IR 05000389/1981005
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' [grG KEGtj'd UNITED STATES
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j NUCLEAR REGULATORY COMMISSION y
REGION 11 g-ar
'f 101 MARIETTA ST.. N.W.. SUITE 3100 o$
ATLANTA, GEORGIA 30303
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Report No. 50-389/81-05 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33101 Facility Name:
St. Lucie Docket No. 50-389
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License No. CPPR-144 Inspection at St. Lucie Site near Fort Pierce, Florida Inspectors: /
I 7f B. R. r y
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Date Signec l-jdaLClff
/4FP/ Wins rge Da W Sfg/ie'd
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Approved by:
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A. R. Herdt, Section Chief Da'te signed Engineering Inspection Branch Engineering and Technical Inspection Divisicn SUVMARY Inspected on April 28 - May 1,1981 Areas Inspected This routine, unannounced inspection involved 55 inspector-hours on site in the areas of licensee action on previous inspection findings, reactor vessel inter-nals, reactor vessel installation, safety related components, reinforcing steel, safety-related piping and reactor coolant pressure boundary piping.
Results Of the seven areas inspected, o violations or deviations were identified in three areas; two violations were fouN in fot.r areas (Violation - Inadequate measures to control preservation of safety-relatea materials and equipment -
paragraph Nos. 9.a. and 10. a., and " clation - Inadequate measures to control welding and welder qualification - paragraph Nos. 7 e.,
10.b.(1), 10.b.(2),
- 11.b. (1) and 11.b.(4)(a)).
8109290633 810918 3 PDR ADOCK 05000389'
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REPORT DETAILS 1.
Persons Cont &:ted
' icensee Employees
"B. J.. Escue, Site Manager
- W. M. Hayward, Supervisor QA Engineering
- G. Crowell, Er.gineering Site Supervisor
- W. F. Jackson, Welding Superintendent
- J. L. Parker, Project QC Supervisor
- J. W. Adams, QA Engineer
- E. W. Sherman, QA Engineer
- 0. J. Karch, QA Engineer
- D. R. Cooper, Supervisor, QA Engineering W. Woodard, QA Engineer - Systems and Audits P. W. Heycock, PSI Coordinator - Power Resources F. T. Carr, Specialist - Power Resources G. Gotch, Staff Specialist - Power Resources Othcr licensee employees contacted included construction craftsmen, QC inspectors, security forr 7 members, and office personnel.
Other Organizations
- K. N. Flanagan, Assistant Site Manager - Ebasco Services, Inc.
- R. W. Zaist, Project Superintendent - Ebasco Services, Inc.
- G. H. Krauss, ESSE Feoject Engineer - Ebasco Services, Inc.
- R. A.~ Garramore, Senior Resident Engineer -Ebasco Services, Inc.
W. A. Shook, Process Control Specialist - Ebasco Services, Inc.
P. M. Dancoes, Job Superintendent - Combust 1un Engineering ( Avery Division)
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M. Carucci, QC Superintendent - Combustion Engineering (Construction Services)
9. R. Harbison, Welding Engineer, Combustion Engineering (Construction i
Services)
NRC Resident Inspectors
'S. A. El rod
- H. E. Bibb
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on May 1, 1981 with those persons indicated in paragraph 1 above. The inspectors described the areas inspected and discussed in detail the inspection :indings listed below. No dis :enting comments were received from the licensee.
(0 pen) Violation 389/81-05-01: " Inadequate Measures to Control Preservation of Safety-Related Materials and Equipment" - Paragraph Nos. 9.a and 10.a.
(0 pen) Violation 389/81-05-02: " Inadequate Measures to Control Welding and Welder Qualification" - Paragraph Nos. 7.e,10.o.(1),10.b.(2), II b.(1) and 11.b.(4)(a).
(0 pen) Inspector Followup Item 389/81-05-03:
"Peference of Incorrect Procedure for Lif ting CSB" - Paragraph 6.a.
(0 pen) Unresolved Item 389/81-05-04:
" Spacing of Reinforcing Steel" -
Paragraph No. 5.b.
3.
Licensee Action on Previous Inspection Findings (0 pen) Infraction (389/80-13-01) Improper Storage. This item concerns the licensee's improper storage of six ASME Class 1, 2 and 3 va;ves.
During the week of April 2S, 1981, the inspectors examined the valve storage areas which had been improved to comply witn regulatory requirements.
