ML20205F331
| ML20205F331 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/19/1999 |
| From: | Harrell P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Dugger C ENTERGY OPERATIONS, INC. |
| References | |
| NUDOCS 9904060182 | |
| Download: ML20205F331 (17) | |
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/* "4e UNITED STATES
[ t NUCLEAR REGULATORY COMMISSION M O E j REGloN IV k 9 y g 611 P.YAN PLAZA DRIVE, sulTE 400 ARLINGTON, TEXAS 76011-8064 MAR I 91999 Charles M. Dugger, Vice President Operations - Waterford 3 Entergy Operations, Inc.
P.O. Box B Killona, Louisiana 70066
SUBJECT:
PLANT PERFORMANCE REVIEW (PPR) - WATERFORD 3
Dear Mr. Dugger:
On February 11,1999, the NRC staff completed a PPR of Waterford 3. The staff conducts ,
these reviews for all operating nuclear power plants to develop an integrated understanding of )j safety performance. The results are used by NRC management to facilitate planning and allocation of inspection resources. PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC's senior management neeting (SMM) i reviews. PPRs examine information since the last assessment of licensee performance to evaluate long-term trends, but emphasize the last 6 months to ensure that the assessments reflect current performance. The PPR for Waterford 3 involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period March 22,1998, through January 25,1999. The NRC's most recent summary of licensee l performance was providad in a letter of April 24,1998, and was discussed in a public meeting !
with you on May 12,1998. I i
As discussed in the NRC's Administrative Letter 98-07 of October 2,1998, the PPR provides an I assessment of licensee performance during an interim period that the NRC has suspended its i Systematic Assessment of Licensee Performance (SALP) program. The NRC suspended its !
SALP program to complete a review of its processes for assessing performance at nuclear '
power plants. At the end of the review period, the NRC will decide whether to resume the SALP 4 program or terminate it in favor of an improved process.
v faterford 3 started the current period of detailed focus (March 22,1998) at 100 percent power until May 29,1998, when power was reduced to approximately 68 percent in response to a dropped control element assembly. The power was restored to 100 percent later that same day. The plant operated at 100 percent power unut July 16, when operators reduced power to 92 percent to perform turbine governor valve maintenance. Approximately 30 minutes later, a manual plant trip was initiated because of rapidly lowering levels in both steam generators.
The following day, power was returned to 100 percent and remained at that level until July 22.
Power was rapidly reduced to 60 percent when a main feedwater pump malfunctioned. Full power operations were resumed tne following day. The plant opera %d at essentially 100 percent power until September 10, when power was reduced to 25 percent to take the main generator off line and disconnect Main Transformer B. On September 12, the main generator was placed on the grid and power was returned to approximately 52 percent, with only Main Transformer A in service. On September 18, the plant was placed in Mode 5 conditions to facilitate replacement of a leaking pressurizer code safety valve. The outage was extended several days because of the threat of Hurricane Georges On October 1, the plant was started 9904060182 990319 PDR ADOCK 05000382 G PDR L
r Entergy Operations, Inc. up and connected to the grid. Power was increased to 100 percent on October 2 and remwned at 100 percent power until November 18 when a reactor shutdown was commenced due to an increase in reactor coolant system leakage. Mode 1 was entered December 2 and 100 percent power was achieved on December 7, where it remained until coastdown for the refueling outage commenced on January 21,1999.
Overall, performance at Waterford 3 was acceptable. Operators handled routine and nonroutine events properly. Effective communications among the operators onshift was apparent during nonroutine events, an improvement from the previous assessment. However, there were individualinstances of weak usage of routine procedures. Maintenance personnel exhibited several instances of inattention to detail in the performance of surveillance activities.
The material condition of plant equipment from visual observation was good. Engineering personnel provided effective support to the operating organization. Equipment ' testing was well coordinated and corrective actions following identified deficiencies were appropriate. The emergency preparedness and radiological control programs were generally effective; however, problems were identified with implementation of some aspects of each program. The security program continued to be satisfactorily implernented, with some problems identified in program implementation.
Operators handled routine and nonroutine events well during this assessment period. This was exemplified by control room operator performance during a rapid power reduction, from 100 to 60 percent power, and actions following a manually initiated reactor trip due to decreasing levels in both steam generators. Effective communications among the onshift operators was apparent during nonroutine events. This was demonstrated by the command and control techniques employed during plant power changes. Instances of weak implementation of routine procedure usage were noted when the operations staff, while conducting a plant cooldown, inappropriately determined that a procedure step to cycle atmospheric dump valves with the plant in Mode 3 was not applicable and did not have to be performed. It was determined that continuing the core inspection program would be sufficient to address the operations area.
In the maintenance area, several instances of inattention to detail in the performance of l surveillance activities were identified. The inattention to details included the conduct of a high I pressure safety injection pump surveillance test where a small oil leak on the inboard bearing was not identified by licensee personnel upon completion of the test. Further lack of attention to detail by the control room supervisor and the nuclear plant operator resulted in a failure to verify the positions of control element assemblies within the required Technical Specification time period. The material condition of plant equipment from visual observations was good. In f particular, the diesel generators, switchgear, and the surrounding areas were acceptably !
maintained in good material condition. It was determined that continuing the core inspection l program was sufficient to address the maintenance area.
Engineering support to the operating organization was, on the whole, effective. However, NRC ,
involvement was necessary to resolve issues related to emergency operating procedures action for postevent mitigation. Following questioning by NRC inspectors, the licensee fabricated and staged jumpers and identified the terminals for installation of the jumpers required as a contingency action to close safety injection system containnent sump isolation valves with a recirculation actuation signal present. System engineering walkdowns were well conducted, as evidenced by the observation of a walkdown of the diesel generators by the cognizant system
Entergy Operations, Inc. engineer. Equipment testing was well coordinated and corrective actions following identified deficiencies were appropriate. In addition to the core inspection program, a followup inspection will assess issues identified during the architect / engineering inspection.
