IR 05000410/1979003
| ML17053B109 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/22/1979 |
| From: | Cerne A, Mcgaughy R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B108 | List: |
| References | |
| 50-410-79-03, 50-410-79-3, NUDOCS 7910180160 | |
| Download: ML17053B109 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-410/79-03 Docket No. 50-410 License No.
CPPR-112 Priority:
Category:
A Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard, Mest Syracuse, New York 13202 Facility Name:
Nine Mile Point Nuclear Station, Unit 2 Inspection at:
Scriba, New York Inspection conducts:
July
1979 Inspectors:
L. Narrow, Reactor Inspector A. C. Cerne, Reactor Inspector CLc, PIP:G.
A. Malton, Reactor nspector Approved by:
R.
M.
McG ughy, i
C nstruction Projects Section,
Branch Ins ection Summar
at sign d
.2o dat si ne
&zv g date signed e signe Inspection on July 10-12, 1979 (Report No. 50-410/79-03)
Areas Ins ected:
Routine, unannounced inspection by regional based inspectors, of gC programs for fabrication and erection of the contain-ment liner; installation of piping; installation of structural steel; and review of the status of outstanding items.
The inspection involved 38 inspector hours onsite by three regional based inspectors.
Results:
No items of noncompliance were identified.
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-2-DETAILS 1.
Persons Contacted Nia ara Mohawk Power Cor oration
- L. G. Fenton, Senior Site QA Representative (Acting)
S.
H. Haybrook, Senior Site Construction Representative C.
G. Honors, QA Engineer
- I. Stupal, Managet of Construction, NM-2
- K. D. Ward, QA Engineer
%%E
- B
- C
%J
- D G.
D.
Cloth, Lead Materials Engineer (Cherry Hill Office)
F. Gallagher, Senior Resident Engineer E. Gay, Superintendent, Field QC E. Karr, Project QA Manager Kolecki, Materials Engineer (Cherry Hill Office)
Page, Assistant Head, Site Engineering A. Smith, Structural Engineer Chica o Brid e and Iron Com an CBI T. J. Dougherty, Project Welding and QA Superintendent L. Johns, QC NDE Inspector The inspector also interviewed other licensee and contractor employees during the inspection.
+ Denotes those present at the exit interview.
~ Denotes telephone discussion during inspection 2.
Plant Tour The inspectors made a tour of the site to observe work activities in progress, completed work and the status of construction.
The inspectors examined work items for any obvious defects or noncompliances with regulatory requirements and observed QC activities and evidence of quality control of the work.
Specific activities and items observed by the inspectors included:
Welding of embedment anchors, installation of downcomers, tnstallation of reactor building structural steel, welding of lower cone section
to knuckle, storage of reinforcing steel, and.UY examination of penetration welds.
No items of noncompliance were identified.
3.
Containment Weldin Procedures The inspector reviewed the Chicago Bridge and Iron (CB&I) "Nuclear Quality Assurance Manual for ASME III Products,"
Issue No.
8 and the Stone and Webster (S&W) Quality Control Instruction FN2-S10.61-06B, Revision A relative to containment construction activities involving welding, NDE, heat treating, and defect removal; and the CB&I QC inspection and S&W QC surveillance of these activities.
He spot-checked the CB&I welding and NDE procedures to verify consistency with the requirements of S&W Specification P-283B, Revision 3.
Two other S&W Specifications (S-204F with addendum 3 and S-203C, Revision 4) were reviewed relative to their applicability to structural steel welding within containment
. being accomplished by contractors other than CB&I.
to determine if any code or procedural conflicts exist.
The following S&W Quality Control Inspection Reports (QCIRs) were examined to verify implementation of a. S&W surveillance inspection program for CB&I containment liner erection work.
The scope of these QCIRs was checked for conformance to the "Test, Inspection and Document Record" attribute list of Specification P-283B, as amended by S&W Engineering
& Design Coordination Report (E&DCR)
P-10607.
S&W CIRs W9015557 W9015635 W9015640 W9015659 W9015693 W9015695 W9015696 All the above procedures and specifications were evaluated against criteria established in the editions of the following documents to which the licensee was committed:
ASME Sections III and VIII AWS D1.1 SNT-TC-iA Regulatory Guides 1. 19 and 1.31
No items of noncompliance were identified.
4.
Containment Structural Steel Procedures The inspector reviewed Division 4 (Construction), of the CB&I Nuclear gA Manual, Issue 8 to verify the existence and adequacy of procedures governing receiving, storage, erection, testing, inspection, and gA requirements for containment materials.
