ML20197H646

Notice of Violation from Insp on 900926-1005.Violation Noted:Corrective Action Program Did Not Assure That Nonconforming Condition Potentially Affecting turbine-driven Auxiliary Feed Pump Was Promptly Reported & Corrected

ML20197H646
Person / Time
Site:	Wolf Creek
Issue date:	11/09/1990
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20197H643	List: IR 05000482/1990034 ML20197H646
References
50-482-90-34, EA-90-185, NUDOCS 9011200032
Download: ML20197H646 (19)

Text

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NOTICE OF VIOLATION Wolf Creek Nuclear Operating Corporation Docket No. STN 50-482 Wolf Creek Generating Station License No. NPF-42 EA 90-185 During an NRC inspection conducted September 26 through October 5,1990, a violation of NRC requirenents was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2 Appendix C (1990), the violation is listed below:

10 CFR 50, Appendix B, Criterion XVI, states, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, nm1 functions, deficiencies, deviations, defective material and equipment, and nonconfonnances are promptly identified and corrected.

Wolf Creek Generating Station Quality" Assurance Procedure QAP 16.1,

" Corrective Action for QA Breakdowns, Revision 3, paragraph 6. states, in part, that corrective action controls, as established in this procedure, shall assure that significant conditions adverse to quality are promptly identified, reported, and corrected.

Contrary to the above, the licensee's corrective action program did not assure that a nonconforming condition potentially affecting the operability of the turbine-driven auxiliary feed pump (TDAFP) was promptly reported and corrected. This condition existed from November 2,1989, to October 1, 1990, before it was corrected and subsequently reported to the NRC.

ThisisaSeverityLevelIVviolation(SupplementI)

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Connission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, and if. applicable, a copy to the NRC Resident Inspector, within 30 days of. the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:

(1) the reason for the violation or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an

~a dequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time. Under the authority of Section 182 of the Act 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.

Dated this at 'l tiArlington, day ofTexas fam [er 1990 9011200032 901109 PDR ADOCK 05000402 0 PNU

. . _ ~ -

. .- ' ENCLOSURE 2 WCNOC ENFORCEMENT CONFERFNCE WITH '

l NRC REGION IV MANAGEMFNT l

TURBINE . DRIVEN AUXlLIARY FEEDWATER PUMP BROKEN CONDUIT CONNECTOR I

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November 6,1990 WMF CREEK NUCLEAR OPERATING CORPORATION 1

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h TDAFP BROKEN CONDUlT CONNECTOR i

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i INTRODUCTION -

JOHN BAILEY l

-DESIGN REVIEW -

JACK PIPPIN WORK REQUEST PROGRAM -

GARY BOYER 1

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l PROGRAM ENHANCEMENTS -

BRAD NORTON  ;

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CONCLUSIONS -

JOHN BAILEY l l-i

' CLOSING REMARKS -

BART WITHERS 1

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ENGINEERING EVALUATION OF THE AS FOUND CONDITION FOR THE TURBINE CONTROL  ;

CONNECTOR  !

TURBINE DRIVEN AUXILIARY FEED PUMP IS A REDUNDANT AUXILIARY FEEDWATER PUMPING SYSTEM TWO MAJOR CONTROL COMPONENTS

. DAMAGED CONNECTOR WAS IN THE CONDUlT CARRYING THE SPEED ERROR SIGNAL FROM EGM TO EGR TWO POTENTIAL FAILURES MODES WERE IDENTIFIED l:

FOLLOW-UP ACTIONS CONNECTOR ANALYSIS ACTION PLAN STATUS OF- ACTION PLAN

AUX FEEDWATER PUMP TURBINE KFCO2 .

