IR 05000278/1988014
| ML20207B408 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/20/1988 |
| From: | Harris R, Kaplan H, Kerch H, Oliveri M, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20207B403 | List: |
| References | |
| 50-278-88-14, NUDOCS 8808020329 | |
| Download: ML20207B408 (16) | |
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U.S. NUCLEAR REGULATORY CCFMISSION
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REGION I
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Report No.
50-273/88-14 Oceket No, 50-278 License No. OpR-56
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Licensee:
Philadelphia Electric Company D 01 Market Street
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Philadelphia Pf T9101 f
Facility Name:
Peach By tom Unit 3
Inspection At:
Delta Pennsylvania Inspection Dates: May 9 through May 20.,_1938 I
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Inspectors:
H. W. Kerlh, Sen or Reactor Engineer dati
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,lan, Senior Reactor Engirieer f(w
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R. H. Harris, ND$ technician date 3R.A.dTIveji,NbEiechnician
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(f_ProcessesSection,EPB,CRS, Region 1
. R, Strosnider, Cnief,~Haterials, and date v
Routine Announced NRC Indegend' int Measurements Insp~ection:
Conducted at FeicT Bottom Nuclear fcTer Station Unit 3 on Wy~4 t'hrough May 20, 1988 (Report No. 50-278/53-14).
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8800020329 OG0721 PDR ADOCK 05000270
PNU
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Areas Inspected: A routine announced inspection was conducted at Peach Bottom Nuclear Power Station Unit 3.
Included in this independent measurements inspection were safety-related piping weldments selected from the plant replacement piping program inspection plan.
Those specific areas inspected
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were selected from the A and B loop Recirculation System piping.
This inspection also included a review of welding, pre-service inspection, i
associated documents and procedures.
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See attachment No. I for a tabulation of specific items examined.
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See attachment No. 2 for a tabulation of specific spool pieces analyzed.
See attachment No. 3 for a list of specific radiographs reviewed.
t See attachrent No. 4 for a summary of surveillance and audit reports inspected.
Inspection Summary and Conclusions: A routine announced inspection was con-ducted on May 4 through May 20, 1933.
(Report No. 50-274/83-14).
In summary,
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the following were reviewed during this inspection.
Liquid penetrant - 19 pipe weldments
Ultrasonic " 12 pipe weldments
Visual - 19 pipe welements
Material analysis - 9 spool pieces
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Ferrite determination - 19 pipe weldments
Personnel Qualification / Certification
- NDE Staffing
- Procedures - 10 procedures were reviewed
Radiographs - 65 pipe weldments a
Conclusions: Gased on this inspection there were two (2) unresolved items.
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One deaTing with missing calibration records, see paragraph 5.0.
The other unresolved item deals with personel qualification procedures, see paragraph
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7.0.
There were two concerns with the radiographic program for the replacement i
piping. One deals with a missed indication in non quality Class 3 weldment;
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the other is with sensitivity of penetrareters, see paragraph 8.
In addition,
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the inspector discussed with the licensee the inservice inspection program for the reactor pressure vessel beltline region.
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i DETAILS
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1.0 P_ersons Contacted (30703)
f Philadelphia Electric Cog any l
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- T. E. Cribbe Regulatory Engineer
'R. H. Zong Sr. Metallurgist
- F. A. Cook Engineer Pipe Replacement
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J. M. Cockroft Superintendent Quality Assurance
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K. P. Powers Project Manager i
J. J. Stanley
!SI Technical Assistant J. B. Cotton Superintendent 005 T. Bazzant Project Manager l
M. Pratt Manager Quality Control j
J. Gallaher Regulatory Engineer
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Chicago Bridge and Iron M. Jenning QA Supervisor f
United States _ Nuclear Rejulatory Cemmission
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- Larry Myers Reactor Inspector Region I
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- T. P. Johnson Sr. Resident Inspector
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- Denotes those attending the exit meeting.
