IR 05000410/1980001
| ML17053B594 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/08/1980 |
| From: | Cerne A, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B590 | List: |
| References | |
| 50-410-80-01, 50-410-80-1, NUDOCS 8004300309 | |
| Download: ML17053B594 (14) | |
Text
80D4800 U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION ANO ENFORCEMENT Region I Report No 50"410/80-01 Oocket No.
icense No CPPR"112 Priority Category Niagara Mohawk Power Corporation 300 Erie Boulevard, West Syracuse, New York 13202 Nine Mile Point Nuclear Station, Unit 2 Ins ection at.
Scriba, New York Inspection conducted.
January 9-11, 1980 A. C. Cerne, Reactor Inspector date signed date signed Approved by:
R.
W. McGaughy, i, Construction Projects Section, RCEES Branch date signed dat si ned Ins ection Summar:
Ins ection on Januar 9-11, 1980 Re ort No. 50-410/80-01)
Areas Ins ected:
Routine, unannounced inspection by a regional based inspector o, licensee action on previous inspection findings, equipment maintenance and storage activities, and plant inspection-tours.
The inspection involved 23 inspector-hours on site by one regional based inspector.
Results:
Of the three areas inspected, one apparent item of noncompliance was i<acetified in one area (Infraction - failure to perforn required equipment maintenance, to furnish recorded evidence of same, and to control equipment storage in accordance with work and inspection instructions).
Region I Form 12 (Rev.
April 77)
t; f'
Persons Contacted Nia ara Mohawk Power Cor oration, NMPC
- J. J.
Bebko, gA Projects Group Leader
- R. J.'ebko, gA Engineer
+J. L. Dillon, gA.Engineer
- K. M. Nilsson, Construction Engineer
- R. A. Norman, Senior Site gA Representative
- R. L. Patch, gA Technician Stone and Webster En ineerin Cor oration S&W)
- J. F. Barrett, Resident Manager T. Britt,. Senior Electrical gA Engineer J.
P. Cardelli, Materials Manager
- J. E. Evans, Advisory Operations Engineer
- B. F. Gallagher, Senior Resident Engineer
- C. E. Gay, Superintendent, Field gC
- C. E. Hilton, Superintendent of Construction
- M. G. Pace, Assistant Project gA Manager
- J.
E. Rogers, Chief Office Engineer
- L. E. Shea, Head, Site Engineering Office ITT Grinnell Cor oration Grinnell)
- D. R. Batchelor, Mechanical Equipment Erection Engineer
- D. R. Giguere, Field gC Manager
- R. W. Graiko, Project Engineer D.
R. Hall, Piping Engineer
- D. F. Shea, Project Manager
- Denotes those present at the exit interview.
Plant Tours The inspector observed work activities in-progress, completed work and plant status in several areas of the plant during general inspection of the plant.
The inspector examined work for any obvious defects or noncompliance with regulatory requirements or license conditions.
Particular note was taken of presence of quality control inspectors and quality control evidence such as inspection records, material identification, nonconforming material identification, housekeeping and equipment preservation.
The inspector interviewed craft personnel, supervision, and quality inspection personnel as such personnel were available in the work area Specifically the inspector observed welding on the containment liner intermediate cone and checked weld rod control and preheat requirements relative thereto.'he inspector also examined the adequacy of temperature controls, curing, and cold weather protection for recently placed concrete, including a wall in the control building which was completed on the previous evening shift.
The use of plant de-icer agents was questioned by the inspector.
He reviewed S&W Specification M070A-CP1, Revision 1, and determined that utilization of prilled urea as an anti-icer was being properly controlled.
No items of noncompliance were identified.
Licensee Action on Previous Ins ection Fi.ndin s (Closed)
Unresolved Item (79-02-05):
Lack of procedure for visual inspection of welds.
The inspector reviewed S8W guality Assurance Directive gAD-10.13, Revision 0, effective November 7, 1979, titled
"Visual -Examination of Welds".
gAD-10.13 references the AWS Dl.l Structural Welding Code and the inspector checked for conformance to this standard with regard to visual inspection of structural welds.
This item is resolved.
(Closed)
Unresolved Item (79-05-02):
Interference in structural steel clip angle welds.
The inspector interviewed personnel and reviewed the following documents to determine that the requirements
,for welding clip angles or beam seats, wher e continuous weld beads-cannot be'attained, have been clarified and that each nonconforming case had been reviewed by engineering and properly dispositioned.
S8W Engineering and Design Coordination Reports E&DCR's F00118, July 17, 1979 and F00122, July 27, 1979 S&W Nonconformance and Disposition Reports N&D's 1391, May 16, 1979 and 1465, July 12, 1979 This item is resolved.
(Open}. Unresolved Item (79-02-04):
Stud welding attributes and inspection.
The inspector reviewed S&W Construction Methods Procedure for Automatically Timed Stud Welding, CMP6.3 -8.79 and S8W gAD 9.3, Revision A, for "Stud Welding Inspection" with its attached attribute list D9.3-1-3319.
Since the applicability of any particular attribute from this list depends upon the project specification under which the stud welding is accomplished, this item remains unresolved pending review by the NRC of some of the newly formulated guality Assurance Inspection Plans for various specifications which include stud weldin.
E ui ment Stora e and Maintenance a.
