ML20151Z940

Forwards Meeting Summary of 880811 Enforcement Conference Re Findings in Insp Repts 50-285/88-22 on 880629-0718.List of Attendees Encl

ML20151Z940
Person / Time
Site:	Fort Calhoun
Issue date:	08/23/1988
From:	Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Morris K OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8808300311
Download: ML20151Z940 (26)

See also: IR 05000285/1988022

Text

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lAUS 23 im -

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In Reply' Refer.To: . .

_ Docket: '50-7.?5/88-22

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Omahc l'ublic Power District ,

ATTN _ Kenneth J. Morris, Divhite. Hanager

Nuclear Operations

1623 Harney Street - i

Omaha, Nebraska -68102

. Gentlemen:

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This refers'to the Enforcement Conference conducted in the NRC Region IV

Office on August.11, 1988, with you and' other members" of your-staff, and _

"

Region IV personnel. This conference was-related to theifindings of the NRC

inspection conducted during tie period June 29:through July 18. 1988,=which e

,

were documented in our NRC Inspeet'on-Report 50-285/88-22 dated July 29, 1988. l

The subjects discussed at this meeting are described in the :nclosed Meeting ~ .

q Sumary.

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In accordance with Section 2.790 of'the NRC's "Rules of Practice," Part 2

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1 Title 10,. Code of Federal Regulations, a copy of t iis letter will be placed in l

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the NRC's Public Document Room.-

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Should yos hwt; any. questions conccrning this matter, we will be pleased to j

discuss theia with you.- i

Sincerely,  !

Original Signed By .

l A. B. Beach

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L. J. Callan, Director .

Division of Reactor Projects

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Enclosure:

! Meeting Sumary w/ attachments (2)

e- cc w/ enclosure:

Fort Calhour Station

ATTN: W. G Gates, Manager .

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P.O. Box 399 ,

Fort J.alhoun, Nebraska 68023 8808300311 880823

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PDR ADOCK 05000285 t

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Harry H. Voigt, Esq. G PNV

Le'oeuf, Lamb, Leiby & MacRae

1: 1 New Hampshire Avenue, NW ,

i W: Uington, D. C. 20036

4 ' ebraska

n Radiation Control Program director

RIV:PSB h C:P5Bk D: DRPH gg/

RPMullikin;df TFWesterman LJCallan gp

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bec distrib by RIV- -

R.D. Martin, RA -RPB-DRSS

SectionChief(DRP/B)- MIS System- .)

RIV File- 'DRP .

RSTS Operator Project Ergineer, DRP/B l

Lisa Shea, RM/ALF P. Milano', NRR Project Manager

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ENCLOSURE

OMAHA PUBLIC POWER DISTRICT

JUNE 8, 1988'

MEETING SUMMARY

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Licensee: Omaha Public Power District (OPPD)

Facility: FortCalhounStation("CS)

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License No.: DPR-40

Docket No.: 50-285

, SUBJECT: ENFORCEMENT CONFERENCE CONCERNING NRC INSPECTION FINDINGS

(INSPECTION REPORT 50-285/88-22)

On August 11, 1988, representatives of Omaha Public Power District, met in

Arlington, Texas, with NRC Region IV and NRR personnel to discuss the findings

documented in the NRC Inspection Report dated June 1,1988. The attendance

list and licensee presentations are attached. The meeting was held at the

request of NRC, Region IV.

The intent of the enforcement conference was to discuss the Fuel Cycle 11

setpoint errors. This resulted in the limiting condition for operation for

excore monitoring of linear heat rate and the thermal margin / low pressure trip-

setting of the reactor protection system being in error.

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Attachment 1

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Enforcement Conference Attendance List - Region ~ IV

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Omaha Public Power Distric{

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. NRC Attendees:

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A. B. Beach, Deputy Director, Division of Reactor Projects, RIV

J.- L. Milhoan,. Director, Division of Reactor. Safety, RIV:

G. F. Sanborn -Enforcement Officer,.RIV

T. F. Westerman, Chief. Project Section B RIV

R. P. Mullikin, Project Engineer, RIV

P. H. Harrell, Senior Resident Inspector, Fort Calhoun

T. Reis, Resident Inspector, Fort Calhoun

OPPD Attendees:

X._ J. Morris, Division Manager

J. F.' Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs

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S. Gambhir, Section Manager, Generating Station Engineering

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Combustion Engineering (CE) Attendees:

H. Fields, Supervisor, Analog Transients and Setpoint Analysis

T. G. Ober, Project Manager

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ATTACIDfENT 2

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FORT CALHOUN STATION

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NRC / OPPD  %

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MEETING

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AUGUST 11,1988 ,

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TM/LP SETPOINT ERROR MEETING AGENDA

August 11, 1988

Inspection Report 50-285/88-22

I. Opening Remarks / Introduction K. J. Morris

S. K. Gambhir

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II. Overview of Meeting J. J. Fisicaro

_ ._.

