IR 05000298/1979016
| ML19257B786 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/21/1979 |
| From: | Constable G, Purdinek M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19257B785 | List: |
| References | |
| 50-298-79-16, NUDOCS 8001180338 | |
| Download: ML19257B786 (7) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No.
50-298/79-16 Docket No. 50-298 License No. DPR-46 Licensee:
Nebraska Public Power District P. O. Box 499 Colnebus, Nebraska 68601 Facility Name:
Cooper Nuclear Station Inspection At:
Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted:
October 23-26, November 5-7, and November 14-16, 1979 Principal Inspector:
G. L. Constable, Reactor Inspector Date Accompanying Personnel:
(11/14-16/79)
M. T. Pardinek, Co-op Student Date Approved By:
T. F. Westerman, Chief, Reactor Projects Section Date Inspection Summary Inspection conducted October 23-26, November 5-7 and 14-16, 1979 (Report No. 50-298/79-16)
Areas Inspected: Routine, unennounced inspection of document control, Station Operations Review Committee, records program, review of plant operations, spent fuel storage racks, and follow-up on LEK's and IE Bulletins.
The inspection involved fifty-six (56) hours on-site by ona NRC inspector.
Results:
No items of noncompliance or devi..tions were noted in the seven areas inspected. Three new unresolved item) were identified, and one safety issue (in situ testing of fuel stort ge racks) was identified and resolved.
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DETAILS Persons Contacted L. F. Bednar, Electrical Engineer R. D. Black, Shift Supervisor P. J. Borer, Engineering Supervisor P. F. Doan, Mechanical Engineer
- L. C. Lessor, Station Superintendent C. R. Noyes, Technical Assistant to Station Superintendent R. O. Peterson, Reactor Engineer J. V. Sayer, Chemistry and HP Supervisor P. V. Thomason, Assistant to Station Superintendent M. G. Williams, Operations Supervisor V. L. Wolstenholm, Quality Assurance Specialist W. H. Wunderlich, Administrative Supervisor
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- Present at the exit interview.
In addition to the above technical and supervisory personnel, the inspector held discussions with various maintanance, operations, technical support and administrative members of the licensee's staff.
1.
Plant Status October 23-26, 1979-Normal Operation to Full Power November 5-7,1979-Normal Operation to Full Power November 14-16, 1979-Conducted Reactor Shutdown on November 14, 1979 due to Emergency Diesel Generator Problems.
2.
Document Control Program The purpose of this inspection effort is to verify that effective administrative controls had been established to control changes to drawings and procedures. The inspector reviewed the following drawings and procedures that were available to the plant personnel and compared them, to the master file to verify that the proper revisions were in use.
Plant Procedures:
2.3.2.23 Revision 5 2.3.2.27 Revisica 5 2.3.2.1 Revision 5 2.4.2.3.2 Revision 3 1770 310 2.4.1.2 Revision 3
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Health Physics Procedures:
9.2.3 Revision 2 9.5.3 Revision 1 Emergency Plan Implementation:
5.7 Revision 5 Plant Drawings:
2036 Revision 13 2040 Revision 7 2012 Revision 20 No items of noncompliance were identified.
3.
Station Operations Review Committee (SORC)
The purpose of this inspection effort is to verify that reviews of safety issues conducted by the Station Operations Review Committee are consistent with license requirements.
The inspector reviewed SORC minutes numbered from 171-186.
This covers the activities reviewed from October 1978 through October 1979.
In addition, discussions were held with two committee members regarding meeting activities and day-to-day management interfaces.
These committee members believe there is excellent cooperation and coordination between the committee members on safety issues and that the committee functions effectively.
During the course of this inspection effort the inspector noted that the licensee's system for documenting procedure reviews had not been brought in line with technical specification and procedural requirements.
Inspection report 77-01 identified this issue as an item of noncompliance catagorized as an infraction.
Subsequent review of this issue has resulted in a determination that the actual review of safety-related procedures is accomplished in a competent, professional manner; however, these reviews are not being properly documented in the SORC minutes.
This item of noncompliance is therefore being downgraded from an infraction to a deficiency. Resolution of this issue will be handled by separate correspondence.
The resolution of this item will be reviewed during a future inspection.
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4.
Records Program The purpose of this inspection effort is to verify that the licensee has implemented an adequate program for storage maintenance and retriev-ability of important plant records.
The licensee is currently in the procass of duplicating many of the facility tecords.
The inspector toured the on-site record storage facilities, verified that required records were being maintained, and by random sample, verified that the records were retrievable.
During the course of the inspection the inspector identified several inconsistencies in record storage requirements.
These issues have been forwarded to NRC headquarters for review.
The following items are considered unresolved.
ANSI N45.2.9, Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants, requires that (Section 5.6) permanent and temporary record facilities shall be constructed to protect the contents from destruction by fire (four hour rating), flooding, and from possible deterioration by temperature and humidity.