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The inspector also contacted other administrative and technical personnel during tne inspection, j
2.0 Independent Measurements - NRC Nondestructive Examination and Quality l
Records Rsview of~SBety_Related Systems
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During the period of May 9 through May 20. 1938 an on-site independent rreasurements inspection was conducted at Peach Botton Nuclear Power i
Station. Unit 3.
This inspection was conducted by hRC regional-based i
inspectors. The purpose of this inspection was to verify the adequacy of
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the Itcensee's nondestructive examination program during plant pipe re-i placement.
This was accomplished by duplicating as near as possible, those examinations required of the licenfee by code and regulations, and evaluating the results.
The examinations performed by the NRC were
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selected frorn the plant pipe replacement program.
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3.0 NondestructiveExa,gnation ALLOY ANALYSIS: (73055)
Nine (9) Spool Pieces selected from the plant pipe replacement program were examined using the Texas Nuclear Model 9266 X-Ray Analyzer.
This is a field portable instrument specifically designed for rapid, nondestruc-tive, on-site verification of "type" a9d "elemental,qomposition" of engineering alloys. A quantitative and qualitative nondestructive analysis of material type ($$ 316) and specific element composition (Cr and N1) content was performed by the NRC inspectors.
Results: Data acquired with the Alloy Analyzer was compared with tables and charts in the manufactures instruction manut) and Certified Material Test Reports to verify material type and composition.
No violations were ider.tified.
Liquid Penetrant Examination (57060)
Nineteen (19) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye pcnetrant technique per NRC procedure NDE-9, Rev. O !n conjunction with the licensee's procedure PT14X, Rev. 5.
Included in this sample were ASME Class I weldments from the licensee's pipe replacement program.
Results: No violations were identified.
Visual Eram_ination (57050)
Nineteen (19) safety related pipt weld ents and adjacent base mate,ial (1/2 inch on either side of the weld) were examined in #N ordance with NRC procedure NDE-10, Rev. O, Appendix A, and associated site QC documen-tation, and drawings.
The examinations were performed specifically to identify any cracks or linear irdications, gouges, leakage, or arc strikes with craters or corrosion, which may infringe upon the pipe ninimum wall thickness.
Mirrors, lights and weld guages were used to aide in the inspection and evaluation of these weldments.
Results: No violations were identifie _
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Ferrite Examination (SP1038)
Nineteen (19) safety related pipe weldments were examined for delta
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ferrite content using a type II ferrite indicator (Severn gage).
This test is intended to verify that the welding filler metal composition had achieved adequate (as-deposited) delta ferrite to eleminate hot cracking.
Six ferrite readings were taken around the circumference of i
the deposited weld material.
The readings obtained were averaged to a single ferrite number, the minimum of which was 7FN (Ferrite Number).
Results: The inspector concluded that the results of the delta ferrite
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determination were acceptable by comparing the results obtain with the Certified Material Test Reports.
Ult-
- amination (57080)
The in.jector selected twelve (12) safety related pipe weldments for i
independent ultrasonic inspection.
Those welds selected were ASME Class 1 stainless steel weldments from the Recirculation pipe replacement program.
l The ultrasonic examinations were performed using a Krautkramer USL48 flaw detector in accordance with NRC procedure NDE-1, Rev. O, Ph'ladelphia Electric Co. procedura UT-PE-002, Rev. 4 and ultrasonic test data reports.
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Instrument calibration (linear verification) was performed using NRC procedure NDE-2, Revision 0.
A distance amplitude correction curve (DAC) was constructed using the licensee's calibration standards No. 12-SS-100.844-56-PEB, 24-SS-80-1.218-54-PEB and 28-SS-X-1,315-58-PEB.
To ensure repeatability of ultrasonic examinations, instrument settings
and search units (transducers) were matched as near as possible to those indicated by the licensee's ultrasonic data reports.
Results: No violations were identified.
Data collected by the NRC inspectors were compared to data collected by the licensee and found to be compatible.
