IR 05000316/1988012
| ML17325A763 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/25/1988 |
| From: | Danielson D, Jeffrey Jacobson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17325A761 | List: |
| References | |
| 50-316-88-12, NUDOCS 8806100242 | |
| Download: ML17325A763 (7) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-316/88012(DRS)
Docket No.
50-316 Licensee:
American Electric Power Service Corporation Indiana Michigan Power Company 1 Riverside Plaza Columbus, OH 43212 facility Name:
D.
C.
Cook Nuclear Plant, Unit 2 Inspection At:
D.
C.
Cook Site, Bridgman, Michigan Inspection Conducted:
March 16-17, 24, 31, April 12, 15, and May 4-5, 17-18, 1988
/
License No.
DPR-74 Inspector:
.
M. Jacobson Date Approved By:
D.
H. Danielson, Chief Materials and Processes Section Date Ins ection Summar Ins ection on Ma 16-17
31 and A ril 12
Ma 4-5 17-18 1988 Re ort No. 50-316/88012(DRS))
findings concerning welder qualification:, polar crane repairs, and modification documentation (92701); preparation for steam generator replacement, Auxiliary Building crane upgrade, and incore thimble type eddy current examination (37702).
Results:
One apparent violation was identified in the area of design control - Paragraph 2.c.
8806t00242 830525 PDR ADOCK 05000316 ac p DETAILS 1.
Persons Contacted American Electric Power Service Cor oration AEP)
Indiana Michi an Power Com an (I&E)
+W. Smith, Plant Manager
~J. White, Site Project Manager B.
Rar rick, QA Supervisor M. Bruce, Engineering Supervisor T. McElroy, Plant Project Engineer T.
Ossmundsen, Construction Supervisor J. Winckel, Construction QA Coordinator S.
Brewer, Radiological Support Manager T. Postlewait, Technical Engineering Supervisor J.
Kauffman, Construction Manager
- S. Heinecke, Project Manager
+Guy Caple, Administrative Compliance Coordinator
+J.
Sampson, Safety and Assessment Superintendent
+R. Tella, Maintenance Engineer
+E. Morse, Safety and Assessment Supervisor
"Denotes those attending the project exit meeting on May 5, 1988.
+Denotes those attending the plant exit meeting on May 18, 1988.
2.
License Action on Previous Ins ection Findin s
a.
(Closed)
Unresolved Item (316/88002-01):
A review of AEP "Welder Performance Qualification," Specification DDC ME 154 QCN di scl osed insufficient detail with regard to welder qualification and record keeping.
Although the specification lacked sufficient detail, the licensee's practice with regard to welder qualification and record keeping was adequate.
In response to this subject, the licensee issued Procedure No.
MHP 5050.SPC.007,
"Welder/Brazer Qualification."
The scope of this procedure is to delineate Code requirements and provide administrative controls for qualification and record keeping.
The NRC inspector reviewed this procedure and found it to adequately address the above concern.
b.
(Closed)
Open Item (316/88002-02):
A walkdown survey performed by the l-icensee of the Unit 2 polar crane disclosed several structural deficiencies.
As discussed in NRC Inspection Report No. 50-316/88002, an engineering analysis of the as found condition verified the seismic qualification to remain valid.
The engineering disposition required that the following deficiencies be repaired.
~
Loose or missing rai 1 plate hold down nuts
0'
'
Rail splice weld cracks and rail flange crack Cut off rail plate hold down bolts The 'NRC inspector reviewed Job Order Nos.
16088, 710524, and 710548 and found the repairs to have been effected.
Documentation of the repairs was found to be complete and thorough.
(Closed)
Open Item (315/88007-01; 316/88008-01):
A Condition Report (12-04-85-792)
was issued to document the inadvertent use of type ER308L weld material in lieu of type ER316 as required in the welding procedure.
Corrective action was taken, however, the RFC package did not contain the identification and disposition of those welds completed with type ER308L weld material.
The NRC inspector reviewed the weld card records and associated documentation and found the weld history to be complete.
With respect to the disposition of the subject welds however, the engineering evaluation was found to be incomplete.
