IR 05000298/1982006
| ML20052G149 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/13/1982 |
| From: | Johnson E, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20052G144 | List: |
| References | |
| 50-298-82-06, 50-298-82-6, NUDOCS 8205140352 | |
| Download: ML20052G149 (7) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-298/82-06 Docket:
50-298 Licensee:
Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility:
Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska, and NPPD General Offices,. Columbus, Nebraska Inspection Conducted:
March 8-10 and March 12, 1982 4 83I8L Inspector:
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E. H. Johnson, Reactor Inspector Date Reactor Project Section A A 1 7'
(//[J/trL Approved By:
T. F. Westerman, Chief, Reactor Project Section A Date Inspection Summary Inspection on March 8-10 and March 12, 1982 (Report 50-298/82-06)
Areas Inspected:
Routine, unannounced inspection of licensee action on previously identified items, fire protection modifications, and review of licensee actions at the corporate offices during a scheduled emergency preparedness exercise.
The inspection involved 24 inspector-hours by one NRC inspector.
Results: Within the areas inspected, no items of noncompliance or deviations were noted.
8205140352 820420 PDR ADOCK 05000298 G
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-2-DETAILS
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1.
Persons Contacted Cooper Nuclear Station P. Borer, Engineering Supervisor W. Gilbert, Training Coordinator R. Jansky, Shift Supervisor-
- L. Lessor, Station Superintendent R. Mcdonald, Health Physicist J. Sayer, Chemistry and Health Physics Supervisor F. Schaaf, Engineer M. Wolken, Engineer Nebraska Public Power District - Columbus General Offices R. Allen, Fire Protection Engineer
+R. Buntain, Division Hanager Operations
+C. Jones, Assistant General Manager - Operations
+R. Kamber, Senior Division Manager, Operations
+L. Kunc1, Division Manager, Engineering J. Pilant, Division Manager, Licensing & Quality Assurance
+J. Weaver, Licensing Manager In addition, the inspector contacted various administrative and operations personnel of the licensee's staff.
- Present at the exit interview at the Cooper Nuclear Station on March 12, 1982.
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+Present at the exit interview at the Columbus, General Office, March 10, 1982.
2.
Status of Previously Identified Items (0 pen) Unresolved Item 8101-03, Summary of Safety Evaluation for Minor j
Design Changes.
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During NRC Inspection 81-01, the licensee's Annual Report' for 1979 was reviewed and it was noted that the report did not contain a summary of the
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l safety evaluations for each-design change.
A full safety evalution was, however, available in the completion records for each design change.
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During this inspection, the NRC inspector reviewed the licensee's 1981 Annual Report and noted that although design changes were described in sufficient detail, the summary of the safety evaluation was still not included.
The NRC inspector selected seven of the minor design changes reported and verified by inspection of the completion records that the
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appropriate safety evaluations were done.
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-3-This item was discussed with the Engineering Supervisor and Station Superintendent.
Because of personnel changes in the Engineering Depart-ment that had occurred since this item was first identified, it had not yet been addressed. The Station Superintendent directed that a procedure, with examples, be prepared to specify the information and the format for future annual reports.
This item remains unresolved.
(Closed) Violation 8114-01, Failure of Safety Review and Audit Board (SRAB)
to Review Audit Program Status.
During the subject inspection, it was determined thet the SRAB had not reviewed the status of SRAB audits between April 1980 and August 1981.
This was determined to be in violation of Technical Specification 6.2.1.8 which requires SRAB to review the audit program status twice each year.
It was pointed out that lack of such review was a contributing factor to the fact that SRAB audits were not being conducted in accordance with the established schedule.
The licensee responded to the Notice of' Violation by letter from J. M. Pilant, NPPD, to W. C. Seidle, NRC Region IV, on November 23, 1981.
The corrective actions taken for this item included tracking SRAB audits via a computerized Action Item Tracking System and discussion of SRAB audits as a standing agenda item for each SRAB meeting.
The NRC inspector reviewed minutes of SRAB meeting numbers 71 and 72 (September 18, 1981, and December 7,~1981, respectively), and SRAB audits covering: major maintenance and inservice inspection program (December 3, 1981); nuclear materials safeguards, accountability, and nuclear perfor-mance evaluation (February 24, 1982); industrial safety (December 14, 1981); and station operations (October 7, 1981).
In addition, the NRC inspector examined outputs from the computerized Accion Item Tracking System and determined that SRAB audits are being tracked as indicated in the licensee's response letter.
The NRC inspector indicated that he had no further questions on this item at this time and it is considered closed.
(Closed) Violation 8114-02, Failure to Follow Requirements of Approved Operator Requalification Program.
During the subject inspection, it was determined that the licensee had implemented a revised opera. tor requalification program in which the criteria for the minimum acceptable grade on lecture series examinations had been lowered from 80 percent to 70 percent.
This lessening of requirements is contrary to 10 CFR 50.54(i).
