ML20128N087

Summary of 930203 Meeting W/Util in Rockville,Md Re Mgt Issues for Facility.Meeting Consisted of OPPD Mgt Discussing Issues Re Pts,Design Basis Reconstruction & Spent Fuel Pool Reracking at Facility

ML20128N087
Person / Time
Site:	Fort Calhoun
Issue date:	02/14/1993
From:	Steven Bloom Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9302220482
Download: ML20128N087 (25)

Text

_ . _ _ _ . . . .

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-February 14, 1993

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Docket No. 50-285 LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1

SUMMARY

OF MEETING HELD ON FEBRUARY 3, 1993, WITH OMAHA PUBLIC POWER DISTRICT TO DISCUSS MANAGEMENT ISSUES FOR FORT CALHOUN STATION The staff met with Omaha Public Power District (0 PPD) on February 3, 1993, at One White Flint North to discuss management issues for Fort Calhoun Station.

The list of meeting attendees is enclosed (Enclosure'l).

The meeting consisted of OPPD management discussing issues such as pressurized thermal shock, PRA/IPE/IPEEE projects, design basis reconstitution, spent fuel pool reracking at Fort Calhoun Station, the July 3 and August 22, 1992 events and lessons learned,1993 challenges and strategic issues. Enclosure 2 is the

]

basic information that was presented.

S It/ven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Project III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION LIST FOR MEETING

SUMMARY

FEBRUARY 3, 1993:

. Docket File NRC & Local PDRs PDIV-1 Reading T. Murley/F. Miraglia J. Partlow J. Roe M. Virgilio G. Hubbard T. Alexion P. Noonan OGC E. Jordan, MNBB 3701 ACRS (10) P. Harrell, RIV 1

0FC PD4-1/LAh PD4A)/PM PDIV-1/ Dug tp l' /</

NAME PNoonhv' SBfo[o*m/vsbGHubbard DATE 9/ D /93 1/ll/93 2/f//93 0FFICIAL RECORD COPY Document Name:

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9302220482 930214 W ADOCK 05000285 q( U PDR

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i NUCLEAR REGULATORY COMMISSION

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, , g ,o February 14, 1993 Docket No. 50-285. '

y LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1

SUMMARY

OF MEETING HELD ON FEBRUARY 3, 1993, WITH OMAHA PUBLIC POWER DISTRICT TO DISCUSS MANAGEMENT ISSUES FOR FORT CALHOUN STATION-The staff met with Omaha PublicL Power District (OPPD)1on February 3,1993, at-One White Flint North to discuss management issues for Fort Calhoun Station.

The list of meeting attendees is enclosed (Fnclosure 1). .

The meeting consisted of OPPD management discussing issues.such as pressurized thermal shock, PRA/IPE/IPEEE projects, design basis ,'econstitutica, spent fuel pool reracking at Fort Calhoun Station, the July 3 and August 22, 1992 events-and lessons learned,1993~ challenges and strategic issues. Enclosure 2 is the-basic information that.was1 presented, e -:

Steven D. Bloom, Project Manager Project Directorate IV Division-of Reactor Project III/IV/V Office of Nuclear Reactor Regulation-- "

Enclosure:

As stated cc w/ enclosure:

See:next page

.)

,..--,__.____i___'__--____._-----------------------------------------------^^-------------^^^^^^'^~^-'~^'---~^^----

i a

Mr. Terry L. Patterson Omaha Public Power District Fort Calhoun Station, Unit No.1 cc:

Harry H. Voigt Esg.

LeBoeuf, Lamb, Leiby & MacRae 1875 Connecticut Avenue, NW Washington, D.C. 20009-5728 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Raymond P. Mullikin, Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health Nebraska Department of Health ~

301 Centennial Mall, South Post Office Box 95007 Lincoln, Nebraska 68509 Mr. James W. Chase, Manager Fort Calhoun Station Post Office Box 399 Fort Calhoun, Nebraska /.3023 0

9- Enclosure-1:

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= MEETING BETWEEN NRC-. STAFF AND OMAHA PUBLIC POWER-DISTRICT-FORT:CALHOUN STATION, UNIT 1 MANAGEMENT ISSUES February 3._1993- -

MEETING' PARTICIPANTS' lLQiE ORGANIZATION

- T.= Murley NRR F. Miraglia NRR J. Partlow- NRR/ADPR J. Roe NRR/DRPW G. Hubba'rd - NRR/PDIV-1:-

S.-Bloom NRR/PDIV-I-C.-Yates NRR/PDIV-I-M. Houston ACRS P. Baranowski EDO . .

. B. Jones '0 PPD / Senior-Vice-President-

~

W.' Gates OPPD/Vice President . .

S. Gambhir

. OPPD/ Division Manager - Production: Engineering:

R;.Short OPPD/ Manager - Nuclear-Licensing / Industry

~ Affairs.

