IR 05000282/1985022
| ML20151L523 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/19/1985 |
| From: | Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20151L522 | List: |
| References | |
| 50-282-85-22, 50-306-85-20, NUDOCS 8601020077 | |
| Download: ML20151L523 (5) | |
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i U. S. NUCLEAR REGULATORY COMMISSION REGION 111 l
Reports No. 50-282/85022(DRP); 50-306/85020(DRP)
Docket Nos. 50-282; 50-306
_icenses No. DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401
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Facility Nam 6:
Prairie. Island Nuclear Generating Flant Inspection At:
Prairie Island Site, Red Wing, MN
Inspection Conducted: October 13:through December 7, 1985
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Inspectors:
J. E. Hard
M. M. Moser d\\ b
~ Approved By:
1. N. Jackiw, Chief Reactor. Projects Section 2B Date Inspection Summary
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Inspection on October 13 through December 7, 1985 (Reports No. 50-282/85022(DRP); 50-306/85020(DRP))
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i Areas Inspected:. Routine unannounced inspection by resident inspectors
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of previous inspection findings, plant operational safety, maintenance,
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surveillance, facility modifications, meeting with corporate management,
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and followup of Licensee Event Reports. The inspection involved a total of 408 inspector-hours by two NRC inspectors including 34 inspector-hours
onsite during off-shifts.
Results: No, violations were identified in the seven areas. inspected.,
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0601020077 051220 PDR ADOCK 000
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DETAILS 1.
Persons Contacted L. Eliason, General Manager, Nuclear Plants F. Tierney, General Manager, Nuclear Engineering and Construction
- E. Watzl, Plant Manager
- 0. Mendele, Plant Superintendent, Engineering and Radiation Protection
- R. Lindsey, Plant Superintendent, Operations and Maintenance
- A. Hunstad, Staff Engineer A. Smith, Senior Scheduling Engineer M. Balk, Superintendent, Operations D. Schuelke, Superintendent, Radiation Protection J. Nelson, Superintendent, Maintenance J. Hoffman, Superintendent, Technical Engineering
- K. Beadell, Superintendent, Quality Engineering M. Klee, Superintendent, Nuclear Engineering R. Conklin, Supervisor, Security and Services D. Vincent, Project Manager, Nuclear Engineering and Construction J. Goldsmith, Superintendent, Nuclear Technical Services A. Vukmir, Site Services Representative, Westinghouse The inspectors interviewed other licensee employees, including members of the technical and engineering staffs, shift supervisors, rcactor and auxiliary operators, QA personnel, and Shift Technical Advisors.
Corporate personnel were visited on October 22, 1985 and are listed in Section 7 below.
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- Denotes those present at the exit interview on December 9 1985.
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2.
Licensee Action on Previous Inspection Findings
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There was no completed licensee action on previous inspection findings during this inspection period.
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3.
Operational Safety Verification (71707, 71710)
Unit I was base leaded at 100% power except for reductions for surveillance testing, special maintenance, and weekend load following. Unit 2 completed the refueling and ten year inspection outage on November 1,1985 and has
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been at 100% power except for reductions * for surveillance testing, special maintenance, and weekend load following.
1he inspector observed control room operations, reviewed applicable logs,
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conducted discussions with control room operators, and observed shift turnovers. The inspector verified operability of selected emergency systems, reviewed equipment control records, and verified the proper
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Tours of the auxiliary i
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a building, turbine building and external areas of the plant were conducted to observe plant equipment conditions, including potential fire hazards, and to verify that maintenance work requests had been initiated for equipment in need of maintenance.
Delays in completing the Unit ? refueling outage during this inspection period were primarily in the area of reactor coolant pump (RCP) seal problems. The first occurrence on October 24 was with No. 21 RCP seal leakage being too high which resulted in replacing the seal assembly.
The second instance on October 29 was with No. 22 RCP seal leakage being too low resulting in repairs to the seal assembly. Unit 2 subsequently achieved criticality on November 1 without further delays.
With Unit 2 critical and on line it was noted that the vibration amplitudes at the exciter end of the main generator (i.e., No nine bearing support)
were higher thar. recommended by the vendor. As a resul.t Unit 2 was powered down and the generator / exciter was rebalanced on November 24. This did not result in sufficient improvement in balance so a second balancing was successfully performed on December 8, 1985.
On October 13, 1985, during testing of the No. 22 diesel cooling water pump, the No. 121 motor driven cooling water pump auto started on low header pressure, caused by differences in the pumping characteristics.of No. 22 and No. 11 cooling water pumps.