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4.0 Review of Site NDE Preecdures The following procedures were reviewed for compliance with the licensee's FSAR commitments and applicable cod a, standards and specifications.
PT14X Rev. 10 Liquid Per.etrant I
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PTIN Rev. 7 Liquid Penetrant
PT11X Rev. 7 Liquid Penetrant
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PT23X Rev. 6 Liquid Penetrant
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UT-PE-001 Rev. 1 Supplement 2 Automatic Ultrasonic a
Examination Dissimilar, Buttering and Cisdding Material UT-PE "^'
Automatic Ultrasonic Examination of
Similar and Dissimilar Metal Welds in Piping Systems UT-PE-002 Rev. 4 Manuel Ultrasonic Fxamination of similar
and Dissimilar Meta; Walds in Piping Systems
MA-16 Rev. 6 General Requirements for Qualification and Certification of NDE Personnel UT-57 Remote Ultrasonic Examination :*ocedure
for Detect'on of IGSCC in Shroud Support Cover Plate TP508-1350 Rev. 1 Immersion Ultrasonic Examination
Rev. 3 Procedure for Detection of IGSCC in Shroud Support Access Cover Plate.
Results:
- No violations were identified, however, there were two unresolved items, see paragraph 7.0.
3.0 Pre-Service (PSI) Data Review (73055)
A sampling of pre-service inspection documentation for the pipe replacement welds was performed.
The purpose of this review was to verify compli nce with ASME Section XI code requirements for accuracy of a
the documentation and interpretation of examinatica data.
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7ne ultrasonic data were considered technically acceptable.
Ther" was one problem identified by the inspector, dealing with the docut intation of the PSI work perfcrmed on Peach Bottom Station pipes at timert;k. Weld data packages for 10-IB-16 spool 3-10 30A1 had missing ultrascnic calibration records.
PECo obtained the missing records the next day; the inspector expressed concerns regarding the possibility of other missing records.
Results:
This item is considered unresolved pending PECo's audit of the pre-service records Tnd NRC review (50-277/88-14-01).
6.0 Discussion with PECo ISI Personnel (92706)
The following subjects were discussed with the supervising engineer in charge of inservice inspection.
Hard stamping of welds:
PECo indicated that they voeld start hard
stamping piping replacement piping during the week of 5/23/88.
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r Containment Liner:
PECo has ti.spected their containment liner and
indicated no problems were identified. These inspections were in
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response to a generic concern of corrosion thinning, i
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Torus:
PECo indicated that the torus is painted and has been i
inspected and indicated their is no corrosion problem.
f Thickne.s Measurements:
Thickness measurements of balance of plant
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piping have been performed by PECo and no corrosion problems have i
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been found.
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i 7.0 NDE and Visual Personnel Qualification and Certification (73051)
i The following personnel records were reviewed.
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General Electric (GE) ultrasonic (EPRI) certification records for e
technicians were reviewed and found to meet SNT-TC-1A and NRC requirements.
Chicago Bridge and Iron Company (CBI) NDE certification records for
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technicians were reviewed and found to meet SNT-TC-1A requirements.
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Philadelphia Electric Company (PEco) certification records were
reviewed and the following was disclosed.
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Radiography Interpreters (Level II) performing contractor
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surveillance at Peach Bottom 3 do not meet SNT-TC-1A minimum
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training nor the required experience needed to qualify to
interpret and evaluate results with respect to applicable ASME
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code, standards and specifications; although, PECo pr.,cedure l
MA-16, Rev. 6 indicates they could perform this function.
(Reference PECc procedure MA-16 Rev. 6 paragrapt 7.1.3, table
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6.3A compared with SNT-TC-1A (1980) table 6.3.1.)
PEco informed the inspector that these radiographic film interpreters
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have never signed off for ASME code work.
PECO's intent was to
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have people with the necessary trainirg and experience to per-form adequate surveillance of coniractors, not to sign off for code radiography requirements.
