IR 05000282/1980015
| ML20002A203 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/08/1980 |
| From: | Burgess B, Feierabend C, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002A198 | List: |
| References | |
| 50-282-80-15, 50-306-80-16, NUDOCS 8011050153 | |
| Download: ML20002A203 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMEhT
REGION III
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Report No:
50-282/80-15; 50-306/80-16 Docket No:
50-282; 50-306 License No: DPR-42; DPR-60
Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN.
55401 Facility Name:
Prairie Island Nuclear Generating Plant Inspection At:
Prairie Island Site, Red Wing, MN
Inspection Conducted: September 1- 0, 1980 N ~6 spps
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Inspectors:
-C. D. Feierabend LjM
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O B. L.
urgess
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Approved By:
W.
le, Chief,
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Projects Section 2
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Inspecticn Summary Inspection on September 1-30, 1980 (Report No. 50-282/80-15; 50-306/80-16)
Areas Inspected: Routine resident inspection of plant operation, raaintenance, surveillance, security, radiation protection, refuel-ing activities, followup on IE Circulars and followup on previous inspection findings. The inspection involved a total of 133 in-spector hours onsite by two NRC inspectors including 33 inspector hours.onsite during off-shifts.
Results:
No items of noncompliance were identified.
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DETAILS
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1. Personnel Contacted F. Tierney, Plant Manager-J. Brokaw, Plant Superintendent, Operations and Maintenance E. Watzl, Plant Superintendent, Plant Engineering and Radiation Protection A. Hunstad, Staf f Engineer R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, Maintenance J. Hoffman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiation Protection A. Smith, Senior Scheduling Engineer M. Klee, Nuclear Engineer K. Albrecht, Senior Quality Assurance Engineer D. Haugland, Engineer W. Phillips, Quality Specialist D. Cragoe, Shift Supervisor G. Edon, Shif t Supervisor P. Ryan, Shif t Supervisor M. Balk, Shift Supervisor J. Meath, Shif t Supervisor D. Walker, Shif t Supervisor 2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance item (282/79-01; 306/79-01)
Implementation of quality assurance inspection program. The inspector confirmed that the licensee had added 4 Quality Specialists to the staff, observed that appropriate procedures included inspection hold points and observed Quality Specialists performing inspections.
(Closed) Noncompliance item (282/79-18; 306/79-15) Documentation of temporary changes to procedures. The inspector has confirmed the licensee's corrective actions. Review of completed procedures has not identified discrepancies.
3. Operational Safety verification a.
General Unit 2 operated routinely except for an unscheduled shutdown September 4-13 to inspect and detorque the steam generator support bolts (Paragraph 5b).
Unit I refueling outage encompasses more maintenance and con-struction activities than usual, including rebuilding the high pressure turbine, several TMI related design changes and ultra-sonic testing of all condenser tubes.
Plant visitors during the month included F. Jablonski and W. S.
Little, IE Region III.
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Control Room Observations c
The inspector observed control room operations, reviewed app-licable logs, conducted discussions with control room operators, and observed shift tu rn overs. The inspector verified the oper-ability of selected emergency systems, reviewed equipment control records and verified proper return to service of affected com-ponents, c.
Tours Tours of the auxiliary, turbine and shield buildings and ext-ernal areas were conducted to observe plant equipment conditions, including potential fire hazards, and to verify that maintenance requests had been initiated for equipment in need of maintenance.
By observation and direct interview, the inspector verified that security procedures were being implemented in accordance with the plant security plan.
The inspectors observed plant housekeeping / cleanliness conditions, and verified implementation of radiation protection controls.
The inspectors conducted several special tours of Unit 1 and Unit 2 containments to observe maintenance and testing in pro-gress and to observe status of installation of TMI related mod-ifications. On two occasions, during the containment tours, the inspector observed personnel apparently dozing inside of containment.
In both cases, t hy personnel had apparently been scheduled to work in higher radiation areas but had been forced to wait for a short period because of other work in progress, so they had been told to wait in the lower area to minimize exposure. The inspector discussed this with plant management.
The plant manager discussed closer supervision of personnel with plant and contractor supervisors at the next morning meeting.
During a tour of Unit 2 containment the inspector noted one non-safety related snubber that needed fluid. The licensee initiated a work request for repair.
4. Maintenance a.
Review of Work Request (WR's) and Work Request Authorizations (WRA's)
The inspector selected and reviewed several WR's and WRA's to determine the status of safety related systems, to verif y that proper priorities were given and to verify that design changes were initiated where appropriate.
