ML20135F134

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Forwards Summary of 961206 Mgt Meeting Re Corrective Action Process & Safey Sys Functional Assessment of Auxiliary Feedwater Sys
ML20135F134
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/09/1996
From: Dyer J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Carns N
WOLF CREEK NUCLEAR OPERATING CORP.
References
NUDOCS 9612120378
Download: ML20135F134 (43)


Text

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f 611 RY AN PL AZA DRIVE, SUIT E 400

%, ,? AR LINGTON. TE X AS 76011 8064 DEC 9 1996 Neil S. Carns, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839

SUBJECT:

MANAGEMENT MEETING

SUMMARY

This refers to the meeting conducted in the Region IV office on December 6,1996. This meeting related to your corrective action process and safety system functional assessment of the auxiliary feedwater system. The meeting was beneficialin providing us with an understanding of your goals, and changes to achieve those goals, in your corrective action process including your Plant Safety Review Committee, as well as the status and findings associated with the functional assessment of the auxiliary feedwater system.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.

Should you have any questions concerning this matter, we will be pleased to discuss them with you.

Sincerely, J. E. Dyer, Director Division of Reactor Projects

Enclosures:

1. Attendance List
2. Licensee Presentation ec:

Vice President Plant Operations Wolf Creek Nuclear Operating Corp.

P.O. Box 411 Burlington, Kansas 66839 9612120378 961209 PDR ADOCK 05000482 p PDR

o Wolf Creek Nuclear Operating Corporation Jay Silberg, Esq.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW l Washington, D.C. 20037 '

Supervisor Licensing Wolf Creek Nuclear Operating Corp.

P.O. Box 411 Burlington, Kansas 66839 Supervisor Regulatory Compliance Wolf Creek Nuclear Operating Corp.

P.O. Box 411 ,

Burlington, Kansas 66839 I Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Rd.

Topeka, Kansas 66604-4027 Office of the Governor i State of Kansas i Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612-1597 County Clerk Cof fey County Courthouse Burlington, Kansas 66839-1798 Public Health Physicist Division of Environment Kansas Department of Health and Environment Bureau of Air & Radiation Forbes Field Building 283 Topeka, Kansas 66620

. 1

's Wolf Creek Nuclear Operating Corporation Mr. Frank Moussa Division of Emergency Preparedness 2800 SW Topeka Blvd Topeka, Kansas 66611-1287 i

4 DEC 9 1996 i Wolf Creek Nuclear Operating l Corporation g;bcc.to DMB (IE45)y7w bec distrib by RIV:

L. J. Callan Resident inspector DRP Director SRI (Callaway, RIV)

Branch Chief (DRP/B) DRS-PSB Project Engineer (DRP/B) MIS System Branch Chief (DRP/TSS) RIV File Leah Tremper (OC/LFDCB, MS: TWFN 9E10)

PAO SLO l

l l

1 To receive copy of document. Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy PE:DRP/B C:DRP /) D:DRP _ _ l DNGraves:cmjf) WDJohngon JEDyer (M7 12/ 6/96 12/(g /96 12/9 /96 OFFICIAL RECORD CONY 120004

. 1 4

DEC 9 1996 Wolf Creek Nuclear Operating Corporation bec to DMB (IE45) bec distrib. by RIV:

L. J. Callan . Resident inspector DRP Director SRI (Callaway, RIV)

Branch Chief (DRP/B) DRS-PSB Project Engineer (DRP/B) MIS System Branch Chief (DRP/TSS) RIV File Leah Tremper (OC/LFDCB, MS: TWFN 9E10)

PAO SLO i

l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy PE:DRP/B C:DRP /) D:DRP _ .

i)NGraves; cmp) WDJohnfon JEDyer @7 12/ b /96 12/9 /96 12/9 /96 OFFICIAL F;ECORD COPY

Enclosure 1 MEETING: WOLF CREEK NUCLEAR OPERATING CORPORATION

SUBJECT:

CORRECTIVE ACTION PROGRAM /SSFA STATUS l l DATE: DECEMBER 6, 1996 ATTENDANCE LIST (PLEASE PRINT CLEARLY)

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Agenda oCorrective Action Program l overview Areas for Improvement Improvements and their status oPSRC Purpose and Scope Improvements and their status

Corrective Action Program:

Overview E

E o Program is comparable with the industry standard:

Contains the Correct elements Trained personnel Low threshold for initiation Screens for proper level of significance 2

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Corrective Action Program:

