ML20003F214
| ML20003F214 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/04/1981 |
| From: | Herdt A, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20003F204 | List: |
| References | |
| 50-369-81-07, 50-369-81-7, 50-370-81-02, 50-370-81-2, NUDOCS 8104200403 | |
| Download: ML20003F214 (9) | |
See also: IR 05000369/1981007
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W., SulTE 3100
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ATLANTA, GEORGIA 30303
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Report Nos. 50-369/81-07 and 50-370/81-02
Licensee: Duke Power Company
422 South Church Street
Charlotte, NC 28242
Facility Name: McGuire
Docket Nos. 50-369 and 50-370
License Nos. NPF-9 and CPPR-84
Inspection at McGuire site near Charlotte, North Carolina
M/
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Inspect :
W. P. Kleinsor' e
Date
Approved by:
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A. Her'dt, Chief,' M&P Section, El Branch
Date
ETI Division
SUMMARY
Inspection on February 3-6, 1981
Areas Inspected
This routine, unannounced inspection involved 29 inspector-hours onsite
in the areas of licensee action on previous inspection findings (Unit
2), storage of installed equipment (Unit 2), marking (Unit 2), containment
Structural Steel Welding) - observation of work and work activities
Unit 2), reactor coolant. pressure boundary piping - observation of work
and work activities (Unit 2); reactor coolant pressure boundary piping -
review of quality records (Unit 2), safety related piping - observation
of work and work activities (Unit 2) and licensee identified items
(50.55(e)) (Units 1 and 2).
Results
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Of the ten areas inspected, no violations or deviations were identified
in eight areas; two violations were found in two areas (Violation -
Failure to Establish Adequate Controls for Storage of Installed Equipment
Paragraph 5.b; Violation - Nonconforming CMTR - Paragraph 11.b(1)).
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DETAILS
1.
Persons Contacted
Licensee Employees
- J. C. Rogers, Project Manager
- E. B. Miller, Senior QA Engineer
- T. E. Touchstone, Senior Construction Engineer
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- J. W. Willis, Project QA Engineer
- R. M. Gillespie, Senior QA Technician
- G. B. Robinson, QA Engineer, Mech.
Other licensee employees contacted included construction craftsmen,
technicians, and office personnel.
Other Organizations
- L. F. Horner, Authorized Nuclear Inspector
- Attended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on February 6,
1981 with those persons indicated in paragraph 1 above.
The violations,
unresolved items and the inspector followup item were discussed in
detail.
No dissenting comments were received from the licensee.
3.
Licensee Action on Previous Inspection Findings
(Closed) Infraction 370/80-03-01 " Paint Contamination on Filler
Metal Wire Surface." Duke letter of response dated June 25, 1980
has been reviewed and determined to be acceptable by Region II.
-The inspector. held discussions.wi.th project manager and. examined
the corrective actions as state'd in the letter of response.
The
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inspector concluded that Duke had determined the full extent of the
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subject noncompliance, performed the necessary survey and follow-up
actions to correct the present conditions and developed the necessary
corrective actions to preclude recurrences of similar circumstances
have been~ implemented.
(Closed) Infraction 370/80-01-01:
" Undersize Socket Welds".
Duke
letter of response dated April 10, 1980 has been reviewed and
determined to be acceptable by Region II.
The inspector held
discussions with project manager and examined the corrective actions
ss stated in the letter of response.
The inspector concluded that
Duke had determined tF.e full extent of the subject noncompliance,
performed the necessary survey and follow-up actions to correct the
present conditions and developed the necessary corrective actions
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to preclude recurrence of similar circumstances.
The corrective
actions identified in the letter of response have been implemented.
This matter is further discussed in paragraph 12.
4.
Unresolved Items
Unresolved items are matters about which more information is required
to determine whether they are acceptable or may involve noncompliance
or deviations.
New unresolved items identified during this inspecti'on
are discussed in paragraph 5.c and 6.b(1).
5.
Independent Inspection Effort (Unit 2)
a.