PECO will revise their pro-
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cedures MA-16. Rev. 6 to reflect this.
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PECas certification records for ASME Section XI visual inspections for VT 1, 2, 3 and 4 do not reflect ANSI 45.2.6
(1978) paragraph 3.5.2(2) experience requirements.
A review of PEco's procedure MA-16, Rev. 6 table 6.3A reflects 10% of the ANSI requirements for experience.
PECo informed the inspector that personnel have t:)en certified to the visual requirements
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and exceed the ANSI three year experience requirements.
PEco indic6ted that they would change procedure MA-16, Rev. 6 to j
reflect this and to update the individual records.
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Results:
These items are considered unresolved pending changes to procedure MA-16, Rev. 6 and NRC review (50-2'E/18-14-02).
8.0 Review of Licensee's Pipe Replacement Radiographs (57090)
A sample of the licensee's radiographs of the recirculation systern pipe replacement was reviewed to verify the adequacy of PECo's modification program.
Radiographs were reviewed for t.chnique, film quality and weld integrity.
See attachnent 3 f or a specific listing of radiographs reviewed.
Results: All radiographic films reviewed were found to be acceptable with the exceptien of weld RWC01A that contained a 3/8" long section of unconsumed insert.
PECo wrote NCR CD.P.1156 that rejected this class 3 non-safety related weld.
This weld had been accepted by Cbl, PECo and the ANI. Af ter this disclosure PECo performed a 100% review of the rad waste radiographs for this modification. An additional two welds wr e rejected by PECo for unconsumed insert, as a result of this re-evaluation of the rad-waste radiographs. Another concern was penetrameter sensitivity.
Several radiographs had marginal penetrameter sensitivity that was caused by the use of a large source size of.173 inches.
The geometric unsharpness was calculated as acceptable, but the physical results of penetrameter sensitivity were margincl.
Basic radiography requires the source size to be as small as practicable; there were smaller source sizes available on site.
The inspector had no further questions regarding this matter.
9.0 Unit 3 Pipe Replacement Program (TI-2512/13, 55050, 49051)
In Inspection Report No. 50-278/87-33 and 50-278/88-08, the inspector reported on the preinstallation and initial installation tctivitics involving the replacement of the recirculation and residual heat removal RHR/ piping systems.
The inspections covered the periods between
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i November 16-20, 1987 and March 14 - 18, 1988.
The replacement activities l
consisted of renoving the old type 304 stainless steel piping and instal-ling new nuclear grade low carbon type 316 stainless steel piping manu-i factored to strict metallurgical controls to assure optimum corrosion
resistance, as well as utslization of automatic welding machine procedures j
to control hea.t input.
In inspection Report 87-33, the inspector concluded that the licensee and principal contractors (CBI and GE) had prep'. red
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technically acceptable proced;res and instructions for the imperJing program.
In Inspection Repart 88-08, the inspector cnneluded that the initial production activities involving the replacement of reactor vessel (RV) safe ends were being performed in strict accordance w!th the designated procedures and instructions.
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1 The purpose of this inspection (88-14) was to continue '.o verify that the replacement activities involving the recirulation and RHR systams were being performed in accordance with ASME Section XI, 1980 edition through Winter 1981 addenda.
The inspector reviewed the travelers in three completed task work packages representing welds 39-NI-8, 40-N2-A and i
41-N2-B, and four incomplete packages representing welds 42-N2-C, 70-REB-081, 70-REB-072 and 57-RHA-5.
The inspector verified that CBI had
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i performed all of the precise cutting, dimensioning etching, welding buttering and inspections specified in Special Instruction (SI) RN2, (SI)
a RN1 and SI-LA1.
The inspector, however, noted an apparent error in i
sequence 22 of the 57-RHA-5 weld traveler in which both a carbon steel
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insert (ht 562..) and a type 316 stainless insert (ht 5623) were identified.
