IR 05000445/1996016
| ML20138K193 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 05/06/1997 |
| From: | Gwynn T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| 50-445-96-16, 50-446-96-16, NUDOCS 9705120245 | |
| Download: ML20138K193 (4) | |
Text
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Mr. C. L.. Terry TU Electric Group Vice President, nluclear i ATTN: Regulatory Affairs Department I P.O. Box 1002 Glen Rose, Texas 76043 l ' SUBJECT: NRC INSPECTION REPORT 50-445/96-16;50-446/96 16 i Thank you for your letter of April 7,1997, in response to our letter and Inspection ' . Report dated January 16,1997. We have reviewed your reply and find it responsive to . the concerns raised in the inspection Report. We will review the implementation of your
l i - corrective actions during a future inspection.
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Sincerely, , ' / ,-p- ' / , l- - homas P. Gwynn, D", ecto ! Division of Reactor oje (s
Docket Nos.: 50-445 50-446 License Nos.: NPF-87 NPF-89 . cc: Mr. Roger D. Walker TU Electric ) Regulatory Affairs Manager / i l P.O. Box 1002
' Glen Rose, Texas 76043 i l. ' )'D f ~ / 9705120245 970506 " , PDR ADOCK 05000445 h .. , , .#* . _ _ _ _ _. _ _ _ _ _ _, _ ~ . . -, , -
i ' . . TU Electric-2-l Juanita Ellis ' President - CASE 1426 South Polk Street Dallas, Texas 75224 TU Electric Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 George L. Edgar, Esq.
Morgan, Lewis & Bockius 1800 M. Street, NW Washington, D.C. 20036 G. R. Bynog, Program Manager / Chief Inspector Texas Department of Licensing & Regulation Boiler Division P.O. Box 12157, Capitol Station
Austin, Texas 78711 Honorab!e Dale McPherson County Judge P.O. Box 851 Glen Rose, Texas 76043 Texas Radiation Control Program Director 1100 West 49th Street Austin, Texas 78756 John Howard, Director Environmental and Natural Resources Policy Office of the Governor P.O. Box 12428 ) Austin, Texas 78711 i l ' i l '
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. i l I l l DOCUMENT NAME: R:\\_CPSES\\CP616AK.ATG To receive copy of document, indicate in box: "C" = Copy wthout enciqputes "E" = Copy with enclosures "N" = No copy j PE:DRP/A C:DRP/A D:DRP M l , RAKoptiva;cnQy M JITapia O{ __,- TPGwynn ([[ Of/ (,/97 I[ V Of / /p /97 i Op (p /97' V
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- , i . l- ! s j <* , P9 Log # TXX-97022 ! - - File # 10130 - - , C C-IR 96-16 1UELECTRIC
[ t ' April 7, 1997 c, wy , 'j; @ ' @ l [ U. S. Nuclear Regulatory Commission I H ' O R ~ 91997 o ', Attn: Document Control Desk t.
, Washington. D.C.
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, , a N REGION IV .; l SUBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) ~ ! DOCKET NO. 50-445 and 50-446 NRC INSPECTION REPORT NOS. 50-445/96-16 and 50-446/96-16
TV Electric has reviewed the NRC's letter dated January 16, 1997 .- concerning the inspections conducted by your resident inspection staff and
others.
The subject inspection report identified several-specific examples ! , and expressed concerns regarding. " operator inattentiveness. potential ! supervisory oversight weaknesses, and inadequate self-verification."
Additionally, the inspection report states that the errors may reflect i l operator training weaknesses with respect to newly qualified operators.
TU Electric management also had concerns with the events cited as examples in the NRC inspection report. TU Electric therefore performed an extensive ! , evaluation for the examples cited in section 05 of the subject inspection i report and as discussed with Mr. James Dyer of your office. is providing ! the following perspective on these issues for your consideration. The NRC ! ' inspection report item number and a summary of TU Electric's conclusions are being provided for your information.
