IR 05000282/1981002
| ML19350B002 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/11/1981 |
| From: | Burgess B, Feierabend C, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19350A997 | List: |
| References | |
| 50-282-81-02, 50-282-81-2, 50-306-81-02, 50-306-81-2, NUDOCS 8103190058 | |
| Download: ML19350B002 (6) | |
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U.S. NUCLEAR REGULATORY COFDtISSION OFFICE OF INSPECTION AND ENFORCEMENT l
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REGION III
f Report No:
50-282/81-02; 50-306/81-02 Docket No:
50-282; 50-306 License No: DPR-42; DPR-60 i
Licensee:
Northern States Power Company l
414 Nicollet Mall
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Minneapolis, MN 55401 Feellity Name:
Prairie Island Nuclear Generating Plant inspection At:
Prairie Island Site, Red Wing, MN.
Inspection Conducted: January 1-31, 1981
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Inspectors:
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C. D. Feierabend pLbr$
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B. L. Burgess
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Approved By:
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ttle, Chief Reactor Projects Section 2
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Inspection' Summary Inspection' on' January 1-31, 1981 (Report No. 50-282/81-02; 50-306/81-02)
Areas Inspected: Routine Resident inspection of plant operation, mainten-
.-ance, surveillcnce, security, radiation protection, followup on IE Bull-etins, review of procedures and followup on licensee event reports. The inspection involved 145 inspection hours onsite by two NRC inspectors
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including 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> onsite during offshifts.
Results:
No items of noncompliance or deviation were identified.
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DETAllS
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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. Hoff=an, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiation Protection M. Klee, Superintendent, Nuclear Engineering K. Albrecht, Senior Quality Assurance Engineer G. Lenertz, Engineer D. Brown, Engineer D. Stenber, Engineer G. Miller, Engineer G. Sabaitis, Responsible Engineer W. Cauger, Instrunent Supervisor D. Svenson, Instrurent and Control Coordinator D. Cragoe, Shift Supervisor G. Edon, Shif t Supervisor P. Ryan, Shift Supervisor M. Balk, Shif t Supervisor P. Valtakis, Shift Supervisor 2.
Operacional Safety Verification a.
General Units 1 and 2 operated routinely throughout the conth.
A Team of NRR Examiners conducted Operator License Exacinatiens onsite from January 20-23, 1981.
b.
Control Room Observations The inspector observed control roo= operations, reviewed applicable logs, conducted discussions with control room operators and observed shift tu rnovers. The inspector verified the operability of selected ecergency syste. s, reviewed equiptent control records, and verified proper return to service of affected cocponents.
c.
Tours Tours of the auxiliary, turbine and containnent buildings, and external areas were conducted to observe plant equip =ent cenditions, including potential fire hazards, and to verify that caintenance requests had been initiated for equipeent in need of =aintenance.
By observation and direct interview, the inspector verified that-1-
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k 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.
d.
Independent Verification The inspector performed a walkdown of the accessible esrtions of the radiation monitoring system. This included confirmation of selected portions of the licensee's procedures, checklists, and plant drawings, inspection of condition of components, inspection of instrument panels and cabinets, and verification of selected instruments for proper valving.
3.
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 verify that proper priorities were given and to verify that design changes were initiated where appropriate.
1.)
WRA D6650-WL-Q and WRA D6645-WL-Q were a portion of design change No. 80Y-125, Route of RHR Sump Pump Discharge to Containment. No items of concern were identified.
2.) WRA D6701-ZG-Q and WRA D6702-ZG-Q were a portion of design change No. 79Y-084, Fire Protection Modification.
These WRA's controlled installation of fire dampers in the control room air treatment system._ The inspector confirmed that the requirements of Technical Specification 3.13.C were met, i.e. operability of the redundant train was ade-quately demonstrated and that the system was again mada operable within the allowable 7 days. The system was demon-
.strated to be operable after completion of the WRA's, how-ever, the operability testing did not include measurement
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of system air flow, as the monthly requ'rement for operation
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does not include flow measurement.
SP-1185 - Control Room Special Ventilation Flow Verification was last performed on August 18, 1980,' demonstrating that the flow met T.S. 3.13.B.2 requirement of 4000 cfm i 10%.