The correct material for the insert in weld 57-RHA-5 is carbon steel (ht
5624) as verified by the CBI Weld Material Distribution (requisition)
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report dated May 7, 1988 and CBI drawing 133.
The joint consisted of a carbon steel pup piece (an extension to a stsinless steel pipe) welded to
the suction side of a 24" carbon steel valve identified as POS81A on CBI
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dwg 133.
The inspector verified that Weld REA 035 on the discharge side
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of Valve P0581M was welded with a carbon steel insert. A check of i
travele,'s covering carbon rteel joints REB-080, RHS-2, & RHB5 indicated
that the proper material was used.
CBI reported that the error occurred in transferring the data from Weld Material Distribution Sheets to the traveler, an operation that is accomplished outside containment.
l It is also noted that the inspector verified that NDE examinations (RT, PT
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and UT) were performed by CBI af ter repairing the original RV-NIB nozzle
'l to s. end joint as discussed in IR 88-08.
The inspector also verified that e GE supplied N2 safe ends wit.h unacceptable thermal sleeve exten-sion welds as fabricated by Ametek (See IR 88-08) were repaired by GE and re-radiographed before installation.
The inspector visually inspected four recirculation and RHA system welds
at various stages of installation.
The welds and percentage of completion were REB-081 (100*4), REB-082 (50?.), RHA-5 (50*4) and REB-072 (50*4). Only weld REB-072 was in the process of being welded.
The inspector verified
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that the specific welding parameters iecorded on the welding data sheet for weld REB-072 conformed to the requirements of automatic tungsten inert gas welding procedure ER 308 LA for sequences 21 and 24. Portions of
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welds REB-081, REB-072, and REB-100 were visually examined in the as-welded condition and found to be free of discernable defects with good fusion into the side walls. Weld REB-082 exhibited a m..chined surface at the 50% level. A review of the traveler indicated that REB-082 had been weld repaired due to radiographic indications and subsequently machined in preparation of completing the weld.
10.0 Quality Assurance The inspector continued his review of PECO audit and surveillante reports as previously discussed in IR-88-08.
Table 1 is a tabulation of recent reports reviewed by the inspector in this inspection period.
The inspector concluded that the licensee had significantly increased his effort in this area. A review of the audit and surveillance reports indicated that PEC0 had performed a meaningful and in depth review of CBI activities. All of the audit findings were corrected or resolved.
PECO concluded that CBI was in general compliance with the referenced documents, procedures and standards in the areas covered.
11.0 Shroud Support Access Hole Cover Weld Cracks As reported in IR 88-08 in January 1988 GE performed an ultrasonic inspection of two Inconel alloy 600 shroud access hole cover weld joints in Unit 3.
The cover plates are welded to the shrourd support and vessel wall ledge with an incomplete penetration joint.
The VT examination disclosed significant indications in the he?.t affected zone (HAZ) which were interpreted to be intergranular stress corrosica cracks.
The licensee subsequently questioned the validity of the test results particularly since GE utilized a 45 shear wave in viola +. ion of GE Pro-cedure TP135 which specified a 45' refracted longitudinal beam. Also the incomplete penetration joint could have caused nonrelevant indications because of the built in crevice.
The licensee is planning to have GE examine Unit 2 and re-examine Unit 3 cover plate welds at the earliest opportunity.
The licensee intends to closely monitor GE activities including th? calibration phase which will utilize a mockup of similar joint design.
12.0 Outstanding Items
Closed-Followup Item (50-277/88-08) - Emergency Service Water (ESW)
System, Units 2 and 3.
The inspector reviewed the corrective actions taken by the licensee regarding their use of unauthorized sketches in the fabrication of the new ESW spool pieces.
The licensee revised Procedure CD 6.2 "Control of Modification Documents" which will permit engineers to reproduce, stamp
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and issue controlled reproductions of engineering drawings using controlled print stamps.
The revised frocedure had just been issued during the inspector's visit and had not been employed in any activity.
Training sessions involving the revised modification procedu e were in progress.