III. Potential Violation - Operated Cycle 11

with Nonconservative Technical Specifica-

tion Sete,oints (285/8822 01)

, K. C. Holthaus

- Background

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Statement of Problem

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TM/LPLogic

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Sequence of Events and Ismediate

Corrective Actions /Results Achieved

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Root Cause

- Completed Corrective Actions

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Safety Significance

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Sumary/ Closure

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IV. Potential Violation - Inaccurate Information

Provided to NRC (285/8822-02) J.- D. Kecy

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Statement of Problem

- Sequence

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Intent of Statement

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Cause

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Future torrective Actions Planned

V. Closing Statement and Conclusions K. J. Morris

, S. K. Gambhir

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BACKGROUND '

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STATEMENT OF PROBLEM

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TN/LP LOGIC

SEQUEHCE OF EVENTS N;D DetEDIATE

CORRECTIVE ACTIONS

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ROOT CAUSES

COMPLETED CORRECTIVE ACTIONS

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SAFETY SIGNIFICANCE

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$UPMARY/ CLOSING I

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BACKGROUND

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OPPD PERFORMING CYCLE 12 RELOAD ANALYSIS

REVIEW OF CYCLE 11 SETPOINT ANALYSIS RESULTED IN

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FINDING TWO NONCONSERVATISMS

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IWtEDIATE CORRECTIVE ACTIONS IMPLEMENTED 1

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STATEMENT OF PROBLEM

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APPARENT VIOLATION 285/6822-01:

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SUMMARY: i

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TM/LP TRIP FUNCTION SET IN A NONCONSERVATIVE

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DIRECTION BY 79 PSIA

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ALL FOUR TM/LP CHANNELS INOPERABLE

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APPARENT VIOLATION OF TECH. SPEC. 2.15

OPPD ADMITS TO VIOLATION AS STATED

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DNBR SAFDL PROTECTION

BY THE TM/LP TRIP SYSTEM

POWER THERMAL MARGIN /

AXIAL SHAPE INDEX ' THERMAL MARGIN TRIP

LO'N PRESSURE

INLET TEMPER ATURE--* Th;P SYSTEM LOW PRESSURE TRIP

PRESSURE  :

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VAR = (f *PF(B) * Al(Y) *B+ [ * Tin +

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THERf AL MARGIN / LOW PRESSURE CALC 0F PVAR

Al ic = 545 ASI = 0.0

RCS PRESSURE (PSIA)

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2100 P

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= 22 Pf(8)A1(Y)B + 22.11 IN- 12603

2000 P = 22 Pf(B)A1(Y)B + 22.1 I ig - 12553

AR SUPom

PVAR

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THERVAL POWER (". Of RATED)

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SEQUENCE OF EVENTS

IM1EDIATE CORRECTIVE ACTIONS /RESULTS ACHIEVED

JUNE 28, 1988: POSITIVE IDENTIFIc/ TION OF ERRORS IN CYCLE 11

SETPOINT ANALYSIS (1700)

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RADIAL PEAXING FACTOR SCALING FACTOR NOT INCLUDED - TECH.

SPEC. FIG. 1-3

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LOCA R0PM NOT (TIILIZED - TECH. SPEC. FIG. 2-6

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REANALYSIS OF CYCLE 11 SETPOINTS INITIATED (1700)

REACTOR ENGINEER NOTIFIES SHIFT SUPERVISORS AND PLANT MANAGER.

