IR 05000282/1985010

Insp Repts 50-282/85-10 & 50-306/85-08 on 850414-0608.No Violation Noted.Major Areas Inspected:Previous Insp Findings,Plant Operational Safety,Maint,Part 21 Repts,Lers, Regional Requests & App R Work

ML20127P495
Person / Time
Site:	Prairie Island
Issue date:	06/26/1985
From:	Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20127P477	List: IR 05000282/1985010 ML20127P471
References
50-282-85-10, 50-306-85-08, 50-306-85-8, NUDOCS 8507020433
Download: ML20127P495 (6)

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NUCLEAR REGULATORY COMMISSION

REGION III

Report Nos. 50-282/85010(DRP); 50-306/85008(DRP)

Docket Nos. 50-282; 50-306 Licenses 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: April 14 through June 8, 1985 Inspectors: J. E. Hard P. L. Hartmann hkbug2M h Approved By: I. N. Jackiw, Chief (o/OG/8'5'

Reactor Projects Section 28 Date Inspection Summary Inspection on April 14, 1985 through June 8, 1985 (Report Nos. 50-282/85010(DRP);

50-306/85008(DRP))

Areas Inspected: Routine, unannounced inspection by resident inspectors of previous inspection findings, plant operational safety, maintenance, surveillance, regional requests, meetings with corporate management, Part 21 report, Appendix R work, and followup of Licensee Event Reports. The inspection involved a total of 368 inspector-hours by two NRC inspectors including 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> onsite during off-shift Results: No violations were identified in the nine areas inspecte PDR ADOCK 05000282 l

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O DETAILS Persons Contacted

• E. Watzl, Plant Manager

• D. 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

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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 The inspectors interviewed other licensee employees, including members of the technical and engineering staffs, shift supervisors, reactor and auxiliary operators, QA personnel, and Shift Technical Advisor * Denotes those present at the exit interview.

4 Licensee Action on Previous Inspection Findings (Closed) Open Item (282/84-18-01(DRP)): Resolution to toxic gas monitor requirements. The licensee received a reply from NRR in a letter dated March 4, 1985. NRR concluded there was no need to maintain the toxic gas (ammonia, hydrochloric and formaldehyde) monitors operable. NRR required training of operators for identification of the gases and corrective action for their presenc The inspector attended one training session, reviewed revised emergency procedure F-6 Section 7.0,

" Toxic Gases in the Control Room" and verified all operations shifts received the required trainin . Operational Safety Verification

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Unit 1 operation was continuous during the period except for an unplanned outage on May 8,1985 which resulted from an instrument air line failure (discussed further below). Unit 2 operation was continuous and at full power for essentially the entire perio The inspector observed control room operations, reviewed applicable logs, 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 return to service of affected component Tours of the auxiliary 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 maintenanc .. . _

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The inspector performed a walkdown of the station battery system in conjunction with the special inspection requested in the C. E. Norelius memo of March 25, 1985 (Discussed in paragraph 6).

At 1:26 p.m. on May 8,1985, Unit 1 tripped on low level in steam generator 12. This was the result of failure of a 2-inch instrument air line which caused the main feedwater valves to shut. The air line was

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repaired, inspected and strengthened where necessary. Reactor operation was resumed at 1:45 p.m. on May 9 but subsequently tripped on low steam generator level at 2:21 p.m. because of feedwater instability problems.

, The reactor was restarted at 4:55 p.m. and paralleled to the grid at 6:47 p.m. Unit 1 operation has been continuous since that time.

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At 2:15 p.m. on April 30, 1985, with both units at full power the #11 TDAFW pump tripped on overspeed during a monthly surveillance tes Sticking of the steam control valve was determined to be the proble The valve stem was lubricated and the pump was retested satisfactorily and returned to service at 4:15 At 8:09 a.m. on May 21,1985 the D-1 diesel generator tripped at the end of its surveillance test while oil was being manually added to the crankcase. The trip was the result of adding the wrong oil which was contaminated with water and caused the crankcase pressure to rise to the trip point. The problem was identified, corrective action taken and the generator declared operable at 1:17 p.m. on May 22. Licensee actions to prevent further diesel generator trips from this cause will be followcd by the inspector. This is an Open Item. (50-282/85010-1(DRP)).

On May 14, 1985, the inspector participated as an observer of portions of the annual emergency exercise and attended the exit meeting on May 15.

! No violations or deviations were identified.