He noted the existence of a S&W evaluation (January 9, 1979),
by FgC in Boston, of the CB&I gA Manual to the specific requirements of 10 CFR 50, Appendix B, AWS Dl.l, and Specification P-283B.
The CB&I Code Backdate Addendum, Revision 0, was examined to check conformance of CB&I procedures to applicable specification requirements.
Updating of the procedural code commitments appears to have been properly evaluated, dispositioned, and documented on various S&W E&DCRs (eg:
P10621 for SNT-TC-1A update).
CB&I procedures SH1N (Revision 2) and SH9X (Revision 2) were reviewed against the requirements of ANSI N45.2.2 and S&W Specification P-283B.
No items.of noncompliance were identified.
5.
Pi in Procedures The inspector examined the documents listed below for conformance to the requirements of Appendix D of the PSAR and ASME Section III with respect to material documentation, receiving, storage, installation, testing and records.
a.
S&W Specification No.
P301C, Rev. 1, "Field Fabrication and Erection of Piping ASME III, code classes 1, 2, 3, and ANSI B 31.1."
b.
ITT Grinnell Industrial Piping, Inc. (ITTG) guality Assurance Manual - Field Installation and Appendix I, gCFA-1 Rev.
which defines interfaces between ITTG and S&W.
c.
ITTG Field gC Procedures controlling organization, document control, field procurement, receiving inspection, installation,'traceability, storage, testing and document control.
d.
S&W guality Standards
t
gS - 7. 1, "Receiving Inspection" gS - 13.11, Rev.
A. "Material/Equipment Storage" gS - 13. 12, Rev.
A, "Material/Equipment Maintenance" e.
S&W gA Directives gAD - 7.7, "Receiving Inspection-General" gAD - 10.9,
"Storage and Work Area Cleanliness Inspection" f.
S&W Specification No.
SM01, Rev. 2, "Storage and Maintenance During Storage of Permanent Plant Equipment" g.
S&W guality Assurance Inspection Plans for storage and maintenance during storage of permanent plant equipment:
No. N2-00SM01-001 for the S&W program No. N2-00SMOl-100 for the ITTG program No items of noncompliance were identified.
6.
Industrial Pi in Su
Com an IPSCO Tanks The licensee was informed of defects identified in tanks furnished at another plant by IPSCO.
Following review of procurement records the inspector was informed by the licensee that no equipment had been ordered from IPSCO and that the company was not on their approved vendor list.
The inspector had no further questions concerning this matter.
7.
Review of Nonroutine Events Re orted b
the Licensee By letter dated October 18, 1977 the licensee had reported a
potentially reportable condition relating to the relief valve control system in accordance with 10 CFR 50.55(e).
This condition had also been reported by General Electric Company to the I&E Division of Reactor Construction Inspection as a generic problem in accordance with 10 CFR 21.
The licensee letter dated March 22, 1979 stated that this problem will be resolved on a generic basis and will be addressed in the Final Safety Analysis Report for this plan In order to avoid further duplication of documentation the
CFR 50.55(e) report is closed.
8.
Licensee Action on Previous Ins ection Findin s
(Open)
Noncompliance (79-02-02):
NDE of containment piping penetration welds.
Initial procedure qualification radiographs of the glued head to penetration sleeve weld were examined by the inspector.
These radiographs confirm< the ability to obtain meaningful results by radiography in accordance with code requirements.
This item remains unresolved.
(Open) Unresolved Item (79-02-03):
Welding Electrode Control.
The inspector reviewed:
S&W letter to the licensee dated June 15, 1979 providing the
.
results of the 10-hour test by Chemetron Corporation of E 8018-Cl electrodes at 90'.
and 95% relative humidity.
CBI letter to S&W dated June 28, 1979 stating that welding electrodes will be issued and unused electrode returned at 5-hour intervals; rebaking of electrodes will not be performed prior to S&W approval of a procedure, and leather pouches will be used.
S&W E&DCR No. P10762 which revises specification P283B, effective June 29, 1979 to provid'e that the maximum exposure
time out of the oven shall be 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, allows for one rebaking and requires use of leather pouches manufactured by Trex Engineering Company or equal.
This item remains unresolved pending review by S&W and an NRC inspector of possible adverse effects due to use of the previously allowable 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> out of oven time for electrodes.
9.
Exit Interview At the conclusion of'he inspection on July 12, 1979, a meeting was held with representatives of the licensee.
The inspectors summarized the results of the inspection as described in this report.