ML19262B381
| ML19262B381 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/13/1979 |
| From: | Feierabend C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262B380 | List: |
| References | |
| 50-282-79-27, 50-306-79-21, NUDOCS 7912210074 | |
| Download: ML19262B381 (9) | |
See also: IR 05000282/1979027
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report Nos: 50-282/79-27; 50-306/79-21
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, Minnesota
Inspection Conducted: October 1-31, 1979
RftU pe,
Inspector:
C. D. Feierabend
//-/3- 7/
RFR)wk
Approved By:
R. F. Warnick, Chief,
//-/ 3 -79
Reactor Projects Section 2
Inspection Summay
Inspection on October 1-31, 1979 (Report No. 50-282/79-27; 50-306/79-21)
Areas Inspected: Routine resident inspection of plant operations, mainten-
ance, security, and observations of plant staff response to steam generator
tube rupture. The inspection involved 123 inspector-hours by the resident
-
inspector.
Results:
No items of noncompliance or deviations were identified.
2162 293
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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
R. Lindsey, Superintendent, Operations
J. Nelson, Superintendeat, Maintenance
J. Hoffman, Superintendent, Technical Engineering
D. Schuelke, Superintendent, Radiation Protection
S. Fehn, Senior Scheduling Engineer
G. Sundberg, Instrument Engineer
G. Edon, Shift Supervisor
P. Ryan, Shift Supervisor
M. Balk, Shift Supervisor
J. Meath, Shift Supervisor
D. Walker, Shift Supervisor
2.
General
Unit 2 operated routinely throughout the month.
Unit I was shut down
from October 2-23 to repair a ruptured steam generator tube. The licen-
see continued inspection and upgrading of pipe support base plates and
seismic design pipe supports in response to IE Bulletins IEB 79-02 and
IEB 79-14 during the outage.
3.
Steam Generator Tube Rupture
At approximately 2:45 p.m. on October 2, 1979 t!.e inspector heard
announcement of Unit I safety injection on the plant page and
proceeded immediately to the control room. The inspector was informed
that the apparent cause was a tube rupture in a steam generator.
The
inspector verified that the air ejector offgas monitor was offscale
(high) and that the pressurizer level and pressure had dropped (level
was offscale low). The inspector observed that a member of the plant
staff had the emergency procedure for steam generator tube rupture and
that automatic actions were being verified.
As soon as immediate response was complete a licensee supervisor ini-
tiated communication with the emergency response centers in IE Head-
quarters and in the Region III office.
The Resident Inspector coor-
dinated communications with the response centers until all systems
were stable.
The licensee plant staff performed professionally in identifying the
problem and in implementing emergency procedures.
2)b
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The Region III emergency response team arrived onsite at approximately
6:50 p.m. to provide independent assessment and monitoring. Results
of the
rgency team efforts are described in a separate inspection
report
The licensee proceded to place the plant in cold shutdown to identify
the ruptured tube, to determine the cause of the gbe failure, and
to complete repairs. The licensee's event report- , accurately des-
cribes the sequence of events, inspection and identification of the
cause and corrective actions completed prior to restart.
Messrs. B. D. Liaw, NRR, and K. D. Ward, IE Region III, participated
in the licensee's examination and observed portions of the licensee's
inspection of the steam generat
. These activities were described
in a separate inspection report
After completion of repairs and inspection of the steam generator,
the licensee proceeded to restart the plant in accordance with
approved procedures.
Prior to restart the Resident Inspector veri-
fied that the licensee had fulfilled commitments made to NRR during
a meeting in Bethesda, Maryland on Octobe E16, 1979. The commitments
were that the events would be documented in a report and available
for review by NRR and that the licensee would implement administrative
controls regarding iodine limits.
4.
Plant Operations
The inspector reviewed plant operations including examination of
selected operating logs, special orders, temporary memos, jumper and
tagout logs for the month of October.
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 and
instruments, to observe for adherence to radiation controls and fire
protection rules, to check proper alignment of selected valves and
equipment controls, and to review status of various alarmed annun-
ciators with operators.
The inspector also reviewed annunciator status, recorder charts,
surveillance records, and logs to serify that plant operations were
maintained in accordance with Technical Specification requirements.
1/
IE Inspection Report No. 50-282/79-26
2/
P-R0-79-27, Tube Rupture in No. 11 Steam Generator, dtd October 16, 1979.
3/ IE Inspection Report No. 50-282/79-25
2162 295
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The inspector performed independent verification of selected plant
systems and instrumentation during the licensee's preparations for
heatup after repairs to the steam generator were complete.
Check-
lists completed included:
C1.1.4-1, Reactor Coolant System
C1.1.5-1, Rod Control and Position Indicating Systems
C1.1.9-1, Nuclear Instrumentation System, Part 1
The inspector also verified valve positions for portions of the
auxiliary feedwater, safety injection, residual heat removal, and
component cooling systems, and reviewed completed checklists to
confirm that the plant staff had completed system checks and survei-
llance tests required to be completed before heatup.
