IR 05000285/1979011
| ML19209B477 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/22/1979 |
| From: | Kelley D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19209B476 | List: |
| References | |
| 50-285-79-11, NUDOCS 7910090772 | |
| Download: ML19209B477 (8) | |
Text
U. S. NU1 LEAR REGULATORY CO!DfISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/79-11 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: August 7-11, 1979 Inspector:
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p-2 2 e 77 D. L. Kelley, Reactor Inspector Date
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s Approved by:
[i M N g,22-79
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T. F. Westerman, Chief, Reactor Projects Section Date Inspection Summary Inspection on August 7-10, 1979 (Report No. 50-285/79-11)
Areas Inspected: Routine, unannounced inspection of the licensee's (1) Fire Prevention / Protection Program; (2) Surveillance Testing; (3) Follow-up of Licensee Event Reports; (4) Follow-up on IE Bulletin Responses. The inspection consisted of twenty-five (25) inspector hours on-site by one (1) hTC inspector.
Results: Of the four (4) areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- R. L. Andrews, Manager, Fort Calhoun Station M. J. McFadden, Plant Engineer W. G. Gates, Supervisor, Operations M. R. Gore, I&C Engineer R. C. DeMeu1meester, Shift Supervisor
- Attended exit interview.
2.
Fire Prevention / Protection Program A.
The inspector reviewed the following elements of the licensee's fire pievention/ protection program:
On and off-site functional responsibilities and lines of communi-
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cations.
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Administrative controls and procedures have been developed for the following:
Periodic Audits
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Fire Brigade qualifications
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Actions to be taken by persons discovering fires
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Control of combustible, flammable and explosive materials in
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safety-related areas Storage of combustible, flammable and explosive materials
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Cleanliness of work activity areas
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Periodic inspection for combustibics
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Welding and flame cutting control
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Posting and control of "no smoking" areas
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Fire fighting procedures and fire plans
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Fire Brigade training
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Review of fire inspe. ion
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Review of Fire Emergency Drills
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Emergency Brea hing Apparatus requirements
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B.
The following documents were reviewed to determine if the above items had been addressed:
01-FP-4, R2, July 1, 1975, " Fire and Smoke Detection System Alarm
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Procedure" OI-FP-6, R27, April 20, 1979, " Inspection and Test"
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OI-FP-7, R3, March 12, 1979, " Emergency Firewater Supply" OI-FP-8, R0, October 17, 1978, "Halon 1211 Fire Extinguishers"
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OI-FP-9, R0, October 17, 1978, " Aqueous Film Forming Foam Fire
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Extinguishers" OI-FP-1, R8, June 19, 1979, " Normal Conditions"
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OI-FP-2, July 2,1975, " Dry Chemical Fire Extinguishers"
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OI-F3-3, R3, July 2, 1975, Carbon Dioxide Fire Extinguishers" EP-10, R3, January 5, 1977, " Fire Reactor Safeguards Equipment,
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Reactor Protective Systems Equipment or Other Equipment Vital to the Safe Operation of the Plant"
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Emergency Plan, Procedure VII - IV - 9, Section F, RI, June 27,
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1978; Appendix X, R4, August 1, 1978, " Fort Calhoun Station Fire Bill" A-M-9, R5, March 12, 1979, " Fire Protection During Flame Cutting
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and Welding Operations"
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A-G-6, R3, September 29, 1978, " Housekeeping"
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A-G-17, R9, March 1, 1979, " Maintenance Orders" American Nuclear Insurers Inspection Reports for 1979
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Fire Drill Records - Drill conducted on July 21, 1979 (In conjunction with the Blair Fire Department)
Records of Two actual Fires, March 27,1979, (Laundry Room);
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March 9, 1979, (Battery Charger No. 1)
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Fire Brigade Training:
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Course content
" Nebraska Department of Education, Nebraska
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Fire Service Training Division" Records of attendance, test score and personnel qualification
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In addition, the inspector toured the accessible areas of the plant and reviewed the licensee's progress of implementing the commitments of Section 3, Table 3.1 of the Fort Calhoun SER on Fire Protection /
Prevention.
C.
The inspector determined that the elements of Section A above have been adequately addressed by the licensee with the following exceptions:
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1.
Appendix X, Section F of the Site Emergency Plan " Fort Calhoun Station Fire Bill," appears to be in conflict with the provisions of the SER " Fire Protection / Prevention. The licensee is requested to clarify the discrepancy between the Fire Bill and the SER.
This item is unresolved pending action by the licensee (7911-201).
2.
It is not clear what the specific responsibilities of the Shift Supervisor are during a fire emergency. The licensee is requested to clarify the Shift Supervisor's responsibilities relative to a fire emergency cnd placing the plant in a safe con-dition.
It should also describe any procedural method for shifting the responsibilities from one to the other without combining both areas of responsibility under one person-D.
A review of the SER, Table 3.1 " Implementation Dates for Modifications,"
and discussion with licensee representatives indicated that the modification to be completed as of this inspection date have been completed and there is reasonable assurance that the remainder of the schedule can be met.
No items of noncompliance or deviations were identified.
3.
Surveillance The inspector reviewed selected procedures a.d records relating to the licensee's surveillance activities.
