ML17312B177

Summary of 961112 Meeting W/Util in Rockville,Md to Discuss Topics of Mgt Interest Re Licensees Engineering Organization.List of Attendees & Handout Encl

ML17312B177
Person / Time
Site:	Palo Verde
Issue date:	01/09/1997
From:	Clifford J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9701210034
Download: ML17312B177 (33)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 January 9,

1997 LICENSEE:

Arizona Public Service Company FACILITY:

Palo Verde Nuclear Generating Station, Units 1, 2, and 3

SUBJECT:

MEETING

SUMMARY

The NRC staff met with representatives of the Arizona Public Service Company (APS) on November 12, 1996, at NRC Headquarters in Rockville, Maryland, to discuss topics of management interest related to the licensee's engineering organization.

Attendees are listed in Enclosure 1.

Nr. Ide introduced himself as the new Vice President, Engineering for APS at Palo Verde.

He identified several additional personnel changes that followed the recent senior management changes at the site.

He provided a handout (Enclosure

2) that provided the outline for further discussions.

Mr. Ide discussed the various monthly trends, with specific emphasis on the areas requiring improvement.

These areas included reactor trips, personnel contamination

events, (NRC) notices of violation, and corrective action timeliness.

In addition, Mr. Ide identified a need for improvement in the licensee's 10 CFR 50.59 program, as the licensee's quality group is still finding issues not found by the line organizations.

Mr. Ide then discussed issues related to the recent 10 CFR 50.54(f) letter regarding certification of licensing and design basis.

Nr. Ide discussed the licensee's previously completed design basis reconstitution program and the resultant design basis manuals (DBM) for each system.

In addition, Mr. Ide stated that the licensee will be doing a detailed Updated Final Safety Analysis Report review, including a full review of the current licensing basis.

They will then compare this with the design basis and implementing procedures.

Nr. Ide asked several questions related to the recent 10 CFR 50.54(f) letter.

He asked if the references in the letter to "design basis" was strictly the 10 CFR 50.2 definition.

The staff suggested that the licensee not be too narrow in interpreting the term.

Nr. Ide asked how long the staff expected the response to be, i.e.,

how extensive.

The staff suggested that the response needed to cover the full scope of the issues addressed in the letter, with detailed supporting information as appropriate.

There was,

however, no specific "right" answer for all licensees.

Each licensee would have to evaluate the extent of the information they have to support their design basis and respond accordingly.

970i2i0034 970109 PDR ADQCK 05000528 P'DR

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Hr. Ide briefly discussed the process the licensee used to develop the improved standard technical specifications submittal that APS recently sent in for staff review.

Hr. Ide then outlined the licensee's plans for dry cask storage.

The licensee is currently working with a cask vendor to design a cask for the System 80 fuel.

No contract has been let with the vendor as yet.

The licensee indicated they plan three years for NRC review of the design.'he staff stressed that new cask designs would require a rule change, and experience has shown that process to take five years from the time the cask vendor submits the design until a plant is able to implement the design.

The staff discussed the implications of the reviews conducted at Hillstone, Haine Yankee, and Dresden on future staff activities.

The staff indicated that licensees should expect more involvement by headquarters personnel, both project managers and technical staff, in verification of licensee activities.

In addition, the staff is working on ways to make licensee commitments and conditions of safety evaluations legally binding on licensees.

No regulatory decisions were requested or made.

~:u>~(1i~D!,,g Ja es W.

Cl iff rd, Seni or Project Hanager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos.

STN 50-528, STN 50-529, and STN 50-530 Attachments:

1.

List of Attendees 2.

Handout cc w/atts:

See next page

Hr. Ide briefly discussed the proces's<tPe" l,icensee used to develop the improved standard technical specifications 'submittal that APS recently sent in for staff review.

Hr. Ide then outlined the licen'see"'s'plans for dry',<cask storage.

The licensee is currently working with,a~ cask~vendor 'to "de'si.gn a'cask,for the System 80 fuel.

No contract has>been,let withth'e,ven'dor as'.yet"."

The licensee indicated they plan three,~years,'for.

NRC< review of the design.