Construction Progress
The inspector conducted a general inspection of the Unit 2
fuel, auxiliary and reactor buildings and welding material
issue station to observe construction progress and construc-
tion activities such as welding, material handling and con-
trol, housekeeping and storage,
b.
Storage of Installed Equipment
With regard to the inspection of paragraph 5.a, the inspector
on February 3-6, 1981, accompained by a representative of the
licensee, noted the following in the Unit 2 reactor and aur.iliary
buildings:
(1) Four examples of rigging from installed safety rela:ed
piping.
(2) Three examples of rigging lines impinging on cable trays
or cables in trays.~ In each case the r.igging lines
distorted the trays or cables in the trays. ~
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(3) Approximately eight examples of material (structural
steel, piping assemblies, piping fittings and buckets)
stored in cable trays containing cables.
(4)
Five examples of scaffolding supported by safety related
piping.
The licensee stated that they control scaffolding on, or
rigging to installed piping by the " good judgement of the
craft".
Rigging line impingement on cable trays and cables is
controlled also by craft judgement.
The licensee further
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stated that storage of materials in cable trays was controlled
by housekeeping inspections.
The inspector informed the
licensee that the above indicated inadequate controls for
storage of installed equipment.
Failure to establish controls
for storage of equipment in accordance with instructions to
prevent damage, is in violation of 10 CFR 50 Appendix B,
Criterion XIII.
The above violation vall be identified as
370/81-02-01:
" Failure to Establish Adequate Controls for
Storage of Installed Equipment".
c.
Markings
With regard to the inspection of paragraph Sa the inspector
noted numerous examples of extraneous markings on installed
stainless steel tanks and piping.
The inspector stated there
was no reasonable assurance that the extraneous markings were
produced with the approved marking materials contained in CP
538.
The licensee indicated that they would look further into
the matter.
The inspector stated that the above would be an
unresolved item, identified 370/81-02-04: " Extraneous Markings
on Safety Related Stainless Steel".
Within the areas examined no violations or deviations were
identified except as described in paragraph Sb.
6.
Containment (Structural Steel Welding) - Observation of Work and
Work Activities (Unit 2)
The inspector observed field welding activities associated with
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steel containment structures and steel supports for major equipment
within the containment at various stages of weld completion.
The applicable Code for containment miscellaneous structural steel
support structure is'AWS D1.1-80.
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The inspector observed'wel' ding' activities where welding was in
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progress to determine conformance with specifications and
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procedures in the areas of; weld identification, specified
weld procedures, qualified welders, specified weld material,
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specified purge (if applicable); repair procedures, specified
NDE being performed and periodic checks of welding variables.
(1)
Containment ' Structures
Weld' Joints
Structural Steel Support
2-SF-E-5
Structure
(2)
Structural Support
Weld Joints
2-SC-22
Upper Lateral Supports
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b.
Observation of weld material control included; identification,
segregation, oven temperatures, issue slips and control of
unused material at issue stations and work areas:
(1) With regard to the above inspection, on February 5, 1981,
it was noted that low hydrogen electrodes intended for
safety related structural application were reconditioned
in baking ovens.
Construction Procedure 92, Rev. 4
" Care, Handling at:d Reconditioning of Low Hydrogen Electrodes"
requires type E7018 electrodes to be baked at a temperature
of 725 F + 25 F.
The licensee stated that they were not
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aware of any temperature verification, independent of the
oven system, to assure compliance to procedural temperature
requirements.
The licensee indicated that they would
look further into the matter.
The inspector stated that
the above would be an unresolved item identified as
370/81-02-03:
" Temperature Control of Baking Oven".
c.
During observation of welding activities there appeared to be
a sufficient number of qualified inspection personnel at the
work site.
Within the areas examined, there were no violations or deviations
identified.
7.
Safety Related Structures - Observation of Work and Work Activities
(Unit 2)
The inspector observed field welding activities associated with
safety related structures and supports outside containment during
various stages of weld completions.