On October 13, 1985, while switching from No. 11 diesel cooling water pump to No. 22 diesel cooling water pump a slightly lower header pressure caused the No. 121 motor driven cool og water pump to auto-start. The operator in the control room stopped No.121 thinking it had started on a momentary drop in header pressure. This condition of low header pressure in turn caused No. 12 diesel cooling water puinp to auto-start.
The operator then restarted No. 11 pump and stopped No J pump.
The cause of this event was low cooling water header pressure, caused by differences in the pumping characteristics of No.11 and No. 22 pumps, which caused the auto-start of No. 12 diesel cooling water pump. See Section 8(282/85022-01)
On October 16, 1985, during the monthly at-power inspection of Unit 1 containment, minct leakage was seen on the cooling water (BI) inlet pipe to No. 14 fan coil unit. The leak 3ge was coming from a circumferential 1" crack in the 2-1/2" diameter Schedule 40 pipe and was presumed to be caused by cyclic fatigue. A temporary patch was installed and repairs will be made during the next refueling citage in spring of 1986.
See Section 8 (282/85022-02)
On December 2,1985, the A.C. input breaker to No.13 inverter was found in the tripped position.
In this condition, power to the inverter was being supplied by the station batteries rather than from the nonnal A.C.
source. The input breaker was reset, thus restoring the normal supply.
(Inverters 'are installed to provide a reliable source of regulated 120v.
A.C.forimportantstationinstruments). On December 5, No. 16 inverter
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i tripped off as a result of electrical disturbances in the instrument load. While returning the inverter to service, a switching error resulted in momentary loss (a few seconds) of all A.C. to certain instruments.
Some feedwater heater instabilities resulted from this but were quickly damped out.
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Maintenance Observation'(62703)
Station maintenance activities on safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides, and industry codes or standards and in conformance with Technical Specifications.
The following items were considered during this review: the limiting condi-tions for operation were met while components or systems were removed
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from service, approvals were obtained prior to initiating the work, activities were accomplished using approved procedures and were inspected as applicable, functional testing and/or calibrations were performed prior to returning components or systems to service, quality control records were maintained, activities were accomplished by qualified personnel, radiological controls were implemented, and fire prevention centrols were implemented.
Portions of the following maintenance activities were observed / reviewed during the inspection period:
No. 22 Diesel cooling water pump preventive maintenance (PM)
No. 12 Diesel cooling water pump heat exchanger repair No violations or deviations were identified.
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Surveillance (61726)
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The inspector witnessed portions of surveillance testing of safety-related systems and components. The-inspection included verifying that the tests were scheduled and performed within Technical Specification requirements, observin7 that procedures were being followed by qualified operators, that Limiting Conditions for Operation (LCOs) were not violated, that system and equipment restoration was completed, and that test results were acceptable to test and Technical Specification requirements.
Portions of the following surveillances were observed / reviewed during the inspection period:
SP 1637 - cold weather preparations SP 2102 - No. 22 turbine-driven auxiliary feedwater pump test SP 2035 protection logic tests D30
- zero power physics testing
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'No violations or deviations were identified.
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6.
Facility Modifications (37700, 37701)
See previous inspection reports for Prairie island, 50-282/85014(DRP);
50-306/85011(DRP) and 50-282/85016(DRP); 50-306/85013(DRP).
The Operations Committee (OC) met on October 21 to review the investigative report of the breaker 12M trip on October 1.
The OC had many comments and suggestions on the report's recommendations for prevention of similar events.
Further management attention will be given to these recommendations. The unresolved item will remain open until the specific corrective actions become better defined.
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Meeting with Corporate Management (30702)
On October 22, 1985, the senior resident inspector met with the following NSP people in corporate headquarters:
K. Albrecht - Director, Power Supply QA D. Musolf - Manager, Nuclear Support Services G. Hudson - Administrator, Nuclear Security Services E. Stewart - Investigator, Loss Prevention Analysis S. Northard - Sr. Nuclear Program Consultant M. Anderson - Materials and Special Processes Engineer L. Dahlman - Materials and Special Processes Specialist Discussions were held on the subjects of the operation of the Prairie Island plant and the NRC inspection program.
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Licensee Event Reports Followup (92700)
Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specifications:
(0 pen) 282/85022-01 Inadvertent start of No.12 diesel cooling water pump (0 pen) 282/85022-02 Cooling water leak in containment 9.
Exit Interview (30703)
The inspectors met with licensee representatives denoted in Paragraph 1 at the conclusion of the inspection on December 9, 1985. The inspectors discussed the purpose and scope of the inspection and the findings.
The inspectors also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any
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document / processes as proprietary.
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