IR 05000285/1980003
| ML19323E645 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/04/1980 |
| From: | Mcdonald D, Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19323E633 | List: |
| References | |
| 50-285-80-03, 50-285-80-3, NUDOCS 8005270087 | |
| Download: ML19323E645 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/80-03 j
Docket No. 50-285 License No. DPR-40 Licensee: tmaha 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:
February 11-14, 25-28 and March 10-14, 1980 Inspector Ed e )
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D. C.~Kelley, Reactor lfTnspe Gr
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4 hse R. G." Spa 61ger,Neacifop Ins ctor
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l00 D. G. Mcdonald, Reactor Inspector
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'Date Approved By:
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T. F. Westerman, Chief, Reactor Date Projects Section Inspection Summary Inspection on February 11-14, 25-28 and March 10-14, 1980 (Report No. 50-285/
80-03)
Areas Inspected:
Routine, unannounced inspection of the licensee's (1) Re-fueling activities; (2) Refueling Maintenance activities; and (3) Refueling Surveillance Activities.
Several plant tours were conducted and an in-containment audit of as-installed safety-related electrical equipment.
The inspection consisted of 126 inspector hours on-site by three (3) NRC inspectors.
067 8005g79g
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Results:
Of the five (5) areas inspected, no apparent items of noncompliance or deviations were identified in three (3) areas, and two (2) apparent items of noncompliance were identified in two (2)' areas (Infraction - Failure to use the correct maintenance procedure, paragraph 3; Infraction - Improper certification of respirator qualification, paragraph 5); and one (1) deviation in one (1) area (wearing contact lenses while wearing a full face respirator, paragraph 5).
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DETAILS 1.
Persons Contacted
- S. C. Stevens, Manager - Fort Calhoun Station
- W. C. Jones, Division Manager - Production Operations
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- R. L. Andrews, Section Manager - Operations W. G. Gates, Supervisor - Operations G. R. Peterson, Supervisor - Maintenance, Fort Calhoun Station L. J. Dugger, Reactor Engineer
- D. D. Wittke, Section Manager - Generation Station Engineering
- F. A. Thurtell, Divison Manager - Environmental and Regulatory Affairs
- K. J. Morris, Manager - Administrative Services
- R. L. Jaworski, Section Manager - Technical Services
- J. M. Gloshen, QA Engineer
- J. L. Connolley, Supervisor, I & C and Electrical Field Maintenance F. F. Franco, Chemistry and Health Physics Supervisor
- B. J. Hickle, Licensing Administrator
- T. J. McIvor, Manager, Operation Technical Support Services
- R. F. Mehaffey, I & C and Electrical, Technical Services Other Personnel
- S. Falh, Stone & Webster
- Denotes those attending exit interviews The inspectors also talk with and interviewed other licensee employees during the inspection.
These included reactor operators and office personnel.
2.
Refueling Activities
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The inspector reviewed the licensee's refueling activities to ascertain that the pre-fuel handling and fuel handling activities were in accordance with approved procedures and applicable section of the Technical
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Specifications.
The inspector reviewed the following pre-fuel handling activities to verify that they had been completed prior to fuel handling:
Technical Specification requirements (T.S.2.8)
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Testing of refueling machine
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Proper ventilation in fuel storage areas
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Testing of refueling interlocks
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Crane Testing
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Testing of refueling floor radiati'on monitors
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Testing of communications
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To verify the above items, the inspector reviewed the following completed surveillance tests:
ST-FH-1, R9, August 10, 1978, Refueling System Interlocks
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ST-CONT-2, R16, August 11, 1977, Containment Local Leak
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Detection Tests Type B (F.1)
Personnel Access Lock (PAL) 0-Ring Seal Test (F.3)
Equipment 0-Ring Seal Test ST-RM-2, R13, May 31, 1979, Process Monitors
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(F.2)
Process Monitor Checks ST-RM-1, R13, May 31, 1979, Area Monitors
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(F.2) Area Monitors Checks OI-CO-4, RS, October 24, 1977, Containment Isolation Status During
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Refueling Operations The inspector also reviewed OP-11, R3, February 4, 1980, " Reactor Core Refueling Procedure."