INTERIM INSTRUCTIONS

JUNEl 29, 1988: PRELIMIMARY ANALYSIS RESULTS (0730)

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ALL FOUR RPS TM/LP TRIP MODULES DECLARED INOPERABLE (0920)

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BEGAN RECALIBRATION WITH FOUR HOUR TIME LINIT FOR SIGNIFICANT

PROGRESS OR SHUTDOWN TO BE INITIATED (~0930)

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COMPLETION OF SETPOINT REANALYSIS

NRC NOTIFICATION PER 10CFR50.72 (1230)

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RECALIBRATION AND SURVEILLANCE TESTING COMPLETED (1730)

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ROOT CAUSES

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SETPOINT UTILITY. MANUAL DID NOT ADEQUATELY DESCRIBE APPLICATION

OF RADIAL PEAKING SCALING FACTOR

TRAINING PROGRAM

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NOT PERFORMANCE BASED

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TRAINING WAS FRAGMENTED

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TRAINING REQUIREMENTS NOT PROPERLY DEFINED

INEXPERIENCED ANALYST AND REVIEWER

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COMPLETED CORRECTIVE ACT!0NS

REVIEW OF CYCLE 10 SETPOINT ANALYSIS <

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REVIEW OF CYCLE Il RELCAD ANALYSES

EXPERIENCE REQUIRENENT ON ANALYSIS VERIFICATION / INDEPENDENT

REVIEW

PERFORMANCE BASED TRAINING

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FUTURE ACTIONS:

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SETPOINT UTILITY CODE MANUAL CORRECTION UNDERWAY ,

EY.PERIENCE REVIEW REQUIREMENT TO BE INCORPORATED INTO

PROCEDURE

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INDEPENDENT REVIEW OF ALL CYCLE I2 ANALYSES TO BE DONC BY CE.

FUTURE ANALYSES TO BE REVIEVED BY INDEPENDENT NON-0 PPD

ORGANIZATION

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SAFETY SIGNIFICANCE

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NO DES!CN LIMITS WERE OR WOULD HAVE BEEN VIOLATED UNDER TRANSIENT OR STEADY

STATE CONDITIONS WITH RESPECT TO TECH. SPEC. FIGS. 1-3 AND 2-6

SAFETY MARGINS EXISTED FOR PVAR EQUATION IN TECH. SPEC. FIG. 1-3 AS A

RESULT OF CONSERVATIVE OPERATION BELOW TECH. SPEC. LIMITS:

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FR MARGIN OF 6.67 PERCENT (200 PSIA)  !

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TC MARGIN OF 4*F (88 PSIA)

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THERMAL MARGIN TRIP ONLY CREDITED IN SAFETY ANALYSIS FOR TWO EVENTS;

RCS DEPRESSURIZATION AND EXCESS LOAD

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SUMMARY / CLOSING

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PAST EXPERIENCE (CORE FOLLOW REPORT) ,

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SETPOINT ERROR DETECTED BY UPGRADED OPPD RELOAD ANALYSIS l

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PROGRAM

CONSERVATISMS IN ANALYSIS ENSURED THAT NO VIOLATION OF DNB

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DESIGN LIMITS WOULD HAVE OCCURRED

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IMMEDIATE AND PROMPT CORRECTIVE ACTIONS TAKEN

REVIEW OF PREVIOUS ANALYSIS (CYCLE 10 SETPOINTS) AND WORK

UNDERWAY (CYCLE 12) l

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CHANGES IN RELOAD ANALYSIS TRAINING AND REVIEWER

REQUIREMENTS WILL PREVENT FUTURE OCCURRENCES OF SIMILAR

PROBLEMS

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APPENDIX A

DETAILED SE00ENCE OF EVENTS

CE CONTRACTED TO ASSIST IN CYCLE 12 SETPOINT ANALYSIS

PARTIAL REVIEW 0F Tile CYCLE 11 ANALYSIS BY CE ANALYST UNDER OPPD

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DIRECTION RAISED QUESTIONS AS TO WilETilER CERTAIN FACTORS WERE

INCORPORATED INTO TilIS ANALYSIS

ON JUNE 28,1988, TWO P0TENTIAL NONCONSERVATISMS IN Tile CYCLE 11

SETPOINT ANALYSIS WERE IDENTIFIED. MEETING !! ELD BETWEEN OPPD STAFF,

REAC10R ENGINEER AND CE WilICll CONCLUDED THAT:

1) A TEMPERATURE DEPENDENT RADIAL PEAKING FACTOR PENALTY FACTOR WAS

NOT APPLIED TO DNB LSSS ANALYSIS. Tills WOULD RESULT IN A

POTENTIALLY NONCONSERVATIVE PVAR EQUATION IN TECH. SPEC. FIG.

1-3.