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Observations The inspector observed portions of safety related maintenance activities to determine that the activities did not violate limiting conditions for operation, that administrative approvals and rytipment control tags were completed prior to initiating the work, that approved procedures were used (or activ2y was within the " skills of the trade"), and that the procedures used were adequate to control the activity.
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Observations included witnessing activities during loosening
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and retorqueing Unit 2 steam generator support bolts and during removal of broken bolts from Unit 1 steam generator.
It also included examination of Unit 2 pressurizer manway bolts and gaskets and observation of removal of the manway for gasket replacement.
5. Steam Generator Support Bolts a.
Identification of Problem In response to NUREG 0577 the licensee began inspection of Unit 1 on September 4 and started to loosen the " heli-coil screws" that bolt the steam generator supports to the bottom head. This was in response to concerns raised concerning potential for brittle fracture of the bolt material (Vascomax 250 CVM) if continuously stressed.
Initial attempts to remove these bolts verified that they were stressed and that brittle fracture had occurred, as several bolts broke. Ultrasonic testing (UT)
identified many more with indication of cracks.
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Unit 2 The licensee immediately ordered Unit 2 shut down for inspection of these bolts.
UT inspection of all Unit 2 bolts identified three bolts with cracks. The licensee was sucessful in removing two of the three - the third broke. The licensee was able to remove two bolts from other locations to replace the two cracked bolts, providing a minimum of five bolts per support. The lic-ensee then proceded to detorque all of the support bolts in Unit 2,.by loosening them until a gap could be verified between the bolt head and the support, and then tightened them sufficiently to eliminate the gap. This eliminated the overstress condition.
The inspector observed initial ef f orts to detorque the bolts, witnessed UT, liquid penetrant (PT) and magnetic particle (MT) examination of the two cracked bolts and also for the two svind bolts that were removed from other locations. The inspec-tor law that the PT and MT testing confirmed the cracks identif-ied by UT and th;t the two sound bolts did not have crack indica-tion during FE testing.
Unit 2 was back on line on September 13.
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Unit 1 The inspector observed the broken bolts removed on September 4, and confirmed the licensee's action in ordering shutdown of Unit 2.
The inspector observed the contractor's performance of setup for removing the bolts from Unit 1 and observed progress of the bolt removal. Removal of the broken bolts was approxi-mately 25% complete.
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6. Refue1ing Activities
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The inspectors witnessed various portions of refueling activities in progress. This' included verifying that containment integrity was established and maintained during fuel handling, verifying that personnel supervising and performing fuel handling functions met Technical Specifications requirements and observing fuel handling act-ivities inside containment, in the spent fuel pool and in the control room. No items of concern were identified.
7. IE Circulars
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The inspector verified thac the licensee had received IE Circulars (IEC's) and had taken actions to review for applicability and
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implementation where required.
(Closed)
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IEC No. 80-12 Valve Shaft to Actuator Key The licensee has identified one actuator on a Unit 2 in-service purge exhaust valve that is positioned as described in the circular. Corrective action will be completed during the next refueling outage. The valve is locked closed at all times that containment integrity is required.
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b.
IEC No. 80-13 Grid Strap Damage in Westiaghouse Fuel Assemblies c.
IEC No. 80-17 Fuel Pin Damage Due to Water Jet From Baffle
. Plate Corners i
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LEC No.-80-19 Not applicable e.
IEC No. 80-20 Not applicable 8. Surveillance The inspectors reviewed results of several surveillance tests and witnessed portions of tests in progress.
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SP1646 Power operated relief valve test
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Test was satisfactory-b.
SP2073 ; Shield. Building Ventilation System Functional Test -
Initial test results for Train A were satisfactory, but Train B 'did not meet test ' acceptance criteria 'for equilibrium neg-ative pressure with recirculation.
Investigation showed that the local indicators were indicating satisfactory results. The test was repeated obtaining satisfactory results.
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The inspector considers this item to be unresolved, pending
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review of the basis for the acceptance criteria as it was not readily apparent how the acceptance criteria demonstrated com-pliance with Technical Specification 4.4.B.1 9. Exit Interviews The inspector attended an exit interview corducted by RIII inspector K. Ward on September 9, 1980.
The inspectors conducted interim interviews during the inspecting period and met with Mr. Tierney at the conclusion of the inspection.
The inspector discussed the scope and results of the inspection.
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