IR 05000315/1998030
| ML17335A511 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/09/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17335A509 | List: |
| References | |
| 50-315-98-30, 50-316-98-30, NUDOCS 9902190251 | |
| Download: ML17335A511 (7) | |
Text
U.S. NUCLEAR REGULATORYCOMMISSION
REGION III
Docket Nos:
License Nos:
50-315; 50-316 DPR-58; DPR-74 Report Nos:
50-315/98030(DRS); 50-316/98030(DRS)
Licensee:
Indiana and Michigan Power 500 Circle Drive Buchanan, Ml49107-1395 Facility:
Donald C. Cook Nuclear Generating Plant Location:
1 Cook Place Bridgman, Ml 49106 Dates:
December 14, 1998 through January 15, 1999 Inspector.
G. F. O'wyer, Reactor Engineer Approved by:
John M. Jacobson, Chief Lead Engineering Branch 9902i9025'i 990209 PDR ADOCK 050003i5
Re ort Details III. En ineerin This inspection involved review of corrective actions relative to NRC identiTied issues.
The inspector reviewed licensee responses, supporting documentation, calculations, and interviewed cognizant licensee personnel.
E8 Miscellaneous Engineering Issues E8.1 Closed Violation 50-315/95005-04 50-316/95005-04:
Inadequate reviewofvalveleak sealant injection calculations.
The inspector verified the corrective actions described in the licensee's response letter, dated May 5, 1995, to be reasonable and complete.
No similar problems were identified.
E8.2 0 en Violation 50-315/95009-03 50-316/95009-03:
Three examples of inadequate post-maintenance testing (PMT).
E8.3 The inspector verified the corrective actions described in the licensee's response letter; dated October 11, 1995, to be reasonable and complete except in the following aspects.
As part of the corrective actions, the licensee had written a component-specific PMT requirements matrix and a controlling procedure requiring the matrix to be used.
The'icensee identified and documented in Condition Report (CR) 98-3156, initiated July 2, 1998, that plant management had subsequently deleted the requirement to use the matrix which rendered the corrective action Ineffective. Without the requirement, the matrix was not consistently used., The licensee identified the requirement deletion as a lack of control of corrective actions. This was another example of the corrective action program problems being tracked by Manual Chapter 0350 Case Specific Checklist Item 2, "Corrective Action Program Breakdown," as listed in enclosure 1 of the letter, dated October 28, 1998, from the NRC to the licensee.
Licensee personnel informed the inspector that the matrix willbe enhanced and the requirement to use the matrix willbe restored to the controlling procedure.
The inspector verified that these corrective actions were documented in CR 98-3156. This item can be closed pending veriTication that the corrective actions have been implemented.
0 en Ins ection Followu Item 50-96013-08'6013-08:
The System Operational Performance Inspection team had questions about D. C. Cook Calculation RD-96-02, Revision 0, "Offsite and Control Room Thyroid Doses From Containment Bypass Associated With a Charging Pump in ECCS Mode."
The NRC requested a response to this IFI. The licensee responded in docketed letter, dated April 10, 1998. NRR willassist the region in reviewing the response to ensure that the review criteria willbe consistent with that used by NRR to review the licensee's control room dose analysis.
NRR requested submittal of the analysis in docketed letter, dated October 28, 199 E8.4 Closed Deviation 50-315/96013-09'0-316/96013-09:
Deviation from NUREG 0737 commitments for Large Break Loss of Coolant Accident Radiological Analysis.
The inspector venfied the corrective actions described in the licensee's response letter, dated March 12, 1997, to be reasonable and complete.
No similar problems were identified.
E8.5 Closed Violation 50-315/97003-01'0-316/97003-01:
Two complex procedures were not designated as "ln-Hand" procedures as required.
The inspector verified the corrective actions described in the licensee's response letter, dated May 5, 1995, to be reasonable and complete.
No similar problems were identified.
E8.6 Closed Ins ectionFollowu Item 50-315/97023-01 50-316/97023-01:
Thelicensee identified: 1) failure to train engineers as required, 2) recurrent failures to implement corrective actions, 3) potentially unqualified personnel processing condition reports, and 4) training department corrective action implementation problems.