The staff stressed that new cask designs "would require Ia rule ',change, and experience has shown that process to", take five> y'ears 'from'he, time'h',"cask",vendor submits the design until a plant is able~Fto imple'm'ent the design..>>"',

The staff discussed the implicati'ons;,o:-the-,reviews coneducted at Millstone, Maine Yankee, and Dresden on future staff activities.",

The staff indicated that licensees should expect more,invol vement~gy headquarters personnel, both project managers and technical'taff(,.in verification'f licensee activities.

In addition, the staff is'workingcop'ways to make. licensee commitments and conditions of safety evaluations,'legally binding-on, licensees.

No regulatory'decisions were 'requested or 'made.

Original Signed, By

', James

-W. Clifford; 'Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos:

STN 50-528, STN 50-529, and STN 50-530 Attachments:

1.

List of Attendees 2.

Handout cc w/atts:

See next page

>70054 Document Name:

11-12-96.sum DISTRIBUTION: (Hard Copy)

/Docket File'UBLIC ACRS PDIV-2 Reading OGC DISTRIBUTION:

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FHi raglia, FJM

AThadani, ACT

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WBateman, WHB JClifford, JWC

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EPeyton, ESP

EJordan, JKR RZimmerman, RPZ JHittchell, JAH

DKirsch, DFK OFC NAME DATE PDIV-2 JCl ord

/(/6 PDIV-2 Eeyo 1

96 PDIV-2 WBatema 1 P /97 P=-:e OFFICIAL RECORD COPY

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Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street

Phoenix, Arizona 85007 Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O.

Box 800

Rosemead, California 91770 Senior Resident Inspector USNRC P. 0.

Box 40 Buckeye, Arizona 85326 Regional Administrator, Region IV U.

S. Nuclear Regulatory Commission Harris Tower

& Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064

Chairman, Board of Supervisors ATTN:

Chairman 301 W. Jefferson, 10th Floor

Phoenix, Arizona 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street

Phoenix, Arizona 85040 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.

Box 52034

Phoenix, Arizona 85072-2034 Mr. John C. Horne, Vice President Power Supply Palo Verde Services 2025 N. Third Street, Suite 220

Phoenix, Arizona 85004 Mr. Robert Burt Los Angeles Department of Water

& Power Southern California Public Power Authority 111 North Hope Street, Room 1255-B Mr. David Summers Public Service Company of New Mexico 414 Silver SW, ¹0604 Albuquerque, New Mexico 87102 Mr. Brian Katz Southern California Edison Company 14300 Mesa Road, Drop D41-SONGS San Clemente, California 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, Ar>zona 85251 Mr. James M. Levine Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999

Phoenix, Arizona 85072-3999

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November 12, 1996 MEETING WITH ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 ATTENDEES

arm, Roy Zimmerman Jim Clifford Bill Ide Affili i n USNRC USNRC APS Enclosure 1

MEETING WITHARIZONAPUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 MANAGEMENTMEETING November 12, 1996 HANDOUTMATERIALUSED AT THE MEETING Enclosure 2

e

November 1996 NRC Engineering Update

Senior Vice President Nuclear Jim Levine I

W W Human Resoecee ds await Wg,~~+ Cr Director Nuclear Assurance Rom Fullmer Department Leader Internal Communlcathns Sue T Ino DepL Leader Opo. Aoeraaxa Ed Dept.

Eng. Assuranc>>

Ron Y PtL Sup. Assuranc>>

StaL Analysis Orp Dale Leech Tom Bracken Department Leader External Communlcathns Craig Nesblt Wce President Nuclear Production Wce President Nuclear Support Jack Balle DepL Leader hrs rcahncroor Hwa-Ja Marks Assistant to VP Larry tkrugttby Woe President Nuc Engineering Bill Ide Dkactor Rad. Protection Mke Shee Director Outagss Tony Rarkke Director Emergency Senrkee Craig Seaman Loader Employee Concerns Poter Rail DepL Loader Steam Oonerator Proloct Rich Schatior Director Kudeer Fuels Paul Crawley DepL Leader Specialty Eng Tom Carvrcn Dkactor ttatntenanco Dave Maukln Tom Shaw David M. Smrrh Dkoclor Olreehr Water Roc FactSty Operations Director Kucloar Training John Vskcta Director Arhntn. Servkee Cad Churchman Director Dept Loader Kucloar Engineering System Engineering

usiness an trate ies Nuclear Safety Industrial Safety Oversight and Industry Performance Economic Performance Plant Performance and Reliability Environmental Performance Professionalism

