IR 05000282/1983009
| ML20024D820 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/06/1983 |
| From: | Feierabend C, Jackiw I, David Williams NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024D812 | List: |
| References | |
| 50-282-83-09, 50-282-83-9, 50-306-83-09, 50-306-83-9, NUDOCS 8308080251 | |
| Download: ML20024D820 (7) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-282/83-09(DPRP); 50-306/83-09(DPRP)
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 Inspection At: Prairie Island Site, Red Wing, MN 55066
. Inspection Conducted: May 1-June 7, 1983 7![/f3 Inspectors: C Fel$r nd 7 '!f 3 D
W iam
/
A I y. Jackiw, Chief 7![kJ
. Approved By:
Reactor Projects Section 2B Inspection Summary
. Inspection on May 1-June 7, 1983 (Report No. 50-282/83-09(DPRP);
50-306/83-09(DPRP))-
-Areas Inspected: Routine resident inspection of previous inspection findings; plant operational safety; maintenance; surveillance; walkdown of cooling water system,' followup on licensee event reports, followup on a reactor trip and followup on a Region III request. The inspection involved a total of 233 inspector-hours onsite by two inspectors including 26 inspector-hours onsite during off-shifts.
Results-No itens of noncompliance or deviations were identified.
8308000251 830707 PDRADOCK05000g a
.
.
-
-
-.
,
,
-.
,
..
-
.
.
DETAILS l
~
- 1.
' Persons Contacted
- E. Watzl, Plant Manager
- D. Mendele, Plant Superintendent, Engineering'and Radiation Protection
,
R. Lindsey, Plant Superintendent, Operations and Maintenance G. Miller, Superintendent, Operations Engineering-A. Hunstad, Staff Engineer-M. Balk, Superintendent, Operations'
D. Schuelke, Superintendent, Radiation Protection J. Nelson, Superintendent, Maintenance M. Klee, Superintendent, Nuclear Engineering G. Lenertz, Lead Production Engineer-D. Brown, Engineer R. Frazier, Engineer K. Beadell, Engineer
.
The inspectors also talked with and interviewed other licensee employees, including members of the technical _and engineering staffs, shift super-visors; reactor _ and -auxiliary operators and QA personnel.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings
~
(Open) Open Item (282/82-24-02; 306/82-24-02 (DPRP)):
a.
Westinghouse NBFD Relays The licensee experienced failure of another NBFD relay (Paragraph 8.c).
The licensee is continuing to pursue the relay problem with
~the vendor. The generic issues have been addressed in NRC Informa-
'
tion Notices 82-02 and 82-54.
- 3.
Operations Safety Verification a.
General Observations Unit I operated at power throughout the inspection period. Unit 2 tripped on May 20 during surveillance testing and returned to power
- .
?
the same day.
-b.
Control Room Observations The inspector observed control. room operations, reviewed applicable
.
logs, conducted discussions with control room operators, and observed shift turnovers. The inspector verified the operability of selected l
emergency systems, reviewed equipment control records, and verified the proper return to service of affected components. The inspector observed portions of Unit 2 startup af ter plant trip and confirmed that required prerequisites were met.
1
+
r
> -. -
,
..,#-
.,,,
,w-,-.
v-
-- e,
,e,m-
.
- -, - -,,
-..n,_em~.s,-m-g,.c-.re..
.-.-,-,ev-
,.
.-s
- - -
.
.
c.
Tours Tours'of the screenhouse, auxiliary, turbine and radwaste buildings and external areas were conducted to observe plant equipment condi-tions, including potential fire hazards, and to verify that main-tenance work requests had been~ initiated for equipment in need of maintenance.
~d.
Independent Verification
'The. inspector performed a walkdown of the accessible portions of.the
.
Auxiliary Feedwater System, Radiatie Monitoring System and Component Cooling-Water System, and a complete walkdown of Cooling Water System.
No' items of noncompliance were identified.
4.
