IR 05000410/1981005
| ML17053C769 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/24/1981 |
| From: | Feil R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053C768 | List: |
| References | |
| 50-410-81-05, 50-410-81-5, NUDOCS 8108110296 | |
| Download: ML17053C769 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-410/81-05 Docket No. 50-410 License No.
CPPR-112 Priority Category B
Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard blest S racuse New York 13202 Facility Name:
Nine Mile Point Unit 2 Inspection At:
Scriba, New York Inspection Conducted:
Jut 23-25, 1981 Inspectors:
R.
. Feil, Reactor Inspector Approved by:
.B. Kiste
, Chief, Reactor Projects Section 1C, Division of Resident and Project Inspection date signed Ins ection Summar
Ins ection on June 23-25 1981 Re ort No. 50-410/81-05 Areas Ins ected:
Routine, unannounced inspection by one regional based in-spector of unresolved items and facility status.
The inspection consi sted of 24 inspector-hours on site and 4 inspector-hours in the regional office by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
8i08110296 8i0727 PDR ADOCK 050004i0
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DETAILS Persons Contacted Nia ara Mohawk Power Cor oration NMPC
- S.E. Czuba, QA Engineer (Site)
~R. Dahlin, Lead Construction Engineer
'J.L. Dillon, Senior Site QA Engineer
"G.C. Doyle, QA Engineer (Site)
L.G. Fenton, QA Engineer (Corporate)
C.G. Honors, Construction Engineer R.A. Norman, Senior QA Engineer (Corporate)
"R.L. Patch, QA Engineer (Site)
J.P.
Ptak, Assistant Manager, Field Construction Stone and Webster En ineerin Cor oration SWEC
- S.W.
- B
- M.R.
"H.J.
"L.E.
"F.M.
Crowe, Field QC Engineer Gay, Superintendent FQC Holsinger, QA Engineer Oceson, Construction Engineer Pierre, Construction Engineer Shea, Head, Site Engineering Office Sheldon, Superintendent, Construction
"Denotes those present at exit interview.
The inspector conferred with other licensee and contractor personnel during the course of the inspection.
Licensee Action on Previous Ins ection Findin s
(Open) Unresolved Item (79-02-06)
Evaluation of semi-automatic welds of cadweld sleeves for sparger ring supports.
Work has commenced on the repair of the sparger ring supports.
This consists of the drilling of the sparger rings, after locating the cadweld sleeve, at the center
'ocation of the cadweld sleeve to be reworked, to a depth where the inner perimeter of the sleeve is identifiable.
The sleeve is then welded to the sparger ring.
The inspector observed the dri lling of one sparger ring and the welding of a sleeve on another ring.
The inspector noted the cleanliness of the work area and that the procedures for NDE and repair were being followed.
Faci1 it Tour 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 condition 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, and quality inspection personnel as such personnel were available in the work areas.
Specifically, the inspector observed the automatic overlay welding for support bases on the biological shield wall.
The welding of the cover plates has been completed and the ultrasonic testing of the cover plate welds is continuing.
The inspector observed magnetic particle testing of a joint in the base plate liner to circumferential ring in the suppression pool liner.
The inspector verified that the technique employed by the tester was in accordance with procedure MT 12X, Magnetic Particle Examination Procedure Continuous Prod, Dry, Visible Particles Class 2,
3 and MC Products.
The inspector observed that the control of weld material and cleanliness in the area of welding in the suppression pool liner were excellent.
No weld rods were left in the work area at the end of each work cycle and weld rod stubs were deposited in appropriate containers for removal from the work area.
The inspector observed an inspection of a joint fit up of a spool piece for the Residual Heat Removal System.
The spool pieces were both designated NM66-105x.
When questioned by the NRC inspector the designated ITT Grinnel (}C inspector explained that the original spool piece NM66-105x had to be cut in order to install it in its present location.
The NRC inspector observed that all attributes on the weld data sheet were checked by the gC inspector.
