IR 05000282/1979011
| ML19254A698 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/29/1979 |
| From: | Daniels F, Feierabend C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19254A694 | List: |
| References | |
| 50-282-79-11, NUDOCS 7907240200 | |
| Download: ML19254A698 (9) | |
Text
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U.S. WUCI. EAR REGUI.ATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-282/79-11; 50-306/79-09 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, Units 1 and 2 Inspection At:
Prairie Island Site, Red Wing, MN Inspection Conducted: April 1-30, 1979 R F U) Fvr Inspectors:
C. D. Feierabend
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Approved By:
R. F. Warnick, Chief SI-2 7-79 Reactor Projects Section, 2 In_spection Summary In_spection on April 1-30, 1979 (Report No. 50-282/79-11; 50-306 79-09)
Areas Inspected:
Routine resident inspection of operations, main-tenance, security, Unit I refueling activities, review and audit, training and followup reportable events and IE Bulletins.
The inspection involved 108 inspector-hours by the resident inspector and 36 inspector-hours by one regional based inspector.
Results:
No items of noncompliance or deviations 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, Staff Engineer R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, Maintenance J. Hoffman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiation Protection S. Fehn, Senior Scheduling Enginee-M. Sellman, Senior Nuclear Engineer M. Klee, Nuclear Engineer S. Northard, Nuclear Engineer J. Leveille, Quality Assurance Engineer G. Sundberg, Instrument Engineer W. Phillips, Maintenance Supervisor D. Crago, Shift Supervisor G. Edon, Shift Supervisor P. Ryan, Shif t Supervisor M. Balk, Shift Supervisor R. Flack, Shift Supervisor J. Heath, Shift Supervisor D. Walker, Shift Supervisor 2.
General Unit 2 operated at power throughout the month.
Unit 1 was shutdown on April 6 for scheduled refueling and maintenance.
Tne inspector accompanied the state governor and members of his staff on a tour of the facility on April 18.
Restart of Unit I was delayed for approximately 5 days due to an error in the fuel loading pattern supplied by the vendor.
Rearrangement of the fuel elements to the appropriate pattern was completed on April 30.
The licensee notified RI3I and will submit an event report.
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3.
Plant Operations.-
The inspector reviewed plant operations including examination of selected operating logs, special orders, tempora ry memos,
jumper and tagout logs for the month of April.
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 instruments, to observe f or adherence to radiation centrols 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.
No items of noncompliance or deviations were identified.
4.
Maintenance The inspector reviewed several work requests (WR's) and work request authorization (WRA's) and verified that all required reviews and approvals had been completed.
Observation of maintenance work in progress included cleaning of reactor vessel studs and flange surfaces, installing portions of part length control rod drive modifications, and reinstalling fan coil unit dampers.
5.
Security The inspector conducted periodic observations of access control, issuing badges, vehicle inupection, escorting, and communication checks.
No items of noncompliance or deviations were identified.
6.
Refueling Activities - Unit 1 The inspector observed reactor shutdown and a portion of the turbine overspeed test at the beginning of the refueling outage.
During the refueling outage the inspector observed work in progress in the areas of a.
Removing and cleaning reactor vessel studs; b.
Removing reactor vessel head and placing in storage location;
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c.
Part length control rcd drive modification; d.
Ultrasonic testing of reactor coolant pipe welds; e.
Removal of a nuclear instrument power range detector; f.
Unlatching full length control rod drive mechanisms; g.
Removal of the reactor upper internals; and h.
Installation of cooling water piping to control rod drive cooling modifications.
No areas of concern were identified.
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7.
Fuel llandling - Unit 1 The inspector reviewed the licensees procedure and verified that prefueling surveillance tests had been completed prior to start of fuel movements. These included:
a.
All Technical Specification requirements b.
Refueling machine operation and indexing Ventilation requirement in fuel storage areas c.
d.
Refueling interlocks e.
Crane testing f.
Refueling deck radiation monitors g.
Communication systems h.
Cooling capabilities for stored fuel i.
Refueling integrity checklist The licensee identified fuel rod bowing greater than seen on previously discharged assemblies.
The inspector viewed the bowed rods during preparations for videotaping to determine the extent of bowing for analysis by the fuel manufacture. The licensee has notified RIII and will submit an event report within 14 days.
8.
Review and Audit The inspector attended an Operations Committee meeting on April 13.
The committee approved changes to emergency pro-cedures E-1, Safety Injection Initiation, and E-4, Recovery Procedure for Steam Generator Tube Rupture.
The changes incorporated additional guidance for maintaining RCS system pressure above saturation pressure and for isolating any power operated relief va;ves that may not have fully closed.
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The reviewsanda[provalswereconductedinaccordancewith Technical Specification requirements. No areas of concern were identified.
9.
Training On April 20th the inspector attended a training session con-ducted by NRC for all operators, engineers and supervisory personnel.