In addition to the procedural and pre-fuel handling tests, the inspector witnessed the movement of the following fuel elements from the refueling floor:
Removed from the core:
Elements E114 and E118 (Combustion Engineering).
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Inserted in the core:
Elements HA36, HA13 and HA40 (Exxon)
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At various times during the inspection the inspector observed the boron concentration, refueling cavity water level, 1/m plotting and check off of fuel shuff7.e steps in OP-11.
At the completion of the refueling activities the inspector reviewed the completed fuel handling procedure (OP-11) and the final verification of fuel location in the core.
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No items of noncompliance or deviations were identified.
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3.
Maintenance Activities During Refueling The inspector reviewed three (3) maintenance activities during the refueling outage.
The following maintenance activities were selected for review:
CEDM Gasket Removal and Replacement Procedures:
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MP-RC-10-4-A, R8, February 9,1980, CEDM Gasket Removal MP-RC-10-4-B, R8, February 9,1980, CEDM Gasket Replacement MP-RC-10-4-C, R1, July 27, 1978.
Equipment Hatch Removal Procedure:
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MP-AE-1-1, R6, March 22, 1979 Main Steam Safety Valve Repair Procedure:
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MP-MS-1, Main Steam Safety Valve Inspection and Repair, R6, January 11, 1980.
The review of the above maintenance activities was conducted to verify that:
There were administrative approvals for removing and returning the
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systems from service.
There were QA/QC hold points.
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i There were operational readiness tests performed.
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There were requirements for firewatches and special permits for flame
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cutting and welding when applicable.
There were material certifications where necessary.
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LCO's were satisfied during the period in which maintenance was
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performed.
Provisions for housekeeping were in effect.
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Provisions for cleaning of safety-related components were prescribed.
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The inspector witnessed a portion of the CEDM removal and replacement.
The review of the completed CEDM maintenance indicated the above require-ments had been met and the work was accomplished using the proper approved procedures.
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The review of the equipment hatch removal also indicated that the work was accomplished in accordance with the' proper approved procedures.
While reviewing the maintenance order (M.0.1802) for the repair of Main Steam Safety Valve MS-MV-281, the inspector noted that the maintenance order referenced maintenance procedure MP-RV-1 This procedure was also attached to the completed M.0. and was signed off as completed.
Procedure MP-RV-1 is the procedure for Type 1900 Dresser valves. MS-MV-281 is a Type 3700 Dresser valve and the procedure MP-MS-1 is the prescribed procedure for repair of Type 3700 Dresser valves.
Failure to use the correct procedure is contrary to Technical Specification, Section 5.8.1, which states in part:
" Written procedures and administrative policies shall be established, implemented and maintained.
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the established approved procedure was not used to perform the maintenance activity.
This is an infraction.
No other items of noncompliance or deviations were identified.
4.
Surveillance Activities Dut.'nc Refueling The inspector reviewed the results of the integrated Engineered Safety Systems actuation tests to determine the following:
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that the current properly approved procedure was used for the test, (2)
that the test prerequisites had been completed prior to conducting the test, (3) that all required data was recorded, (4) that the procedure was performed by qualified individuals, (5) and that the test results were consistent with the acceptance criteria of the procedure and the license.
The procedures reviewed were:
ST-ESF-2-F3 - Automatic and Manual Actuation of SIAS, CSAS and CIAS, performed February 21, 1980.
ST-ESF-4-F3 - Containment Spray Logic, performed December 20, 1980.
ST-ESF-6-F3; F4 - Automatic Diesel Generator Operation, DG(1); DG(2),
performed February 21-22, 1980.
Within the areas noted above, the inspector had the following findings.
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--s During the review of ST-ESF-2-F3 the inspector found that steps 5.19 and 5.41 had been initialed and dated as co'mplete by the test conductor.
These steps indicate that all valves, pumps, and fans listed in procedare appendicies A, B, and B1 go to their accident position. However, there were numerous notes in these appendicies indicating that components were inoperable, tagged out, or did not work.
The electrical and I&C Supervisor indicated that these components were to be retested prior to the unit's startup.
