IR 05000285/1978015
| ML19259B234 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/04/1978 |
| From: | Cupp E, Johnson W, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19259B231 | List: |
| References | |
| 50-285-78-15, NUDOCS 7901170425 | |
| Download: ML19259B234 (5) | |
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U. S. flVCLEAP, REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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Report flo. 50-285/78-15 Docket No. 50-285 License No. DPR-40 Licensee:
Omaha Public Power District 1623 Harney Street Omaha,tiebraska 68102 Facility flame:
Fort Calhoun Station - Unit 1 Inspection At:
Fort Calhoun Station, Blair, Nebraska Inspection Conducted:
flovember 13-16, 1978 Inspectors: _M _
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W. D. Je nson, Reactor Inspector
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E. A. Cupp, Reactor lIrfpector
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Approved by:_ g I
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G. L. Madsen, Chief, Reactor Operations Date and Nuclear Support Branch Inspection Summary inspection on November 13-16,1978 (Report flo. 50-285/78-15)
Areas In_spected:
Routine, unannounced inspection of surveillance, maintenance, and plant operations activities (. :ng a refueling outage.
The inspection consisted of fif ty-four (54) inspector-hours on-site by two (2) NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- R. L. Andrews, Plant Manager J. L. Connolley, Instrumentation and Control Engineer L. J. Dugger, Reactor Engineer J. J. Fisicaro, Supervisor, Administrative G. R. Fleischmann, QA Engineer W. G. Gates, Supervisor, Operations M. J. McFadden, Plant Engineer
- Attended exi t interview.
2.
Refueling Activities The inspector reviewed the completed Reactor Core Refueling Procedure, OP-11. All the required checklists and data sheets, such as those for fuel transfer, i.urce transfer, inverse multiplication calculations and plots, and core verification were properly completed and filed with the basic procedure.
All procedure changes had been properly authorized and documented.
No items of noncompliance or deviations were identified.
3.
Surveillance (Refueling)
The inspector reviewed the procedures for the following surveillance tests:
Procedure No.
Title ST-ESF-2-F.3 Channel A Automatic Engineered Safeguards Actuation, Manual Safety Injection Actuation, Manual Containment Spray Initiation and Manual Containment Isolation Initiation ST-ESF-6-F.3 Diesel Generator Automatic Operation -
Diesel Generator, Dl.
These procedures were verified to be properly approved and consistent with the Technical Specification surveillance requirements. One (1)
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area of apparent weakness in those procedures was noted and discussed with a licensee representative.
These rather complex procedures require that numerous breakers, switches and valves be placed in an abnormal position or operating mode.
Some of the abnormal conditions imposed in preparation for the test are specifically directed by the procedures to be returned to normal at the completion of the test.
Other important components are not specifically directed to be returned to normal, but are intended to be restored by a general step near the end of the procedures which states, " Place pumps, fans, switchgear and control switches in desired position per applicable operating instructions and procedures." The licensee representative stated that many of these items would be administratively controlled through equipment tagouts.
He pointed out that failure to return a piece of equipment to normal v;ould not be critical since the plant will be in a refueling shutdewn condition at the time of the test and the Technical Specification equipment operability requirements are relaxed in this condition.
In addition, equipment lineup checklists, which are performed prior to startup, would detect any abnormal conditions.
The licensee representative said he would review the procedures to determine if any other equipment should be covered by specific instructions to return it to its normal operating condition (0 pen Item 285/258).
Test results will be reviewed during a future inspection.
No items of noncompliance or deviations were identified.
4.
Maintenance (Refueling)
The inspector reviewed procedures for three (3) major maintenance activities scheduled to be completed during the current refueling outage.
This review included verification that the procedures include the following:
a.
Administrative approvals for removing the system from service and returning it to service, b.
Appropriate quality control hold points.
c.
Provisions for testing following maintenance or modification.
d.
Provisions for assuring that system valves, breakers, etc.,
are aligned for normal servic.
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The maintenance activities reviewed are indicated below:
(slintenance Activity Associated Documents / Procedures Feedwater Flow Nozzle Flange DC0 78-40; DCR FC-77-101; WPS-6A; Installation QW 406, Supplement No.1 and QW 407, Supplement No. 1.
Component Cooling Water Heat MO 15076; MO 15077; MO 20642; Exchanger Cleaning and MO 20643; EEAR FC-78-60; EEAR Modi fication FC-78-62; SRDC0 78-36.
Incore Detector Replacement MO 19674 and SP-IC-5 The inspector witnessed portions of the maintenance activities
'isted above.
Activities witnessed included welding, weld preparation and liquid penetrant examination of feedwater flange welds.
For the component cooling water heat exchanger cleaning and modification activity, the inspector observ l tube cleaning, preparation of heat exchanger heads for welding and baffle plate modifications. All of the work observed was being accomplished by qualified personnel in accordance with app..ved procedures.
No items of noncompliance or deviations were identified.
5.
Follow Up on Unresolved Item (Closed) Unresolved Item (7706-2):
Feedwater Flow Nozzles - During inspection 77-06, the inspector found that the licensee had no means for celibrating or inspecting the feedwater flow nozzles.
These flow nozzles are installed in each of the two feedwater lines to provide indication of the feedwater flow to the team generators.
The feedwater flow transmitters also provide a r gnal to the process compu ter. This computer input of feedwater fic.. 's a key parameter in the calculation of core thermal power.
The ins actor was concerned e
that with time the flow nozzle characteristics could be changed by erosion or crud buildup; but since the nozzles were welded into the feedwater lines and were not accessible, they could not be inspected or calibrated.
During this inspection, the licensee was completing DCR FC-77-101, which was a design change involving installation of flanges so the feedwater nozzles could be removed for inspection.
The inspector witnessed portions of this design change installation, as reported in paragraph 4 of thir report.
The inspector also visually inspected the feedwater flow nozzles and could see no evidence of erosion or crud buildup.
The licensee made dimensional measurements of the flow nozzles and verified that no dimensional changes have occurred since the flow nozzles were originally placed into operatio.
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6.
Plant Tour The inspectors conducted tours of the plant at various times of the inspection.
Areas toured included the containment building, the auxiliary building, the control room and the intake structure.
Housekeeping conditions were considered to be satisfactory.
flo items of noncompliance or deviations were identified.
7.
Review of Plant _ger_atio_n_s_(Refueling)
The inspector reviewed startup procedures, startup checklists, special test procedures, scheduled surveillance tests and systems checklists to verify that plans exist to test systems and components that underwent maintenance or were disturbed during the refueling outage.
In addition, the inspector reviewed plant startup procedures to verify that they require adherence to the licensee's technical specifications and commitments as they pertain to startup testing and power operation prerequisites.
No items of noncompliance or deviations were noted in this area.
8.
_ Exit Interview The inspectors met with the Plant Manager at the conclusion of the inspection on November 16, 1978.
At this meeting the inspectors summarized the scope and findings of the spection.