The first issue of this item was closed by the issuance of non-cited violation (NCV)
50-315/316-98003-01.
The violation was not cited because the licensee's proposed corrective actions were evaluated as reasonable and complete.
However, the licensee, identified and documented in CR 98-7307 initiated on November 24, 1998, that the engineering training program had several problems with some being the same as those stated in the NCV. This condition report demonstrated that the proposed corrective actions for the NCV had not been implemented adequately.
This was another example of the corrective action program problems that are already being tracked and addressed by Manual Chapter 0350 Checklist Item 2, "Corrective Action Program Breakdown." The NRC willperform a corrective action program inspection to ensure the remediation ofthe program before the plant restarts.
The engineering training problems documented by CR 98-7307 willbe tracked by a new inspection follow-up item (IFI) 50-315/316-98030-01(DRS).
Allother aspects of this IFI were closed in NRC inspection report 50-315/316-98003.
This item fs closed.
V. Mana ement Meetin s X1 Exit Meeting Summary The inspector presented the inspection results to licensee personnel after the conclusion of the inspection on January 15, 1999. The licensee acknowledged the findings presented.
No proprietary information was Identified by the licensee.
PARTIALLIST OF PERSONS CONTACTED Licensee K. Baker, Engineering B. Bradley, Senior Engineer
¹P. Carteaux, Engineering Training Supervisor
¹D. Cooper, Plant Manager
¹M. DePuyot, Regulatory Compliance Lead
¹E. Eckstein, Nuclear Engineering A. Feliciano, Senio'r Engineer
¹M. Finissi, Electrical and AuxiliarySystems Engineering Manager C. Gilmore, Asst Work Control M Greendonner, Protection D. Hafer, Plant Engineering Manager D. Kosloff, Nuclear Licensing B. O'ourke, Nuclear Licensing F. Pisarsky, Performance Engineering D. Powell, Plant Engineering W. Shafer, Nuclear Licensing T. Taylor, Nuclear Licensing C. VanderZwaag, Senior Engineer T. Zimmerman, Nuclear Engineering
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¹G. O'wyer, Reactor Inspector B. Bartlett, SRI
¹J. Maynen, Rl
¹ Denotes those at the exit on January 15, 1999.
INSPECTION PROCEDURES USED-IP 92903 Followup - Engineering
I ITEMS DISCUSSED 50-315/95009-03 50-316/95009-03 50-315/96013-08 50-316/96013-08 ITEM OPENED 50-315/98030-01 50-316/98030-01 ITEMS CLOSED 50-315/95005-04 50-316/95005-04 50-315/96013-09 50-316/96013-09 50-315/97003-01 50-316/97003-01 50-315/97023-01 50-316/97023-01 ITEMS OPENED, CLOSED, AND DISCUSSED VIO Three Examples of Inadequate Post-maintenance Testing IFI Questions on a Control Room and Offsite Dose Calculation IFI Engineering Training Program Problems VIO Inadequate Leak Sealant Injection Calculations Reviews DEV Deviation from NUREG 0737 Commitments for Loss of Coolant Accident Radiological Analysis VIO Two complex Procedures Were Not Designated Properly IFI Corrective Action and Engineering Training Concerns
Qe AEP AR CFR CR DCC DEV DRP DRS ECCS IFI IP IR LOCA MC MI NCV NOV NRC NRR PMT RI SRI UFSAR.
URI VIO LIST OF ACRONYMS American Electric Power Action Request Code of Federal Regulations Condition Report
'onald C. Cook Deviation Division of Reactor Projects Division of Reactor Safety Emergency Core Cooling System Inspector Followup Item inspection Procedure
Inspection Report
Loss of Coolant Accident
Manual Chapter
, Michigan
Noncited Violation
Nuclear Regulatory Commission
Nuclear Reactor Regulation
Post-maintenance
Testing
Resident Inspector
Senior Resident Inspector
Updated Final Safety Analysis Report
Unresolved Item
Violation