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2) LOCA R0PM FACTOR Sil0VLD llAVE BEEN USED IN GENERATING TECil. SPEC,

FIG. 2-6. COMPARISON TO PREVIOUS CYCLE'S MAXIMUM PERMISSIBLE

POWER FOR EXCORE LHR LOC MONITORING INDICATED TilIS POWER SHOULD

BE APPROXIMATELY 85 PERCENT.

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3) SIGNIFICANT MARGINS EXISTED BETWEEN Tile OPERATING VALUES OF

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FXY ' IR AND TC AND THEIR RESPECTIVE TECll. SPEC.

LIMITS. IF NONCONSERVATISM EXISTED IN 1 AND 2 AB0VE, TilESE

MARGINS Sil0VLD BE SUFFICIENT TO PREVENT VIOLATION OF ANY SAFDL.

REVIEW 0F CYCLE 10 SETPOINT ANfsLYSIS TO ENSURE CORRECT APPLICATION OF

METil0D0 LOGY,

CE WAS DIRECTED TO REANALYZE Tile CYCLE 11 SETPOINTS AND PROVIDE:

1) A QUANTIFICATION OF NONCONSERVATISMS IN TECH SPEC. FIGS. 1-3 AND

, 2-6, IF TilEY WERE NONCONSERVATIVE

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2) A DETERMINATION OF ANY OTilER CYCLE 11 SETPOINT NONCONSERVATISMS,

IF TilEY EXISTED

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REANALYSIS INITIATED AT APPROXIMATELY 1700 JUNE 28,1988 l

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REACTOR ENGINEER NOTIFIED ON DUTY P.N. SHIFT SUPERVISOR OF ERROR IN

TECH. SPEC. FIC. 2-6 AND POTENTIAL TECH. SPEC. FIG. 1-3 NONCONSERVA- i

TISN. CONSERVATIVE INSTRUCTIONS PROVIDED TO SHIFT SUPERVISOR I

INCLUDED:

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I) BRING REACTOR TO 80 PERCENT INSTEAD OF 90 PERCENT IF TECH. SPEC. I

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FIG. 2 6 REQUIRED TO BE ENTERED. 80 PERCENT PREVIOUSLY

DETERMINED TO BE CONSERVATIVE

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2) REACTOR ENGINEER TO BE NOTIFIED IN EVENT OF ITEN I AB0VE

3) UNIT TO BE MAINTAINED AT 90 PERCENT POWER AND TC AT 541*F TO

GAIN ADDITIONAL THERMAL MARGIN AND PREVENT ANY POTENTIAL l

REACTIVITY CHALLENGE RESULTING FRON CHANGING CURRENT OPERATING l

PARANETERS

- REACTOR ENGINEER CALLED PLANT MANAGER AND APPRISED HIM OF ABOYE

EVENTS. LCO NOT ENTERED BECAUSE QUANTIFICATION OF FIGURE 1-3 HAD NOT  ;

BEEN COMPLETED. REACTOR ENGINEER INSTRUCTED TO CALL MANAGER - l

EJMINISTRATIVE AND TRAINING SERVICES

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PLANT MANAGER CALLED SHIFT SUPERVISOR TO CONFIRM THAT UPON ENTRY INTO l

TECH. SPEC. FIG. 2 6 AN IM EDIATE POWER REDUCTION TO  !

80 PERCENT WOULD OCCUR l

MANAGER - ADNINISTRATIVE AND TRAINING SERVICES COPMUNICATED WITH OTHER

MANAGEMENT PERSONNEL

REACTOR ENGINEER AGAIN CALLED PM SHIFT SUPERVISOR. GUIDANCE PROVIDED

THAT VHPT NOT TO BE P.ESET - LIMITS POWER INCREASES TO 10 PERCENT

BEFORE TRIP RESULT

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100 703'ON '15 33rOf 'IdO 10 0t E3 4T<80

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TECllNICAL DATA BOOK UPDATE FIGURES FOR EXCORE MONITORING OF LHR LC0

AND TM/LP TRIP / PRE-TRIP WERE APPROVED BY THE PRC ON JULY 1,1988

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OPS MEMO 88-05 (JULY 1, 1988) INSTRUCTED OPERATIONS PERSONN.~.' TO

UTILIZE THE AB0VE TDB FIGURES IN LIEU OF CORRESPONDING TECilNICAL

SPECIFICATIONS l

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OPTIMIZED SETPOINT ANALYSIS COMPLETED BY CE CONFIRMED THAT Tile

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REQUIRED TM/LP ADJUSTMENT WAS 47 PSIA AS OPPOSED TO THE EARLIER

CONSERVATIVE CALCULATION OF 79 PSIA  !