The inspector noted that the licensee presently stores one-of-a-kind
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radiographs in a storage area that does not meet the recommended fire rating.
(Unresolved Item 7916-1)
In addition, contrary to recommendations in the standard, the
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inspector noted a pipe in the room tb:,t was identified as a drain from the roof.
(Unresolved Item 7916-2)
The inspector noted that records in the main storage area were
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stored in cardboard boxes.
Fire protection for this area is provided by an automatic sprinkler system.
It appears that the system designed to protect the records from fire could inadvertently damage these same records by flooding.
(Unresolved Item 7916-3)
Since the standard only recommends consideration of these issues, it is not clear what storage requirements are actually required.
These issues will recieve futher review during a future inspection.
5.
Review of Plant Operations The purpose of this inspection effort was to verify that routine facility operations are conducted in accordance with license conditions and procedural requirements.
The inspector reviewed logs and records (listed below), and discussed various plant conditions with management and shift personnel.
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Augmented Off-Gas Log October 2, 1979 - November 6, 1979 Night Orders September 14, 1979 - November 6, 1979 Control Room Log October 22, 1979 - November 6, 1979 Shift Supervisor's Log October 25, 1979 - November 6, 1979 The inspector verified that an instruction in the night orders regarding precoat mix for condensate demineralizers was implemented by plant staff.
On several occasions during the inspection the inspector verified that the shift was properly staffed.
Tours of accessible areas were co". ducted to observe work activities, check system lineups, and to verify that appropriate radiation control practices were in effect.
On November 14, 1979 the facility was shutdown due to failures of the emergency diesel generators.
The inspector observed plant shutdown and ongoing repairs of the generators.
No items of noncompliance or deviations were identified.
6.
Spent Fuel Storage Racks The purpose of this inspection effort was to verify that the new spent fuel storage racks were constructed, installed and inspected in accordance with NRC. requirements.
During the course of this review the inspector observed that the licensee had not conducted in-situ tests to verify that the fuel racks were actually built to design specifications regarding neutron attenuation.
Futher review of records indicated that the licensee had made no commitments in this area.
In view of the potential seriousness of an accidental criticality in the fuel pool, the inspector identified his concerns to the plant superintendent on October 26, 1979, and requested that no fuel be moved in the fuel pool until this issue was resolved. This issue was forwarded to NRC Headquarters for resolution.
During a meeting in NRC Headquarters on November 27, 1979, the inspector learned that in 1976 NRR had made a commitment to ACRS to require on-site neutron attenuation testing. A review of correspondence between NRR and NPPD indicate that NRR had asked NPPD (letter D. K.
Davis (DOR) to NPPD, dated October 4, 1977) to provide a description of on-site tests to verify that the fuel racks contain the required boron content.
NPPD's response (dated November 30, 1977) was interpreted by NRR as a commitment to conduct on-site testing.
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Immediately following this meeting the inspector notified NPPD management (J. M. Pilant) of the apparent misunderstanding.
The inspector was informed that the licensee had already initiated contact with a firm to conduct the neotron attenuation tests.
NPPD has committed to conducting these tests prior to refueling which is presently scheduled for March 15, 1980.
This matter will receive continuing review during subsequent inspections.
7.
Follow-up on Licensee Event Reports (LER)
The inspector reviewed the following licensee event reports to verify that reporting requirements were met and to assess whether futher NRC action is appropriate.
LER Title, Status 19-11 RWCU-MO-18 failed to close Closed when maually actuated 79-20 Failure of relief valve Closed bellows monitoring pressure switch 79-23 High steam flow D/P switch
. Closed Failure 79-24 NBI-PS-550 Set point drift Closed 79-25 HPCI turbine stop valve Closed Coupling Failure 79-26 Excessive leakage due Closed to seal failure 79-27 MS-DPIS-119B Set point Closed Drift 79-28 Degraded fire barrier Closed 79-30 Loss of drywell/ torus D/P Closed 79-32 Fire watch not established Closed
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79-33 Failure to test diesel Closed 1770 314 generator
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79-34 Broken oil hose on Closed diesel generator No items of noncompliance or deviations were noted in this area.
8.
Follow-up on IE Bulletins The inspector reviewed the licensee's response for each bulletin and performed on-site follow-up to verify that the licensee's actions were responsive.
IEB Title Status 79-15 Deep Draft Pumps Closed 79-18 High Noise Areas Closed 79-23 Potential Failure of Closed Diesel Generator Exciter 79-24 Frozen Lines Closed No items of noncompliance or deviations were noted in this area.
9.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable, items of non-compliance or deviations.
The following unresolved items were identified during this inspection.
7916-1 Records Storage - One-of-a-kind Records (Paragraph 4)
7916-2 Records Storage - Roof drain (Paragraph 4)
7916-3 Records Storage - Fire Protection (Paragraph 4)
10.
Exit Interviews The inspector met with the station superintendent several times during the course of the inspection.
The scope of the findings were discussed.
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