The inspection showed several examples which indicated that the improvement program was not yet fully implemented.
In that the licensee's commitment was in full compliance by May 1,1981, this item will remain open pending review af ter that date.
4.
Unresolved Items
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Unresolved items are matters about which more information is required to determine whether tney are acceptable or may involve violation or deviation.
New unresolved items identified during this inspection are discussed in paragraph 5.b.
5.
Independent Inspection Effort a.
Construction Activities The inspectors condJcted a general inspection of the reactor building, auxiliary building and stainless steel pipe faorication shop to observe construction progress and construction activities such as welding, welding filler material control, material controls, and housekeeping and storage.
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b.
Reinforcing Steel With regard to the above general inspection on April 29, 1981, the inspectors accompanied by a representative of the licensee roted several examples of groups of three to five re1nforcing bars with the clear distance between bars less than one inch. Each group of bars was in a single layer. The above bars were extending out of the completed concrete containment cylinder wall at penetration 43 and at the equip-ment hatch. The above appears to be in conflict with the requirements of ACI-318-1971, paragraphs 7.4.1 and 7.4.5.
This will be examined in a subsequent inspection and will be identified as unresolved item 389/81-05-04: " Spacing of fleinforcing Steel".
Within the areas inspected, no violations or deviations were noted.
6.
Reactor Vessel Internals The inspectors reviewed procedures, reviewed records, and observeu wu*k activities as described below relative to the reactor vessel internals tc determine whether regulatory requirements are being met. The reactor vessel internals consisting of the upper guide structure (UGS) assembly, the core support barrel (CSB) assembly, the core shroud and lower support (CS-CS)
assembly and miscellaneous equipment are being installed by Combustion Engineering (CE) using FP&L procedures as listed below.
a.
Review of Quality Assurance Implementing Procedures The inspectors reviewed the following procedures and specifications:
(1) CE Specification CEND-353, Revision 6, " Field Handling, Mainten-ance, and Storage Requirements for Combustien Engineering Furn-ished Equipment"
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(2) QI 7.1, Revision 3, " Instructions for Receiving Inspection of Seismic or Safety-Related Material" (3) SQP-75, Revision 0, " Permanent Plant Equipment Installation CSS-CS Lifting Procedures" (4) SQP-76, Revision 0, " Reactor Vessel Intervals Installation and Alignment, CSCS-CSB to RV" (5) SQP-77, Revision 0, "UGS Lift Rig Assembly and Lif ting Procedure" (6) SOP-73, Revision 0,
" Permanent Plant Equipment Installation CSB/ Lifting" (7) SQP-72, Revision 0, " Reactor Vessel Internals Installatiol Into the Reactor Vessel"
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(8) SQP-68, Revision 1, " Reactor Vessel Internals Installation of RV Keyway" (9) SQP-69, Revision 0, " Reactor Vessel Internals ~ Instaliation of Core Support Barrel"
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(10) SQP-70, Revision 0, " Reactor Vessel Internals Installation CSB Keyway" (11) SQP-71, Revision 0, " Reactor Vessel Internals Installation of Dummy Alignment Key" (12) SQP-74, Revision 0, " Reactor Vessel Internals Installation Aligr-ment During Welding CSS to CSB" (13) SQP-76, Revision 0, " Reactor Vessel Internals Installation and Alignment CSCS-CSB to RV" (14) SQP-28, Revision 0, " Operation and Maintenance of Lifting and Handling Equipment" (15) SQP-3, Revision 2, " Material Control" (16) SQP-23, Revision 0, " Preventative Maintenance" (17) SQP-29, Revision 2, "NSSS Access and Cleanliness" (18) C0P 5-19, Revision 2, "Loadout, Transport and Placement Upper Guide Structure Inside Containment" (19) C0P 5-20, Revision 2, "Loadout, Transport and Placement of the Core Shroud / Support Structure Inside the Containment"
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(20) C0P 5-23, Revision 0, "Loadout, Transport and Placement of the Core Support Barrel Inside Containment" The above procedures were reviewed in the areas of receipt inspection, storage, handling, crane testing and lifting of internals, installation of internals, inspection of internals installation, and post-installa-tion activities.
During review of the above procedures, the inspectors noted that paragraph 5.2.4 of SQP-72 referred to SQP-32.for lif ting the CSB.
