ML20024J550
| ML20024J550 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/13/1994 |
| From: | Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Barkhurst R ENTERGY OPERATIONS, INC. |
| References | |
| NUDOCS 9410200036 | |
| Download: ML20024J550 (24) | |
Text
e en PtGw UNITED STATES NUCLEAR REGULATORY COMMISSION j,(
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REGION IV G11 RYAN PLAZA DRIVE SUITE 400 o
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A R t.INGTON, TE X AS 76011 8064 g,,,
OCT I 31994 Docket:
50-382 License:
NPF-38 Entergy Operations, Inc.
ATTN:
Ross P. Barkhurst, Vice President Operations, Waterford P.O. Box B Killona, Louisiana 70066
SUBJECT:
SEPTEMBER 22, 1994, WATERFORD 3 MANAGEMENT MEETING This refers to the meeting conducted in the Region IV office on September 22, 1994.
This meeting related to discussions regarding recent reactivity management events, your recent initiatives in operations, the status of your corrective action program, and an overview of recent deficiencies that you have identified with the testing of AB swing bus loads.
Our discussions regarding the recent reactivity management events of June 7, July 20, August 19, and September 16, 1994, were detailed and comprehensive and provided a useful understanding of the potential root causes of these events.
Your personnel also provided detailed answers to our questions and your plans to address these issues. Although each of the individual events were not significant, in the aggregate, these issues indicate weaknesses in your operator's conduct of operations and a potential weakness in licensed operator training. We look forward to the results of your evaluation of this root cause.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.
t Should you have any questions concerning this matter, we will be pleased to discuss them with you.
Sincerely, 3w hA.Bi1 Beach, Director Division of Reactor Projects Attachments:
1.
Attendance List 2.
Licensee Presentation gg ru mqEn COPY u
190001 9410200036 941013 e
i PDR ADOCK 05000382 V
P PDR
Entergy Operations, Inc. cc:
Entergy Operations, Inc.
ATTN:
Harry W. Keiser, Executive Vice President and Chief Operating Officer P.O. Box 31995 i
Jackson, Mississippi 39286-1995 Entergy Operations, Inc.
ATTN: Jerrold G. Dewease, Vice President Operations Support P.O. Box 31995 Jackson, Mississippi 39286-1995 Wise, Carter, Child & Caraway ATIN:
Robert B. McGehee, Esq.
P.O. Box 651 Jackson, Mississippi 39205 Entergy Operations, Inc.
ATTN:
D. F. Packer, General Manager Plant Operations P.O. Box B Killona, Louisiana 70066 Entergy Operations, Inc.
ATTN: Donald W. Vinci Licensing Manager P.O. Box B Killona, Louisiana 70066 i
Chairman Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge, Louisiana 70825-1697 1
Entergy Operations, Inc.
ATIN:
R. F. Burski, Director Nuclear Safety P.O. Box B Killona, Louisiana 70066 William H. Spell, Administrator i
Radiation Protection Division P.O. Box 82135 Baton Rouge, Louisiana 70884-2135 4
1 Entergy Operations, Inc. Parish President St. Charles Parish P.O. Box 302 Hahnville, Louisiana 70057 Mr. William A. Cross
.Bethesda Licensing Office 3 Metro Center Suite 610 Bethesda, Maryland 20814 Winston & Strawn ATTN: Nicholas S. Reynolds, Esq.
1400 L Street, N.W.
Washington, D.C.
