ML19323E927

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IE Insp Rept 50-285/80-07 on 800324-27.No Noncompliance Noted.Major Areas Inspected:Response to Open & Unresolved Items,Lers,Responses to IE Bulletins & Review of Turbine Insp
ML19323E927
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/04/1980
From: Kelly D, Rich Smith, Westerman T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML19323E923 List:
References
50-285-80-07, 50-285-80-7, NUDOCS 8005270413
Download: ML19323E927 (5)


See also: IR 05000285/1980007

Text

1

O

U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION IV

Report No. 50-285/80-07

Docket No. 50-285

License No. DPR-40

Licensee: Omaha Public Power District

1623 Harney Street

Omaha, Nebraska

68102

Facility Name: Fort Calhoun Station - Unit 1

Inspection At: Fort Calhoun Station, Blair, Nebraska

Inspection Conducted: March 24-27, 1980

Inspectors:

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T. F. Westerman, Chief, Reactor Projects

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Section

Inspection Summary

Inspection on March 24-27, 1980 (Report No. 50-285/80-07)

Areas Inspected:

Routine, unannounced inspection of the licensee's (1) Response

to Open and Unresolved Items; (2) Licensee Event Reports; (3) Response to

Inspection and Enforcement Bulletins; (4) progress on NUREG-0578; and (5) Review

of the licensee's Turbine inspection. The inspection consisted of fifty-two

(52) inspector hours onsite by two (2) NRC inspectors.

Results: Of the five (5) areas inspected, no items of noncompliance or

deviations were identified.

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DETAILS

1.

Persons Contacted

  • S. C. Stevens, Manager, Ft. Calhoun Station
  • W. G. Gates, Supervisor, Operations

J. F. Gass, Training Coordinator

J. J. Fisicaro, Supervisor, Administrative Services

G. Fleischman, QA Engineer

F. F. Franco, Supervisor, Chemistry and Health Physics

G. R. Peterson, Supervisor, Maintenance

J. L. Connolley, Supervisor, Instrumentation and Control and

Electric Field Maintenance

  • Denotes those attending exit interview.

The inspectors also talked with and interviewed other licensee employees

during the inspection. These included reactor operators and office

personnel.

2.

Inspection and Enforcement Bulletin Follow-up

The inspector reviewed the licensee's response to the following

Inspection and Enforcement Bulletins to verify that:

The written response was within the time period specified

.

The written response included the information required

.

Adequate corrective action was specified

.

Information in the response was adequate

.

Corrective action was accomplished as specified

.

IE Bulletins reviewed:

IE Bulletin 79-23

IE Bulletin 79-24

IE Bulletin 79-25

IE Bulletin 79-26

IE-Bulletin 79-28

No items of noncompliance or deviations were identified.

.

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3.

Progress Review of NUREG-0578, Category A Items

The inspector reviewed the licensees progress in implementing the

Category A items of NUREG-0578.

Progress to date is satisfactory

and completion should be accomplished by the end of the present

refueling outage.

During the next inspection the inspector will

verify the implementation of the Category A items.

4.

Review of Licensee Event Reports (LER's)

Selected LER's were reviewed to verify that correct reporting requirements

were met, that proper corrective action was identified and taken, that

licensee administrative procedures were followed in evaluation and

review of the event, and to determine safety of continued operations.

The

LER's listed below were reviewed in the regional office and were further

reviewed and actions inspected on-site during this inspection.

'

LER No.

Subject

79-22

Failure of Engineered Safety Feature

Lockout Relay 86A/CRHS

80-01

Containment Cooling Fan Motor (VH-3B)

Circuit Breaker Trip

80-02

Containment Sump Safety Injection

Recirculation Valve HCV-383-4 Failure

80-03

No. 2 Diesel Generator Voltage Regulator

Reference Voltage Failure

80-04

Failure To Establish A Fire Watch In An

Area With A Degraded Fire Barrier

No items of noncompliance or deviations were identified.

5.

Follow-up on Open Items

(Closed) Open Item 285/268:

Licensee agreed to revise the administrative

procedures to require that two licensed operators be in the control

room at all times. This requirement is documented in Special Order

No. 29.

This item is closed.

(Closed) Open Item 285/264:

Clear definition of performance of the

surveillance test of the supervision monitoring circuitry for the fire

)

zone alarms listed in Technical Specification (Table 3.15) were not

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included in Surveillance Test Procedure ST-FD-1.

This procedure was revised

to include these items. This item is closed.

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(0 pen) 285/269:

Valve HCV-312 is listed in Technical Specification

Table 3-5, item 14, as HCV-372. Per the licensee, this is a typographical

,

A change to the technical specification will be processed

error.

to correct this error.

This item will remain open until this change

is processed.

(0 pen) 7908-01: The timeliness of drawing revision was discussed

with the licensee.

The inspector emphasized the need to make revised

drawings available to the power station as quickly as possible after

design changes or modifications are accomplished.

The licensee

acknowledged that the drawing revisions are taking longer to

accomplish than originally anticipated. There is a backlog of revisions

and a limited number of draftsmen available. The licensee indicated

that solutions to the problem are being sought.

This item will remain

open pending review of the revised drawing for the above listed design

changes / modifications and until the inspector can ascertain that the pro-

blem area of drawing revisions for Fort Calhoun Station has been

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resolved.

A review of this activity was conducted during this

inspection and action identified in this item has not been completed.

This item will remain open.

6.

Follow-up on Unresolved Item

(Closed) 7911-201: Appendix X, Section F of the Site Emergency Plan

" Fort Calhoun Station Fire Bill" stated in part that the fire fusible

links in the diesel generator rooms are rated at 500 F.

The

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SER states these sgrinkler system fusible links will be replaced by

links rated at 250 F or less. The Fort Calhoun Station Fire Bill has

been revised to state that the fusible links in the diesel generator

room are rated at 212 F.

Also, the licensee has installed 212 F fusible

links in the Diesel Rooms. This unresolved item is considered closed.

7.

Turbine Inspection

An ultrasonic inspection of the LP-A and LP-B rotors was performed

on all the shrunk-on wheels assembled on the low pressure shafts.

This

inspection was performed by a General Electric (GE) subcontractors, McDorman

Metals.

GE has recommended that a complete magnetic particle

inspection be performed on this turbine at a future outage.

GE also

recommenis that after six years, a complete ultrasonic inspection of the

congential entry dovetails and the wheel bores should again be performed.

Although minor indications were noted during this injectfE, ?.he turbine

was considered to be satisfactory for operation.

8.

Plant Tour

At various times during the inspection, the inspecurs tourd the

facility to observe the progress of the refueling outage, plant

modifications and work area housekeeping.

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No items of noncompliance >r deviation were identified.

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9.

Exit Interview

The inspectors met with licensee representatives (denoted in paragraph 1)

at the completion of the inspection on March 27, 1980 to discuss

the scope and finding of the inspection.

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