The inspectors indicated that the sign-off of steps 5.19 and 5.41 is apparently inconsistent with the present status of the test.
In addition, they expressed the concern that the retesting of components be conducted with sufficient overlap of ST-ESF-2-F3 to guaranty automatic actuation. These issues are considered an unresolved item.
(8003-01)
The inspectors noted during this review that these completed surveillance tests are reviewed and initialed by the discipline Engineer and the Electrical and I&C Supervisor. This review is not required by current administrative procedurcs; however, it does satisfy the requirements for a review of test result-. by qualified individuals as outlined in OPPD's Quality Assurance Program. Although Standing Order G-23, Surveillance Test Program, requires that completed surveillance test r(sults shall be reviewed by the Plant Review Committee, the inspectors requested that plant management consider epecifically adding to G-23 a requirement that the area supervisors date and initial completed test results on their review. This item is an open item.
(8003-02)
Further review indicated that completed surveillance tests with no de-ficiencies were reviewed by the Technical Services Supervisor, stamped
"PRC Reviewed, PRC Mtg. Minutes Dated
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This appears to be out of context with the described use of the PRC review stamp in paragraph 6.2.2 of Standing Order G-5, Plant Review Committee.
This itea is considered an open item.
(8003-03)
No further items of noncompliance or deviation were identified.
5.
Plant Tour At various times during the inspection, the inspectors toured the plant and observed the following:
Fuel Shuffle (from both containment and fuel building)
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Surveillance Testing
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Maintenance activities
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Control room operations (related to refueling activities)
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Low pressure turbine rotor inspection
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Fire protection modifications
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Implementation of NUREG-0578 short-term requirements
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General housekeeping during unit outage
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Health physics control of various work areas
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Cutting / welding activities including stationing of fire watches
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Work in progress relating to IEB 79-02 and IEB 79-14
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On February 26, 1980, the inspector and a licensee employee entered the containment where he noted a licensee employee wearing a full face respirator while wearing contact lenses.
The inspector verified that the employee did indeed have contact lenses on while wearing the respirator. This is contrary to NUREG-0041 " Manual of Respiratory Protection Against Airborne Radioactive Material."
(8003-04)
This is a deviation.
On exiting the containment, the inspector randomly selected two other persons with beards who were certified as being qualified to wear re-spirators. No evidence was found to indicate that the orginal mask fits had been accomplished contrary to plant procedures.
However, one of the individuals had been inadvertantly certified without supportive evidence of a mask fit retest which is required every two years.
This individual was rebadged with respirator " white dot" certification on January 28, 1980.
The only mask fit test that could be located was dated October 11, 1977.
No evidence of retest during October 1979 or after could be located.
Certifying a person as qualified to wear a respirator without a current (2 year) mask fit. is contrary to Section 2.12.3.1, " Quantitative Man Test," of the Radiation Protection Manual.
(8003-05)
This is an infraction.
6.
Followup Review on IEB 79-01B The inspectors collected data on the installation of the Low Pressure Safety Injection (LPSI) System for use in evaluating OPPD's response to IEB 79-01B.
Installation details were obtained from electrical and instrument schematic drawings and verified during a physical inspection of LPSI components located in the Reactor Containment Building.
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This review included the following equipment:
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Equipment Drawing Reference
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A/PI 102, B/PI-102 Pressurizer Pressure 161-F-611 C/PI 102, D/PI-102 Transmitters FI 330, FI 328 Low Pressure E561 sheets 111-114 FI 334, FI 332 Safety Injection Flow HCV-327, HCV-329 LPSI Valves E-29 sheet 3 HCV-331, HCV-333 HCV-348 Shutdown Cooling Inboard E-51 sheet 2 Isolation Valve No items of noncompliance or deviation were identified.
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Unresolved Items Unresolved items are those items for which further information is required to determine whether the items are acceptable items, items of noncompliance or deviations. Unresolved items are discussed in paragraph 4.
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Exit Intervt.:w The inspectors met with licensee representatives (denoted in paragraph 1)
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on February 14 and 28, 1980, and on March 13 and 14, 1980 to summarize the scope and results of the inspection.
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