The NRC inspector reviewed the Deviation Report which described the problem with the spool piece NM66-105x as being too long to fit into the building.
Drawings and materials records were reviewed.
The NRC inspector verified that the Isometric Drawing 66-20, Rev B identified the weld joint, FW008, for the joining of spool piece NM66-105 to NM66-105.
The inspector examined a section of spent fuel pool piping which had undergone a hydrostatic test in the pipe fabrication shop.
The pipe section had 2 welds which had to be observed by NDE inspectors under hydrostatic conditions in the shop since the welds would be embedded in concrete and would not be visible during the normal system hydrostatic test.
The observation is required by ASME Section III, ND6215.
Primar Containment The inspector reveiwed the status and results of the dimensional survey conducted by Chicago Bridge and -Iron (CBI) of the primary containment chimney section and dome.
The results indicated that the
chimney section would have a +1 7/16" elevation after being installed on the lower flange seal surface of the upper cone assembly of the primary containment.
The maximum allowable tolerance for the chimney section is -0 + 2 inches.
Subsequently, on June 30, 1981, the inspector was informed by the licensee that the chimney section had been set in place without the dome on June 29, 1981 and that the elevation dimension was
+
1 7/8". The licensee stated that an anticipated reduction in the dimension would occur when the chimney section was welded to the lower flange seal.
~store e
During the tour of the facility the inspector observed that the Reactor Core Isolation Cooling (RCIC) turbine, pump, cooler and gland seal compressor were stored in place in the reactor building.
The area was exposed to weather, water was on the floor, and condensation and humidity were extremely high.
This unsatisfactory storage condition of these components as well as the storage condition of other safety related components in the reactor building is documented in Nonconformance Report (NCR) No.
0309 by the licensee to Stone and Webster Engineering Corporation (SWEC).
Control measures for storage have been delegated by the licensee to SWEC for the components identifed in the NCR as well as other identified items.
SWEC Specification NMP2-SM0-1, Rev.
5, dated February 3, 1981, provides for storage conditions for "Warehouse Storage" and "In-Place Storage."
The subsections in the Specification SMO-1 for "Warehouse Stora e" are categorized into various levels (A, B, C & D) as defined in ANSI N
45.2.2, 1972.
The subsections in the Specification SMO-1 for "In-Place Stora e" are noticibly deficient in providng the equivalent level of storage as that required for warehouse storage.
For RCIC Turbine and Accessories, Specification SMO-1 states the following for "Warehouse Stora e" and
"In-Place Stora e."
SUBSECTION I (Warehouse Storage)
A.
Storage-Level B
B.
General 1.
The manufacturer's shipping package shall be preserved and utilized during storage.
2.
VPI powder is not effective indefinitely unless the space is totally sealed.
3.
Components with desiccant protection shall be plainly tagged stating that desiccant is contained internally and the number of desiccant bags utilize.
The turbine shall be stored in accordance with GE/Terry Turbine extended storage requirements in Document No.
VPF 3622-368-2 as outlined in this instruction.
C.
Materials-None D.
Preventive Maintenance Card-Required E.
Maintenance.
1.
Initial a.
Megger motor in accordance with Specification No.
NMP2-E061A.
b.
Energize space heaters.
(Ensure that the voltage applied satisfies the minimum requirements of the heaters).
2.
Periodic Megger motors in accordance with Specification No.
NMP2-E061A.
F.
Inspections 1.
Weekly-Inspect heaters 2.
Monthly-Visual G.
Quality Control l.
Every 3 months-Visual 2.
Witness E.2.a SUBSECTION II (In-Place Storage)
A.
Storage-Instal led in System B.
General Care should be taken to ensure all VPI crystals are purged prior to turnover for testing.
C.
Materials-None D.
Preventive Maintenance Card-Required E.
Maintenance
1.
Megger motors in accordance with Specification No.
NMP2-E061A.
2.
Energize space heaters.