Maintenance Observation l 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 Specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service, approvcls 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 controls were implemente ~_ - . . _ _ -

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Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may affect system performanc Portions of the following maintenance activities were observed / reviewed

during the inspection period

12 Diesel Cooling Water Pump - Semi-annual inspection

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D-1 Diesel Generator - Investigation and correction of high crankcase pressur Auxiliary Building. Ventilation Damper 34035 - Correction of incorrectly installed actuato No violations or deviations were identifie . Surveillance 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, observing 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 requirement Portions of the following surveillances were observed / reviewed during the inspection period:

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STP 1007 Nuclear Instrument System Power Range Functional Test STP 1032 Safeguards Logic Test l SP 1093 Diesel Generator Functional Test

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SP 2003 Analog Protection Functional Test SP 2093 Diesel Generator Functional Test

SP 2096 Station Battery Monthly Test No violations or deviations were identifie . Regional Requests By memo dated March 25, 1985, C. E. Norelius requested all Senior

, Resident Inspectors to conduct a special inspection in the area of

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station battery operation and maintenance. During the inspection a

! discrepancy was found between the Battery Inspection Hints attached to the memo and the battery vendor's manual. Specifically, the

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Battery Inspection Hints refer to a proper spacing between cell and rack of 1/8 inch to one inch. However, the vendor's manual specifies a spacing which is proper if a sheet of paper can slip between cell and rack. Other than this item, battery operation and maintenance practices are within the memo guidelines and are otherwise acceptabl By memo dated April 18, 1985, C. E. Norelius requested all Senior Resident Inspectors to gather information in response to Temporary Instruction 2515/67, Survey of Licensees Response to Selected Items. The inspector reviewed the licensee response to INP0 50ERs 84-2 and 84-3, and IE Information Notices 83-75 and 84-06. The information obtained was supplied to Region III managemen No violations or deviations were identifie . Meeting with Corporate Management On May 10, 1985, the inspectors met with the following people:

D. McCarthy - Chairman of the Board B. Richard - President D. Gilberts - Sr. Vice President, Power Supply C. Larson - Vice President, Nuclear Generation G. Neils - General Manager, Headquarters Nuclear Group F. Tierney - General Manager, Nuclear Engineering and Construction P. Kamman - Superintendent, Nuclear Operations QA P. Suleski - Superintendent, Nuclear Projects QA On May 30, 1985, the inspector mat with the following people:

D. McCarthy - Chairman of Ll.e Board G. Neils - General Manager, Headquarters Nuclear Group K. Albrecht - Director, Power Supply Quality Assurance E. Eckholt - Sr. Engineer, Nuclear Safety and Technical Services Discussions were held on the subjects of the NRC inspection program and operation of the Prairie Island Plan . Part 21 Report In an April 15, 1985 letter to NSP, Chicago Tube and Iron (CT&I) trans-mitted Part 21 notifications that CT&I had received from their suppliers Hub, Inc. and Phoenix Steel Corporation. The problem related to the identification of a small length (21'7") of 8" Schedule 120 pipe as being Schedule 160. Reanalysis of the support constructed of this pipe was done by Teledyne Engineering Services who concluded that Schedule 120 pipe was adequate for the servic No violations or deviations were identified.

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. Appendix R Modifications Extenstve 10 CFR 50 Appendix R work has been in progress since about the first of the year. This work involves the wrapping of cable trays and conduic,s in certain fire areas with an approved one-hour fire barrie The licensee had originally committed to finishing the work by June 1, 1985, however, by May 31, the work was only about 94% complet In a conference call to NRR on May 31, the licensee revised their commitment to completion of Appendix R wrapping by June 15. As of June 8, the work was essentially completed. Followup information will be provided in the next inspection repor No violations or deviations were identifie . Licensee Event Reports Followup 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 Specification (Closed) 282/85-07 Inadvertent Start of One Component Cooling Pump (Closed) 282/85-08 Operation Above Licensed Power Level (Closed) 306/85-02 Control Switch for One Diesel Cooling Water Pump Found in Manual No violations or deviations were identifie . Open Items Open items are matters which have been discussed with the licensee which will be reviewed further by the inspectors, and which involve some action on the part of the NRC or licensee or both. Open items disclosed during the inspection are discussed in paragraph 3 and . Exit Interview The inspector met with licensee representatives denoted in Paragraph 1 at the conclusion of the inspection on June 10, 1985. The inspector discussed the purpose and scope of the inspection and the finding The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the

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inspector during the inspection. The licensee did not identify any

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documents / processes as proprietary.

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