While the welding engineer had considered the metallurgical aspects of the substitution, no documentation was available to support a mechanical review.
This review is required as the allowable stresses for ER308L are less than those for ER316.
As a result of the NRC inspector's inquiry, Calculation No.
DCCPY12PWOIN was performed to verify that an over-stressed condition did not exist.
Failure to execute adequate design control in that a thorough engineering review was not performed is an example of a violation of
CFR 50, Appendix B, Criterion III (316/88012-01).
It should be noted that a similar occurrence was found with regard to inadequate engineering review associated with a section replacement of the CCW piping.
3.
Review of Incore Flux Thimble Tubin Examination The NRC issued Information Notice No. 87-44,
"Thimble Thinning in Westinghouse Reactors" September 16, 1987, in an effort to alert licensee's of the potential for thimble tube degradation.
The NRC inspector reviewed the licensee's Procedure 2 THP SP. 171
"Multifrequency Eddy Current Examinations of Incore Flux Thimble Tubing" and found it acceptable.
The inspector also observed a portion of the examination and data collection.
The results are not available as of this report, however, preliminary results indicate tube degradation.
Prior to this examination, an examination was performed on Unit 1 thimble tubes with inconclusive results.
4.
Steam Generator Re air Pro ect The upcoming replacement of the Unit 2 steam generators requires modifications to the existing Auxiliary Building crane.
The modification includes replacing the existing 150T/20T trolley with a 150T trolley
designed to single-failure-proof (SFP) requirements, and installation of a
new SFP crane with150T and 20T trolleys.
Additionally, the existing crane rail girder was upgraded to accommodate the higher design wheel loads and a second holding brake and an inching mechanism was added to the bridge drive.
The modifications were performed to meet the requirements of NUREG-0612 and 0554 and to permit the movement of the steam generators in and out of the Auxiliary Building.
The NRC inspector reviewed Work Package'o.
210, "Erection of Auxiliary Building Cranes" and associated Change Notices and found the package acceptable and documentation complete.
The inspector observed various stages of the crane erection including the 187 ton load testing of the west crane and found the work acceptable.
In preparation for the Steam Generator replacement, the NRC inspector reviewed the following MK-Ferguson procedures:
Qualification and Certification of Personnel Performing Special Processes Visual Weld Examination Liquid Penetrant Examination Magnetic Particle Examination Radiographic Examination Ultrasonic Examination Ultrasonic Thickness Measurement Welder Qualification Filler Metal Control Control of Welding Controlled Preheat and Postweld Heat Treatment General Welding Requirements Control of AWS Welding WPS M-l-l"B (AWS)
Document Control Rigging and Handling Control of Special Processes FQP-2. 2 FQP-9. 1 FQP-9. 2 FQP-9. 3 FQP-9. 4 FQP-9. 5 FQP-9. 6 FWP-2. 1 FWP-7. 1 FWP-9. 1 FWP-9. 2 FWP-9. 3 FWP-9. 4 FWP-15. 11 SQP-6. 1 SQP-13.3 SQP-9. 1 In addition, the NRC inspector reviewed the following D.C.. Cook Plant procedures:
Design Change Control Program Preparation of SFRP Procedures SGR QA Procurement Document Review Quality Action Requests NRC Control and Condition Report Interface Technical Document Control Plant Area Turnover PMI-5040 SGR-PP-05-01 SGR-PP-04-01 SGR-PP-15-01 PP-15-02 PP"06-02 PP-14-01 All procedures reviewed were found to comply with applicable codes, standards, and licensee commitments.
Region III management and the D.C.
Cook Plant, NRC Senior Resident Inspector attended a briefing on April 27, 1988, at the site concerning SGR project controls and documentation turnover.
The discussion was informative and no adverse comments were note.
Exit Interview The Region III inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on May 5 and 18, 1988.
The inspector summarized the purpose and findings of the inspection.
The licensee representatives acknowledged this information.
The inspector also discussed the likely informational content of. the inspection report with regard to documents or processes reviewed during the inspection.
The licensee representatives did not identify any such documents/processes as proprietary.