2560 in the

Post-Accident Sampling System was not providing proper control and

repairs were initiated. It was determined that new internals were

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required. The NRC inspector observed the work being performed and

noted that qualified craftsmen were assigned to the task, that

current technical manual information was present at the jobsite,

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that. isolation tags were properly hung, and that appropriate HP

precautions were observed. The NRC inspector reviewed the M0 for

completeness and proper approvals.

No violations or deviations were identified.

7. Followup of IE Information Notices

The NRC inspector reviewed the licensee's program to handle IE Information

Notices. This review included verification that the notices issued in

1984 were received by the licensee, entered into their licensing tracking

system, and distributed to appropriate personnel for review.

The NRC inspector reviewed the licensee's actions taken in response to IE

'Information Notice 84-06, " Steam Binding of Auxiliary Feedwater Pumps,"

issued on January 25, 1984. This issue was reviewed in more detail in

response to a request from the NRC Office of Inspection and Enforcement.

The NRC inspector determined that the licensee actions were as follows:

. The auxiliary feedwater (AFW) piping is monitored once per shift by

touching the pipe. A permanent local temperature indicating device

is scheduled for installation during the 1985 outage.

. AFW operating and surveillance procedures were reviewed but revisions

were not required with regard to check valve leakage because the

auxiliary feedwater piping and check valves are not placed inservice

dwing testing or normal operation of the pump except for the

refueling outage tests.

. Procedure 01-AFW-2, " Auxiliary Feedwater System Operation - Special

Procedures," was revised to provide guidance on detecting and

correcting AFW pump steam binding.

. The licensee is performing periodic leakage tests of the AFW check

valves and periodic inspections of the AFW discharge isolation

valves.

No violations or deviations were identified.

. 8. , Followup of Licensee Event Reports (LERs)

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i LERs83-005, 83-006, and 83-007, " Failed RPS Dual Potentiometer Modules."

l This item was discussed in NRC Inspection Report 50-285/84-04 and remained

l open pending replacement of these modules by the licensee. Based on

l reconinendations contained in Combustion Engineering Letter CE-18074-1528

dated January 26, 1984, the licensee elected to replace all Bell & Howell

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Model 3846 12-01 modules with upgraded Bell & Howell Model 20-320. Work-

Order 908 was issued to cover procurement of 60 potentiometers and this

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work was completed this reporting period under SRDC0 85-7/MR-FC-84-29.

L The corrective actions taken by the licensee appeared to be adequate.

9. Exit Interview

The NRC inspector met with licensee representatives on May 17 and

June 10, 1985, to summarize the scope and findings of the inspection.

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