SPEED CONTROL BLOCK DIAGRAM -

BROKEN -

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CONNEC TOR EGR AMPLIFIER --

RGSC  :

SPEED SET SIG N A L' SION AL - + CONVRTH -+ LOW SIGNAL SELECTOR

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_ , RAMP W ,x G E N E R ATO R OS TEST CONTRLR /

REMOTE i LIMITS SPEED FREO/DC H Y DR AUtiC SWITCH PICKUP  : CONVRTR SERVO

' S U P P LY / I T & T VALVE GOVERNO3 VALVE EGR - Et.ECT RO-HYDR AUt IG ACTUATOR Er.M - T UROINE SPEED GON T ROLLER Hr.5G R AMi> GENER ATOR/ SIGNAL. CONVLil1 Ell

.a e EGR HYDRAULIC ACTUATOR EXPLODEO VIEW ,

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SEQUENCE OF EVENTS I l

l ON 11/02/89 AT 1625 CST, MECHANICAL MAINTENANCE BROKE AN ELECTRICAL CONNECTOR THAT ATTACHES _ l THE -DC CONTROL CABLE TO THE ELECTRO-HYDRAULIC l VALVE ACTUATOR ON THE AUXILIARY FEEDWATER PUMP l TURBINE. THIS WAS DONE WHILE ATTEMPTING TO l TIGHTEN A UNION ON .THE LUBE OIL LINE FOR THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP.

(WORK REQUEST 00915-89) l AN INVESTIGATION BY THE INSTRUMENTATION AND l CONTROLS GROUP SHOWED THAT THE DC CONTROL l

CABLE WAS STILL INTACT.

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1 ON 11/02/89 AT 1732 CST THE TDAFP WAS l SURVEILLANCE TESTED TO ENSURE THAT IT WAS '

OPERABLE WITH THE BROKEN ELECTRICAL CONNECTOR THE TEST WAS SATISFACTORlLY COMPLETED. ;l 1

A PRIORITY 3 WORK REQUEST (04814-89) WAS i WRITTEN TO REPAIR THE CONTROL CABLE ASSEMBLY. l t .

ON 11/03/89 THE WORK REQUEST TAG WAS HUNG.

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SEQUENCE OF EVENTS (CON'T)

ON 12/07/89 THE WORK REQUEST WAS RECEIVED IN PROCURMENT ENGINEERING NUCLEAR REGULATORY COMMISSION INSPECTORS QUESTION THE ENVIRONMENTAL QUALIFICATIONS OF THE EXPOSED DC CONTROL CABLE DURING AN INSPECTION HELD MAY 7-11, 1990.

(INSPECTION REPORT 90-21)

ON 5/10/90 THE INSTRUMENTATION AND CONTROLS GROUP INVESTIGATED THE CONCERNS OF THE NRC INSPECTORS AND CONCLUDED THAT THE EXPOSED DC CONTROL CABLE DID NOT AFFECT OPERABILITY.

OF THE TDAFP.

ON 5/18/90 PROCUREMENT ENGINEERING COMPLETED THEIR EVALUATION OF THE WORK REQUEST ON 5/21/90 PR-127039 WAS RECEIVED IN PU RCH ASIN G.

ON 5/22/90 PURCHASING REQUISITION WAS PREPARED AND SENT OUT FOR BIDS.

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SEQUENCE OF EVENTS (CON'T)

ON 6/25/90 AND 7/09/90 A NOTICE WAS SENT OUT STATING THAT THE BIDS WERE OVERDUE.

ON 9/26/90 DURING A ROUTINE PLANT TOUR A RESIDENT INSPECTOR NOTED A BROKEN CONDUlT CONTAINING WIRING TO THE TDAFP GOVERNOR.

ON 10/01/90 A RESIDENT INSPECTOR QUESTIONED NUCLEAR PLANT ENGINEERING ABOUT THE ENVIRONMENTAL QUALIFICATIONS OF THE TDAFP.

NPE DETERMINED THAT THE WEIGHT OF THE CONDUlT AND. FITTINGS BEING CARRIED BY THE DC CONTROL CABLE AND CONNECTOR REPRESENTED

' AN UNANALYZED CONDITION.

ON 10/01/90 AT 1843 CDT THE TDAFP WAS DECLARED INOPERABLE BASED ON THE' INDETERMINATE SEISMIC QUALIFICATION STATUS OF THE DC CONTROL CABLE.

ON.10/01/90 AT 2346 CDT THE TDAFP -WAS DECLARED OPERABLE AFTER THE CONDUIT WAS TEMPORARILY MODIFIED PER DESIGN DISPOSITION.

ON 10/05/90 AN NRC EXIT MEETING WAS HELD TO DISCUSS THE PROPOSED FINDINGS CONCERNING THE EVENT.

