ML20151Z940
| 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
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In Reply' Refer.To: .
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_ Docket: '50-7.?5/88-22
Omahc l'ublic Power District
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ATTN _ Kenneth J. Morris, Divhite. Hanager
Nuclear Operations
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1623 Harney Street -
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
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inspection conducted during tie period June 29:through July 18. 1988,=which
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were documented in our NRC Inspeet'on-Report 50-285/88-22 dated July 29, 1988.
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The subjects discussed at this meeting are described in the :nclosed Meeting ~
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Sumary.
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In accordance with Section 2.790 of'the NRC's "Rules of Practice," Part 2
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Title 10,. Code of Federal Regulations, a copy of t iis letter will be placed in
the NRC's Public Document Room.-
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Should yos hwt; any. questions conccrning this matter, we will be pleased to
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discuss theia with you.-
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Sincerely,
Original Signed By
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A. B. Beach
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L. J. Callan, Director
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Division of Reactor Projects
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Enclosure:
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Meeting Sumary w/ attachments (2)
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cc w/ enclosure:
Fort Calhour Station
ATTN:
W. G Gates, Manager
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P.O. Box 399
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Fort J.alhoun, Nebraska 68023
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8808300311 880823
ADOCK 05000285
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Harry H. Voigt, Esq.
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PNV
Le'oeuf, Lamb, Leiby & MacRae
1: 1 New Hampshire Avenue, NW
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W: Uington, D. C.
20036
' ebraska Radiation Control Program director
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Lisa Shea, RM/ALF
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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.:
Docket No.:
50-285
SUBJECT:
ENFORCEMENT CONFERENCE CONCERNING NRC INSPECTION FINDINGS
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(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
Omaha Public Power Distric{
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. NRC Attendees:
A. B. Beach, Deputy Director, Division of Reactor Projects, RIV
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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
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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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
II. Overview of Meeting
J. J. Fisicaro
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III.
Potential Violation - Operated Cycle 11
with Nonconservative Technical Specifica-
tion Sete,oints (285/8822 01)
K. C. Holthaus
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Background
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Statement of Problem
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TM/LPLogic
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Sequence of Events and Ismediate
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Corrective Actions /Results Achieved
Root Cause
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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
Statement of Problem
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Sequence
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Intent of Statement
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Cause
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Future torrective Actions Planned
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V.
Closing Statement and Conclusions
K. J. Morris
S. K. Gambhir
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ASDEA
BACKGROUND
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STATEMENT OF PROBLEM
TN/LP LOGIC
SEQUEHCE OF EVENTS N;D DetEDIATE
CORRECTIVE ACTIONS
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ROOT CAUSES
COMPLETED CORRECTIVE ACTIONS
SAFETY SIGNIFICANCE
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$UPMARY/ CLOSING
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BACKGROUND
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OPPD PERFORMING CYCLE 12 RELOAD ANALYSIS
REVIEW OF CYCLE 11 SETPOINT ANALYSIS RESULTED IN
FINDING TWO NONCONSERVATISMS
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IWtEDIATE CORRECTIVE ACTIONS IMPLEMENTED
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STATEMENT OF PROBLEM
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APPARENT VIOLATION 285/6822-01:
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SUMMARY:
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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
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OPPD ADMITS TO VIOLATION AS STATED
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BY THE TM/LP TRIP SYSTEM
POWER
THERMAL MARGIN /
THERMAL MARGIN TRIP
AXIAL SHAPE INDEX
LO'N PRESSURE
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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
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Al ic = 545
ASI = 0.0
RCS PRESSURE (PSIA)
2200
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2100
P
= 22 Pf(8)A1(Y)B + 22.11 IN- 12603
2000
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= 22 Pf(B)A1(Y)B + 22.1 I
- 12553
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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)
RADIAL PEAXING FACTOR SCALING FACTOR NOT INCLUDED - TECH.
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SPEC. FIG. 1-3
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
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JUNE 29, 1988:
PRELIMIMARY ANALYSIS RESULTS (0730)
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ALL FOUR RPS TM/LP TRIP MODULES DECLARED INOPERABLE (0920)
BEGAN RECALIBRATION WITH FOUR HOUR TIME LINIT FOR SIGNIFICANT
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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
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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
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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
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EY.PERIENCE REVIEW REQUIREMENT TO BE INCORPORATED INTO
PROCEDURE
INDEPENDENT REVIEW OF ALL CYCLE I2 ANALYSES TO BE DONC BY CE.
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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:
T
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;
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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
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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)
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
T
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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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A DETERMINATION OF ANY OTilER CYCLE 11 SETPOINT NONCONSERVATISMS,
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IF TilEY EXISTED
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REANALYSIS INITIATED AT APPROXIMATELY 1700 JUNE 28,1988
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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-
TISN. CONSERVATIVE INSTRUCTIONS PROVIDED TO SHIFT SUPERVISOR
INCLUDED:
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BRING REACTOR TO 80 PERCENT INSTEAD OF 90 PERCENT IF TECH. SPEC.
FIG. 2 6 REQUIRED TO BE ENTERED. 80 PERCENT PREVIOUSLY
DETERMINED TO BE CONSERVATIVE
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
REACTIVITY CHALLENGE RESULTING FRON CHANGING CURRENT OPERATING
PARANETERS
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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 -
EJMINISTRATIVE AND TRAINING SERVICES
PLANT MANAGER CALLED SHIFT SUPERVISOR TO CONFIRM THAT UPON ENTRY INTO
TECH. SPEC. FIG. 2 6 AN IM EDIATE POWER REDUCTION TO
80 PERCENT WOULD OCCUR
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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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
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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 FR
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OPTIMIZED ANALYSIS Sil0WS REQUIRED PVAR ADJUSTMENT OF 47 PSIA Wil!Cil
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RESULTS IN EVEN GREATER MARGIN OF 153 PSIA OR 5.11 PERCENT IN
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FR
OPERATION AT A CORE INLET TEAPERATURE (T ) 0F 541*F RESULTS IN AN
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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
THERMAL MARGIN TRIP REACHES LOW PRESSURE TRIP FLOOR AT APPROXIMATELY
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72 PERCENT POWER.
BELOW THIS POWER LEVEL, A LOW PRESSURE TRIP WILL
OCCUR
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SAFETY MARGIN EXIS1ED IN TECll. SPEC. FIG. 2-6:
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MAXIMUM FXY DURING CYCLE WAS 1.72 VS. TECil. SPEC. LIMIT OF
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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
TECH SPEC. FIG. 2-6 HAS NOT BEEN ENTERED SINCE Tile VERY EARLY FUEL
-
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
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SEQUDICE
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JUNE 28
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ANALYTICAL EARORS IDENTIFIED
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INFORMED EVENING SS
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INFORMED PLANT MANAGER
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IhFORMED NIGHT SS
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JUNE 29
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INPACT OF ERRORS
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NRC BRIEFING
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PRC-LOC CONDITION
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NRC FOUR HOUR REPORT
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RECALIBRATION 0F RPS
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NIGHT NOTES
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JUNE 30
TELEPHONE DISCUSSION WITH NRC
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(0 PPD INITIATED)
JULY I
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TECH. DATA 900K FIGURES
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INTENT OF STATEMENT
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
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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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CORRECTIVE ACTION
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