IR 05000282/1979014
| ML19249C570 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/12/1979 |
| From: | Feirabend C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19249C569 | List: |
| References | |
| 50-282-79-14, 50-306-79-11, NUDOCS 7909130391 | |
| Download: ML19249C570 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
, REGION III Report No.:
50-282/79-14; 50-306/79-11 Docket No.:
50-282; 50-306 License No.:
Northern States Power Company
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414 Nicollet Mall
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Minneapolis, MN 55401 Facility Name:
Prairie Island Nuclear Plant, Units 1 and 2 Inspection At:
Red Wing, MN Inspection Conducted: June 1-30, 1979 RFO) %
Inspector:
C. D. Feierabend 7-/2-SIj'
Date RFU)J
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Approved By:
R. F. Warnick, Chief, Reactor 9F-f i
,'9 Projects Section 2 Date Inspection Summary Inspection on June 1-30, 1979 (Report No. 50-282/79-14; 50-306/79-11 Areas Inspected:
Routine resident inspection of plant operations, maintenance, security, calibration, radiation protection, radioactive vaste system, followup of licensee reported events, IE bulletins and previously identified items of nonccmpliance. The inspection involved 87 inspector-hours onsite by the resident inspector.
Results: No items of noncompliance or deviations were identified.
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32sade 7 909130 2f9I
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DETAILS 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, Staff Engineer
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R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, Maintenance J. Hoffman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, R 'iation Protection M. Sellman, Senior Nuclear Engi R. Warren, Office Sunar.isor K. Albrecht, Quality Assurance Engineer G. Sundberg, Instrument Engineer J. Lyons, Chief Electrician M. Mulhausen, Maintenance Supervisor W. Phillips, Maintenance Supervisor D. Crago, Shif t Supervisor G. Edon, Shift Supervisor P. Ryan, Shift Supervisor P. Valtakis, Shift Supervisor R. Held, Shift Supervisor
J. Meath, Shift Supervisor D. Walker, Shift Supervisor 2.
Licensee Action on Previous Inspection Findings (Closed)
Noncompliance (282/79-08; 306/79-07) Delayed fire system surveillance test.
The inspector verified that surveillance test SP 1189 had been completed and that the tests had been included in the computerized schedule.
3.
Organization and Administration Mr.K.AlbrechtwasselectedtobetheQualityAssurance{gA)
Engineer to replace Mr. J. Leveille who recently resigned:
Mr.
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Albrecht was a member of the plant technical craff from June, 1973 through May,1978 and held a Senior Reactor Ope) ator (SRO) license for Prairie Island.
Discussions with Mr. Albrecht and plant management personnel indicate that Mr. Albrecht will be scheduled for additional QA training as soon as is feasible.
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-- IE Inspection Report Nos. 50-282/79-13; 50-306/79-11.
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4.
Plant Operations Unit 1 shut down on June 8 for scheduled maintenance and to conduct volumetric examination 'of feedwater nozzles.
Evaluation by the licensee and an authorized inspector in accordance with Section XI of the ASME Boiler and Pressure Vessel Code determined that the feedwater nozzle to pipe welds were satisfactory.
The unit was restarted on June 12 and operated at power for the balance of the month.
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The FW lines experienced some water hammer during draindown of the system in preparation for Radiographic testing.
As the water level dropped below the feed ring, water hammer was audible in the plant.
Water level was then slowly increased to a level that would cover the feed ring and the water hammer ceased.
Both the shif t supervisor and the systems engineer walked down the system inspecting for any sign of damage, such as displaced hangers, insultation, etc.
No damage was observed.
The resident inspector also inspected the accessible pipe, components, hangers and snubbers in the auxiliary building and found no evidence of damage.
Unit 2 experienced a ground in a feedwater pump motor on June 3, during restart in conjunction with load following operation.
The pump motor was removed, shipped to the manufacturer for rebuilding and was reinstalled on June 19th.
The plant returned to full power and continued load following operation for the balance of the month.
The inspector reviewed plant operations including examination of selected operating logs, special orders, temporary memos, j umper and tagout logs for the month of March.
Tours of the plant included walks through the various areas of the plant to observe operations and activities in progress, to inspect the status of monitoring instrumcats, to observe for adherence to radiation controls and fire protection rules, to check proper alignment of selected valves and equipment controls, and to review the status of various alarmed annunciators with operators.
