IR 05000282/1987015
| ML20235X227 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/09/1987 |
| From: | Gardner R, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235X212 | List: |
| References | |
| 50-282-87-15, 50-306-87-14, GL-83-28, NUDOCS 8710190262 | |
| Download: ML20235X227 (6) | |
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O.S. NUCLEAR REGULATORY COMMISSION i
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REGION III
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Reports No. 50-282/87015(DRS); 50-306/87014(DRS)
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' Docket Nos. 50-282; 50-306 Licenses No. DPR-42; No. DPR-60 l
Licensee:
Northern States Power Company
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414 Nicollet Mall i
Minneapolis, MN 55401 i
Facility'Name:
Prairie Island Nuclear Generating Plants, Unit 1 and 2 Inspection At:
Prairie Island Site, Red Wing, Minnesota Inspection Conducted:
August 31 through September 24, 1987 O-h a~ d Inspector:
J. H. Neisler 10 ~'I-87
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$.\\\\. h W A'pproved By:
R. N. Gardner, Chief
/ 0 - f 47 Plant Systems Section Date
Inspection Summary Insp_ection on August 31 through September 24, 1987 (Reports No. 50-282/87015(DRS); 50-306/87014(DRS))
Areas Inspected:
Routine announced inspection of the licensee's implementation of Generic Letter 83-28 in the areas of equipment classification, vendor interface, post maintenance testing and reactor trip system reliability.
Closed TI 2515/64R1 and TI 2515/91.
Results:
No violations or deviations were identified.
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I 8710190262 871009 i
{DR ADOCK 05000282 I
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'r DETAILS l
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. Persons Contacted
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Principle ~ Licensee Employee
'*E. Watz1', Plant Manager
- K. Beadel,. Superintendent, Quality Engineering.
T. Reding, Document Control. Supervisor
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J. Daley,nPlant Administration Specialist
- J. Curtis,. Production Engineer
- A.. Hunstad, Staff Engineer
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'*J. Hoffman, Superintendent,. Technical Engineering'
- J. Maki, Production Engineer
- J. Ruether, Lead. Production Engineer i'
R. Fraser, Lead Production' Engineer C. Mundt, Production Engineer.
- G. Lenertz, General Superintendent, Plant Maintenance
- Denotes those persons attending exit interview.
2.
TI 2515/64R1 (Closed) TI 2515/91 (Closed)'
a.
Equipment Classification The inspector selected four components in the Reactor Trip' System I
(RTS) and eight components in the containment spray. system for
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examination during this inspection.
The components selected.were:
I RTS Containment Spray System
. Reactor trip breaker Containment spray pump Manual ~ trip switch Containment spray pump motor.
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Control rod drive Valve MV.32103 24 volt power supply Valve MV 32096 Control rod drive latch Check valve CS-18 assembly Pressure transmitter PT 17090 Level transmitter LT 24061 4.16 KV circuit breaker For the selected components, the inspector performed the following reviews:
(1)' The. inspector reviewed the Prairie Island safety-related component list (Q-List) and Q-List extensions for each system.
Each of the above components was identified on the Q-List or Q-List extension for their respective systems.
In addition, the inspector reviewed work requests, maintenance and test procedures, surveillance procedures, modification packages, (;
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drawings and procurement documentation, to determine whether activities involving safety-related components were properly classified as safety-related.
No improperly classified activities were identified for those components included'
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I (2) To determine the level of plant management oversight the inspector reviewed plant procedures controlling maintenance,
modifications, procuremnt and issue, inspection and testing of safety-related itemb quality assurance procedures, audits
and surveillance activities, and corporate level procedures
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for activities impacting safety-related structures, systems j
and compcnents.
(3) Equipment classification is controlled by Directive SACD 2.1 (" Quality Programs Bour.dary").
This directive establishes a Q-List committee whose responsibility is to determine the safety classification of plant structures, systems and components.
The committee's recommendations are forwarded to the Superintendent of Quality Engineering for approval and. addition to the Prairie -
Island Q-List or Q-List extension.
(4) The inspector reviewed approved procedures issued by I
corporate and plant management for procurement, maintenance, modifications, inspection, testing and surveillance activities affecting safety-related structures, systems and components.
(5) The inspector reviewed procedures established to control the training and indoctrination of personnel performing activities
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affecting safety-related equipment.
Included in the review were procedures for training maintenance and I&C personnel, staff engineers, and quality personnel.
In addition, the inspector reviewed personnel training and indoctrination records to verify that the required training was being accomplished.
(6) The inspector reviewed eight audit reports and twenty-nine surveillance inspection reports documenting Quality Assurance activities involving safety-related activities.
The Quality Assurance organization maintains a schedule of planned audits and surveillance inspections for safety-related activities at the facility.
(7) The corrective action program for safety-related equipment is i
described in the Quality Assurance procedures.