During this assessment period, the emergency preparedness and radiological control programs were found to be well defined; however, problems were identified with implementation of aspects of each program. Concerns included: (1) a failure to survey an overhead work area prior to workers entering the area; (2) failure to limit the hours worked by an acting health physics supervisor to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7-day period; and (3) an error in the annual mailing in April 1998 of the public information booklets, which resulted in some residents not receiving the booklets, as required. Of special note is the excellent quality of planning and response displayed by the licensee during Hurricane Georges. The security program continued to be l
considered satisfactory, but problems were identified in program implementation. An example was the compensatory measure procedures for a degraded vehicle barrier which were found to be inadequate. In addition to the core inspection program in the plant support area, regional initiative inspections will be conducted to review identified deficiencies in the security area.
Enclosure 1 contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIM), that were considered during this PPR process to arrive at en integrated view of licensee performance trends. The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and Entergy Operations, Inc. The NRC does not attempt to document all aspects of licensee programs and performance that may be functioning appropriately. Rather, the NRC on!y documents issues that the NRC believes warrant management attention or represent noteworthy aspects of performance. In addition, the PPR may also have considered some predecisional and draft material that does not appear in the attached PIM, including observations from events and inspections that had occurred since the last NRC inspection report was issued but had not yet received full review and consideration. This material will be placed in the PDR as part of the normalissuance of NRC inspection reports and other correspondence. Enclosure 2 provides definitions for some of the l information listed in the PIM.
This letter aavises you of our planned inspection effort resulting from the Waterford 3 PPR review. It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite.
Enclosure 3 details our inspection plan for the next 8 months. Also included in the plan are NRC noninspection activities. The rationale or basis for each inspection outside the core i inspection program has been provided in this letter so that you a;e aware of the reason for {
emphasis in these program areas. Resident inspections are not listed due to their ongoing and l continuous nature.
5 Entergy Operations, Inc. Because of the anticipated changes to the inspection program and other initiatives, this inspection schedule is subject to revision. Any changes to the schedule listed will be prornptly discussed with your staff. If you have any questions, please contact P. Harrell, Chief, Reactor
- Project Branch D, at (817) 860-8250.
Sin g)r >
Harrell, Chief Project Branch D Division of Reactor Projects Docket No. 50-382 License No. NPF-38
Enclosures:
- 1. Plant issues Matrix
- 2. General Description of PIM Table Labels
- 3. Inspection Plan l cc w/ enclosures:
Executive Vice President and Chief Operating Officer Entergy, Operations, Inc.
P.O. Box 31995 Jackson, Mississippi 39286-1995 Vice President, Operations Support .
. Entergy Operations, Inc.
P.O. Box 31995 Jackson, Mississippi 39286-1995 Wise, Carter, Child & Caraway P.O. Box 651 Jackson, Mississippi 39205 General Manager, Plant Operations Waterford 3 SES Entergy Operations, Inc.
' P.O. Box B -
Killona, Louisiana 70066
. .s Entergy' Operations, Inc. ,
' Manager - Licensing Manager Waterford 3 SES Entergy Operations, Inc.
. P.O. Box B Killona, Louisiana 70066 Chairman
-- Louisiana Public Service Commission One American Place, Suite 1630
. Baton Rouge, Louisiana 70825-1697' Director, Nuclear Safety & -
Regulatory Affairs Waterford 3 SES Entergy Operations, Inc.
P.O. Box B -
Killona, Louisiana 70066 William H. Spell, Administrator Louisiana Radiation Protection Division
' P.O. Box 82135 Baton Rouge, Louisiana 70884-2135 Parish President St. Charles Parish P.O. Box 302 Hahnville, Louisiana 70057 Winston & Strawn 1400 L Street, N.W.. l Washington, D.C. 20005-3502 -l Arnold Labat, President St. John the Baptist :
1801 W. Airline Hwy Laplace, Louisiana 70068 Federal Emergency Management Agency R. L. " Buddy" Young, Regional Director Region VI, Federal Center 800 North Loop 288 .
1 Denton, Texas 76201-3698 Mr. Ronald Wascom, Administrator Department of Environmental Quality j P.O. Box 82135 -
Baton Rouge, LA 70884-2135' L
Entergy Operations, Inc. Col.' William Croft, Assistant Director
' State Emergency Management Military Department Office of Emergency Preparedness P.O. Box 44217 Baton Rouge, LA 70804 i
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Entergy Operations, Inc. h!AR I 91999 bcc to DCD (IE40) l bec distrib. by RIV- ,
Regional Administrator Resident inspector DRP Director DRS Branch Chiefs (3 copies)
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Project Engineer (DRP/D) Branch Chief (DRP/TSS) ;
Chief, NRR/ DISP /PlPB Chief, OEDO/ROPMS I B. Henderson, PAO C. Gordon l T. Boyce, NRR/ DISP /PIPB Records Center, INPO C. Hackney, RSLO W. D. Travers, EDO (MS: 16E15)
Associate Dir. for Projects, U 9 Associate Dir. for insp., and Tech. Assmt, NRR PPR Program Manager, NRR/lLPB (2 copies) l Chief, inspection Program Branch, NRR l Chief, Regional Operations and Program Management Section, OEDO i J. Hannon, NRR Project Director (MS: 13H3) 1 C. Patel, NRR Project Manager (MS: 13H3)
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