No items of noncompliance or deviations were identified.
5.
Security
The inspector conducted periodic observations of access control,
issuing badges, vehicle inspection, escorting, and communication
checks.
No items of noncompliance or deviations were identified.
6.
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. The inspector observed work in progress
during troubleshooting of controls for a Unit 1 power operated
relief valve and restoration to service.
The inspector also observed work in progress in Unit I containment
during inspection and repair of the No. 11 steam generator and
during repairs to cooling water system seismic restraints.
No items of noncompliance or deviations were identified.
7.
Licensee Event Reports (LERs)
The inspector reviewed the following LERs submitted by the licensee,
determined that reporting requirements had been met, and determined
that corrective actions were being implemented. (Closed)
P- 0-78-21 Excessive Leakage through Unit 2 Containment Purge
a.
Supply Valves
2}b
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'
The licensee has submitted an update report to identify the cause
and corrective actions. Purge valves remain closed under admin-
istrative control.
b.
P-RO-79-17 Loss of both source range channels at shutdown
c.
P-LO-79-22 Instrument drift, Steam exclusion system
d.
?-RO-79-26 Axial offset outside target band
e.
P-R0-79-27 Tube Rupture in No. 11 Steam Generator (See Para-
graph 3 above)
8.
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
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OFFICE OF INSPECTION AN.' IN.T.iOLN!:. *
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Fnr.LIMINARY INSPECTION FINDINGS
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1.
LICENSEE
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REC 10NAL O!'l'1CE
Northern States Power Company
U.S. Nuclear Regulatory Comission
414 Nicollet Mall
Office of Inspection & Enforcemen*, RIII
'
?!inneapolis, MN 55401
799 Roosevelt Road
Prairie Island 1 (Redwing, MN)
Glen Ellyn, IL 60137
Prairie Island 2 (Redwing, MN)
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3.
DOCKET N"MBERS
4.
'! CENSE N"M3ERS
5.
DATE OF INSPECTION
50-282: 50-306
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DPR-42: DPR 6^~
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6.
'n'ithin the scope of the inspection, no itens of nonconpliance or deviation
were found.
7.
The following eatters are preliminary inspection findings:
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These preliminary inspection findings vill be reviewed by NRC Supervision /
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Mar.agenent at the Region III Office and they will correspond with you
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concerning any enforcenent action.
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1.
LICENSES
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R2010NAL O!'!!!CE
Northern States Power donpany'
" S. Nucient Reguintory Com ission
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414 Nicollet Mall
'!inneapolis, MN 55401
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Office of Inspection & Enforcement. RI!!
799 Roosevelt Road
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Prairie Island 1 (Redving. MN)
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Prairie Island 2-(Redving. MN)
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DOCKET N'33ERS
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1.: CENSE N"M3ERS
5.
DATE OF INSPECTION
50-282: 50-306
??R-42: DPR 60
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6.
'a'ithin the scope of the inspection, no itens of noncompliance or deviation
were found.
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The folleving natters are preliminary inspection findings:
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These preliminary inspection findings vill be reviewed by N"C Supervicion/
Management at the Regien I" Cffice and they vill correspond with you
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concerning any enforcement action.
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Neelear Rer"'.ntory rn- e e-
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0FFICE OF INS."ECTION AN." IN.T.10L'22. '-
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PREL!v.INA7Y INS?ECTION FIS"JINGS
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1.
L!cENSEE
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Northern States Po w. co pany
" S. Nuclear Regulatory Com-ission
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414 Nicollet Mall
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Office of Inspection L Enforce ent, n,::
'!inneapolis, MN 35401
799 Roosevelt Road
Glen Ellyn, IL 60137
Prairie Island 1 (Redving, MN)
Prairie Island 2 (Redving, MN)
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3.
DOCKET N','MBERS
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5.
DATE OF INSPECTION
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'a'ithin the scope of the inspection, no itens of nonconpliance or deviation
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The folleving eatters are preliminary inspection findings:
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These preliminary inspettien findinge vill be reviewed by NRC Supervit: ion /
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LICENSEE
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EC10NAL 01'FICE
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Northern States Power dompany'
U.S. Nucl. ear Regulatory Comission
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414 Nicollet Mall
Office of 1r.9pection 4 Enforcement. RIII
'inneapolis, MN 35401
799 Roosevelt Road
Prairie Island 1 (Redving, MN)
Glen Ellyn, IL 60137
Frairie Island 2 (Redving, MN)
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DOCKET N"MBERS
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DATE OF INS?ECTION
50-282: 50-306
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'a'ithin the scope of the inspection, no itens of noncompliance or deviation
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The fo11oving natters are preliminary inspection findirgot
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These preliminary inspection findinge vill be reviewed by NRC Supervicien/
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Management at the Region ::: Office and they vill correspond with you
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concerning any enforcement action.
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Neelear R'ec catory cn
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