Paragraph 2.1.2 of SQP-32 specifically eliminates application to reactor vessel internals. Discussion with the-licensee revealed that the reference for lifting should have been SQP-73. The procedure will be revised to refer to the correct procedure for lifting the CSB. - This matter will be identified as inspector followup item number 389/81-05-03, " Reference of Incorrect Procedure For Lifting CSB".
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b.
Observation of Work and Work Activities
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The inspector observed the UGS, CSB and CS-CS 'n temporary storage location inside the containment.
Protective coverings and storage supports were observed. A modification was being performed to add CEA.
shroud flow channel extensions to the UGS. This modification was being performed by CE in accordance with Field Action Request FAR-13172-108A.
The inspectors examined this work to determine whether installation
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specifications and work procedures were being followed and QC activi-ties were being performed in accordance with established procedures.
(See paragraph 7. below for examination of welding associated with the modification.)
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c.
Review of Quality Records
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The inspectors reviewed the receipt inspection records and the 1980 and l
1981 storage and protection records for the reactor vessel internals, t
The receipt inspection records consisted of FP&L receipt inspection i
report and the CE " Certificate of Equipment". The storage and protec-tion records consisted of Form SQP-23.1 for MRR 13804 covering the major components and MRR 14443 covering the miscellaneous equipmer.t.
The records were reviewed to determine whether:
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(1) Storage inspections were made at the required frequency J
(2) protection requirements were maintained
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(3)
Receipt inspection requirements were met
(4) Adequate protection was maintained during temporary storage, j
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e Within the areas inspected, no violations or deviations were identified.
7.
Reactor Vessel Internals (Welding) - Observation of Welding and Associated Activities
The inspectors observed welding activities for reactor vessel internals as described below to determine whether applicable code and procedure require-
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ments were being met. The applicable code for the welding observed is the i
ASME-Boiler and Pressure Vessel Code.Section III, Subsections NA and NG,
1974 Edition.
The following was examined relative to welding associated with modificat:en to the flow channels on the UGS.
a.
Welding Identification
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The welding records for the following welds were reviewed and compared
to the identification en the component to insure that weld identifi-i cation records had been established to permit clear retrieval of
accurate weld date:
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Weld 82 Weld 72 Weld 63 Weld 15 Weld 68
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Weld 56 b.
Weld Preparation Welds 73 and 21 were observed during fitup. Condition of the surface to be welded, protection of weld area from environmental conditions and other construction activities and alignment were examined.
c.
Welding Material Control of welding materials was examined in the areas of:
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Storage conditions (2)
Issue practices (3) Documentation controls for dispensing (4)
Evidence of ur ontrolled material at the work area or storage area d.
Observation of Welding Weld No. 52 was observed during in process welding.
The welding activity was examined in the following areas:
(1) Weld identification / location (2) Use of specified welding material (3) Welder qualification (4) Use of applicable welding procedure (5)
Fitting and alignment methods
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(6) Tack welds
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(7) Shielding and purging gas (8) Essential variables of the procedure qualification are being followed in production (9) Welding technique (10) Weld surface condition (11) Observance of inspection points (12)
Interpass temperature (13) Return of unused welding material (14) Weld repair (15) Weld inspection e.
On April 28, 1981, during examination of above welding activities, the inspectors found the following proolems:
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i (1)
For three sets of welding equioment being used, the purge gas flow rate and shielding gas flow rate being used were outside procedure limits as follows:
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Procedure GTA-8.8Y-300 Actual Requirements Being Used Purge Flow (CFH)
5-10 18-22 Shielding Flow (CFH)
10-20 22-27
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(2)
The welder performance qualification records show the welders to be qualified to weld on thicknesses from 1/16" to 3/8". Based on the thickness of the qualification test assembly, i.e., 1/8",
Section IX of ASME specifies an upper thickness limit of 2t or
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j 1/4". The performance qualification records were corrected during
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the inspection.
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The above problems indicate inadequate measures for the control of
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special processes and are examples of violation 389/81-05-02 discussed further in paragraph 11.b.(4)(a).
Within the areas inspected, no violations except as noted in paragraph 7.e.
or deviations were identified.
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Reactor Vessel Installation
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The inspectors reviewed records and observed work activities as described below relative to the reactor vessel to determine whether regulatory
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requirements were being met.
CE specification CEND-353, FP&L Procedure
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SQP-23, FP&L Procedure SQP-3, and FP&L procedure SQP-29 (see paragraph 6.
above for titles) govern the records and work activities examined.
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a.
