ML20045H345
| ML20045H345 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/13/1993 |
| From: | Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 9307200112 | |
| Download: ML20045H345 (17) | |
Text
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p Riou UNITED STATES '
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,g NUCLEAR REGULATORY COMMISSION
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j R EGION IV I
8 611 RY AN PLAZA DRIVE, SulTE 400 k,
8 ARLINGTON, TEXAS 760114064 R I 3 E3
-Dockets:
50-445 50-446 j
Licenses:
NPF-87 NPF-89 TV Electric ATTN:
W. J. Cahill, Jr., Group Vice President Nuclear Engineering and Operations Skyway Tower l
400 North Olive Street, L.B. 81 Dallas, Texas 75201
SUBJECT:
MANAGEMENT MEETING ON THE COMANCHE PEAK STEAM ELECTRIC STATION OPERATOR PERFORMANCE ISSUES This refers to the management meeting, open to public observation, conducted at the Personnel Processing Center at the Comanche Peak Steam Electric
.l Station site on July 8, 1993, pertaining to operator performance issues related to the May 15, 1993, incident where reactor. power was increased at a q
rate in excess of procedurally prescribed fuel conditioning limits. ' This' d
meeting was attended by those on the attached Attendanca. List.
The subjects discussed are described in the enclosed Meeting Summary.
Your presentation was beneficial and provided a better understanding of the event, the surrounding circumstances, and the results of your self-evaluation.
In accordance with Section 2.790-of the NRC's " Rules of Practice," 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.
m Sincerely, l'
l L i t h,, h
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_e A. Bill Beach. Direct 6r',
Division!of Reactor Projects
Enclosure:
Meeting Summary w/ attachments cc:
(see next page) 9307200112 930713
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PDR ADOCK 05000445 g
TV Electric,
r cc w/ enclosure:
TV Electric ATTN:
Roger D. Walker, Manager of Regulatory Affairs for Nuclear i
Engineering Organization Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Juanita Ellis President - CASE 1426 South Polk Street Dallas, Texas 75224 GDS Associates, Inc.
Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237 TU Electric Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 Jorden, Schulte, and Burchette ATTN: William A. Burchette, Esq.
Counsel for Tex-La Electric Cooperative of Texas 1025 Thomas Jeffersen St., N.W.
Washington, D.C.
20007 Newman & Holtzinger, P.C.
ATTN: Jack R. Newman, Esq.
1 1615 L. Street, N.W.
Suite 1000 Washington, D.C.
20036 Texas Department of Licensing & Regulation ATTN:
G. R. Bynog, Program Manager /
Chief Inspector Boiler Division P.O. Box 12157, Capitol Station Austin, Texas 78711 Honorable Dale McPherson County Judge i
P.O. Box 851 Glen Rose, Texas 76043 i
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TV Electric !
Texas Radiation Control Program Director 1100 West 49th Street Austin, Texas 78756 Owen L. Thero, President Quality Technology Company
.P.O. Box 408 201 West 3rd Lebo, Kansas 66856-0408 t
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1 TU Electric JUL I 31993 bcc to DMB (IE45) bcc distrib. by RIV:
J. L. Milhoan Resident Inspector (2)-
Section Chief (DRP/B)
Lisa Shea, RM/ALF,-MS: MNBB 4503 MIS System DRSS-FIPS i
RIV File Project Engineer (DRP/B)
Section Chief (DRP/TSS) i-l I
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TV Electric vUL i 3 1993 bec to DMB (IE45) bcc distrib. by RIV:
J. L. Milhoan Resident Inspector (2)
Section Chief (DRP/B)
Lisa Shea, RM/ALF, MS: MNBB 4503 MIS System DRSS-FIPS RIV File Project Engineer (DRP/B)
Section Chief (DRP/TSS) i
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MEETING
SUMMARY
Licensee:
TU Electric j
.l Facility:
Comanche Peak Steam Electric Station, Units 1 and 2 (CPSES) i License Nos.: NPF-87 and NPF-89 Docket Nos.:
50-445 and 50-446 i
Subject:
MANAGEMENT MEETING ON OPERATOR PERFORMANCE On July 8,1993, at the CPSES site, representatives of TU Electric made a presentation pertaining to the May 15, 1993, incident where licensed operators on Unit 2 increased reactor power at a rate in excess of procedurally prescribed fuel conditioning limits. The background information to this event
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was contained in NRC Inspection Report 50-445/93-19; 50-446/93-19.
The presentation included an overview of the event, the safety significance of it, a discussion of the performance by the operators and supervisors, and corrective actions implemented. A presentation was made on the Evaluation _
Team Report on Operations Notification Evaluation Form 93-1077, which covered the May 15 event and compared this event to the loss of spent fuel pool cooling event of a year ago.
l The licensee responded to several questions by the NRC staff, and the meeting was concluded with closing remarks by the licensee and the Regional-Administrator.
