ML20205E899
| ML20205E899 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/19/1999 |
| From: | Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Horm G NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| AL-98-07, AL-98-7, NUDOCS 9904060050 | |
| Download: ML20205E899 (31) | |
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p tS8 4g UNITED STATES l
e- 3 4 NUCLEAR REGULATORY COMMISSION Tn r REGloN IV 1 l l
611 RYAN PLAZA DRIVE, sulTE 400 y,g ARLINGTON, TEXAS 76011-8064
! MAR I 91999 G. R. Horn, Senior.Vice President _
of Energy Supply Nebraska Public Power District l 141415th Street :
Columbus, Nebraska 68601
SUBJECT:
PLANT PERFORMANCE REVIEW (PPR) - COOPER NUCLEAR STATION ;
Dear Mr. Horn:
1 On February 9,1999, the NRC staff completed a PPR of Cooper Nuclear Station (Cooper). l The sta" conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance. The results are used by NRC management to facilitate planning and allocation of inspection resources. PPAs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC's senior management meeting (SMM) reviews. PPRs examine 5 formation since the last assessment of licensee performance to evaluate long-term trends but en.phasize the last 6 months to ensure that the assessments reflect current performance. The PPR for Cooper involved the !
' participation of all technical divisions in evaluating inspection results and safety performance information for the period July 11,1998, to January 25,1999. The NRC's most recent summary of licensee performance was provided in a letter of August 17,1998, and was discussed in a public meeting with you on September 3,1998. 1 As discussed in the NRC's Administrative Letter 98-07 of October 2,1998, the PPR provides an !
assessment of licensee performance during an interim in which the NRC has suspended its 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 i program or terminate it in favor of an improved process. l From the beginning of the currer . period of detailed focus (April 22,1998),'when the reactor began a coastdown at the end of the operating cycle, the unit operated at or near 100 percent power. On October 3, licensed operators placed the plant in Mode 3 to begin Refueling
. Outage 18. Plant restart activities were commenced on December 15,1998. The reactor was taken critical two times and shut down to evaluate emergent equipment problems. On December 17, the reactor was taken critical again, and the main generator was placed on line on December 20. The plant achieved full power on December 23,1998. On January 16,1999, a main feedwater pump tripped and operators stabilized reactor power at 70 percent. The pump was repaired and the plant restored to full power on January 23 and operated at or lear 100 percent power through the end of the period.
Overall, the performance of the Cooper staff during the assessment period was acceptable. No significant events occurred, conservative decision making was. noted, and licensed operators routinely demonstrated professionalism in the main control room. Plant management was, in 9904060050 990319 PDR ADOCK 05000298 G PDR
Nebraska Public Power District l general, involved in daily plant activities. Problems with communications in the control room resulted in several minor events and, at times, licensed operators failed to identify or understand equipment operability requirements Occurrences of inadequate and improperly implemented procedures continued to result in equipment unavailability. Cooper engineering i continued to experienco significant problems in maintaining the design basis. Plant staff i effectively implemented programs for physical security, access authorization, radiation protection, and emergency preparedness. Although the threshold for documenting problems was low, the corrective action program was not always formally implemented, thereby resulting in failures to identify and correct the cause of plant problems in all functional areas.
Licensed operators routinely demonstrated professionalism in the main control room and plant !
managers were ;onsistently involved in daily plant activities. One exception to thess normally effective standards was when a licensed operator failed to follow station operating procedures to bypass the suam discharge volume high level trip, resulting in a second reactor scram. A l peer check had detected the error, but the shortcoming was not communicated. A second exception was when indicated reactor water level dropped 58 inches when the reactor vessel head vent was removed. During this event, operators failed to question or evaluate the change I in reactor pressure on reactor water level. These examples were the direct result of weak communications in the main control room. There were also occasional instances where licensed operators failed to identify or understand equipment operability requirements. For example, operators failed to identify that required postaccident instrumentation was rendered i inoperable during the development and implementation of a clearance order, and operations issued a standing order which did not specify the temperature at which the reactor equipment cooling system would become inoperable. Finally, while the corrective action program was fully supported by the operations organization, there were occasions when it was not always formally implemented, resulting in failures to identify and correct the root cause of plant oroblems. For example, as a result of untimely implementation of corrective actions, the licensee failed to prevent a fifth example of improperly restoring a radiation monitor to service. Only core inspection efforts have been scheduled in the operations area over the next 8 months; however, the corrective action inspection will sample numerous operations-related activities.
