ML20209C537

Insp Rept 50-285/86-21 on 860701-31.Violations Noted: Failure to Rept Nonfunctional Fire Barrier & Failure to Properly Store Critical Quality Element Matl

ML20209C537
Person / Time
Site:	Fort Calhoun
Issue date:	08/21/1986
From:	Harrell P, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20209C519	List: ML20209C515 ML20209C532 ML20209C537
References
50-285-86-21, NUDOCS 8609090046
Download: ML20209C537 (6)

See also: IR 05000285/1986021

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APPENDIX B

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/86-21 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

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Inspection Conducted: July 1-31, 1986

Inspector:

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Wnior Resid@ntMFeactor Date'

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ector

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' Approved: /[]d, d -A - ff Z/ 8d

D.7<. Hunter, Chief,' Project Section B

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Dat'e

Reactor Projects Branch

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, Inspection Summary

Inspection Con' ducted July 1-31,~1986 (Report 50-285/86-21)

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Areas' Inspected: Routine, unannounced inspection including operational safety

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

walkdowns, security observations, and followup on a previously identified item.

Results: Within the seven areas inspected, two violations (failure to report a

nonfunctional fire barrier, paragraph 4, and failure to properly store CQE

material, paragraph 4) were identified.

8609090046 860902

PDR ADOCK 05000285

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DETAILS

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1. Persons Contacted

• W. Gates, Plant Manager

- C. Brunnert, Operations Quality Assurance Supervisor

M. Core, Maintenance Supervisor

D. Dale, Quality Control Inspector

• J. Flechr, Station Training Supervisor

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

• J. Gasper, Administrative Services Manager

• J. Gass, Training Supervisor

, M. Kallman, Security Supervisor

L. Kusek, Operations Supervisor

• T. McIvor, Technical Supervisor

• R. Mueller, Plant Engineer

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 a Previously Identified Item

(Closed) Open Item 8602-04: Issuance of revised Table 1 for the

Electrical Equipment Qualification Manual (EEQM)

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The licensee has issued a revision to the EEQM to provide a new Table 1.

Table 1 now includes the values of the uncertainties for.the plant

instrumentation loops.

7 3. Operation'al Safety Verification

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The NRC inspector conducted reviews and observations of selected

g activities to verify tha't facility operations were performed in

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conformance with the requirements established under 10 CFR, administrative

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procedures, and the TS. The NRC. inspector made several control room

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l. observations to verify:

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. Proper shift staffing

. . Operator adherence to approved procedures and TS requirements

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. Operability of' reactor protective system and engineered safeguards

equipment

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

switch positions complied with the appropriate requirements

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Proper return to serv'ce of components

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. " Maintenhnce orders (MO) initiated for equipment in need of

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• maintenance

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. ApprOpYIsle Cuisdust of t uiitrol s'ousu drid ulher licensed operators

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No violations or deviations were noted.

4. 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

. Adherence to the reauirements of radiation work permits

. Work activities performance in accordance with approved procedures

During a plant tour, the NRC inspector noted that extraneous material was

piled on top of the paper sacks containing boric acid. The extraneous

material consisted of piping, tools, and rags. The sacks of boric acid

are used by the licensee for boration of the reactor coolout system.

The licensee purchased and maintained the boric acid as CQE material.

Criterion XIII of Appendix B to 10 CFR Part 50 and Section 7.3, " Storage,

Shipping, and Handling," of the licensee's QAP require that CQE material

be stored such that da.nage or deterioration will be prevented. The

i licensee has established a program to erect temporary CQE storage areas

for CQE material whenever the material is stored inside the plant. The

licensee failed to store the boric acid in a temporary CQE area, thus

providing the potential for damage or deterioration to the acid. The

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failure to properly control the storage of CQE material in the plant is an

apparent violation. (285/8621-01)

Upon notification by the NRC inspector, the licensee evaluated the boric

acid and determined that no deterioration or damage had occurred. The

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licensee established a temporary CQE area for the boric acid and has

maintained the area for boric acid storage since notification of the

problem by the NRC inspector.