The inspector verified that during an inspection of the fabrication shop, controlled drawing FSK-M244 was being used.
No informal sketches were evident.
13.0 Attachments Attachment No. 1 is a tabulation of specific pipe weldments examined and results.
Attachment No. 2 is a tabulation of specific spool piece material analyzed with results (type of material, nickel and chromium content).
Attachment No. 3 is a list of specific radiographs reviewed.
Attachment No. 4 is a tabulation of audit and surveillance reports.
14.0 Unresolved Items Unresolved items are matters ak which more information is required in order to ascertain whether thej e acceptable items or violations.
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Unresolved items are discussed in paragraph 7.0.
15.0 E jrance and Exit Meetings (30703)
Licensee management was informed of the scope and purpose of the inspection at the entrance interview.
The findings of the inspection were discussed with licensee representatives during the course of the inspection and presented to licensee management at the exit interview (see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the inspector.
The licensee did not indicate that proprietary information was involved within the scope of this inspectio.
DATG: 5/24/80 INDEPENDENT MEASUREMENTS P(ANT: PEACH EDITOM
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F F<DGF AM PAOC_1_CF_1_
ATTACHMENT NO.
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WELD /100 CLASL f N.
MAIRL.
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ACC.
- .l c. 5 0 M.C.
ALL.
ACC.
REA-000
ACC.
316 SS ACC.
ACC.
ACC.
REA-03C
ACC.
316 SS ACC.
ACC.
ACC.
REA-035 i
ACC.
316 SS ACC.
ACC.
ACC.
REA-007
ACC.
316 SS ACC.
ACC.
ACC.
i REA-086 i
ACC.
316 SS ACC.
ACC.
ACC.
REA-024
IACC.
316 SS NA.
ACC.
ACC.
REA-023
ACC.
316 SS NA.
ACC.
ACC.
s
REA-033
ACC.
316 SS NA.
ACC.
ACC.
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REB-065 i
ACC.
316 SS ACC.
ACC.
ACC.
REB-071
ACC.
316 SS ACC.
ACC.
ACC.
REB-073
ACC.
316 SS ACC.
ACC.
ACC.
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REB-066
ACC.
316 SS NA.
ACC.
ACC.
l REB-074
ACC.
316 SS NA.
ACC.
ACC.
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l REB-067
ACC.
316 SS NA.
ACC.
ACC.
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REA-080
ACC.
316 SS NA.
ACC.
ACC.
SHOP WELD
ACC.
316 SS ACC.
ACC.
ACC.
ISI# 10-IB-21 t
SHOP WELD
ACC.
316 SS ACC.
ACC.
ACC.
191# 10-19-24 SHOP WELD
ACC.
316 SS ACC.
ACC.
ACC.
ISI# 10-18-20
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REf4CH DOTTOM
ATTACHMENT 2
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t1ATERI AL ANALYCIS REF OR1
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DATC: ' ' t a /.o.i
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i I aNi tr AC TilF E R MATERIAL nVSTEM
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A RECIRC.
nS ELO PC 12B 17.10 HITACHI LTD 55 316 i
A FECIRC.
S kH4-10-30A2 17.29 12.06 HITACHI LTD 55 316 i
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A;B RECIRC.
66 REB PC 12A 16.84 10.64 HITACHI LTD SS 316 B RECIRC.
3G RHB 3-10-30A6 17.67 11.44 HITACill LTD SS'316 B RECIRC.
64 RED PC 13 17.09 11.43 HITACHI LTD SS 316 A RECIRC.
74 N5A SAFE END 17.18 12.13 HITACHI LTD SS 316 A RECIRC.
- /4 N5A CORESPRAY 17.12 13.37 HITACHI LTD SS 316 D RECIRC.
74 NSB SAFE END 16.98 11.43 HITACHI LTD SS 316 i
i B RECIRC.