Observations were made in order
to determine whether the requirements of applicable specifications,
standards, work and/or inspection procedures are being met for the
activities involved and in .the following stages of weld completion..
a.
The inspector examined weld joints where welding is in process
to determine whether weld identification, weld procedures,
welder qualification, weld material, defect removal (if appli-
cable), specified NDE, and periodic checks of welding variables
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are in conformance with existing requirements.
Drawing No.
Structure
MC-1220-146, Rev. 2
Access Platform
The applicable code for safety related structural welding out
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side of containment is AWS D1.1-80.
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b.
Observation of weld material control included; identification,
segregation, oven temperatures, issue slips and control of
unused material at issue stations and work areas.
c.
During observation of welding activities there appeared to be
a sufficient number of qualified inspection personnel at the
work site.
Within the areas examined, there were no violations or deviations
identified.
8.
Reactor Coolant Pressure Boundary Piping - Observation of Work and
Work Activities (Unit 2)
The inspector observed field welding of reactor coolant pressure
boundary piping at various stages of weld completion.
The applica-
ble Code of reactor coolant pressure boundary piping is ASME B and
PV Code Section III 1971 Edition with Addenda through the Winter
1971.
a.
The inspector examined the following welds where nondestruc-
tive testing (NDE) had been accomplished to determine surface
suitability, specified NDE being performed and with qualified
personnel. The below listed joints, records, and radiographs
were examined:
Weld Joint
Size
System
NI-2F-560
10"
Safety Injection
NC-2FW-24-7
6"
NC-2FW-24-1
10"
The inspecto'r obse'ved activities at weld material issue
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str.tions to determine adequacy of; weld material storage /
segregation, oven' temperatures, ! issue records and return of
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unused weld material.
Also,the inspector observed work areas
for uncontrolled weld material.
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Within the areas examined, there were no violations or deviations
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identified.
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9.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records
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(Unit 2)
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The inspector reviewed the quality records described below relative
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to reactor coolant pressure boundary pipe welding to determine
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whether these records reflected work accomplishment consistent with
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NRC requirements and SAR commitments.
For the applicaole code see
paragraph 8.
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a.
The following completed weld records were reviewed in the
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areas of; visual and dimensional inspections, weld history,
preheat and interpass temperature, stress relief, NDE, weld
repair, welder qualification, and inspector qualification, as
applicable to each weld:
Weld Number
Pipe Size
System
NI-2F-560
10"
Safety Injection
NC-2FW-24-7
6"
NC-2FW-24-1
10"
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b.
The welding material records, for the joints listed in paragraph
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9a, relative to; receipt inspection, weld material certification,
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issue ?.nd storage control, and disposition of unused materials
were revieu d.
c.
With regard to the above inspection and the inspection of
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paragraph 11.b the inspector noted that as listed below,
qualification examinations and the eye examination records for
the dates indicated, were not retrievable.
Inspector I,D.
Note
PJH-PT-Level II
No Qualification Examination
HAD-MT Level II
No Qualification Examination
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and no Eye Examination Record
for 4-3 78
TLT-PT Level II
No Qualification Examination
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TDT-Welding Inspector
No Qualification Examination
KWK-Welding Inspector
No Qualification Examination
TOB-Welding Inspector
No Qualification Examination
and No Eye Examination for
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4-9-79
Th'e licensee indicated 'tihat a'll' the above' inspectors were
qualified at Duke sites other than McGuire and that the missing
records were at the site of qualification.
The licensee
stated that they would retrieve the records for a future inspec-
tion.
The above is an inspector followup item identified as
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370/81-02-05:
"Non-Retrievable NDE Personnel Records".
Within the areas examined, there were no violations or deviations
identi fied.
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10.
Safety Related Piping - Observation of Work and Work Activities
(Unit 2)
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The inspector observed field welding of safety-related piping
outside the reactor coolant pressure boundary at various states of
weld completion.
For the applicable code see paragraph 8.