W]rk observed in the field continued to be effective and indicated proper implementation of improved work practices; however, examples of inadequate and improperly implemented procedures continued to result in equipment unavailability. For example, a reac;or recirculation pump seal failed because craftsmen impioperly installed the thrust collar; additionally, implementation of the work instructions for repair of diesel generator air system check valves 1 would have increased the risk of damaging the O-rings. Maintenance personnel usually .
demonstrated an appropriately low threshold for the identification of problems; however, I corrective actions were not always identified or properly implemented. Maintenance personnel failed to properly implement corrective actions for inadequate torquing instructions, causing safety system inoperability. Several examples of inadequate postmaintenance testing resulted in the failure to identify maintenance induced failure mecharisms of safety-related equipment.
Following postmaintenance testing, the scram discharge instrument volume Channel A2 level transmitter failed to actuate on a valid high water level. Only core inspection efforts have been scheduled in the maintenance area over the next 8 months.
The licensee issued a major revision to the Strategy for Achieving Engineering Excellence and began to implement the action plan that it contained. Direct inspection indicated that the
Nebraska Public Power District licensee was implementing the strategy with some success. Staff size has increased and there has been noticeable improvement in the capabilities and contributions of system engineers.
The overall quality of engineering products has improved. More work, however, is necessary to -
ensure that the full extent of problems is identified and corrected.
During the assessment period, licensee personnel implementing the unauthorized modifications ;
review program failed to identify seven unauthorized modifications, and the engineering evaluations for'an additional seven of the conditions adverse to quality identified by the review i were inadequate. In addition, engineering produced several poor quality unreviewed safety question determinations, resulting in continuing weakness in the maintenance of the design basis. Contemporary evaluations performed for older Updated Safety Analysis Report changes or modifications were not always rigorous in identifying the basis for the determination that an unreviewed safety question was not involved. Additionally, a safety evaluation failed to identify that a change to the methods used to test the high pressure steam admission valves rendered these valves inoperable during testing, inspectors and licensee engineers continued to identify inadequacies in engineering products relatM to design and plant configuration changes. NRC-identified inadequacies included: (1) an incorrect service water temperature was used in an RHR heat e'xchanger fouling factor calculation; (2) calculations were not appropriate to demonstrate the capability of service water to cool the safety-related reactor equipment cooling system; and (3) calculation changes to implement a change in fuel length failed to change the reference point for the top of active fuel on fuel range level indicators and emergency operating procedure parameters.
Engineering support to operations was more formal but of mixed quality. Notably, the engineering response to a through-wall leak in the nonessential service water system was prompt, supporting operations' demands, but was not comprehensive regarding the analysis of piping integrity or the adequacy of the flooding analysis. Finally, while engineers performed thorough and complete technical evaluation of a complex issue involving dynamic loading on torus strainers and effectively integrated operations and licensing staff in the evaluation and interim resolution, significant plant management and NRC involvement was required. The core inspection program will be supplemented by several regional initiative efforts. An inspection focusing on one of the engineering strategy elements will be conducted as part of the Region's continuing oversight of engineering problems; additionally, the site-wide assessment of the engineering improvement program will be monitored for its adequacy and intrusiveness.
Finally, the corrective action inspection (core) will focus extensively on the development and implementation of engineering work products.
The radiation protection program was generally well conducted, and the ALARA program produced excellent results. Physical security performance was consistently effective and plant !
staff effectively implemented programs for access authorization and fitness for duty, in the emergency preparedness program, one exercise weakness was identified for the failure to implement proper radiological contamination controls in the operational and technical support centers. Only core inspection efforts are scheduled for the plant support area over the next 8 months.
Enclosure 1 contains a historical listing of plant issues, referred to as the Plant issues Matrix (PlM), that were considered during this PPR process to arrive at an integrated view of licensee performance trends. The PIM includes items summarized from inspection reports or i
n-e Nebraska Public Power District j i
other docketed correspondence between the NRC and Nebraska Public Power District. The NRC does not attemp 'o document all aspects of licensee programs and performance that may be functic ig appropriately. Rather, the NRC only 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 information listed in the PIM.