Observation of Work and Work Activities a
The inspectors observed the installed vessel for protection to deter-
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mine whether:
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(1)
procedures for protection were being followed (2)
protective devices were installed around the top of the vessel
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(3)
vessel side openings were blanked off (4) work platforms and scaffolding inside vessel were nonflammable (5)
access control met requirements i
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b.
Review of Quality Records The inspectors reviewed the 1980 and 1981 storage and protection inspection records consisting of Form SQP-23.1.
The records were reviewed to determine whether installed vessel protection records anfirmed that access control, cleanliness and protection met procedure equirements. The records were compared with the existing condition of the vessel as observed in paragraph a. above.
Within the areas inspected, no violations or deviations were identified.
9.
Safety-Related Components The inspectors reviewed records and observed work activities as described below relative to safety-related components to determine whether regulatory requirements are being met.
FP&L Procedures SQP-47, Revision 3,
" Pipe Erection"; SQP-23, Revision 0,
" Preventative Maintenance"; and SQP-3, Revision 2,
" Material Control" govern the records and work activities examined.
a.
Observation of Work and Work Activities The inspectors observed installed gas decay tanks 2A, 28 and 2C; gas surge tank 2A; waste gas compressor 2A; and charging pumps 2A, 28 and 2C. The equipment was inspected to insure that procedures for storage, cleanliness, preservation and protection were being met. On April 29, 1981, during inspection of the above components, the inspectors found the following problems:
(1) A 1" nozzle on the side of gas surge tank 2A and a flanged pipe connection at the waste gas compressor 2A were open.
Paragraph 3.1.2 of SQP-47 reo' ires that open pipe, fittings, valves and
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equipment shall be capped or covered when no work or inspection activity is in progress. Upon being informed, the licensee took immediate action to cover the openings.
(2) The electric motor for the waste gas compressor 2A was not being heated. SQP-23 and Form SQP-23.1 for the compressor requires that the motor be heated.
It was noted that the compressor had been worked on, but no work was in process during the shift (night) of the inspection or on the next day shift. Upcr. being informed, the licensee took immediate action to place heat on the motor.
The above problems indicate inadequate measures to control preservation of safety-related materials and equipment and are examples of violation 389/81-05-01 discussed further in paragraph 10.a.
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b.
Review of Quality Records The inspectors reviewed the 1981 Equipment Storage / Maintenance record consisting of Form SQP-23.1 for those components noted in paragraph a.
above.
In addition, the " Shaft Rotation Checklist for Motors and Pumps" for the first quarter of 1981 for the waste gas compressor were reviewed. The records were reviewed to insure that inspection require-ments for cleanliness, preservation, and protection were being met.
Within the areas inspected, no violations except as noted in paragraph 9.a or deviations were identified.
10.
Safety-Related Piping The inspectors observed non-welding and welding work act.vities for safety-related piping as described below to determine whether applicable code and procedure requirements were being met.
The applicable code for safety-related piping is the ASME B&PV Code,Section III, Subsections NC and NO, 1977 Edition with addenda through summer 1977.
a.
Observation of Non-Welding Ac '< * ti is Observation of specific work activities were conducted to determine conformance, where applicable, with the following; inspectio.. and/or work procedures, recordkeeping, installation specifications or plans, specified materials, specified NDE, calibration and use of proper test equipment and qualified inspection and NDE personnel.
Activity System or Comoonent Procedure Protection Piping, Various SQP 3-R2 SQP 47-R3
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Handling Piping, Various SQP 3-R2 SQP 6-R1 SQP 28-R0 SQP 47-R3 With regard to the above inspection in the area of protection, the inspectors accompanied by a representative of the licensee on April 30, 1981, noted approximately 15 examples of scaffolding supported by, or rigging from installed safety-related piping. The licensee stated that they had no documented procedures controlling the above practices.
Therefore, the licensee had not established adequate measures to protect stored equipment and materials.
The above combined with the axamples discussed in paragraph 9.a.
indicates that the licensee has not established adequate measures to control storage and preservation of equipment and materials. Failure
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to establish adequate measures to control storage and preservation of materials and equipment in accordance with work and inspection instruc-tions to prevent damage is in violation of 10 CFR 50, Appendix B, Criterion XIII. This violation will be identified as 389/81-05-01:
" Inadequate Measures to Control Preservation of Safety-Related Materials and Equipment",
b.
The inspectors observed in process welding activities of safety-related piping field welds as described below to determine whether applicable code and procedure requirements were being met.