The inspector also reviewed annunciator status, recorder charts, surveillance records, and logs to verify that plant operations were maintained in accordance with Technical Specification requirements.
One omission of an appropriate entry for the Unit 1 operator log was noted during review of preventive maintenance performed on the diesel fire pump on June 25, 1979.
The required review and approvals and documentation of removal from and restoration to service were documented on the work request authorization, but removal from service had not been entered in the Unit 1 log.
A late entry in
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the log was made on June 26, and the shift supervisor and operator involved were counseled by licensee supervision concerning log requirements.
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The inspector performed an independent verification of portions of
the station and instrument air prestart value checklist.
No items of noncompliance or deviations were identified.
5.
Maintenance The inspector reviewed several work requests (WR's) and work request authorizations (WRA's) and verified that all required reviews and approvals had been completed.
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The inspector witnessed maintenance activities during scheduled maintenance being performed on a diesel generator, replacement of a feedwater pump motor and annual preventive maintenance of the diesel fire pump.
No items of noncompliance or deviations were identified.
6.
Security The inspector conducted periodic observations of access control.
issuing badges, vehicle inspection, escorting, and communication checks. The inspector observed special precautions implemented during possibility of demonstrations in the area.
No items of noncompliance or deviations were identified.
7.
Calibration The inspector received the licensee's procedure SWlI&C T1-1, Rev.
3, Test Instrument Calibration Control, and verified that the following primary standards had been calibrated as required and are traceable to the National Bureau of Standards.
a.
Mancfield and Green Deadweight Tester No. PI-l b.
Hewlett Packard VM/DC Standard No. PI-41 c.
Hewlett Packard Electronic Counter No. PI-48 The inspector observed that the resistance standards PI Nos. 301, 302, 303, 304 and 305 were due for calibration and had been removed from service to be sent out for calibration.
No items of noncompliance or deviations were identified.
6.
Licensee Event Reports (LER's)
The inspector reviewed the following LER's submitted by the license.e, determined that reporting requirements had been met, and that corrective actions appeared appropriate.
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a.
P-RO-79-06 pressurizer level and steam line pressure transmitter drift (open).
b.
P-RO-79-09 possible SAR nonconservatism.
(This was in conjunction with review of IEB'79-06A.
Closed)
c.
P-RO-79-10 valve failure to respond (closed).
d.
P-RO-79-ll Unit 2 operation with one source of offsite power (open).
P-RO-79-12 increased rod bow (previously observed and reported 2/
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e.
closed).
f.
P-RO-79-14 loading pattern error (closed).
9.
Radiation Protection The inspector examined radiation protection instruments in use on June 13, 1979 including area monitors, air sampler, continuous air monitors and portable survey instruments (friskers) at various locations within the auxiliary building.
The two containment vessel area monitors, 1-R-2 for Unit 1 and 2-R-2 for Unit 2 remain out of service awaiting connectors and a special tool for installing a connection of the signal cable at the vessel penetration.
The inspector observed work in progress in areas requiring radiation werk permits and observed radiation area posting and controls in several work areas in the auxiliary building.
The inspector observed and participated in the licensee's whole body counting program for internal exposure monitoring.
No items of noncompliance or deviations were identified.
10.
Radioactive Waste Systems The inspector reviewed records for all liquid and gaseous releases for the week of June 3-9, 1979, verified that the required samples and approvals were obtained and that they were performed in accordance with approved procedures. The documentation included verification that effluent release control instrumentation was operable.
No items of noncompliance or deviations were identified.
11.
IE Bulletins IEB 79-02 Pipe Support Base Plate Designs Using Concrete a.
Expansion Anchor Bolts.
The inspector participated in discussions involving preparations for performing the necessary evaluations and testing and observed demonstrations of the test equipment.
By the end of 2/
- IE Region III Inspection Report No. 050-282/79-11.
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June the licensee had pull tested a total of 215 anchors
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selected from several systems in both units.
No failures were identified. Testing is continuing and the licensee plans to report the results in accordance with the bulletin.
b.
IEB 79-13 Cracking in Feedwater System Piping.
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The licensee was verbally informed of gpe potential problem by the resident inspector and by a letter-from NRR, which requested information on feedwater lines.
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The licensee elected to shut down Unit 1 on June 8, 1979 to perform volumetric examination of the feedwater nozzle to pipe wc] ds. No cracks were identified.
The licensee will forward a written report of the results of the examination in accordance with the bulletin.