Recirculation Pum s
The inspector reviewed the specified equipment storage require-ments, checked the level of storage, and examined the overall
- condition of each of the following components, as part of the reactor recirculation pump system:
Volute Pump Cases (2RCS-P1A and P18)
Mechanical Shaft Seal Assemblies (2RCS - P1A and PlB)
Pump Motor (2RCS - M1B)
The inspector reviewed a
S8W Returned Material Report, dated March 21, 1978 indicating the return of Pump Motor (2RCS-MlA)
to General Electric (GE) in Schenectady, New York.
The following documents were examined to determine the specific preventive maintenance, storage, test and inspection requirements for the recirculation pumps and motors:
SSW Specification P275C, with Addendum 1, October 20, 1977 GE Specifications 22A3126, Revision 2, accepted for use on January 29, 1979 GE Specification 34A180535, issued March 27, 1974 Instructions for "Boiling Hater Nuclear Reactor Recirculating Water Pump Motors",
GEK 42714, dated March 12, 1976 The inspector noted that Grinnell had taken over the preventive maintenance responsibilities of Specification P275C from Stone and Webster on February 1, 1979.
Upon examination of the Grinnell Preventive Maintenance System Records for the recir-culation pump motors, the following discrepancies and deficiencies were observed:
(1)
The last complete lubrication check and maintenance on recirculation pump motor 2RCS-MlB was performed on December 6,
1978 (reference:
GE Installation and Service Engineering Division letter, dated December 7, 1978).
This is in violation of the yearly lubrication requirements of GE Specification 34A180535 and is an infraction with regard to 10 CFR 50, App'endix B, Criterion V.
(2)
guality records were not available to substantiate all quarterly electrical test and lubrication inspection entries on the Preventive Maintenance Card for recir-culation pump motor 2RCS-M1B and also were not available to substantiate all quarterly lubrication entries for Residual Heat Removal Pump 2RHS-PlB.
This is a deficiency with regard to 10 CFR 50,, Appendix B, Criterion XVII.
(3)
With regard to recirculation pump motor 2RCS-MlA, which was and had been in Schenectady, New York since March 21,
'l978, all entries on the Grinnell Preventive Maintenance Card indicating the performance of, el.ectrical tests, lubrications, and visual inspections from May to November, 1979 were in error.
This record falsely represents the status of that equipment and makes suspect the validity of the entire Grinnell maintenance program, as it is documented, and is an infraction with regard to 10 CFR 50, Appendix B, Criterion XIII.
These apparent failures to perform required equipment maintenance, to furnish recorded evidence of all maintenance activities, and to control, equipment storage in accordance with work and inspection instructions represent a noncompliance with the above specified criteria of 10 CFR 50, Appendix B, (80-01-01).
The inspector noted that. the licensee took immediate action to determine the extent and causes of the above noncompliance and issued a comprehensive plan for program'eview of the Grinnell Preventive Maintenance Program to determine the course of corrective action, including that which would prevent recur-
- rence of'his proble b.
Oikkers Safet Relief Valves The Dikkers Safety relief -valves are currently i.n storage and in "Reject" status pending determination as to the acceptability of their radiographs (r eference:
NRC unresolved item 79-07-04).
The inspector examined the condition of the valves, as crated, in storage and checked the level of storage.
He interviewed'ersonnel and reviewed the following documents with regard to required maintenance/inspection activities.
GE Specification 22A3126, Revision
Dikkers Storage Procedure, Revision
S8W advance copy to Grinnell of "Warehouse and Inhouse Storage Requirements for Main Steam - Safety Relief Valves" A GE requirement for an inspection for corrosion every six months. of all valve stems around which the packing is installed had, not been implemented to date for these relief valves, which were received on site in May, 1979.
Since the Dikkers storage program does not call for such inspections, the applicability of this GE requirement to the Dikkers valves remains unresolved (80-01-02).
c.
Reactor Pressure Vessel RPV and Shroud Head The inspector checked the level of storage and examined the overall condition in storage of the following components:
RPV and RPY head RPV closure 0-ring Core structure/Shroud head Shroud head bolts RPV closure studs
He reviewed the following documents for applicable storage/maintenance requirements:
S8W Specification SMO-l, Revision
GE Specification 22A3126, Revision
GE Specification 22A4645, Revision 1, accepted for use on December 6,
1979 GE Field Deviation Disposition Request FDDR KG1-19, December 5,
1979 During visual inspection of the various components, the inspector verified that specific storage requirements were being met.
He interviewed various licensee personnel regarding plans for continued long term storage of these items.
The maintenance of a specification - required nitrogen purge internal to the RPV was checked and the inspector noted that SQl N&D report 1662 had properly documented a previous problem with maintenance of this purge.
The inspector also examined the SSW QA Inspection Reports for the RPV closure flange studs, nuts, and washers, noting an attached Product, Quality Certification (GE PQC M487), as required for receipt of items that were source inspected by Procurement Quality Control.
Inspection attributes utilized for actual receipt of these items on site were evaluated with regard to the applicable requirements of SSW QAD-7.7, Revision A.
No items of noncompliance were identified.
5.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 4b.
6.
Exit Interview At the conclusion of the inspection on January ll, 1980 a meeting was held at the Nine Mile Point Unit 2 site with representatives of the licensee.
Attendees at this meeting included personnel whose names are indicated by notation (*) in paragraph 1.
The inspector summarized the results of the inspection as described in this r epor Cs
'P
~
ff
~
~
J t
/
t h
I
~ i
~l