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r During-a plant tour, the NRC inspector also noted that a portion of the

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fire barrier between the upper and lower electrical penetration rooms had

not been; functional.(intact) fer seme time. The licensee is currently in

the-process of installing a stairway between these two areas. During this

period of construction, the fire barrier has been breached by a hole

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approximately 8 feet by 10 feet. The NRC inspector reviewed past station

logs.and noted that the fire barrier has no'. been functional since

approximat'ely May 15, 1986. The review also indicated that the licensee

verified the operability of the fire detectors in the upper electrical ,

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penetration: room and established an hourly fire patrol. The fire patrol

- has been m'aintained since the barrier was nonfunctional. The NRC

'in'spector' requested the licensee provide a copy of the report the licensee

i sent to the NRC notifying the NRC of a fire barrier being nonfunctional

l for.an' extended period of time. The licensee. informed the NRC inspector

,. that a report had not been sent.

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TS 2.19(7), requires that a nonfunctional fire barrier be restored withing

,7 days or a-written report be prepared and submitted to the NRC within an

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additional,30 days. The licensee did not prepare or submit a letter to

the NRC within.the required timeframe. This is an apparent violation.

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(285/8621-02)

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! , When it was verified that a report had not been submitted, the licensee-

immediately completed and transmitted the report to the NRC.

5. Security Observations

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l The NRC inspector verified the physical 'ecurity s plan was-being

implemented by selected observation of the following items

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j . The security organization is properly manned.

j . Personnel within the protected area (PA) display their identification

i badges. .

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. Vehicles are properly authorized, searched, and escorted or

controlled within the PA.

. Persons and packages are properly cleared and checked before entry

l into the PA is permitted.

(- . The effectiveness of the security program is maintained when security

! equipment failure or impairment requires compensatory measures to be

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employed.

No violations or deviations were identified.

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6. Safety-Related System Walkdowns

j The NRC inspector walked down accessible portions af the following

safety-related systems to verify system operability. Operability was

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determined by verification of selected valve and switch positions. The

systems were walked down using the drawings and procedures noted in

parenthesis.

. Main steam system (Drawing M-252, Revision 40 and Procedure OI-MS-2,

Revision 14)

. Main feedwater system (Drawing M-253, Revision 51 and

Procedure OI-FW-2, Revision 15)

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

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

conditions for the selected areas checked. None of the conditions noted

affected the oper6bility or safe operation of the systems. Licensee

personnel stated that the noted minor discrepancies would be corrected.

No violations or deviations were identified.

7. Monthly Maintenance Observation

The NRC inspector reviewed and/or observed selected station maintenance

activities on safety-related systems and components to verify the

maintenance was conducted in accordance with approved procedures,

regulatory requirements, and the TS. The following items were considered

during the reviews and/or observations:

. The TS 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 M0s and were inspected,

as applicable.

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. Functional testing and/or calibrations were performed prior to

returning components or systems to service.

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. . Quality control records were maintained.

. Activities were accomplished by qualified personnel.

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! . Parts and materials used were properly certified.

. Radiological and fire prevention controls were implemented.

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. The NRC inspector reviewed and/or observed the following maintenance

activitids:'

. Troubleshooting transformer for security systems power supply

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(M0 862447)

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. Inspection and installation of cable tray covers (M0 862038)

No violations or deviations were noted.

8. Monthly Surveillance Observation

The NRC inspector observed selected portions of the performance of and/or

reviewed completed docume.itation for the TS required surveillance testing

on safety-related systems and components. The NRC inspector verified the

following items during the testing:

. Testing was performed by qualified persannel using approved

procedures.

. Test instrumentation was calibrated.

. The TS limiting conditions for operation were met.

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

accomplished.

. Test results conformed with TS and procedure requirements.

. -Test results were reviewed by personnel other than the individual '

. directing the test.

. Deficiencies identified during'the testing were properly reviewed and

resolved by appropriate management personnel.

The NRC inspector observed and/or reviewed the documentation for the

.following surveillance test activities. The procedures used for the test

- activities dre noted in parenthesis.

Monthly auxiliary' feedwater pump check (ST-FW-1-F.2)

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

No violations or deviations were identified.

9. Exit Interview

TheNRCinspec$ormetwith'Mr.W.G. Gates (PlantManager)andother

members of the'0 PPD staff at the end of this inspection. At this meeting,

the NRC inspector summarized the scope of the inspection and the findings.