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The
nspector examined the following welds where non-destructive
a.
test'ng (NDE) had been accomplished to determine; surface
suitability, specified NDE being performed and with qualified
personnel.
The below listed joints, records, and radiographs
were examined.
Joint Number
Size
System
8"
2"
Chemical and Volume
Control
b.
The inspector observed activities at weld material issue
stations to determine adequacy of; weld material storage /
segregation, oven temperatures, issue records and return of
unused weld material. Also, the inspector observed work areas
for uncontrolled weld material.
Within the areas examined, there were no violations or deviations
identified.
11.
Safety Related Piping (Welding) - Review of Quality Records (Unit
2)
The inspector reviewed the quality records described below relative
to safety related pipe welding to determine whether these records
reflected work accomplishment consistent with NRC recc'irements and
SAR commitments.
For the applicable code see paragrapn 8.
a.
The following completed weld records were reviewed in the
. areas of; visual and dimensional inspections, weld history,
preheat and interpass temperature, stress relief, NDE, weld
repair, welder qualification, and inspector qualification, as
applicable to each weld:
Weld Number.
aSize
System
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CF-2FW-49-8
2"
CF-2FW-49-9
2"
8"
8"
2"
Chemical and Volume Control
NV2FWFE-5310-7
3/4"
Chemical and Volume Control
CA-2F-269
8"
Aux.'Feedwater
CA-2F-82
8"
Aux. Feedwater
2"
2"
b.
The welding material records for the joints listed in paragraph
lla, relative to; receipt inspection, weld material vertifica-
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tion, issue and storage control, and disposition of unused
materials were reviewed.
(1) With regard to the above inspection, the inspector, on
February 5,1981 noted that the Certified Material Test
Report (CMTR) for type 308 consumable weld insert material
heat No. D 3403R308, used in ASME Class 2 Chemical and
Volume Control System weld joint No. 2fNp-187-1 did not
conform to the requirements of ASME B and PV Code Section
II, Part C, SFA-5.9.
SFA-5.9, Table 1, Note 1 states:
" Analysis shall be made for the elements for which specific
values are shown in this table.
If, however, the presence
of other elements is indicated in the course of routine
analysis, further analysis shall be made to determine
that the total of these other elements, except for iron,
is not present in excess of 0.70 per cent."
The total of other elements except iron was 0.744 per
cent for the material represented by the above CMTR.
The
above CMTR represents 3700 ft of material.
Therefore, it
appears nonconforming material was installed in the
plant.
Failure to fabricate and inspect systems to
quality standards commensurate with the importance of the
safety (a)nction to be performed is in violation of 10 CFR
fu
50.55a
(1).
The above violation will be identified as
370/81-02-02:
" Nonconforming CMTR."
Within the areas examined, there were no violations or deviations
identified, except as described in paragraph 11.b(1).
12.
Licensee Identified Items (50.55 (e)) (Units I and 2)
a.
(Closed) Item 370/80-06-09 " Socket Welds Do Not Meet Appliable
. Quality Standards" (10 CFR 50.55(e)).
On April 3, 1980, Duke
notified IE:II of a 50.55(e) item concerning under size socket
welds. .The Construction Deficiency Report was submitted on
May 2,'1980.
The~ report'ha's been review and determined to be
acceptable by IE:II.
The inspector held discussions with the
responsible licensee representative, reviewed supporting
documentation, and observed representative samples of work to
verify that the corrective action identified in the report
have been completed.
This item is closed.
b.
(0 pen) Item 369/80-10-10 " Socket Welds Do Not Meet Applicable
Quality Standards".
On April 3, 1980,
Duke notified IE:II of a 50.55(e) item concerning under size
socket welds.
The final Construction Deficiency Report was
submitted on May 2, 1980.
The report has been reviewed and
determined not be acceptable by IE:II, because the licensee's
sampling plan for thin wall flange socket joint and non-flange
socket joint acceptability covered Unit 2 only.
The licensee
indicated that they would look further into the matter.
This
item remains open.
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