I This letter advises you of our planned inspection effort resulting from the Cooper PPR review. l 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. The rationale or basis for each inspection outside the core inspecdon program has been provided in this letter so that you are aware of l the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.
Yot ..:ility has been selected to be a pilot plant for the new reactor oversight process. We will notify you of the associated changes to planned inspections by separate correspondence. if you have any questions, please contact Charles Marschall at (817) 860-8185.
Sincerely, j
/
un #
/ Divisiort
<enE.(roc ma' tor, Director Projects i
Docket Nos. 50-298 License Nos. DPR 46
Enclosures:
- 1. Plant issues Matrix
- 2. General Description of PIM Table Labels
- 3. Inspection Plan cc w/ enclosures:
John R. McPhail, General Counsel Nebraska Public Power District P.O. Box 499 Columbus, Nebraska 68602-0499 l
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Nebraska Public Power District l J. H. Swailes, Vice President of Nuclear Energy ;
Nebraska Public Power District i P.O. Box 98 Brownville, Nebraska' 68321
- 8. L. Houston, Nuclear Licensing j and Safety Manager ,
Nebraska Public Power District j P.O. Box 98 I Brownville, Nebraska 68321
. Dr. William D. Leech MidAmerican Tnergy 907 Walnut Street P.O. Box 657 Des Moines, Iowa 50303-0657 Mr. Ron Stoddard Lincoln Electric System 1040 O Street P.O. Box 80869 Lincoln, Nebraska 68501-0869 Randolph Wood, Director Nebraska Department of Environmental Quality P.O. Box 98922 Lincolr., Nebraska 68509-8922 Chairman
- Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street '
Auburn, Nebraska 68305 Cheryl Rogers, LLRW Program Manager Environmental Protection Section !
Nebraska Department of Health 301 Centennial Mall, South P.O. Box 95007 ,
Lincoln, Nebraska 68509-5007 i R. A. Kucera, Department Director
! - of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176 ~
Jefferson City, Missouri 65102
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. 1 L Nebraska Public Power District ~
l L Jerry Uhlmann, Director i State Emergency Management Agency
' P.O. Box 116 Jefferson City, Missouri' 65101 ;
I Mr. Marlin L. Logan !
Presiding Commissionur j Atchison County P.O. Box 280 Rock Port, MO 64482 i
Mr. Dennis Martin, Sheriff Atchison County Sheriff's Office
. 511 West Clay Rock Port, MO 64482 i
Mr. John George, Chairman l Nema.N County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 l Mr. Loras Baumhover, Sheriff 1805 N Street Auburn, NE 68305 John Miller, Regional Director Federal Emergency Management Agency, Region Vil 2323 Grand Blvd., Suite 900 Kansas City, MO 64108-2670 Deb Thomas, Director
. Regulation and Licensure Health and Human Services P.O. Box 95007 Lincoln, NE 68509-5007 l
i Kenneth Miller, Chief Bureau of Radiological Health ;
Radiation Control Program Director Department of Health P.O. Box 570 Jefferson City, MO 65102
Nebraska Public Power District 1 -7 S. Pardeen Baig, Chief
. State Liaison Officer lowa Utilities Board
' lowa Department of Commerce -
Lucas State Office Building,5th Floor Des Moines, Iowa 50319 i
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,1 Nebraska Public Power District MAR I 91999 l
i- ' bec to DCD (IE40) bec distrib. by RIV:
! Regional Administrator Resident inspector
I DRS Director . MIS System Branch Chief (DRP/C) RIV File Branch Chief (DRP/TSS) Chief, NRR/ DISP /PIPB
. Project Engineer (DRP/C) Chief, OEDO/ROPMS Branch Chief (DRP/TSS) 8. Henderson, PAO T. Boyce, NRR/ DISP /PIPB Records Center, INPO C. Hackney, RSLO - C. Gordon W. D. Travers, EDO (MS: ,16E15)
Associate Dir. for Projects, NRR Associate Dir. for insp., and Tech. Assmt, NRR PPR Program Manager, NRR/lLPB (2 copies) .
Chief, inspection Program Branch, NRR l Chief, Regional Operations and Program Management Section, OEDO l W. Bateman, NRR Project Director (MS: 13E16)
L. Burkhart, NRR Project Manager (MS: 13D1) l.
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