'The inspector considers that 'a flow ve,rification test is required after the modification to demonstrate that the sys-tem flow has not been affected. The licensee will perform SP-1185'to. verify acceptable flows. This item remains un-
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resolved pending review of the test results.
3.)
WR E0317 - Calibration of Instrument for Control Room '
PAC Filter:No.122.
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I b.
Observations The inspectors observed work in progress:
(1) PM-3002-2 Diesel Cooling Water Pump Inspection (2) WR E0146 Loop A Feedwater Regulating Valve Control (3) WR E0136 Calibration of Instrument for Control Room PAC Filter No. 121.
4.
Surveillance-Thi inspector observed SP-1106A 12; Diesel Cooling Water Prmp Monthly Test. The test was satisfactory
- The inspector observed SP-1091 Containment Fan Coil Units Monthly ' Sur-veillance. Current measurements taken during the test exceeded test acceptance criteria. Acceptance criteria was based on preoperational test data vs measured current. The criteria did not include sufficient allowance for bus voltage variations. Evaluation by the electrical engineer and the chief electrician determined that the test results were acceptable. The licensee is reviewing the procedure to revise as necessary.
5.
IE' Bulletins-IEB 80-24 - Prevention of Damage Due to Water Leakage Inside Containment The inspectors reviewed the licensee response I/ o the bulletin and t
conducted initial inspections to determine the' status for detection
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and isolation of water leakage into containment.
The inspector visually inspected containment "A" sump pumps and alarms insitu.and verified that no water was visible in the Reactor Vessel Cavity Sump, sump "C".
The inspector reviewed results of test and calibration data of the sump pump control and sump-alarm switches and verified that appropriate-surveillance proceduresEwere being performed. For' sump "C" the licensee-has additionally implemented an alarm response procedure to pump the sump'and_to make'a_ containment' entry _to inspect for moisture.
The inspector-verified that a prompt report would be made whenever service water leaks were found in contaigyent.- The licensee also submitted a' supplement to their response-upon a request' by the
- inspectors for additional information.
f /l NSP ltr'to RIII response to'IE3 80-24 dtd January.5, 1981-
2/ LNSP.ltr;to RIII' supplemental response to IEB 80-24, dtd January,28,s 1981
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6.
Licensee Event Report Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to deter-mine that reportability requirements were fulfilled, immediate correc-ti t: action was accomplished, and corrective action ro prevent recur-rence had been accomplished in accordance with Technical Specifica-tions.
a.
P-RO-79-23 Design Deficiency, MD AFP Lockout Relay b.
P-RO-80-20 Loss of Offsite Power Due to Electrical Storm c.
P-RO-80-23 Missed Surveillance, Control Room Special Vent Flow Verification d.
P-RO-80-28 Control Switch for Fan Coil Unit Found in Manual e.
P-RO-80-32 Inoperability of No. 21 Cooling Water Pump f.
P-RO-80-35 Inoperability of Containment Spray Pump g.
P-RO-80-36 Inoperability of No. 12 Battery Charger 7.
Procedure,s -
The inspectors reviewed the licensee's procedures with respect to shut--
down of the reactor, related to addressing anticipated transient without scram.
(ATWS)
The licensee's administrative procedure ACD 5.3.1 - Prairie Island Plant Organization, assigns authority and responsibility to the operator for shutting down the reactor when operating parameters exceed the reactor protection' circuit setpoint and' automatic shutdown has not occurred.
The licensee's procedure E-27 - Failure of an RCCA Bank to Move ad-dresses inability to move or drive control rods.
TheLlicensee's procedure C1.7 - Reactor Trip provided response to reactcr trips, but did not address failure of trip actions to occur.
-The-licensee has initiated a change to procedure C1.7 to include addi-tional actions following failure to trip when required, including.
immediate-initiation ef emergency boration.
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I 8.
Exit Interviews The inspectors attended exit interviews conducted by RIII inspector, I. N. Jackiv on January 8,1981 and by J. Buzy, NRR Operator Licensing Branch on January 23, 1981.
The inspectors conducted interim interviews during the inspection period and met with Mr. k'atzl at the conclusion of the inpsection. The inspec-tors discussed the scope and results of the inspection.
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