IR 05000409/1979001
| ML19276E519 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/01/1979 |
| From: | Little W, Riden M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19276E518 | List: |
| References | |
| 50-409-79-01, 50-409-79-1, NUDOCS 7903140595 | |
| Download: ML19276E519 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/79-01 Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue - South Lacrosse, WI 54601 Facility Name:
Lacrosse Boiling Water Reactor Inspection At: Lacrosse Site, Genoa, WI Inspection Conducted: January 10-12, 1979 Inspectors:
M. D. Riden 2[/[7T
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Approved By: W. S. Little., Chief Nuclear Support Section 2 Inspection Summary Inspection on January 10-12, 1979 (Report No. 50-409/79-01)
Areas Inspected: Routine, unannounced inspection to review records, procedures, equipment and performance of (1) employee training, (2) requalification training and (3) fire preventior/ protection. The inspection involved 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> of onsite inspection effort by two NRC inspectors.
Results: Of the three areas inspected no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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D. Parkyn, Assistant Plant Superintendent
- P.
J. Wiley, Operations, Training and Relief Supervisor J. B. Gallaher, Fire and Security Protection Supervisor H. A. Towsley, Quality Assurance Supervisor P. Grey, Maintenanse Supervisor The inspector also talked with and interviewed several other licensee employees including operations personnel, radiation protection technicians, instrument technicians, administrative personnel and maintenance personnel.
- Denotes licensee representatives attending management interview.
Other Personnel Mr. R. Phillips, Chief, Genoa Fire Department 2.
Training The inspector reviewed the training records and interviewed eight employees from various parts of the plant staff rc cerify that the general employee, technician, and craft training was being provided as required by the following Administrative Control Procedures (ACP's):
ACP-21.1, Rev. 2, 4/6/78, "LACBWR Training Responsibilities" ACP-21.5, Rev. O, 2/14/78, " Fire Watch Training" It was noted that some forms within individual training files were not identified in such a way that they could be traced back to the individual if they were ever separated from the file. This was usually because the forms were not completely filled out.
It was also noted that supervision was not performing the required review and signef f s of training records in a timely manner. The licensee agreed to correct these items.
At the time of the inspection the licensee had identified a few (6-8)
employees who had not recei.d all of the required annual r training in 1978. All of these had been immediately scheduled to make up this training, and at the time of the inspection most had been made u,
-3-During the previous inspection (Report No. 50-409/77-25) the inspector noted that the training program did not require annual retraining for offsite badged personnel, and expressed concern that the training of these escorted persons be kept correct.
The licensee responded to this concern in Rev. 2 of ACP-21.1 by making the entire training program applicable to all badged personnel onsite. The inspector had no further questions in this area.
No items of noncompliance or deviations were identified by the inspector.
3.
Requalification Training The inspector reviewed records and interviewed personnel to verify that the licensed employee requalification program was being conducted in accordance with the following:
ACP-21.2, Rev. O, 12/7/76, " Operator - Senior Operator Requalification Program"
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ACP-21.2, Addendum No. 1, 11/22/77 The inspector confirmed that the requalification training program has not been revised since the previous inspection, during which the program content and requirements were examined.
Since there were no outstanding items from previous inspections and no program changes had been made, this inspection concentrated on program implementation.
Some of the training records such as reactor manipulations were not being reviewed and initialed by supervision in a timely manner.
The licensee agreed to expedite this review.
No items of noncompliance or deviations were identified.
4.
Fire Prevention / Protection a.
Work Control Procedures Work control procedures were reviewed for operations personnel approval and control of all construction, modification and maintenance activities involving welding, open flames, ignition sources and fire watch. Work involving welding, cutting, or grinding is documented on the special work permit (SWP) and reviewed for fire hazards by responsible personnel.
The maintenance request and SWP forms state precautions to be taken and fire watch requirement,
-4-No items of noncompliance or deviaticas were identified.
b.
Quality Assurance Surveillance An inspection was conducted to determine if the quality assurance program performed periodic audits to verify that the controlling procedures were in use.
Work procedures were reviewed by quality assurance to insure cable penetration seals were reinstalled or replaced when removed.
No items of noncompliance or deviations were identified.
c.
Design Change Controls Facility changes ate implemented by a maintenance request and completed in accordance with the design of the facility change request as outlined in administrative control procedure, ACP- 04. 2.
Fire barrier seal material replacements are verified to be as specified by routine procedure, I&E 03-77.
No items of noncompliance or deviations were identified.
d.
Emergency Procedures The inspector verified that emergency procedures for fire fighting in vital areas contained special instructions for the fire brigade and alternate methods for accomplishing an orderly plant shutdown. The facility's guidelines for scheduling of fire drills are to have quarterly drills for each shift per year.
Review of the records indicated the fire drills were performed and critiqued as required.
No items of noncompliance or deviations were identified.
e.
Facility Inspection The facility fire inspections are performed by NELPIA Insurance Underwriters. The recommendations of American Nuclear Insurers inspection on July 6, 1978 were reviewed for corrective action and timely resolution.
The inspectors toured the plant to observe equipment, wiring controls, etc. required for fire detection, fire fighting.
Two potential fire hazards were identified:
(1) An oily rag stored in the IB diesel generator room was removed by the licensee; and
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- 5-(2) Wooden boxes used for storage of refueling equipment inside of containment were observed to be in need of fire retardant coating repair.
The licensee employee conducting the plant tour stepped across a " step-off" pad into a ribboned area without shoecovers to show the inspectors the inside of a fire hose cabinet. The inspectors did not follow the employee and later expressed concern to the employee that he would risk spread of contamination by not putting on shoe protective covers before stepping into the ribboned area.
The employee stated that he knew where the contaminated areas were and therefore did not risk spreading contamination by his action.
The inspectors expressed concern about his action, especially the importance of he as a supervisor setting the proper example for other employees. This was discussed with plant management at the exit meeting, who promised to talk with the employee and emphasize the importance of his following acceptable radiation protection practices.
No items of noncompliance or deviations were identified.
5.
Management Interview The inspectors met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on January 12, 1979 and talked by telephone on January 23, 1979. The areas in the preceeding paragraphs of this report were discussed.
The licensee representative acknowledged the following comments on facility change requests administrative control procedure, ACP-04.2:
a.
Should reference that cable penetration seals are to be re-installed in accordance with routine procedure, I&E 03-77.
b.
Should reference the fire watch requirement of ACP 17.3, Section 6.3.4 c.
Should include a mechanism for fire brigade review of latest plant design changes af fecting fire fighting plans.