In addition, the inspector witnessed selected surveillance tests. The following are the procedures selected:
- -ST-RA-1 (F.1), R9, February 17, 1978, " Reactivity Anomolies"
- -ST-ESF-6(F.2), R34, April 30, 1979, Appendix B, D1 Diesel, " Diesel Start and Diesel Fuel Oil Transfer Pump" 1117 221
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- -ST-RPS-11 (F.1), R3, August 1, 1973, "RPS Logic Units"
- -ST-Cont-2 (F.2), R16, August 11, 1977, " Containment Local Leak Detection Test Type B (PAL Door)"
-ST-ISI-CA-1, R2, October 17,1978, " Compress Air Valve Teservice Test"
-ST-ISI-CC-3, R3, May 21, 1979, " Component Cooling Water Pump Inservice Test"
-ST-ISI-CYCS-3, R7, June 12, 1979, " Chemical and Volume Control Pump Inservice Test"
-ST-ISI-DW-1, R0, August 12, 1977, " Demineralized Water Valves Inservice Test"
-ST-ISI-FW-1, R1, January 20, 1978, "Feedwater Valves Inservice Test"
-ST-ISI-MS-1, R4, November 2,1978, " Main Steam Valve Inservice Test"
-ST-ISI-RW-3, R0, October 3, 1977, " Raw Water Pump Inservice Test"
-ST-ISI-SF-3, R1, October 27, 1978, " Spent Fuel Valves Inservice Test"
-ST-ISI-SI-3, R1, October 14, 1977, "SI/CS Pumps Inservice Test"
-ST-ISI-VA-1, R4, November 1, 1978, " Ventilation Air Valves Inservice Test"
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Several drawings were used to verify the technical content and correctness of th2 above tests.
These drawings were:
-11405-M-10, R8, " Component Cooling System Flow Diagram"
-11405-M 5, R7, " Demineralized Water System Flow Diagram"
-11405-M-253, R11, " Steam Generator Feedwater and Blow Down Flow Diagram"
-11405-M-252, RIO, " Steam Flow Diagram"
-11405-M-100, R8, " Raw Water Flow Diagram"
-11405-M-1, R10, " Containment Heating, Cooling and Ventilating Flow Diagram" i i i ~/
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-11405-11-11, R6, " Spent Fuel Pool Cooling System Flc.., Diagram" The above single asterisked (*) tests were witnessed and the double asterisked (**) test results were reviewed by the inspect r.
The remaining test procedures were reviewed to verify that they met the following conditions:
Prerequisites
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Acceptance criteria
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Instructions for restoration to operability Tests were in conformance with Technical Specification and ISI Program
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requirements Test were reviewed and approved
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Tetts were performed within the specified time requirements Tests were performed by qualified individuals
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No items of noncompliance or deviations were identified.
4.
Review of Licensee Event Reports (LER's)
Selected LER's were reviewed to ascertain that:
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Reporting requirements had been met.
Appropriate corrective action was taken.
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Licensee procedures were followed in the review and evaluation of the
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event.
Continued operation did not pose a safety hazard.
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The following LER's were received in the regional office and followed up on-site during this inspection:
LER 79-04 Weld Leak on Controlled Bleed-0ff Line RCP-RC-3C LER 79-06 Water Inleakage to D/G Underground Storage Tank LER 79-14 ASCO Solenoid Valves
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LER 79-15 Seismic Support on Containment Cooler-Filter VA-3A LER 79-13 Hot Leg Temperature Indicator C/TI-122H Failure No items of noncompliance or deviations were icentified.
5.
Follow-up of Part 21 Report The NRC was notified by Gibbs and Hill of a possible deficiency in the seismic support for containment cooler-filter VA-3A cooling water piping on May 17, 1979.
Gibbs and Hill notified the licensee on May 11, 1979 and the licensee issued LER 79-15 on May 25, 1979. The unit was declared inoperable at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 15, 1979. The unit was repaired by replacing the missing "U" bolts on May 17, 1979.
The inspector reviewed LER 79-15 and Part 21 Report, sequential No.79-236, of June 11, 1979. The results of the review verified that the provisions of 10 CFR 21 had been satisfied and the repair of the cooler-filter is in agreement with the seismic analysis and can reasonably be expected to withstand the Fort Calhoun design seismic event.
No items of noncompliance or deviations were identified.
6.
Follow-up on IE Bulletins IE Bulletin 79-03 The licensee's response indicates that the stainless steel piping spools identified in this bulletin were not installed at Fort Calhoun.
IE Bulletin 79-04 The licensee's response indicates that the valves identified in this bulletin were not installed at Fort Calhoun.
IE Bulletin 79-07 The licensee's response indicates that the computer codes for seismic stress analysis for safety-related piping identified in this bulletin were not used at Fort Calhoun.
IE Bulletin 79-09 The licensee responded that GE type AK-2 Circuit Breakers are used in the entire 480V plant distribution system. The licensee has initiated a 11i7 224
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preventative maintence program incorporating the recommended action described in the circuit breaker manual.
IE Bulletin 79-10 The licensee has provided the information on operator requalification training program statistics as required by the bulletin.
No items of noncompliance or deviations were identified in the above reviews.
7.
Unresolved Items Unresolved items are matters about which more infonnation is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item, disclosed during this inspection, is discussed in paragraph 2.C.
8.
Exit Interview The inspector met with Mr. R. L. Andrews on August 10, 1979 and summarized the scope and findings of the inspection.
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