IR 05000410/1985046
| ML17055B035 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1985 |
| From: | Mcbrearty R, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055B033 | List: |
| References | |
| 50-410-85-46, NUDOCS 8601130206 | |
| Download: ML17055B035 (10) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/85-46 Docket No.
'0-410 License No.
CPPR-112 Pri ori ty Category B
Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Unit 2 Inspection At:
'criba New York Inspection Conducted:
December 9-12 1985 Inspector:
R. A. McBrearty, Reactor En eer 6~. w j ques date Approved by:
J.
sggins, C ief, Materials 5 Processes ction, EB, D
S fBg/ g5 da e
Ins ection Summary:
Ins ection on December 9-12 1985 Re ort No. 50-410/85-46 Areas Ins ected:
Routine, unannounced inspection of licensee action on pre-vious inspection findings and PSI activities including observations of work in progress, program review, review of implementing NDE procedures and review of PSI data.
The inspection involved 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> on site and 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> in the regional office by one regional-based inspector.
Results:
No violations were identified.
SEOii30206 860i07 PDR ADOCK 050004iO
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DETAILS 1.
Persons Contacted Nia ara Mohawk Power Cor oration NMPC
- C. Beckham, Quality Assurance Manager - Projects
"W. Hansen, Manager Quality Assurance Nuclear
- E. Klein, Manager - Project Engineering Design
"M. Ray, Manager - Special Projects J.
Shepherd, Quality Control Lead Unit II
"J. White, Special Projects Stone and Webster En ineerin Com an SWEC
- T. Baumgartner, Quality Assurance Supervisor J.
De Bonis, PSI Coordinator
'R. Hyslop; Site Licensing Engineer F. Morales, QA/NDT Engineer
- A. Rovetti, Supervisor Engineering E. Schroeder, Startup/Special Projects Supervisor C. Terry, Project QA Manager Nuclear Ener Services NES A. Pennanen, NDE Level III
- C. Taylor, Site Manager Factor Mutual L. Anderson, ANII
"J3enotes those present at the exit meeting on December 12, 1985.
2.
Licensee Action on Previous Ins ection Findin s
(Closed)
Inspector Follow Item 410/85-23-01:
PSI Program implementation.
Inspection Report 50-410/85-23 documented the inspector's concerns regard-ing implementation of the original program.
A review of that program indicated that the ASME Code-required information was included but was presented in a manner that appeared to be unnecessarily complex and confusing.
The inspector's review of the licensee's revised PSI plan indicates that the required examinations are identified, and items which are subject to examination are more clearly defined than they were in the original plan.
The information is presented in a manner that should min-imize potential administrative problems.
Based on the inspector's review of the revised PSI Program Plan, the item is considered close C
3.
Preservice Ins ection PSI Pro ram Plan The revised Preservice Inspection Plan is divided into three parts.
Part One, which includes all nondestructive examination items required by ASIDE Section XI for nuclear piping systems and the reactor pressure vessel, its internals, and safe ends, was reviewed by the inspector to ascertain compliance with ASME Code requirements and with regulatory requirements.
The remaining portions of the Plan were not available for.
review at this time.
The Plan is intended to meet the requirements of the 1980 Edition of ASME Section XI through Minter 1980 Addenda.
The revised plan shows improve-ment over the original version in that items which have been selected for examination are clearly identified as are the Code-required examinations.
No violations were identified.
4.
Review of Preservice Ins ection Procedures The following procedures were selected for review by the inspector to ascertain compliance with applicable ASNE code and regulatory requirements:
~
Document No. 80A7717, Revision 1, "Ultrasonic Examination General Requirements"
~
Document No. 80A7718, Revision A, "Ultrasonic Examination Procedure For Austenitic Piping"
~
Document No. 80A7719, Revision 2, "Ultrasonic Examination Procedure For Ferritic Steel Piping Welds"
~
Document No. 80A7720, Revision 3, "Liquid Penetrant Examination Procedure"
~
Document No. 83A1754, Revision 0,
"Automated Operations General Examination Requirements"
~
Document No. 83A1749, Revision 0, "Automated Ultrasonic Procedure For Reactor Vessel Shell Welds and Nozzle to Shell Melds From the OD Surface"
~
Document No. 83A1750, Revision 0,
"Automated Ultrasonic Examination Procedure For Reactor Vessel Nozzle Safe End Welds From the OD Surface" The inspector's review indicated that the procedures meet applicable code and'egulatory requirements, and were technically adequate for their intended use.
The automated examination procedures incorporate the use of the Ultrasonic Data Recording and Processing System (UDRPS)
and were found to address the requirements of Regulatory Guide 1. 150.
No violations were identifie c K
I
Observations of NDE in'ro ress The inspector observed nondestructive examinations in progress to ascertain that procedural requi rements were met, and that applicable ASHE Code requirements were met.
The ultrasonic examination of the following welds were included in the inspector's observations:
~
Meld No. 2ICS-57-9-FW020, 10" diameter pipe to tee field weld
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Weld No. 2ICS-57-9-SW029, 10" diameter pipe to reducer shop weld The inspector's observations included calibration of the examination system, 0'ongitudinal wave examination and 45'hear wave egamination of the two welds.
Additionally, the qualification/certification records of the examiners were reviewed by the inspector.
The inspector found that the examinations were done in accordance with procedure 80A7719, Rev.
2 by properly qualified personnel.
No violations were identified.
Review of Preservice Ins ection Data The inspector reviewed data associated with the examinations discussed in paragraph 5 of this report to ascertain that findings were properly recorded and evaluated, and that applicable Code, regulatory and procedural requirements were met.
Weld No. 2ICS-57-9-FW020 displayed an indication which was evaluated and determined to be a geometrical reflector.
The reflector's location was plotted using the recorded information and technical justification was provided for the geometrical determination.
The inspector found that PSI data sheets are subject to review by the vendor (NES),
SWEC acting as the licensee's agent and by the ANII.
The data review process was discussed with licensee representatives and the inspector was unable to determine whether any of these reviewers were responsible for licensee-acceptance of the data.
This was further dis-cussed at the exit meeting on December 12, 1985, and the matter will be explored by the licensee.
The item is considered unresolved pending licensee action and subsequent NRC review of that action (410/85-46-01).
No violations were identified.
Unresolved Items Unresolved items are items about which more information is required to ascertain whether they are acceptable, violations or deviations.
An unresolved item is discussed in paragraph V
8.
Exit Interview The inspector met with licensee representatives denoted in paragraph
at the conclusion of the inspection on December 12, 1985.
The inspector summarized the purpose and the scope of the inspection and the findings.
At no time during this inspection was written material provided by the inspector to the license T