(1) Welding The below listed welds were examined in process to determine work conducted in e r:ordance with traveler; welder identification and location; wt ig procedure; WPS assignment; welding technique and sequence; materials identity; weld geometry; fit-up; temporary attachments; gas purging; preheat; electrical -kr;teteristics; shielding gas; welding equipment condition; interpass temperature; interpass cleaning; process control systems; identity of welders; qualification of inspection personnel; and weld history records.
Joint Number Size System CS-0024-903 6"
x 0.280" Containment Spray CS-0024-902 6"
x 0.280" Containment Spray SI-0457-002 12" x 0.406" Safety Injection CS-0032-002 4"
x 0.237" Containment Spray With regard to the above inspection, the inspectors accompanied by a representative of the licensee, on April 29, 1981, noted the following examples of welders failing to follow welding procedure e
back purge gas flow rate requirements.
Required Ac'tual Weld Number WPS No.
Back Purge Back Purge CS-0024-902 43-R3 4-10 CFH 31 CFH CS-0024-903 43-R3 4-10 CFH 31 CFH CS-0032-002 43-R3 4-10 CFH 40 CFH The above condition indicates inadequate measures for the control of special processes and is an example of violation 389/81-05-02 as discussed further in paragraph 11.b.(4)(a).
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(2) Welder Qualifications The inspectors reviewed the FP&L program for qualification of welders and weldirg operators for compliance with QA procedures and ASME Code requirements.
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The following welder qualification status records and " Records of Performance Qualification Test" were reviewed relative to the weld joints listed in paragraph 10.b.(1),11.b.(1) and 11.b.(4)(a).
Welder Symbol Application PYP Safety-Related Piping PWP Safety-Reisted Piping PYI Reactor Coolant Pressure Boundary Piping PVP Reactor Coolant Pressurg Boundary Piping BAF Control Eleme,t Dirve Mechanism With regard to the above inspection, the inspectors, on April 29, 1981, noted that several welders took combination process welder qualification tests in accordance with Welding Procedure Specifi-cation Nos. 24, 39 and 50, on an 0.812" x 6" diameter grooved pipe test assembly. The tests consisted of 1/8-inch thick gas tungsten arc weld (GTAW) metal deposit followed by an 11/16-inch thick shielded metal arc weld (SMAW) metal deposit. The Welder Qualifi-cation Records fer the above qualification test states the welders are qualified for welding pipe butt joints from 3/16-inch to unlimited wall thickness.
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The preceding is contrary to ASME Interpretation IX-78-92 dated September 25, 1978 in that the above test conditions would only qualify the testad welder for a maximum thickness of 1-5/8-inch.
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Therefore the licensee has been granting welders unlimited thick-ness qualifications when the welders are actually only qtalified to 1-;/8-inch thickness maximum.
The above condition indicates inadequate measures for the control of special processes and is an example of violation 389/81-05-02 as discussed further in paragraph 11.b.(4)(a).
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Welding Filler Material Control The inspector r? viewed the FP&L program for control of welding materials to determine whether materials are bning purchased, accepted, stored and handled :q accordance with QA procedures and applicable code requirements. The following specific areas were examined:
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Purchasing procedures, receiving, storing, distributing and handling procedures, material identification, inspection of welding material issuing stations
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Welding material purchasing and ' receiving records for the following materials were reviewed for conformance with
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applicable procedures and code requirements:
Material ID Tyoe Size Code ER-308L 1/8" 0181 ER-308 3/32" 0137 ER-NiCrFe-5
.045" 0187 ER-NiCrFe-5 3/32" 0191 E-308-16 3/32" 0031 E-308-16 1/8" 0027 (4) Welding Procedure Specifications
The following welding procedure specifications (WPS) were selected for review:
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WPS Process 43-R3 GTAW (Manual)
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50-R4 GTAW/SMAW (Manual)
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75-R0 GTAW ( Automatic / Manual)
j Gas Tungsten Arc Welding (GTAW)
Shielded Metal Arc Welding (GMAW)
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The above WPSs and their supporting Procedure Qualification Records (PQR) were reviewed to ascertain whether essential,
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supplementary and/or nonessential variables including thermal
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treatment were consistent with code requirements; whether the WPS were properly qualified and their supporting PQRs were accurate
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and retrievable; whether all required mechanical tests had been performed and the results met the minimum requirements; whether
the PQRs had been reviewed and certified by appropriate personnel and, whether any revisions and/or changes to nonessential vari-
l ables were noted.