All except one non-licensed operator attended one of the three sessions. The licensee training supervisor scheduled makcup training for those who had not attended, utilizing tapes made during the NRC sessions.
The inspector attended a licensee training session conducted for personnel that may wear respirators while working in the plant. The instruction and leak testing of masks on each individual were well presented.
No areas of concern were identified.
10.
IE Bulletins IEB 79-06A dated April 14, 1979 including Revision No.
1, a.
dated.\\pril 18, 1979.
The it.spector reviewed the licensee's response 1/ and verified that the actions of placing all Unit 2 low level inputs for S1 initiation in trip had been completed on April 26.
Unit I remained shut down and is scheduled for completion of a design change prior to startup. The change to the SI initiation logic will provide two-of-three low pressurizer pressure actuation and will remove the pressurizer level inputs from the logic.
b.
IEB 79-09 dated April 17, 1979, Failure of GE Type AK Circuit Breakers (Closed).
The licensee does not have this type circuit breaker installed or planned.
The licensee's response to the bulletin will be forwarded as requested.
11.
Licensee Event Reports (LER's)
The inspector reviewed the following LER's submitted by the licensee, determined that reporting requirements had been met, and that corrective actions appeared appropriate.
(Closed)
1/
NSP Letter to Region III, Response to IE Bulletin No.79-06A -
Revision 1, dated April 30, 1979.
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P-RO-79-02 Ipoperability of No. 22 Diesel Cooling Water a.
Pump.
b.
P-RO-79-03 Missed Surveillance Test.
12.
Exit Interview The inspector conducted an exit interview with Mr. Tierney at the conclusion of the inspection.
The inspector discussed the scope and results of the inspection and stated that no items of noncompliance or deviations were identified.
Attachment:
Preliminary Inspection Findings-6-
- OFFICE OF INSPECTION AND ENFORCE"ENT
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PREII':INARY INSPECTION FINDISCS
!
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I 1.
LICENSEE 2.
REGIONAL OFFICE Northern States Power Company U.S. Nuclear Regulatory Commission 414 Nicollet Mall Office of Inspection 6 Enforcement, RIII flinneapolis. PJi 55401 799 Roosevelt Road (Red W ng, MN)
Glen Ellyn, IL 60137 Prairie Island I i
Prairie Island 2 (Red Wing, M'O 3.
DOCKET NUMEERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION g / _ g[7c 50-282; 50-306 DPR-42: DPR 60 T32 6.
Within the scope of the inspection, no items of noncompliance or deviation A*
were found.
7.
The following matters are preliminary inspection findings:
i 8.
These preliminary inspection findings will be reviewed by NRC Supervision /
Management at the Region III Office and they will correspond with you concerning any enforcement action.
.
(
f s
Nuclear /hegulatory Commidsion Inspector
.
OFFICE OF INS?ECTION AND ENFORCEME:0
.
PRELIMINARY INSPECTION FINDINCS I
.
1.
LICENSEE 2.
REGIONAL OFFICE Northern States Power Company U.S. Nuclear Regulatory Connission 414 Nicollet Mall Office of Inspection 6 Enforcenent, PI Mianeapolis, M?; 35401 799 Roosevelt Road Glen Ellyn, IL 60137 (Red W ng, MN)
Prairie Island I i
Prairie Island 2 (f(ed Wing, MN)
3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
D TE OF INSPECTION g g _J(jgp 50-282; 50-306 DPR-42: DPR 60 6.
k'ithin the scope of the inspection, no items of noncompliance or deviation were found.
7.
The following catters are preliminary inspection findings:
8.
These preliminary inspection findings will be reviewed by NRC Supervision /
Management at the Region III Office and they will correspond with you concerning any enforcement action
.
/
Nuclear R(gulatory Commissio'n Inspector
i
,
OFFICE OF INSPECTION AND ENTORCEME.'.:
.
PRELIMINARY INSPECTIO:; FINDINGS I
1.
LICENSEE 2.
REGIONAL OFFICE Northern States Power Company U.S. Nuclear Regulatory Commission 414 Nicollet Mall Office of Inspectien & Enforcement, RIII
!!inneapolis,
!".
55401 799 Roosevelt Road Glen Ellyn, IL 60137 (Red W ng, MN)
l Prairie Island I i
Prairie Island 2 (Red Wing, MN)
3.
DOCKET NUMSERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION 50-282; 50-306 DPR-42: DPR 60 7/ - Jo
y 6.
Within the scope of the inspection, no items of noncorpliance or deviation
<
were found.
7.
The following matters are preliminary inspection findings:
8.
These preliminary inspection findings will be reviewed by NRC Supervision /
Management at the Region III Office and they will correspond with you concerning any enforcement action.
- e N
NuclearR[gulatoryCow.ission\\ Inspector