Areas for Improvement .

eChallenges:

Trending Resource Allocation Planning and Scheduling of Resources Root Cause analysis Ownership of Corrective Action Program Management oversight t

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Corrective Action Program:

Improvements .

i e Electronic initiation document for Performance Improvement Requests (PIRs}

(9-16-96}

e Electronic initiation increases ease of tracking and trending (1C-14-96}

e Resource loading of PIRs (1st qtr '97}

e Integrated work control software (4th qtr '97) 5

.j Corrective Action Program:

Improvements

.l e PIR Coordinators assigned in each line organization (11-22-96) e PIR Coordinators will track and trend PIRs (1st qtr '97) e Failure Prevention Inc. (FPI) will conduct Root Cause and Causal Factors training for PIR Coordinators and line management (1st qtr '97}

e Quarterly sampling of PIRs by PIR Coordinators (1st qtr '97)

Corrective Action Program:

Improvements I E

e Performance Indicators o Corrective Action Review Board:

Membership: Plant Manager (chairman),

VP Engineering, Director Site Support, Manager Pl&A, and subject PIR Manager Reviews Root Cause, Causal Factors, and Corrective Actions for each Significant PIR Teaches and re-inforces proper corrective action methods, and sets standard for the Site 7

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KEY Elements eComprehensive Corrective l Action Program

eLine Management Ownership, and involvement in the program I

8

PSRC:

Purpose and Scope e Advises Plant Manager on all matters related to Nuclear Safety, per Technical Specification 6.5.1 e Sets performance standards and teaches the organization the attributes of safe plant operation 9

PSRC:

Improvements e New PSRC Chairman Recent INPO loaned employee (12 plants}

e ' Conduct Standard' under development (1st qtr '97)

Input from Chief Operating Officer and Plant Manager to ensure short term improvements were implemented right away Use of industry best practices to ensure that PSRC provides maximum value in their reviews e Line Organizations will present materials i

10

PSRC:

Improvements .

e Reviews selected topics each Quarter to assure Plant is operated safely (1st qtr '97):

Training performance by organization System Health Self Assessments Audits and Surveillances Regulatory findings Performance Trends

Corrective Action 11

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O I; Auxiliary Feedwater System O

Functional Assessment 0

o Status 0

o , December 6,1996 0

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0 iA ALSFA Commitment Sources a

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O E*J m Enforcement Conference meeting of May 8 10,1996 (Icing Event) 0 h oO 0

m LER 96-006, Roll Pin m LER 96-007, Missed PMT E },

0 m NEIIndustry Initiative to Address g

o License Basis Conformance Issues O

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O 8 A Most Risk Significant Systems 0

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0 EJ System Functional Assessment 0 m Auxiliary Feedwater a ALSFA(12/31/96) o a Stand'oy Diesel Generators a EDSFA(91/92)

O o a Essential Service Water a Planned (6/30/97)

S , a Component Cooling Water a Planned (12/31/97) .

O m Emergency Fuel Oil a EDSFA(91/92) 0 m Residual Heat Removal u Planned (4/30/98)

O m Diesel Building HVAC a EDSFA(91/92) o a Auxiliary Turbines a ALSFA(12/31/96)

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O A Purpose O{

O gaJ m Assess agreement of USAR with the design O

basis and current design output documents 8S 0

m Assess adequacy of current design assumptions o m Assess effectiveness of the testing and E{

S surveillance program to verify design basis (active functions) 0 o u Assess effectiveness of our operating o experience program 0

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A Additional Tasks 0 m Assess if design changes effectively addressed spare parts 0

and procurement. In addition, determine if design changes O are correctly reflected in vendor manuals and drawings 0 m Verify the Technical Specification requirements for the 0 AFW are met by current AFS surveillance testing U m Survey USQDs, OIRs and TS clarifications to determine if o they agree with the design and licensing bases of the plant O , a Evaluate the targeting and prioritization tool and the work 0 Product evaluation tool O m Review a sample of completed design modifications to g ensure necessary post modification testing was completed O m Assess the adequacy of equivalency evaluations O

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O Assessment Team iA l 8 =====

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0 3 Review Panel Members:

l 0 Abdy Khanpour-INPO Britt McKinney - Piant Manager '

O Biii ausseii- consultant nick Muench - VP Engineering Jim Kammer- Duke Power Brad Smith - Project Engineer O Mark Kachmar- Westinghouse Brad Norton - Manager O

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  • Previous or current Estimated Workforce IIours Expended to Date: 8120 0 SRO license or certified individual Estimated Workforce Ilours Remaining: 1760

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O Relevant Findings to Date O

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o u 3 LERs O

O m 0 Apparent Design Bases issues O

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A License Basis Review 0[E; 0

O a Assume all requirements were established in license S documents in place at time ofinitial license.