Cooling Water System The inspector conducted a detailed review of the Cooling Water System including independent verification of component status and valve position, review of completed surveillance tests and work requests, verification.that Technical Specification operability requirements were met and observation of portions of surveillance testing and maintenance in progress.
a.
Technical Specification Surveillance Requirements The inspector reviewed the following surveillance test records for completeness and meeting of schedules. The test were completed
. satisfactorily.
SP 1106A 12 Diesel Cooling Water Pump Test
'SP 1106B-
~22 Diesel Cooling Water Pump Test SP.1180 Diesel Cooling Water System Test SP:
1151 Cooling Water System Test SP 1158 Cooling Water Valve Test SP-1193 Cycling Cooling Water to AFW Pump Suction, Unit 1 SP 2193 Cycling Cooling Water to AFW Pump Suction, Unit 2
.SP 1528 Backflush of Emergency Bay Intake Pipe 5.
~Naintenance-The inspector reviewed maintenance procedures, observed maintenance.in progress, observed ~ quality. assurance and radiation protection activities and reviewed maintenance records for several inspection, repair and design change activities.
1WR-G2291-CO Number 16 Inverter
.
-The inspector observed trouble shooting activities to determine cause'of automatic transfer of power source from preferred to back-up. The cause, a failed capacitor, was identified and
l _
_ _ - _
.
.
.
~
replaceJ. :The. inverter was then returned to the preferred source of-power.
.b.
WRA-G1393-VC-Q Valve-VC-11-140 Leaking
~ The inspector observed the issuance of hold cards and isolation
-
of valve VC-11-140, replacement of_a,diaphram and subsequent i
restoration to _ service of.the valve while adhereing to RWP
- Requirements.
c.
WRA-G2261-VC-Q Boric Acid Transfer Pump (BATP) Seal Leak
_
The inspector observed maintenance activities including isolation,
~
. disassembly'and; restoration of a BATP while the licensee observed RWP requirements-. Repairs were satisfactory.
.
d.
WRA-G2368-DG-Q Diesel Generator #2 Air Compressor Leak The. inspector observed. work in progress and restoration of equip-ment to operability.
e.-
WRA-G1806-FP-Q Proving Operability of Diesel Driven Fire Pump after Maintenance-The inspector observed-the initiation, operability testing and restoration to service.
f.
PM 3122-1 Diesel Driven Fire Pump Annual Inspection The~ inspector observed the inspection in progress and reviewed the completed documentation.
g.
PM 3122-2 Diesel Driven Fire Pump 2 Year Inspection
,
The inspector observed the inspection in progress and reviewed the completed documentation.
h.
PM 3513-1. Fire Pump Water Strainer Inspection The inspector observed the inspection in progress.
si.
.WR-G1622-SI DCN82L697 Replacement of RC Valve Test Flowmeter This design change was made to improve the quality of local flow
~
indication.. The inspector observed isolation, work in progress and-restoration to normal status.
. 6 '.
~ Surveillance Observation
.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
,
,
L
rc S.
.
l(TS) requirements, observing that procedures were being followed by qualified operators, that LCO's were not violated, that system and equipment restoration was_ completed, Land.that test results were accept-able to test and: Technical: Specification requirements.
a.
SP 2111 Main Steam Power Operated Relief Valve Test The inspector observed initiation, testing and restoration of the
. valves, The testing was-satisfactory.
b.
SP 2093 Diesel Generator Manual and 4KV Rejection-Restoration Test The inspector observed portions of this test.
It was satisfactory.
c.
SP_.1524 Diesel Fire Pump Weekly-Test The inspector observed this weekly test twice during this period, including observation from initiation to restoration. -The_ tests were satisfactory.
-d.
SPl1028 Radiation Monitoring Monthly Functional Test The inspector observed a portion of the test involving comparing local and' control room meter readings and alarm activation.
e.'
SP 1106B 22 Diesel Cooling Water Pump Test
.The inspector observed startup of the pump and confirmed that operating parameters were documented and were within allowable limits.
f.