The inspector's
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review of corrective action for audit and surveillance I
inspection findings revealed that the corrective actions for those findings were timely and adequate.
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(8) Review and evaluation of information concerning malfunctioning l
of equipment is controlled by the licensee's nonconformance
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(NRC) and Discrepancy Report (DR) program.
Equipment i
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malfunctions identified by NRC or DR are reviewed by management and engineering to determine whether an identical replacement
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could be expected to perform reliably.
(9).The. inspector reviewed.five safety-related modifications involving the reactor trip system and containment spray system.
The modification packages, drawings, work requests and inspection reports were clearly identified as safety-related.
No violations or deviations were identified.
b.
Vendor Interface The inspector reviewed the licensee's corporate and in-plant procedures established to assure that vendor information for safety-related components is current and complete.
Vendor manuals for.four components in the reactor trip system and eight components in the containment spray system were reviewed for completeness and to determine whether the manuals accurately reflected the installed equipment. Guidance provided in the manuals has been included in the maintenance, test and inspection procedures used in the facility.
The inspector reviewed vendor recommended modifications on the RTS breakers.
The modifications were the modification to automatically activate the shunt trip and the modification to ensure that on-line functioned testing of the reactor trip system can be performed.
Post modification test results indicated that the modifications functional according to design requirements.
The licensee's procedures controlling maintenance, modifications, and the document control procedures pertaining to vendor technical information were reviewed. The procedures were determined to be adequate to control replacement of equipment in situations where a vendor goes out of business or will not supply adequate information to the plant.
The licensee is participating in the INP0 Nuclear Plant Reliability Data System (NPRDS) and Nuclear Utility Task Action Committee (NUTAC). The inspector determined that procedures are in place to e'
require periodic surveillance of safety-related vendors.
Reporting of deficiencies has been proceduralized and during the inspection, the licensee initiated procedure revisions to enhance the controls relative to NPRDS and SEE-IN participation.
No violations or deviations were identified.
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c.
Post Maintenance Testing The inspector selected three valves, one RTS breaker, one containment spray pump and one level transmitter for review to verify that the licensee was implementing a post maintenance test program.
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For theLselected components, %hJ inspector determir.ed the
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'(1)
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~ The licensea.has written procedures and check % hts c$ntrolling,
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post maintenance testing and nurveillar.ces. Th4'inspentar o
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reviewed eleven completed porkL r'equests' involving phevnintf ve
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orLcorrective maintenance.- Each ' work yequest i'ndichted that',
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the required post maintenance testi hadbeenpe{#rmed.
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-(2)' Criteria and responsibilities for maintenance app'roval and,for.
. designating maintenkng activities as safety-related and r.on safety-related ha'vW been established in work request initiktionL a
procedures and in'the plant modification procedure.
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T maintenance testTinspection.is controlled by the quality assurance. surveillance. inspection' program.
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- (3). Methods,for perfording*J'unctional testing following maintenance
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for safety-relatedhcomponents have b"een developed and are i
delineated in publi,shed technical ~ staff procedures, operator surveillance' procedures, and preventive, maintenance'and surveillance procedures.
(4) The inspector reviewed completed work request gnd supporting documentation retrieved from the document' d ntrol records storage.
The documentation contained ap'pr' ova?g of work requests, the7 identity of persons who performed the act,1vity.
y and the individuals who performed the inspection.;
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The inspector verified th,at th' surveillance of the shunt t' rip attachae
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e licensee was perforn of;:
completed surveillance p cefbres and surveillance,e ihspection reports for both RTS trains.
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t (6) Verificationthattheliconseewasinde'pendentip'testingthe
ability to manually trip the RTS breakers thrcugh the use. of i
either the underdoltage' Erip attachment or the' shunt trip
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attachment was acW mplished by reviewing coroleted surveillance 6
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procedure /checklistsjand surveillance inspect. ion reports.
No violations o'r deviations wer identffied.
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d.
Reactor Trip System reliability Theinspectorverifiedthatthelicenseehasestablisdedapreventive s
maintenance and surveillance program for the rea t.cr 3,t;'ip breakers.
Procedure MT-PP7.44 " Maintenance of Westinghouse 08-50 Reactor and Bypass Reactor Trip Breaker," includes periodicWainter since,
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lubrication,' UVTA and shunt trip force measurements, httmekeeping.
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and other activities recommended by the ) manufacturer.
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The inspector reviewed life cycle testing documentation for the reactor trip breakers (08-50), shunt trip attachments and undervoltage trip attachments to determine whether periodic refurbishment and
' replacement of components was consistent with the results of the
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life cycle tests.
The licensee's program for replacement of aged components falls within the parameters established during life-cycle tests.
3.
Exit Interview The inspector met with licensee' representatives (denoted under Paragraph 1) at the conclusion of the inspection and summarized the scope and findings of the inspection.
The licensee acknowledged the inspector's
. comments.
The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify any such documents or processes as proprietary.
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