20005-3502 f
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Entergy Operations, Inc. bcc to DMB (IE45) bcc distrib. by RIV:
L. J. Callan Resident Inspector Branch Chief (DRP/D)
Leah Tremper, OC/LFDCB, MS: MNBB 4503 MIS System DRSS-FIPB RIV File Project Engineer (DRP/D)
Branch Chief (DRP/TSS)
K. E. Perkins, D:WCF0 J. T. Gilliland, PA0 C. A. Hackney, SLO IV:DRP/D
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Entergy Operations, Inc. OCT I 31994 bcc to DMB (IE45) bec distrib. by RIV:
L. J. Callan Resident Inspector Branch Chief (DRP/0)
Leah Tremper, OC/LFDCB, MS: MNBB 4503 MIS System DRSS-FIPB RIV File Project Engineer (DRP/D)
Branch Chief (DRP/TSS)
K. E. Perkins, D:WCF0 J. T. Gilliland, PA0 C. A. Hackney, SLO RIV:DRP/D
) C:DRP/D( h D:DRP GAPick:chf CAVanDendgh ABBeach M l
10/ 3/94 10/6/94 10/\\h/94
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ATTENDANCE LIST Licensee Personnel R. Burski, Director Nuclear Safety D. Matheny, Operations Superintendent D. Packer, General Manager Plant Operations R. Starkey, Manager, Operations and Maintenance D. Vinci, Licensing Manager NRC Personnel
- E. Adensam, Associate Director, Project Directorate PDIII/IV, Office of Nuclear Reactor Regulation (NRR)
A. Beach, Director, Division of Reactor Projects (DRP)
- E. Ford, Senior Resident Inspector, Waterford 3, DRP A. Hodgdon, Acting Regional Council
- C. Patel, Project Manager, Project Directorate PDIV-1, NRR J. Pellet, Acting Deputy Director, Division of Reactor Safety G. Pirk, Project Engineer, Project Branch D, DRP C. VanGenburgh, Chief, Project Branch D, DRP t
- via telephone
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WATERFORD3 NRC Management Presentation September 22,1994 i
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AGENDA
/ Introduction D. Packer
/ Discussion Topics A. Recent Boron Dilution /
D. Packer Reactivity Management Events at Waterford 3 B. Initiatives in Operations D. Matheny l
C. EDG Integrated Testing of R.Starkey Swing AB Bus Components D. Corrective Action Program R. Burski
/ Closing Remarks D. Packer 8
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Management Events at Waterford 3 I
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June 7,1994 - Letdown Rad Monitor purge resulted in inadvertent dilution of RCS and a power increase to 100.5%. Once source of dilution realized, operators reacted to quickly stabilize reactor power. Operator performance met expectations.
R.C. - Inadequate SMP review, misleading drawings July 20,1994 - Improper blended makeup to VCT resulted in power increase to 100.4%. PNPO did not notify CRS in timely manner & injected boric acid directly to RCS.
R.C. - Personnel error due to lack of self-checking Contributing Factor-Lack of communi-
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August 19,1994 - Malfunction of check valve BAM-146 during CVC ion exchanger rinse resulted in power increase to 100.4% and PPS pretrips on high linear power. CRS decided to continue with evolution once problems with boric acid flow were realized.
R.C. - Believed to be mechanical deficiency of check valve BAM-146 Contributing Factor - Decision to continue evolution September 16,1994 - PNPO initiated blended makeup to VCT correctly and secured from evolution due to annunciator ground testing. When he recommenced the makeup, he failed to properly align the system. This resulted in direct boration.to RCS and a power decrease to 98.5%.
R.C. - Personnel error due to lack of self-checking Contributing Factor - Improper use of procedure ENTERGY
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,amaer Recent Boron Dilution / Reactivity Management Events at Waterford 3 Corrective Actions June Event - Update drawings; include event in training.
July Event - Counseled PNPO; management discussions of event with Ops. department; include event in training.
August Event - Procedure review; management communication on conservative decision making; others pending on system test.
September Event - Counseled PNPO and removed him from shift; changing requirements for CVC procedure usage.
Following each event, a CR was generated to begin the corrective action process, and an Event Review Team was assembled to perform a Root Cause Investigation. In addition, a Voluntary LER will be submitted for each event.
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Recent Boron Dilution / Reactivity Management Events at Waterford 3 Additional Actions as a Result of Reactivity Management Events Development of Joint Test Group for configuration changes
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Requested an Independent Review (by INPO) to evaluate events during upcoming plant evaluation i
Observations by Management of Shift Crews j
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Marked Improvement in NAO Performance
- Reduction in Clearance Errors
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EDG Integrated Testing of Swing AB Bus Components Problem - Failure to include AB bus components as part of integrated EDG testing that satisfies TS surveillance requirements.
The most probable root cause of this event is an inadequate procedure developed during initial plant startup (1983) apparently caused by one or more of the following three conditions:
- Originator of Revision 1 to OP-903-069 acted inappropriately when he deleted the AB equipment from the test.
- Possible misunderstanding of the concept of permanently connected loads, as described in TS 4.8.1.
- The technical review for that procedure was inadequate in that it did not detect the problem.
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EDG Integrated Testing of Swing AB Bus Components CORRECTIVE ACTIONS
- TS 3/4.8.1 will be reviewed to verify surveillance requirements are properly i
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- OP-903-115 and OP-903-116 will be revised to properly implement TS surveillance i
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- The Integrated Emergency Diesel Generator / Engineered Safety Features tests required by the Technical Specifications will be implemented prior to startup following Refuel 7.
- TS Bases for 3/4.8.1 will be revised to clarify what is meant by " permanently connected loads".
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- Selected surveillance procedures will be reviewed to assure that TS surveillance requirements are fully implemented.
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Corrective Action Program Program and Its Implementation On Track to Becoming One ofIndustry's Finest Better defined and lower threshold has resulted in increased number of CRs initiated
- Backlog of CRs have stabilized
- Identification of EDG surveillance testing deficiency
- Many other examples of corrective action program at work t
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