ON 10/10/90 THE PROPER PARTS WERE OBTAINED FROM THE WAREHOUSE AND THE TDAFP WAS PERMANENTLY REPAIRED.

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l WOLF CREEK GENERATING STATION CORRECTIVE WORK REQUEST PROCESS l

NONCONFORMANCE I IDENTIFIED l o

j REQUESTOR RECORDS PRE LIMIN ARY INFORM ATION o

SHIFT SUPERVISOR EVALUATES ENGINEERING [ NEED FOR IMMEDIATE ACTION REVIEW j (INCLUDING OPERABILITY AND REPORTABILITY POTENTIAL) o 1 P RESPONSIBLE WORK

', ORG A NIZ ATION ASSIGNS SAFETY

/ANYASPECTS DESIGNyN C L AS SlFIC ATIO N S N AFFECTING NO P E R A BILIT Y o

/ DESIGN RESPONSIBLE WORK /

/ ORG ANIZ ATION DETERMINES: REWORK: / DISPOSITION REQUIRE D REPAIR, OR / FOR REPAIR USE- AS-IS / OR USE- AS-ISj REVIEW .

GROUP LEADER DEVELOPS WORK INSTRUCTIONS o

SHIFT SUPERVISOR GIVES

! ' PERMISSION TO WORK L

ll L' WORK AND TEST PHASE l'

L 1r SHIFT SUPERVISOR DECLARES EQU1PMENT OPERABLE AND CLOSES WORK REQUEST l

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WORK REQUEST SCREENING CRITERIA WORK REQUESTS THAT DESCRIBE CONDITIONS WHICH FALL INTO ANY OF THE CATEGORIES LISTED BELOW DO NOT REQUIRE FURTHER REVIEW.

-1. PMR IMPLEMENTATION

2. TEMPOR ARY- MODIFICATION INSTALLATION

3. SURVEILLANCE TEST IMPLEMENTATION 4.. PREVENTATIVE / PREDICTIVE MAINTENANCE IMPLEMENTATION

5. WORK WHICH DOES NOT REQUIRE CONTROL ROOM COORDINATION (E.G., INSPECTION, WAREHOUSE EQUIPMENT MAINTENANCE, INSULATION REMOVAL / INSTALLATION, ETC.)

• 6. DOOR SEAL DAMAGE (NO BUILDING PRESSURE BOUNDARY CONCERNS)

NOTE: THE PM PROGRAM FOR. PRESSURE BOUNDARY DOOR AND ' DAMPER SEALS MAINTAINS THE OVERALL BOUNDARY CONDITION WELL ABOVE THE MINIMUM REQUIRED TO MEET BUILDING PRESSURE REQUIREMENTS. ISOLATED DOOR OR DAMPER SEAL DAMAGE IDENTIFIED THROUGH THE. PM PROGRAM IS NOT AN IMPACT TO PRESSURE BOUNDARY. INTEGRITY.

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y SCREENING CRITERIA 1 (CON'T)

7. BORIC . ACID RESIDUE

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. +8. DAMPER SEAL DAMAGE (NO BUILDING J PRESSURE BOUNDARY CONCERNS)  ;

NOTE: SEE NOTE UNDER CATEGORY 6.

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<' , 9. SPARE PARTS ' REFURBISMENT/ TESTING /  !

. CONTROL

.10. WRs' USED TO CONTROL COMPONENTS E THAT ARE- MISSING SCAVENGED PARTS l

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. 1 1. - WRs : FORWARDED .TO NPE i

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12. WRs WRITTEN TO ADDRESS. PREVIOUS q

+ ' ENGINEERING DISPOSITION FOLLOW-UP

'j REQUIREMENTS (' INSPECT LATER', ?l

' REPLACE. LATER', ' MONITOR CONDITION',.

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• 13.- MINOR COMPONENT- LEAKS (PACKING, FLANGE,-  !

F, . BODY-TO-BONNET, SEAL, OIL, AIR, ETC.) t

', 4 >N OTE: ALL VALVES- (EXCLUDING DRAIN,. VENT AND TEST  !

CONNECTION - 1S01 VALVES), . LEAKING PAST-. THE

+ SEAT? MUST GET FURTHER REVIEW.