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-4-The licensee's response to this item (same letter as referenced above),
indicated that the inspection report and response were reviewed with the personnel involved and the minimum acceptable grade was restored to 80 per-cent.
The NRC inspector discussed this item with members of the licensee's training staff and verified the corrective actions indicated above.
This item is considered closed.
(Closed) Violation 8114-03, Failure to Post a Radiation Area.
During NRC inspection 50-298/81-14, an NRC inspector discovered 20 boxes of radioactive material stored in a work / storage area next to the NRC Resident Inspector's office.
Radiation levels at 18 inches from the surface of the boxes were measured at 5 to 8 millirems per hour.
The area was not posted as a radiation area although readings at these levels would require such posting.
The licensee's response letter (same letter as referenced above) indicated that this room had been used to store anti-contamination clothing needing mending.
Over some period of time, a sufficient number of additional boxes of this material had been added to cause the radiation readings as noted above, however, updating the status of this area had not been accomplished.
To correct this, the protective clothing was removed from this area and the item was discussed with Health Physics personnel.
The NRC inspector verified these actions.
A tour of accessible areas of the facility did not reveal any similar accumulations of unposted radio-active material.
The NRC inspector verified that the licensee's Health Physics staff had similarly surveyed the Station and had not discovered any unposted or improperly posted areas.
This item is considered closed.
(Closed) Open Item 8114-07, Fire Brigade Training Program The licensee has issued the revised fire brigade training program.
The NRC inspector examined the program and had no questions.
This item is considered closed.
(Closed) Open Item 8114-08, Procedure for Control of Cutting Operations.
The licensee issued Procedure 7.10, " Fire Process Control," on February 20,
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1982.
The NRC inspector examined this procedure to ensure it provided proper control over cutting operations.
The inspector had no questions.
This item is considered closed.
3.
Review of Fire Protection Modifications In Appendix A to Branch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976,"
the Nuclear Regulatory Commission forwarded basic fire protection guide-lines to each licensee and requested that the licensee respond with his plans for meeting these guideline.
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-5-On October 10-13, 1978, an NRC review team visited the Cooper Nuclear Station to review the proposed modifications.
In a letter dated November 1, 1978 (T. A. Ippolito, NRC, to J. M. Pilant, NPPD), the NRC set out staff positions on required fire protection modifications for Cooper Nuclear Station and requested that the licensee provide an implementation schedule. The licensee's responses to these items were contained in a letter dated December 11, 1978 (J. M. Pilant, NPPD, to T. A. Ippolito, NRC).
On May 23, 1979, in Amendment 56 to Facility Operating License DPR-46, the Nuclear Regulatory Commission issued the Safety Evaluation Report (SER) for the licensee's fire protection program.
Section 3 of the Fire Protection SER provided a summary of the required modifications and the implementation schedule.
Supplement 1 to the Fire Protection SER was issued on November 21, 1980, to provide an evaluation of three items (Item 3.8 - Reactor Building cable trays, elevation 903';
Item 3.11 - Reactor and Control Building automatic suppression water feed independence; and Item 3.16 penetration fire stop barriers) that had required further information at the time the initial Fire Protection SER was issued.
The purpose of this inspection effort was to verify by direct observation and review of records that all modifications required in the Fire Pro-tection SER and its supplement had been accomplished.
The NRC inspector toured the facility to observe fire protection modifications, reviewed completed minor design change packages for several modifications, and held
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discussions with members of the licensee's staff.
The NRC inspector
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reviewed the status of each of the 46 modifications required in the Fire Protection SER and its supplement.
The NRC inspector concluded that all modifications had been completed as required.
4.
Review of Emergency Preparedness Exercise On March 10, 1982, the licensee conducted an emergency preparedness exercise at the Cooper Nuclear Station to verify capabilities to handle an onsite emergency.
The licensee's onsite and local area offsite actions were reviewed by an NRC raview team consisting of personnel from Region IV and NRR.
Their findings will be the subject of a separate report.
During this inspection, the NRC inspector visited the Columbus, Nebraska, general offices of NPPD on March 10, 1982, and was thus in a position to review the actions taken there in response to the simulated onsite emergency.
The NRC inspector observed communications with the onsite staff and attended planning sessions of the general offices staff held during the drill to evaluate the information received.
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-6-At the conclusion of the portion of the exercise involving the general offices staff, the NRC inspector made recommendations for improving the method of handling and controlling the flow of communications concerned with plant conditions.
Also discussed was the necessity to provide contingency plans for providing around-the-clock coverage at the general offices during an emergency.
These recommendations were noted by the licensee's staff who indicated they would be included in the licensee's
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own critique of the drill.
5.
Exit Interview An exit interview was conducted at the Columbus, Nebraska, general offices
- on March 10, 1982, with those persons noted in paragraph 1, and on March 12, 1982, with the CNS Station Superintendent.
The NRC inspector summarized the scope and findings of the inspection.
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