Nuclear Safety Low Risk Significant 8 stems

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Contractor Industrial Safe

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Industrial Safety

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';<<Perfolmsnce Ng t3 Oversight &

industry Performance Ucensee Event Reports Business Ptan Trend

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'Pr"i ~~ tx,i";~i~'s Economic Performance

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v W@aQ Petfori%ko:-'lant Performance

&Reliability

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Environmental Performance

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Professionalism

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Significant

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Strength Satisfactory Improvement Needed Significant Weakness Code Year-to-Date Target rev ous 0

~ l4:<i'+jp ~~}&St Total Accomplishment B Business Plan Accomplishment Employee Incentive Plan (as a percent of base pay)

SIP/o 80'Yo 5'Yo September 1996 Palo Verde Nuclear Generating Station Monthly Trend Report

e ort Superior Safety Performance in Operations, Maintenance, Engineering Good Safety Performance in Plant Support Strong Management Leadership and Involvement Strong Self-Assessment Culture

xecutive ummar Strengths 0 Critical Self-Assessments I Effective Communication of Management's Priorities 0 Appropriate Use of Probabilistic Safety Assessment

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n ineerin trate ic an Vision 1 Power Plant Equipment, Systems, and Fuel Treated As Customer I Focus on Safety, Reliability and Availability

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ttri utes o oo n ineerin Timely Resolution of Technical Problems Rigorous Application of Engineering Principles an Analysis Effective Technical Communication Preservation of Design and Licensing Basis Technical Conscience Focused on Safe Operations Strategic Application of New Technologies Strong Technical Program Management Effective Engineering Business/Project Management Maintenance of Plant Configuration

n ineerin I asis Engineering Self-Assessment Improved Technical Communications Support Plant in Resolving Operation Workarounds, etc.

Monitor System Performance Maintain Pristine Design Basis Consistent with Licensing Basis Timely Resolution of Emerging Issues and Corrective Actions Simple, Cost Effective and On Time New Designs

n ineerin tren t s 0 Flexible, Qualified Staff Committed to Continuous Improvement 0 Focused Team Performance for Functional Groups Valve Services Steam Generators Nuclear Fuels Fire Protection Probabilistic Risk Assessment

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n ineerin a en es I Sustain High Level of Performance and Plant Focus I Continuous Improvement through Self-Assessment Focus I Inter-Engineering Departmental Communication

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i ni icant n ineerin ctivities Licensing l Design Bases Reviews Use of PRA Steam Generator Program Nuclear Fuel Management

icensin esi n

ases eviews Comprehensive FSAR Strong Focus on 50.59 Program Design Basis Reconstitution Completed 12/95 Preliminary FSAR Review Using NEI Guidelines Detailed FSAR Review Action Plan in Progress Improved Technical Specification Preparation 10CFR 50.54{f}Letter

se 0 Maintenance Planning 0 Emergent Plant Conditions 0 Graded Procurement 1 Pilot IST Program

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team enerator rimar ssues 0 Analyses Supports Full Cycle Operation in Units 2 and 3 Long Term Trends Indicate SG Replacement in Unit 2 Desirable Participation in Alternate Repair Initiatives for Circumferential and Axial Cracking 0

Tech Spec Amendment for Sleeving

uc ear ue ana ement Independent In-House Reloads Comprehensive Reactivity Management Program Safety Analysis Design Basis Reconstitution Completed 6/96 Dry Cask Storage Ongoing Fuel Improvement Programs SOER 96-02 Evaluation Actions in Progress

en in tems NRC Approval of Improved Technical Specifications t SG Performance t CBLAs Steam Generator Tube Sleeving Technical Specification Amendment I Approval of Lead Test Assembly Clad Exemption

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