O m Identify differences between the USAR and the FSAR 0 '

s Strategy will verify the USAR is currently accurate O m Review the present license basis to identify functional S requirements.

0 m Identify active functions design bases from the USAR O

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A License Basis Review Observations O

Sf; a Approximately 35 USAR corrections noted 0

o a Problems noted were typically:

0 o + Editorial 0

0 + Typographical 0 + Some technical changes during conversion 0 process that do not have specific USQD o evaluations referenced iA O

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A RCMS Review Conclusions 0

Sf; a No USAR cLiscrepancies noted O

o a No cases were found in which we failed to meet a commitment o a 10 administrative problems with RC MS/Procec ure '

0 , references 0

o .1 m 120 RC MS items reviewed 0

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TSC/OIR Review Purpose O

E J m Reviewed active AFW OIRs and TS E clarification to determine if they are in ES esteement withthe de8isn se8eeaed E licensing basis of the plant.

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A rsc/01R Review Discussion O

O 8 {m J m Technical Specification clarifications 8 associated with Auxiliary Feedwater aS reviewed - F1R ieeeed cio/8/96) eed E further work delegated to the TSC IIT.

O g3 oI m Reviewed open OIRs against Auxiliary 0

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O o Design Change Review Preliminary g Observations O

Ef; a Changes and outputs accomplished by the packages 0 are consistent with the design basis e Input / assumptions are consistent with design basis.

o a Improvement in the documentation of design inputs S , coincident with new procedures.

O O 1. m 1 USAR discrepancy noted out of 190 packages O

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Calculation Review Preliminary Observations O

O m Calculations inputs and assumptions are accurate and consistent with and 2 support the design bases with a few exceptions.

O O m Subject matter and purpose is normally well defined and a consistent O

methodology is used to produce similar calculations O a Calculation methodology is based on sound engineering principles and O consistent with normally accepted industry standards with one exception O

o , a Civil, structural, stress and seismic calculation assumptions are sometimes O based on engineeringjudgment rather than reproducible references. The O basis for this engineeringjudgment is often undocumented O

O m 3 USAR discrepancies found during review in which the assumptions in O the USAR needed to be updated O

O m 17 discrepancies noted out of 330 calculations reviewed to date such as O lack ofinput reference source documents O

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o a Of 371 change packages reviewed for material .

i S considerations, five di.screpant parts issues were 0

discovered.  ;

E a 3 discrepancies were parts in warehouse that were O f, not per design.

E a 2 cases found where parts were install in plant 0 (Airset and MFW Bypass Valves) m No USAR discrepancies noted O

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This reviewis looking at the ststability of testing to venfy system O  ;

g 250 fmetions. . ___.. - _ _ _ - . _ _ . _ _ _ _ _ . _ . . _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ ___

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F unct ion and Testing Review A Preliminary Observations 0

Sb 0

u For every technical specification and USAR function, an active design function was identified 0 that fulfills the functional requirement.

0 m With 3 exceptions, the surveillance requirements of 0 TS were complied with.

O 1 0 m Four USAR discrepancies were noted i S a Verifying that active function design bases are being 0 met 0

O O 22 0 i J

O '

O Lessons Learned Review A Methodology O

U OTRJ m Reviewed the following documents associated with o Auxiliary Feedwater O

o + Approximately 80 ITIPs associated with the ,

O Auxiliary Feedwater System were reviewed 0 + Approximately 200 PIRs associated with Auxiliary U

Feedwater were reviewed.

0 m Follow-on review by PSE Group of approximate 111 O Operation Experience notifications from INPO to U

ensure appropriate documents were entered into the 0 program.

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0 23 0

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O O

Lessons Learned Review A Preliminary Conclusions 0

J m PIR and ITIPs review did not identify any new impact o the design or license basis of the plant i O

o a The PIR process needs enhancement U

a Corrective actions associated with PIRs needs 0 improvement a Trending and monitoring of PIRs should be enhanced O

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Sf; a 5 people years expended on an extensive system 0

functional assessment o E No significant issues discovered o a No recommended change in scope for ESW 0

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