74 NSB CORESPRAY 16.53 12.76 HITACHI LTD SS 316 ALLOY COMPOSITION DATA Thi s data has been compared with the Alloy Analy:ers table of assumed max-min composi tion data f or library alloys.
This data has been compiled largely from ASTM, ASIA and other recokimed
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standards where available.
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t ASSUMED MAX-MIN COMPOSITION DATA FOR LIBRARY ALLOYS t
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ALLOY Ti V
Cr N
Cu Mo Nb W
Co Fe Mn DISPLAY MAX O.10 0.00 18.00 14.00 0.00 3.00 0.10 0.00 0.00 72.00 2.00
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MIN O.00 0.00 16.00 10.00 0.00 2.00 0.00 0.00 0.00 61.82 0.00 SS 316 i
SS 316
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List of Specific Radiographs Reviewed Pages 1 of 2 Attachment No. 3
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Weld #
Status Weld #
Status 151-10-18-20 accepted REA-093-N2G accepted
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ISI-10-1B-21 accepted REB-103-N-20 accepted REA-033-A-62-R-2 accepted REA-025 accepted RPB-03-N138 accepted RPA-1-N13 accepted REB-073 accepted RPA-007-N13A accepted REB-107-N1B accepted REB-097-N2A accepted
REA-095-N2F accepted RPS-N12 accepted j
RPS-1-N12 accepted REA-081-N2J accepted RPS-007-N12 accepted REB-099-N2B accepted RPA-2-N13A accepted REA-024 accepted RPB-007 accepted RPB-2-N138 accepted REA-087-N2K accepted REB-074 accepted REA-086-NIK accepted REA-023 accepted REB-045 accepted R48-N1B accepted
REB-105-NZE accepted REB-107 accepted REA-091-NZH accepted RWC-6C accepted REC-8-N14 accepted RWC98 accepted REB-101-N2C accepted RWC11C accepted
RWC-10 accepted RWC8A accepted
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List of Specific Radiographs Reviewed Pages 2 of 2 Attachment No. 3 Weld #
Status Weld #
Status RWC-6B accepted RWC10B accepted RWC-38 accepted RWC9A accepted RWC-12C accepted RWC10A Rejected for insert RWC-41 accepted 1120383G001 accepted RWC-4C accepted 11203893P002 accepted RWC-5C accepted 1103728P001S/NN3517-1-1 accepted
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RWC9C accepted 1103728P0015/NN3517-1-3 accepted RWC7C accepted 1860209520 accepted RWC6A accepted 1860209520-1 accepted RWC46 accepted 1860209480 accepted 1860209510 accepted 11203894-P001SN/416 accepted 1080126670 accepted 1870389110 accepted 8031-P-107AS/N43446 accepted 1870389100N3460 accepted 1860209550 accepted
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Attachment No. 4 TABLE 1 - SURVEILLANCE & AUDIT REPORTS SURVEILLANCE REPORTS Report Date Subject Findings 22-10 4/29/88 Repair of NIB Nozzle None 22-07 3/31/88 Ferrite check on castings None 22-88-8 4/15/88 NDE of Nozzle 358-N2B None 22-11 4/26/88 Weld Filler Metal Control None 22-13 4/29/88 Machining Activities None 22-12 4/26/88 Welding & Welder Operator None Performance Qualifications AUDIT REPORTS
)
OP-388-5 4/9/88 NDE activities
- 0ne finding is
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procedure does not require all indications to be recorded -
finding corrected OP-3881 4/21/88 Site storage One finding safe end maintenance, 1411 not tagged -
receiving and finding corrected rigging activities OP-388K 1/29/88 Weld filler metal 2 Findings
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control (1) Unability tests not run (2) No traceability findings (1) & (2)
corrected OP-3889 3/24/88 Procurement One Finding -
Instruction CBI QA Manual did not i
cover LP mat's.
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Finding corrected OP-3886 Procedures One finding -
superseded procedures
found in doc. control
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Finding corrected
- Licensee audit findings.
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