IR 05000410/1987011
| ML17054C088 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/24/1987 |
| From: | Gregg H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17054C087 | List: |
| References | |
| 50-410-87-11, NUDOCS 8705110314 | |
| Download: ML17054C088 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/87-11 Docket No.
50-410 License No.
NPF-54 Priority Category B
Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Nuclear Power Station Unit 2 Inspection At:
Scriba New York Inspection Conducted:
March 23-27 1987 Inspector H. I. Gregg, Le actor Engineer date Approved by:
.
R. Strosnider, Chief, Materials and Processes Section, Engineering Branch, DRS date Ins ection Summar:
Ins ection on March 23-27 1987 Re ort No. 50-410/87-11 Areas Ins ected:
This inspection was a routine unannounced inspection of the licensee s activities related to the installation of the new Rockwell "Y" pattern globe type MSIVs.
These new valves are replacing the Crosby ball type MSIVs.
This inspection effort focused on the mechanical aspects of the new valve installation including:
review of the new valve details of operation, refurbishment and documentation; observations of in process welding of pipe attachments to the valves; review of the organizational plan to accomplish this major task; and review of QA/QC involvement.
Results:
No violations were identified and the work activities reviewed were being adequately performed.
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DETAILS 1.0 Persons Contacted 1.1 Nia ara Mohawk Power Cor oration NMPC
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"R. Cohen, Manager, Site Services J. Guiler, Principal Modifications Engineer W. Hansen, Manager, Nuclear QA Operations J,
Michaud, Receiving QC Head
- T. Perkins, General Superintendent
- 0. Pike, MSIV Engineering Manager
"A. Pinter, Site Licensing Coordinator
"M. Ray, MSIV Project Manager 0. Student, QA Surveillance Engineer 1.2 Stone and Webster En ineerin Cor oration T. Arrington, Resident Manager, FQC CD Crocker, Project engineer P.
Hanks, Welding Foreman E. Lighthall, Materials Engineer E.
Magi lley, Assistant Superintendent, FQC 0. Parker, Receiving QC Inspector 1.3 Factor Mutual Com an C. Mellon, Authorized Nuclear Inservice Inspector M. Roby, Authorized Nuclear Inservice Inspector 1.4 General Electric Com an C. Nieh, Principal Engineer S. Bellows, Piping Engineer J.
Boseman, Principal Engineer 1.'5 New York State Electric and Gas
- P. MacEwan, Site Representative 1.6 New York State Public Service Commission
"P.
Eddy, Site Representative 1.7 U.S. Nuclear Re viator Commission
- W. Cook, Senior Resident Inspector
"Denotes those present at the exit meetin.0 Installation of "Y" Pattern MSIVs Oue to the ball valve problems encountered during.recent in-plant and prototype testing, the licensee made the decision to replace their ball type MSIVs with "Y" pattern MSIVs.
2.1 Pur ose of Ins ection
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2.2 The licensee's program to install the new Rockwell "Y" valves that have replaced the Crosby ball valves was divided into eleven distinct phases.
Each phase has an individual Safety Evaluation Report (SER)
and a separate modification package, The purpose of this inspection was to review the mechanical aspects of the new MSIV installation to assure compliance with regulatory requirements and commitments to applicable codes, standards and procedures.
The inspection plan included:
review of the new valve details of operation and refurbishment; observations of the valves, the in-process shop welding'f pipe attachments to the valves, and the in-process welding of the valves to the plant piping; review of documentation relating to the work and the licensee's system for controlling this major modification.
Two specific SER and modification work packages were selected for review for this inspection.
They were item number 204, MSIV Installation, and number 203, Remove/Refurbish Actuator.
Review of MSIV Recei t Documentation During a plant tour, the inspector observed valve 6A being installed inside containment.
The nameplate data from the valve (Valve 6A, Serial No. PK-30) was recorded for the purpose of tracking the documentation package of this specific valve.
The receiving documentation for MSIV 6A, Serial No. PK-30, was readily available (the documentation package for all 8 MSIVs was also available)
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From the review of the documentation, the inspector determined that all aspects of the purchasing and specification requirements were through General Electric Company.
The valves are 26 inch "globe" type valves manufactured by Rockwell International Corporation.
The valves were originally purchased and shipped to Black Fox Station, Unit 2, in 1981.