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Within the areas examined, no violations or deviations were identified except as described in paragraph Nos.10.a,10.b.(1) and 10.b.(2).
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11.
Reactor. Coolant Pressure Boundary Piping
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The inspector observed non-welding and welding work activities for reactor coolant pressure bc ida ry (RCPB) piping.
The applicable code for the installation of RCPB piping is the ASME B&PV Code,Section III, Subsection NB,1977 Edition through the summer 1977 addenda.
a.
Observation of Non-Welding Activities Observation of specific work activities were cuaducted to determine
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conformance, where applicable, with the following:
inspection and/or work procedures, recordkeeping requirements, installation specification
requirements, specified material and qualified insoection personnel.
Safety Injection System and Reactor Coolant System Activity Identification Procedure Protection Piping Various SQP 3-R2
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SQP 47-R3
i Handling Piping Various SQP 3-R2 SQP 6-R1 SQP 28-R0
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SQP 47-R3 b.
Observation of Welding Activities The inspector observed in process welding activities of RCPB piping j
field welds as described below to determine whether applicable code and procedure requirements were being met.
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(1) Welding i
l The below listed welds were examined in process to determine work
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conducted in accordance with traveler; welder identification and
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location; welding procedure; WPS assignment; welding technique and-
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sequence; materials identity; weld geometry; fit-up; temporary I
attachments; gas purging; preheat; electrical characteristics; shielding gas; welding equipment conditions; interpass tempera-ture; interpass cleaning; process control systems; identity of welders; qualifications of inspection personnel; and weld history records.
Joint Number Size-System RC-0228-007 3/4" x 0. 219" Reacto-Coolant
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RC-0154-001 12" x 1.312" Reactor Coolant RC-0154-002 12" x 1.312" Reactor Coolant
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With regard to the above inspection, the inspectors accompanied by l
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a representative of the licensee, on April 19, 1981, noted the following examples of welders failing to follow welding procedure shielding gas and back purge gas flow rate requirements.
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Required Actual Weld WPS Shielding Back Shielding Back Number Number Gas Purge Gas Purge RC-0228-007 43F-R3 15-25 CFH
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30 CFH
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4-10 CFH
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45 CFH RC-0154-001 50-R4
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45 CFH 4-10 CFH RC-0154-002 50-R4
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i The above condition indicates inadequate measures for the control of special processes and is an example of violation 389/81-05-02 as discussed in paragraph 11.b.(4)(a).
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(2) Welder Qualification
Welder qualification is discussed in paragraph 10.b.(2).
(3) Welding Material Control Welding material control is discussed in paragraph 10.b.(3).
(4) Special Welding Activities The inspectors examined special welding activities as described below to determine whether applicable code and procedura.1 require-e ments were being met.
(a) Seal Welding The below listed weld was examined in process to determine:
whether work was conducted in accordance with travelers; welder identification and location; welding procedcre; WPS assignment; welding technique and ' sequence; ;naterial s identity; weld geometry; fit-up, temporary attachments; gas purging; preheat; electrical characteristics; shielding gas;-
welding equipment condition; interpass temperature; interpass cleaning; process control systems;. identity of welders; and weld history records.
Weld No.
System CDM-0069-001 Control Element Drive Mechanism i
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4 With regard to the above inspection, the inspectors accom-panied by a representative of the' licensee, on April 29,
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1981, noted the following examples of welders failing to follow welding procedure parameters:
Back purge was _16 CFH. WPS-75 RO requires back purge to j
be 3 to 5 CFH.
The tungsten electrode extention beyond the gas cup was
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1/4-inch. WPS-75 R0 requires electrode extention to be
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5/8-inch.
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The above combined with the example as discussed. in paragraphs 7.e,10.b(1),10.b(2) and 11.b.(1) indicate that the licensee does
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not have adequate taasures for the control of special processes.
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Failure to establish adequate measures to control special pro-l cesses including welding is in violation of 10 CFR 50, Appendix B, Criterion IX. This violation will be identified as 389/81-05-02:
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" Inadequate Measures to Control Welding and Welder Qualification".
(5) Welding Procedure Specifications Welding procedure soecifications are discussed in paragraph 10.b.(4).
Within the areas examined, no violations or deviations were identified except as described in paragraph Nos.11.b.(1) and 11.b.(4)(a).
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