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SCREENING CRITERIA

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• 14. MINOR INSTRUMENTATION PROBLEMS (NO CONTROL OR INTERLOCK -QUESTIONS,

{ PLANT ACTUAL CONDITION VERIFIED NORMAL)

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• 15. CORRECTION OF SURVEILLANCE TEST DEFICIENCIES

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+ 16. .WRs LWRITTEN TO ADDRESS PERFORMANCE-OR RELIABILITY ENHANCEMENTS

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• 17. BROKEN, STRIPPED OR MISSING FASTENERS ON COVERG/ ACCESS PANELS--(NO PRESSURE BOUNDARY, EQ INTEGRITY OR SEISMIC

- QUESTIONS)

FOR CONDITIONS WHICH FALL IN THESE CATEGORIES REFER TO ATTACHMENT B, ITEM 5. CRITERIA TO ASSIST IN THE SCREENING PROCESS.

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WORKRREQUEST REVIEW-y_

1. Component (s) investigat'ed:

'(Component No.(s))

2. Safety-related or-Special-Scopa: . [Yes CNo

3. Drawings reviewed:

(Drawing No.(s))

4. Documents reviewed:

(USAR Sections, Tech Spec Sections, Reg Guides, Tech Manuals, Design Specs, other Design-Documents)

5. FIT, FORM, FUNCTIONS reviewedi (Check all that were reviewed.)

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ess-on Structitral Interferences R Seismic R IIfI

- ] Integrity - (External) SI Connections P

q ressure Boundary -

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Barrier

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q Thermal Electr.ical .

Electrical " ~

- Insulation' Insulation ' Separation Controls *

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Indication / System Component Alarm Allowable Output / Capacity Output / Capacity Leakage-q Interfcrences Open/Close Fall Safe- Fire Fire

- (Internal) Time q- Position Barrier q- Alarm Fire Flood ""U 88 "

Suppression 'Other Hazard Ha d H st)

6. Discussion of reviews f

7. Condition ~of component-impacts

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its ability to perform its ]No ]Yes Contact

]N/A appropriate Component safety Design Basis Function: Supervision and already Out-l follow-up with of-Service Control Roorn Reviewer: "

Signature Date

.Yigure 1 Rev. a ADH 05-001 l

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, CORRnCTIVE WORK REQUEST (CWR)

REVIEW STATUS L

,' *- REVIEW OF CURRENT CWRs 233 REVIEWED SINCE 10/04/90 4 IDENTIFIED AS REQUIRING MORE IN- DEPTH REVIEW

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r a NONE- HAD IMPACT ON EQUIPMENT OPERABILITY.-

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• - REVIEW: OF BACKLOG OF OPEN CWRs 2448 REVIEWED 104 REQUIRED ~ IN-DEPTH REVIEW

.NONE HAD ' IMPACT ON.' EQUIPMENT OPERABILITY t

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s. z s p ENCLOSURE 3 e

$, ENFORCEMENT CONFERENCE ATTENDEES Attendance at the WCNOC/NRC enforcement conference on November 6,1990, in the Region IV office was as follows:

y. WCNOC B. D. Withers, President and Chief Executive Officer  !

~'

J.' A. Bailey, Vice President, Nuclear Operations

.G. D. Coyer, Plant Manager- j J. M. ' Pippin, Manager.1 Nuclear Plant Engineering  ;

C.-. E. Parg, Director, Quality Assurance i LW. B. Norton, Manager, Technical Support {

J. D. Weeks, Manager, Operations i

.1

, H.. K. Chernoff, Supervisor, Licensing NRC. i T.lP.-Gwynn, Deputy Director, Division of Reactor. Projects (DRP)

~

J.:P. Jaudon, Deputy Director . Division of Reactor Safety (DRS) j Ma J. Virgilio, Assistant-Director, Region IV and V Reactors, Office of j Nuclear Reactor Regulation .(NRR) -l W; H. Swenson, Technical Assistant, NRR j A. T. Howell, Chief, Project Section D DRP G. F. Sanborn, Region'!V Enforcement Officer D.,V.- Pickett Project Manager, NRR L .M. E. Skow, Senior Resident Inspector for WCGS, DRP l

=0.-C. Williams., Region IV Coordinator, NRR

.L. L.-Gundrum, Resident' Inspector for WCGS, DRP

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