Although the valves were never used, they were refurbished at the Rockwell plant in Raleigh,.North Carolina, per G.E. requirements in December 1986 to ready them for use at Nine Mile Point, Unit The inspector verified that the documentation package for MSIV 6A was complete and that the original data report forms represent the nameplate recorded data and that the valves were built to ASME Section III, Class 1.
The inspector reviewed the material test reports and records of weld repairs made to the valve body.
A 1100~F post-weld heat treatment was performed after the repairs.
The inspector also verified that the refurbishment documentation was complete and acceptable.
2.3
"Y" Pattern Valve Installation The inspector reviewed the SER (PN2Y86MX204) and modification package for the valve installation work.
The inspector determined that installation of the "Y" pattern MSIVs is being performed as a
replacement under ASME Section XI Code, 1980 Edition through Winter 1980 Addenda, however, all installation work will also meet the requirements of the ASME Section III Code, 1974 Edition, no addenda, that was used during the original system construction.
The controlled modification plan was reviewed and each activity was described, appropriate references were listed, and acceptance signatures by the installer and gA were required.
The inspector observed numerous work activities involving the valves and also reviewed documents relating to the work as follows:
Shop welding of the transition pieces being welded to the outlet ends of MSIVs 7A and 7B (FW 001)
Weld data sheets for the welds being made to verify hold and inspection requirements and preheat and post-weld requirements Welders performance qualification test records Radiographic inspection records of the shop and in position welds Machining of weld joint preparation Welding of the valves at their installed locations in the drywell and in the steam tunnel Engineering and Design Coordination Reports (E&DCR M00033 relating to joint fit up)
Nonconformance and Disposition Reports (N&D 17176 relating to a liquid penetrant indication and N&D 17174 relating to large tack weld 'size)
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gA Surveillance Reports 87-10178 relating to the work Piping Systems, Reactor Component Welding Procedure W-3-NSSS, Revision
During each of the above activities, there was continuous gA and gC oversight.
There was also a constant interface and oversight of engineering and work effort from NMPC, SWEC, GE and the ANII.
2.4 Valve Actuator Refurbishment The inspector reviewed the licensee's SER (PN2YMX203) and modifica-tion package relating to the valve actuator upgrading.
This modification involved the removal of the NAMCO limit switches and replacement of the air cylinder assembly with a new assembly manufactured by Ralph A. Hiller Company.
The inspector observed the completed actuator assemblies.
All eight actuators were fully assembled and attached to the spring guide tubes of the upper valve works.
Each assembly was protectively covered and ready to be moved to its valve.
The inspector reviewed the GE FDDR and the SWEC rework control forms associated with the actuator rework.
Specific documents reviewed were:
EADCR M-10120 requesting instructions of actuator changeout and retrofit GE FDDR K61-0774 that provided the above requested instructions Modification No. 203(P) that described the actuator work in detail Rework Control forms SB 2085, 2088 and 2089 for the work to be performed The inspector verified that documentation contained the necessary instructions, hold and witness points, and sign-off by appropriate personnel.
2.5 Leaka e Control S stem The inspector reviewed the licensee's information concerning installation of a leakage control system (LCS).
The inspector determined that the installation of an LCS has not fully been finalized.
On March 18, 1987, the licensee submitted to NRC an evaluation and proposal based on NUREG 1169 methodology to show that
an LCS is not required.
According to cognizant licensee personnel, the NRC, via phone request, asked several questions regarding the submittal.
The response to these questions was in the preparation stage and was to be submitted by March 31, 1987.
At the time this inspection was concluded, the issue of whether an LCS would be required was not finalized.
2.6 Conclusions The inspector reviewed, MSIV installation (mechanical aspects),
actuator upgrading, documentation, welding, organizational structure, scheduling, interface and oversight by QA and gC, engineering interfacing between NMPC, SWEC, GE and the ANII.
No unacceptable conditions were identified.
A separate organizational structure with clearly defined areas of responsibility was established to accomplish this major rework effort.
No violations were identified.
~KN The inspector met with the licensee's representative (identified in paragraph 1.0) at the conclusion of the inspection on March 27, 1987, to summarize the findings of this inspection.
The NRC Senior Resident Inspector, W. Cook, was also in attendance.
During this inspection, the inspector did not provide any written material to the licensee.
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