Based on the results of the Unit 1 examination, the licensee has scheduled an examination of Unit 2 for the next refueling outage, but will complete the inspection sooner if an unscheduled outage of sufficient duration occurs.
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12.
Exit Interviews The inspector attended exit interviews conducted by IE III regional based inspectors.
a.
L. G. Galagher - June 28, 1979.
b.
J. S. Belanger - June 29, 1979.
The inspector conducted an exit interview with Mr. Tierney each weekend at the conclusion of the inspection. The inspector sumsarized the scope and findings of the inspection and stated that no items of noncompliance or deviations were identified.
Attachment:
Preliminary Inspection Findings S Ltr V. Stello, NRR to all PWR's, dtd 5/25/79.
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OFFICE OF INSPECTION AND ENFORCEMEn
PRELIMINARY INSPECTION FINDINGS l'
1.
LICENSEE 2.
REGIONAL OFFICE
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Northern States Power Company U.S. Nuclear Regulatory Commission 414 Nicollet Mall Office of Inspection & Enforcement, RIII Minneapolis, MN 55401 799 Roosevelt Road ;.
Glen Ellyn, IL 60137 Prairie Island 1 (Red W ng, MN)
i Prairie Island 2 (Red Wing, MN)
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DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION
_ { j f f/ 7 50-282; 50-306 DPR-42: DPR 60
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6.
Within the scope of the inspection, no items of noncer fance or deviation were found.
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The following matters are preliminary inspection findings:
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8.
These preliminary inspection findings will be reviewed by NRC Supervision /
Hanagement at the Region III Office and they will correspond with you concerning any enforcement action.
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Nuclear Regulatory Commission Inspector W. ?Wik
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OFFICE OF INSPECTION AND ENFORCEy.E.vr
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PRELIMINARY INSPECTION FINDINGS
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1.
LICENSEE 2.
REGIONAL OFFICE
Northern States Power Company U.S. Nuclear Regulatory Commission 414 Nicollet M ll Office of Inspection & Enforcement RIII Minneapolis, MN 55401 799 Roosevelt Road len llyn, 60157 Prairie Island 1 (Redwing, MN)
Prairie Island 2 (Redwing, MN)
3.
DOCKET NLHBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION 50-282; 50-306 DPR-42: DPR 60 p_ fj p
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6.
Within the scope of the irspection, no items of nondd pliance or deviation were found.
7.
The following matters are preliminary inspection findings:
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8.
These preliminary inspection findings vill be reviewed by NRC Supervision /
Management at the Region III Office and they will correspond with you
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concerning any enforcement action.
-a Nuclear R du'latory Commission :nspector
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PRELIMINARY INSPECTION FINDINOS
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1.
LICESSEE 2.
RCC10NAL 0FFICE Northern States Power Company U.S. Nuclear Regulatory Co==ission 414 Nicollet Mall Office of Inspection & Enforcement, R!II Minneapolis,10: 55401 799 Roosevelt Road Glen Ellyn, IL 60 m Prairie Island 1 (Redwing, 10,')
Prairic Island 2 (Redwing, MN)
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3.
DOCKET NUM3ERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION
[-2f/f7p 50-282; 50-306 DPR-42: DPR 60 (/
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6.
Within the scope of the inspection, no items of nonco=pliance or deviation were found.
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GQ 7.
The following =atters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC Supervision /
Management sL the Region III Offich and they will correspond with you
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concerning any enforcement action.
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Nuclear Regulatory Commission Inspector I.I"2'bObf
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PRELIMINARY INSPECTION FINDINGS
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1.
LICENSEE 2.
REGIONAL OFFICE Northern States Power Company U.S. Nuclear Regulatory Commission 414 Nicollet Mall Office of Inspection & Enforcement, R!!I Minneapolis, MN 55401 799 Roosevelt Road
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Glen Ellyn, IL 60137 Prairie Island 1 (Redwing, MN)
Prairie Island 2 (Redwing, MN)
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DCCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION 50-282; 50-306 DPR-42: DPR 60 y -p jp77 F
6.
Within the scope of the inspection, no items of non ompliance or deviation were found.
7.
The following catters are preliminary inspection findings:
S.
These preliminary inspection findings will be reviewed by NRC Supervision /
Management. nL t.he Region 111 Office and they Will C0ffesp06d With you
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concerning any enforcement action.
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Nuclear Re;(ulatory Commission Inspector us3@