, f NRC Concerns: . Item 05.1 An operator error during initial main turbine loading resulted I in a significant reactor coolant system temperature transient and a loss of ! reactor coolant system letdown.
TU Electric Evaluation As stated in the inspection report An Operations < Notification and Evaluation (ONE) Form 96-1455 was initiated to determine ! - . the causes of the event and recommend appropriate corrective actions to prevent recurrence. TV Electric's Nuclear Overview Department (N00) l performed a root cause analysis and recommended appropriate corrective actions with respect to this event.
TU Electric's evaluation concluded that less-than-effective supervisory oversight was the major contributor to the event. The NRC Inspection Report concludes the same. Corrective Actions for this event are extensive, and include reinforcement of supervisory responsibilities, changes to the pre-evolution brief, and improved simulator training.
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Item 05.2 An operator inadvertently deenergized a safety bus when the wrong component was operated during an emergency diesel generator surveillance.
< TU Electric Evaluation. An Operations Notification and Evaluation (0NE) . Form 96-1526 was initiated. The evaluation of the event concluded that r while performing the surveillance test, the operator was distracted by an unrelateo event which caused him to remove his hand from the hand switch ! used to lower the load and when he returned to the task he inadvertently f operated the hand switch adjacent to the correct hand switch. This action caused the Train B 480v switchgear to deenergize.
- The event was caused by less-than-adequate self verification, which-resulted in failure to follow procedure as indicated via NCV 50-446/9616- .
TV Electric determined this event to be a self-verification error in l , that it was an error of commission, as opposed to inattentiveness which
would relate to an error of omission.
Corrective action includes
reemphasis on self verification techniques.
, , ! Item 05.3 Auxiliary operators were inconsistent in fuse replacement ! processes, and the inconsistency may contribute to premature fuse holder
degradation.
' I TU Electric Evaluation An Operations Notification and Evaluation (ONE) ' Form 96-1490 was initiated to document the event. The recommended ! corrective actions included replacement or adequate tightening of the fuse l clips.
Additional evaluation by engineering and N00 (NDE-EVAL-97-000028) , concluded that the apparent loosening of the fuse clips was due to the i ductile properties of the clip, i.e., failure appears to be plastic l deformation of the copper clip and distortion of the copper due to frequent
exercising of the fuse clips during the fuse removal and installation process during initial unit startup testing.
Interviews with numerous operators revealed reasonably consistent methods used in the field for installing the fuses in this clip type.
Initial communication by TU Electric to the NRC concerning the loose fuse clips was not effective in providing the NRC a clear understanding of the loose fuse clip problem prior to the issuance of the subject inspection report. The NRC inspector , was not made aware that the loose fuse clip concern was focused on the fuse clips located in the termination cabinets which use only one style of fuse block.
Nonetheless, TV Electric concluded that this is primarily a material issue, and not an operator performance issue. Various hardware ,. fixes are under consideration to address the hardware anomaly, l ! ! '. t _
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. ., ? ! TXX-97022 , Page 3 to 3 l \\ ' Conclusion The extensive evaluations performed by TU Electric indicate that these were random. 1solated events. TU Electric will continue to monitor such events i l very closely, and will take actions to correct any potential trends.
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TU Electric's review of these events identified only one concern related to
the license training program. The recently qualified Reactor Operator was j not aware of the time response of the turbine load control, and action will
be taken to improve simulator modeling for changes in turbine load. TU l Electric will continue to monitor this area to assure ourselves that our i review conclusions remain valid.
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l Should you have any questions please feel free to contact Roger Walker at i (817) 897-8233.
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l Sincer . I i - , l ! C. L. Terr ! i i ! ! OB:ob i . I , ' i CCg!Ned64ENefM19ff3809deMIV* i Mr. J. E. Dyer, Region IV
Mr. J. I. Tapia. Region IV l Resident Inspectors '
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