(Ensur that the voltage applied satisfies the minimum requirements of the heaters.)
F.
Inspections Weekly-Visual G.
Quality Control 1.
Every 3 months-Visual 2.
Witness E. 1 ANSI N 45.2.2-1972 states in part in Paragraph 2.7, "Items shall not be classified according to the requirements of one level, then packaged, shipped, received, stored and handled according to a level of lower grade."
In addition,
CFR 50, Appendix B, Criterion II states in part,
"The quality assurance program shall provide control over activities affecting the quality of the identified structures, systems, and com-ponents, to an extent consistent with their importance to safety."
The SWEC storage program is deficient in that it does not provide adequate control measures and requirements for items and areas within their jurisdiction of responsibility.
Pending SWEC revi sion of their storage program as requested by the licensee to conform to ANSI standards and
CFR 50, Appendix B and provisions for the storage of components consistent with their importance to safety, this item is unresolved (81-05-01).
During the facility tour, the inspector observed that the housekeeping in the primary containment building was very poor.
Much piping and some equipment had been moved into the primary containment prior to setting the upper cone in place.
This was necessary because of the limited space between the reactor vessel/biological shield wall and the primary containment wall after the upper cone was set in place.
The piping located in the containment is subject to many kinds of debri.
Some equipment is covered with boxes and tarps but the equipment is subject to normal construction abuse.
The poor housekeeping is the subject of a Nonconformance Report (NCR) by the licensee to SWEC.
As evidenced by the inspector the housekeeping does not meet the requirements of ANSI N.45.2.3-1973, Housekeeping During the Construction Phase of Nuclear Power Plants.
The licensee is committed to Regulatory Guide 1.3.9, 1973 which generally accepts ANSI N45.2.3-1973.
Pending resolution of the NCR this item is unresolved (81-05-02).
7.
Site ualit Staffin The licensee has added 2 persons to the site quality staff.
The present active quality staff consists of six persons.
Under the proposed reorganization plan for.Nine Mile Point Unit 2, which has been submitted to NRR, the Project Manager wi 11 have a sizable on-site staff.
The inspector was informed that site staffing under the Project Manager would be incr eased to 60 persons to included personnel in construction, records management, quality control, cost and scheduling and cost accounting.
An additional 35 persons would be added for test and startup at the appropriate time.
The inspector expressed concern about the adequacy of the quality staff for the licensee and SWEC considering the extensive build up of craft personnel in the site and the increased staffing by the licensee.
The inspector was informed that the licensee's quality control staff on site would be increased to 11 persons under the reorganization reporting through the Manager, Project guality to the Project Manager.
The inspector was informed that SWEC field quality staff has been increasing to cover the increased site activities.
The adequacy of SWEC field quality control staffing and the licensee's site quality staffing will be reviewed during a subsequent inspection.
Pending the verification of the adequacy of overall site quality staffing this item is unresolved (81-05-03).
8.
Faci lit Status The licensee informed the inspector that the project completion (con-struction and engineering)
is 39% complete.
Construction is 33% com-plete.
Manpower has increased to 1605 manual and 574 non manual.
Principal ongoing activities include cable tray installation, primary containment wall rebar and concrete work, piping installation in the turbine and reactor buildings, welding on primary containment liner upper to intermediate core, welding 'on biological shield wall, con-tinued effort on lake tunnel intake structures, excavation for Radwaste building, cooling tower rebar and concrete placement, welding on the fuel pool liners and continuing civil/structural work on the control building, turbine building and tunnels.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance.
Unresolved items are discussed during the inspection are detailed in Paragraphs 5,
6 and 7.
10.
Exit Interview The inspector met with licensee's representatives (denoted in Para-graph I) at the conclusion of the inspection on June 25, 1981.
The
g f 'P (I J y,
inspector summarized the findings of the inspection.
The licensee acknowledged the inspectors comments.
The inspector discussed clarification details of the inspection by telephone with the licensee on July 2, 198 'I