E. Hiruo McGraw-Hill Nuclear-' Publications:

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OMAHA PUBLIC POWER DISTRICT NRC/OPPD MANAGEMENT MEETING FEBRUARY 3,1993 i

Omaha Public Power District l 4

l AGENDA Opening Comments Bill Jones Pressurized Thermal Shock Sudesh Gambhir PRA/IPE/IPEEE Projects Sudesh Gambhir Design Basis Reconstitution Sudesh Gambhir Spent Fuel Pool Reracking Sudesh Gambhir July 3 and August 22,1992 Events Lessons Learned Gary Gates 1993 Challenges Gary Gates Strategic issues Bill Jones 4

1

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'J. PRESSURIZED THERMAL SHOCK (PTS)  !

1 l

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• Condition of FCS Reactor Vesselis Well Documented- l 1

l a Limiting weld / plate material chemistry known m 100% ISI Completed 1992 Outage a 6 Surveillance Capsules Currently Installed a FCS Specific Limiting Weld Surveillance. Capsule

- 1993 Outage Installation

• Employed L.r.e/ Extremely Low-Radial Leakage Cores-Since Cycle 8

• Cycle 14 Core Flux Reduction Features a Hafnium Flux Suppression Rods a Natural Uranium Fuel Assemblies in Peripheral--

Locations a Integral Fuel Burnable Absorbers

• PTS. Screening Criteria Reached 2010/2011 with Cycle 14 Type Core 2

F a

5.

6 PRESSURIZED THERMAL SB_OCK (PTS) (Continued 1 5 .

I;

• Cycle 15 Design Results in Further Flux Reductions

• I ,

s PTS Screening Criteria Reached After 2013 i

• Upper Shelf Energy Maintained Above 50 ft-Ibs

• Monitoring NRC/ Industry Enhancements a ABB/CE Reactor Vessel Group Member a NUMARC ADHOC Advisory Committee Member

• Summary: Proactive Management of PTS Issue 3

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i k .PRA/IPE/IPEEE PROJECTS E

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• Committed to Full Scope Level lli PRA 9

• A Living PRA is our Goal 1

• Dedicated Staff Working with Outside Consultant

,

• PRA Status:

. m Level I & il Models Complete i

• PRA Oversight Committee Formed Summer 1992 m Membership - Operations, Maintenance, Design and System Engineering, Training and Licensing a Review Criteria

• Core Damage Frequency (> 10 4)

• Important Contributors to Core Damage Frequency or Poor Containment Performance a Preliminary Finding Regarding Potential Overpressurization of CCW System Shared with NRC Staff 5

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b PRA/IPE/IPEEE PRO _JECCIS (C_ontinued)

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• PRA Results are Being Used g

a 1992 Refueling Outage a Modification Activities e e Station Battery Replacement t

-

• PRA Schedule:

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- m Final Level I/II/lli Models to NRC -

December 1993 i

- e IPEEE Schedule:

. m All Events except Seismic and Fire -

. December 1993

^

m Seismic and Fire Events - June 1995 E a To be Combined with USI A-46 Resolution

- Outage Walkdowns Required

[ e Summary: FCS PRA wili be a living program and

, exceed GL 88-20 requirements 6

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!- Df3JGN BASIS RECONSTITUTION 1

• DMectives:

m Index and Sort the Original Construction and Design Basis Records e

j u Create Plant Level and System Level Design Basis Documents

' s Perform Verification to Confirm That Safety Systems Con Perform Their Normal and Post

! Accident Design Functions

• Results Achieved:

! u Over 50,000 Design Documents Indexed a 33 System Level Documents Developed a 16 Plant Level Documents Developed a Several Significant Design Deficiencies Have Been Identified and Corrected

• Containment Spray System

• MS and MFW Piping -

a Numerous Calculations Have Been Recreated t

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DESIGN BASIS RECONSTITUTION (Continued) i I.

o Ooen item Definitions / Status:

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a Categorized by Safety Significance s Majority of Safety Significant items Closed i a Closure of Remaining Open items: Planned Based on Safety Significance i e Resign _ Basis Document (DBD) Maintenance:

I a Design Engineers - Assigned as System / Plant Level Sponsors l

a Procedures in Place to Require Use and Updating of DBDs e Summary:

s Several Design Basis Problems That Probably Would Not Have Been Found Were identified and Corrected l m DBDs Will Provide the Basis for Future

. Modifications i

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SPENT FUEL POOL RERACKING Capability for Full Core Offload Lost During 1995 Outage

• Last Reracking Completed in 1984 l

j

• Higher Density Racks Planned 1 m Storage Capacity to be Increased g

from 728 to 1083 j

• Will Extend Full Core Offload Capability to 2006

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• Schedule

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a Application Submitted - 12/92 l

a NRC/0 PPD Meeting - 12/15/92 m NRC Requested Approval - 5/93 a New Racks Installed - 1994 f

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'!. JULY 3_and AUGUST 22,1992 EVENTS LESSONS LEARNED s

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• Importance of Operator Simulator Training

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• Upgraded EOPs/AOPs were key T

e e Emergency Organization Response &

Quarterly Readiness Drills

• Primary System Challenges due to Secondary i Side Single Failure Vulnerabilities 1

• Pressurizer Safety Valve Setpoint Testing s Loop Seal Effects

u In-situ vs. Laboratory Testing Differences i

• Improved Handling of Circuit Boards with

. Jumpers i

$

• Plant Reliability Sensitization 10 1

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PRESSURIZER SAFETY VALVE y 3,gogy