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APPENDIX B

SAFETY SIGNIFICANCE

NO SAFETY LIMITS WERE OR WOULD llAVE BEEN VIOLATED UNDER TRANSIENT OR STEADY

STATE CONDITIONS WITil RESPECT TO TECil. SPEC. FIGS. 1-3 AND 2-6

SAFETY MARGINS EXISTED FOR PVAR EQUATION IN TECilNICAL SPECIFICATION

FIGURE 1-3:

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MAX. FR DURING CYCLE WAS 1,68 VS. TECH. SPEC. LlHIT OF 1.80.

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RESULT IS 6.67 PERCENT MARGIN IN FR OR APPROXIMATELY 200 PSIA

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IN PVAR. OFFSETS NONCONSERVATISM 0F 79 PSIA (2.63 PERCENT FR)

AND STILL MAINTAINS MARGINS OF 121 PSIA OR 4.04 PERCENT F R I

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OPTIMIZED ANALYSIS Sil0WS REQUIRED PVAR ADJUSTMENT OF 47 PSIA Wil!Cil

RESULTS IN EVEN GREATER MARGIN OF 153 PSIA OR 5.11 PERCENT IN l

FR

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OPERATION AT A CORE INLET TEAPERATURE C(T ) 0F 541*F RESULTS IN AN l

ADDITIONAL MARGIN GAIN OF APPROXIMATELY 88 PSIA WillCH IS SUFFICENT

TO OFFSET Tile 47 PSIA NONCONSERVATISM

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THERMAL MARGIN TRIP ONLY CREDITED IN SAFELY ANALYSIS FOR TWO EVENTS;

RCS DEPRESSURIZATION AND EXCESS LOAD l

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THERMAL MARGIN TRIP REACHES LOW PRESSURE TRIP FLOOR AT APPROXIMATELY

72 PERCENT POWER. BELOW THIS POWER LEVEL, A LOW PRESSURE TRIP WILL

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SAFETY MARGIN EXIS1ED IN TECll. SPEC. FIG. 2-6:

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1.85. RESULT IS A 7.03 PERCENT MARGIN IN FXY . SUFFICIENT TO

0FFSET 4 PERCENT POWER NONCONSERVATISM IN FIG. 2-6 AND STILL

MAINTAIN A MARGIN OF 3.03 PERCENT

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CYCLES FOR FORT CALHOUN. SHOULD LOSS OF THE INCORE MONITORING

SYSTEM HAVE OCCURRED ON JUNE 28, 1988, ENTRY INTO TECH. SPEC. FIG.

2-6 WOULD NOT HAVE BEEN REQUIRED UNTIL JULY I, 1988 WHEN THE LAST

VALID INCORE POWER DISTRIBUTION WOULD EXPIRE

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STATEMENT OF PROBLEM

CAUSE

CORRECTIVE ACTION

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- JUNE 28

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- ANALYTICAL EARORS IDENTIFIED

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- INFORMED PLANT MANAGER l

- IhFORMED NIGHT SS

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- INPACT OF ERRORS

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NRC BRIEFING

- PRC-LOC CONDITION

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NRC FOUR HOUR REPORT 1

- RECALIBRATION 0F RPS

- NIGHT NOTES

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- TELEPHONE DISCUSSION WITH NRC

(0 PPD INITIATED)

JULY I

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INTENT OF STATEMENT

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SS'S WERE ALL KEPT CURRENT

ON THE SITUATIONS

SS'S WERE APPRISED 0F ALL

APPROPRIATE ACTIONS

PLANT IN SAFE CONDITION

AT ALL TIMES

SS WAS DIRECTED TO RECORD

CONVERSATION IN $$ LOG

' ACTUAL STATENENT JULY 1, 1988

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LETTER TO NRC l

SS PLACED IN HIS LOG INSTRUCTIONS THAT IF ANY SITUATION AROSE THE UNIT

WOULD BE BROUGHT TO 80 PERCENT, NOT THE 90 PERCENT STATED IN TECH. SPEC.

FIG. 2.6 ,

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PERSONAL ACCOUNTABILITY (0N-G0!M)

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MD *15 33 0f Cod) 20101 88/21.130 I

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