This meeting was open to public observation.
Attachments:
1.
Attendance List i
2.
Licensee Presentation (NRC distribution only) e
ATTACHMENT 1 ATTENDANCE LIST Attendance at the management meeting between NRC and TV Electric on July 8, i
1993 TU Electric W. Cahill, Jr., Group Vice President, Nuclear Production l
C. Terry, Vice President of Nuclear Engineering and Support J. Kelley, Jr., Vice President of Nuclear Operations J. Donahue, Manager, Operations j
R. Walker, Manager of Regulatory Affairs j
- 0. Bhatty, Licensing Engineer A. Husain, Manager of Reactor Engineering i
W. Isom, Senior Security Representative J. Rumsey, Manager, Corporate Security W. Guldemond, Manager, Independent Safety Engineering Group J. McMahon, Manager, Nuclear Training i
T. Daskam, Operations Quality Assurance S. Palmer, Stipulation Manager i
D. McAfee, Manager, Quality Assurance D. Davis, Manager, Plant Analysis D. Fiorelli, Public Information F. Shants, Community Relations q
NRC J. Milhoan, Regional Administrator S. Black, Director, Project Directorate IV-2, Office of Nuclear Reactor Regulation (NRR)
T. Gwynn, Acting Director, Division of Reactor Projects (DRP)
J. Pellet, Chief, Operator Licensing Section, Division of Reactor Safety L. Yandell, Chief, Project Section B, DRP D. Graves, Senior Resident Inspector, DRP G. Werner, Resident Inspector, DRP T. Bergman, Project Manager, NRR J. Gilliland, Public Affairs Officer Other S. Frantz, Newman & Holtzinger (Attorney for TU Electric)
R. Bauman, WFAA-TV M. Stewart, WFAA-TV
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ATTACHMENT 2 a
7 MANAGEMENT MEETING r
ON CONTROL OF POWER INCREASES.
FOR COMANCHE-PEAK UNIT 2-t a
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h JULY 8, 1993 1
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AGENDA o
OPENING REMARKS J. J. KELLEY o
OVERVIEW 0F EVENT J. W. DONAHUE o
SAFETY SIGNIFICANCE J. W. DONAHUE o
PERFORMANCE OF REACTOR J. W. DONAHUE OPERATORS AND SUPERVISORS o
CORRECTIVE ACTIONS J. W. DONAHUE o
C0HPARISON WITH SPENT J. R. WALKER FUEL POOL EVENT o
MANAGEMENT PERSPECTIVE J. J. KELLEY ON PERFORMANCE o
CONCLUSIONS J. J. KELLEY o
CLOSING REMARKS W. J. CAHILL 2
1 OVERVIEW 0F 5/15/93 EVENT o
UNIT 2 AT APPR0XIMATELY 50% POWER WITH PLANS TO INCREASE POWER (0230 HR) o UNIT SUPERVISOR DIRECTS REACTOR OPERATORS (R0s)
TO INCREASE POWER TO APPROXIMATELY 75% AT 3%/HR.
(0230 HR) o R0 PROVIDES BORON DILUTION (0230 HR) o R0 FOCUSING ON REACTOR COOLANT SYSTEM (RCS)
TEMPERATURE i
o R0 TRIES TO COMPENSATE BY INSERTING RODS AND B0 RATION (0310 HR) o RATE OF POWER INCREASE ABOUT 10%/HR.
(0230 HR - 0330 HR) o EVENT DISCOVERED BY PERFORMANCE AND TEST PERSONNEL ON 5/15/93 (1300 HR) o OPERATIONS (0PS) DEPARTHENT PERFORMED INITIAL EVALUATION o
EVALUATION TEAM ESTABLISHED (5/21/93) 3 i
4 SAFETY SIGNIFICANCE o
EVALUATION OF SAFETY SIGNIFICANCE NO APPLICABLE TECHNICAL REGULATORY REQUIREMENTS l
IPO-003B SPECIFIES AN ADMINISTRATIVE LIMIT.OF < 3%/ HOUR FOR NON-l PRECONDITIONED FUEL T0-REDUCE PROBABILITY OF FUEL PROBLEMS FSAR SECTIONS 4.2.3.3 AND 4.3.2.4.13
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PERMIT LOADING FOLLOWING AT 5%/ MIN.