2. NOZZLE y , 3. I4CZILE RING 7 l 4 NCZ2LE RING 3 r' ,X SET SCREW

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.1993 CHALLENGES e improve Forced Outage Rate / Station Reliability l 4

a While Maintaining Safe &

Cost Effective Operation 4

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• 1993 Refueling Outage - 56 Days

• Further Improve Shutdown Safety during 1993 1 Outage 1

L

• 10 CFR 20 Project implementation - July 1993 1

, o GL 89-10 MOV Design Basis Testing - 1993 i Outage I

• Individual Plant Evaluation (IPE) Completion i ,

I

• Strive for Continued lmprovement i e Avoid Complacency 1

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12 r

STRATEGIC ISSUES

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• Power Uprate Status  !

• Decommissioning Funding increase - $116.5 l

million to $312 million 1

• Cost Effective Operation 1

• Performance indicators I

• Second 161KV Offsite Power Source t ,

i e

13

i I

I I APPENDIX A .

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.- FORT CALHOUN-STATION SIGNIFICANT IMPROVEMENTS i .

PROJECTS / PROGRAMS t l u Project 1991 Projects (see attached description) e Design Basis Reconstitution 5 m AOPs/EOPs I

a Reactor Vessel 100% ISI I

a Thermal Shield Repair I a Fire Barrier Upgrade l

MODIFICATIONS a Third Auxiliary Feedwater Pump r

a Security System Upgrade

a 480V Breaker Trip Devices a Diesel Generator Upgrades

]

t a Shutdown Cooling Low Flow Alarm 4-a MS/MFW Pipe Supports l-a Station Battery Replacement s SIRWT Discharge Valve Replacement f

15 1

.o. _

j .

i OTHER l m Plant Specific Simulator a New Warehouse, Chemistry /RP and Administration Buildings '

s System Engineering j f r A

f.

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1 I

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1 I

4.

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16-3

. . - - . - - . - - - . . . . . . . . . , - - . . ~. . ..-. . ..

l '

PROJECT 1991 PROJECTS

-l . .

, FACILITY APPEARANCE UPGRADE

1. Restored the physical appearance of the Fort Calhoun Station to a like-new or better-than-new condition.

2. Established an ongoing program to maintain the site and the plant in a condition to be a model for both OPPD and the nuclear industry, f

i PREVENTIVE MAINTENANCE PROGRAM UPGRADE j 1. Maximize the performance and availability of critical plant equipment through the implementation of periodic, predictive and planned i

maintenance actions.

2. Reduce corrective (and total) maintenance costs.

PROCEDURES UPGRADE

1. Upgrade the Fort Calhoun Station Operating Manual procedures to current industry standards, including both technical and human-performance. considerations. This involves a total of approximately .

. 3000 procedures.

2. Establish a methodology to ensure that procedures are maintained in a-upgraded condition.

3 3. Achieve a substantial reduction in the nurrSer of human performance

., problems which can be attributed to procedural inadequacles.

a Y

4 F

's 17

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mii ie l EftQECT 1991 PROJECTS (Continuedl TRENDING AND ROOT CAUSE ANALYSIS L

Established a methodology for conducting trending and completing root cause analyses.

VENDOR MANUALB PROGRAM UPGRADE

1. Facilitate reliable and safe power generation consistent with NRC

( Generic Letter 83-28 by establishing a continuing program to ensure I that safety-related vendor technical information is complete, current and controlled.

1

2. Optimized rnalntenance and operations support by performing a review e of non safety-related manuals, l

COE PROCUREMENT AND__ STORAGE

[

Established / upgraded station spare parts, shelf life and procurement i procedures for cafety-related material to meet currently accepted NRC and industry standards, e LABELING i

1. Developed labeling standards and implemented a program which clearly, i accurately and permanently identifies equipment, components, fixtures, I rooms and areas.

9 1 2. Established a program to ensure that the labeling improvements are maintained for the operating life of the station.

{

4 I

18 l

PROJECT 1991 PROJECTS (Continued)

ASBESTOS MANAGEMENT Developed a program and database to manage all asbestos-containing material in the Fort Calhoun Station to protect the health and safety of employees and to comply with EPA, OSHA and State requirements.

WELplNG AND_ TORQUING f 1. Developed and implemented a comprehensive welding program that is ,

A among the best in the industry. The program includes:

l a. A programmatic document that addresses all applicable regulatory requirements.

b. Procedures that comply with the applicable editions of the ASME

. and AWS codes.

c. Procedures for testing and qualifying welders and performing required welding Quality Controlinspections.

[ 2. Developed and implemented a procedure to control and document the i torquing of safety related threaded fasteners.

I I

INSTRUMENT LOOP UNCERTAINTIES 1 Determine the device, loop and test equipment accuracies for safety-related instrumentation and verify their adequacy.

, CHAMPS DATA BASE UPGRADE -

i Developed an equipment data base which contains all plant equipment, I completely reflects all maintenance and modification activities and is I maintained in an accurate and upgraded condition.

k f

i 19 4

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