'SP 1601 Fire Alarm and Emergency Evacuation Alarm The test was satisfactory.
g.
SP 1093 & 2093 Diesel Generator Manual Test The inspector observed initiation, portions of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> operability run and restoration to normal status.
7.
Reactor Trip-Unit 2 tripped from 100% power at 1429 on May 20, 1983. A spurious negative flux rate trip signal was initiated while performing STP 2007A Power Range Functional Test, when the licensee technician failed to reset red channel bistables before testing the white channel. This completed the 2/4 logic. All systems functioned as expected and no ECCS systems were challenged. The unit was back on line at 1811 the same day.
' Because of a suspected fuel pin failure a Dose' Equivalent Iodine spike was detected shortly after the trip, exceeding allowable limits for RCS activity for a short period of time. The licensee has issued an' event
.
_
_
.:
.
.._
-
report.
(Paragraph 8.e) During return to power, the operator was unable to maintain axial flux. difference aithin the allowable target band.
Power was maintained below'50% until-the~ axial flux was back within the target band (approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />) and was then maintained below.50%
- for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to comply with the action requirements of Technical Specification T.S.3.10.B.7.b a
No items of noncompliance were identified.
8.
. Licensee Event Report Followup Thelinspector reviewed the following event reports to determine that
~reportability requirements were' fulfilled and that corrective actions wereJaccomplished to prevent recurrence. The review included verifica-tion that the reports accurately describe the event, that the licensee conducted required investigations and management reviews and that con-tinued operation was not in violation of regulatory requirements.
'
.a.
_(Closed) P-RO-82-26 No. 11' Turbine Driven Auxiliary Feedwater Pump Failed to Deliver Full Flow The inspector previously reviewed this report and observed the test of the pump during startup after completion of the Unit 1
~
refueling outage.
b.
(Closed) P-RO-83-05 Failure of One Diesel Generator to Start
'
~
-Details of the events were described in a previous inspection report.1
c.
(Closed) P-RO-83-06 21 Motor Driven Auxiliary Feedwater Pump Inoperable
- The cause -was failed Westinghouse. (W)' NBFD relay. Licensee actions related to NBFD relays have been described in a previous-inspection report.2-Licensee actions for this failure are con-
!
sistant with previous actions related to_NBFD relays...The li-censee is continuing to pursue the problem with jW) and plans t
_
to replace additional NBFD relays with BFD relays during the summer 1983 Unit'2 refae:ing outage. This event is considered
'
-closed, but the NBFL relay concern remains an open item.
(Paragraph 2)
j.
t d.
(Closed) P-RO-83-08 Unit 2. Turbine Stop Valve This event was described'in a previous inspection report. The inspectors reviewed all aspects of the event. No items of concern
[
were identified.
o 1.
.IIL Inspection Report' No. 50-282/82-24; 50-306/82-24
_
2.
Ibid'
,
'~
..-
-
.
-.
,,
-
.
,. _..-,- -
.-,
- -.. -
c.
.
.
.
_ _ _ _ - _ _ _ _ _ _ _ - _ _ _ -
. __ -.
.
..
,
e.
(Closed) P-RO-83-09 RCS Iodine Spike After Shutdown The special report is required whenever RCS Activity exceeds the Technical Specification Limit of 1.0 uci/gm. This is expected for any reactor trip after identification of a fuel defect. The li-
.censee is not scheduling Unit 2 for load following to minimize iodine spiking.
No items of noncompliance were identified.
- 9.
LFollowup'on Region III Request
~ Region III requested that the inspector perform a review of circuit breakers that are required to close to fulfill their safeguards functions. The information requested was. forwarded to Region III.
No items of noncompliance were identified.
Exit Interviews The inspector conducted interim interviews during the inspection period
.and met with Mr. Watzl and other members of your staff as indicated in Paragraph 1 at the conclusion of the inspection.
No items of noncompliance were identified.
.
r
.
.
_ _ - - _ _ _ = - - - -