G NO RELEVANT TECHNICAL SPECIFICATION i
REACTOR ENGINEERING EVALUATION NO INDICATIONS OF FUEL PROBLEMS t
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PERFORMANCE OF R0s AND SUPERVISORS o
PROCEDURAL COMPLIANCE BY R0s ADMINISTRATIVE LIMIT ON POWER INCREASES EXCEEDED o
COMMUNICATION BY R0s R0 DID NOT ADEQUATELY APPRAISE THE SUPERVISORS OF ACTIVITIES INSUFFICIENT COMMUNICATION BETWEEN R0 AND BALANCE OF PLANT (B0P) R0 o
APPLICATION OF KNOWLEDGE BY R0s R0s DID NOT APPLY UNDERSTANDING OF PLANT RESPONSE TO CHANGES IN PARAMETERS 5
PERFORMANCE OF R0s AND SUPERVISORS (CONT'D1 0
SUPERVISION SHIFT SUPERVISOR DID NOT MAINTAIN THE BIG PICTURE AVAILABLE EXTRA SENIOR REACTOR OPERATOR NOT UTILIZED R0s NOT ADEQUATELY BRIEFED ON MAINTAINING PROCEDURAL LIMITS SUPERVISORS DID NOT ADEQUATELY MONITOR ACTIVITIES OF R0s SUPERVISORS DID NOT COMPARE ACTUAL POWER VS. LIMITS o
OTHER ISSUES NO LOGGING OF POWER INCREASES OTHER POWER INCREASES HAVE EXCEEDED 3%/HR GENERALLY PERMITTED BY PROCEDURE 6
CORRECTIVE ACTIONS o
CORRECTIVE ACTION FOR PROCEDURAL COMPLIANCE BRIEFING 0F CREWS ON MANAGEMENT EXPECTATIONS FOR POWER RAMP RATES ENHANCE POWER RAMP CONTROLS MONITOR EACH CREW DOING A POWER RAMP o
COMMUNICATION BRIEFING OF EACH CREW ON TEAMWORK, COMMUNICATIONS, AND LOGGING SIMULATOR OBSERVATION OF CREWS TEAM TRAINING o
APPLICATION OF KNOWLEDGE RAMP RATE QUESTIONNAIRE DEVELOPED TO DETERMINE IF GENERIC WEAKNESS EXISTS ADDITIONAL NORMAL OPERATIONS WILL BE ADDED TO SIMULATOR TRAINING 7
CORRECTIVE ACTIONS (CONT'D) o SUPERVISION TRAINING ON MONITORING BY SUPERVISORS ENHANCE TRAINING ON SHIFT AND TIME MANAGEMENT MANAGEMENT EVALUATION OF PERFORMANCE OF SUPERVISORS o
APPROPRIATE PERSONNEL ACTIONS WERE TAKEN 8
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4 COMPARIS0N WITH SPENT FUEL POOL (SFP)
EVENT o
SFP EVENT AND POWER RATE INCREASE EVENT INVOLVED SOME APPARENT COMMONALITIES PROCEDURE COMPLIANCE NOTIFICATION OF SUPERVISORS MONITORING BY SUPERVISORS o
APPARENT COMMONALITIES NOT INDICATIVE OF INEFFECTIVE CORRECTIVE ACTION FOR SFP EVENT PERFORMANCE OF CREW ACCEPTABLE SIGNIFICANT PERSONNEL ERRORS HAVE DECREASED OVERVIEW PERFORMANCE BASED REVIEWS SHOW THAT MANAGEMENT'S EXPECTATIONS ARE BEING MET o
POWER RATE INCREASE EVENT DUE TO INDIVIDUAL WEAKNESSES AND ISOLATED CONDITIONS AND NOT PROGRAMMATIC PROBLEMS PROCEDURES PROVIDED ADEQUATE GUIDANCE APPROPRIATE TRAINING PROVIDED 9
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t 1992 1993 Numbers Significant Significant h
fictual 30 8
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e MANAGEMENT PERSPECTIVE ON PERFORMANCE o
INP0 ASSIST VISIT FOLLOWING SFP EVENT REEMPHASIZE SEVEN STEPS OF SELF VERIFICATION SUPERVISORY INVOLVEMENT MANAGEMENT OVERVIEWS o
MANAGEMENT OBSERVATIONS o
ADDITIONAL INDEPENDENT OVERVIEWS 11
H CONCLUSIONS o
TU ELECTRIC DISCOVERED AND AGGRESSIVELY EVALUATED THE EVENT o
EXCEEDING LIMIT DID NOT-VIOLATE TECHNICAL-REGULATORY REQUIREMENTS OR-IMPACT PLANT SAFETY o
POWER RATE INCREASE EVENT DUE:TO INDIVIDUAL PERFORMANCE AND NOT PROGRAMMATIC CONCERNS o
EXTENSIVE CORRECTIVE AND PREVENTIVE-ACTIONS 1
o REVIEWS SHOW MANAGEMENT'S EXPECTATIONS ARE BEING MET o
PREVENTIVE ACTIONS FOR PREVIOUS EVENTS WERE q
EFFECTIVE l
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