IR 05000417/1979023
| ML19253C487 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/23/1979 |
| From: | Herdt A, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19253C485 | List: |
| References | |
| 50-416-79-23, 50-417-79-23, NUDOCS 7912050618 | |
| Download: ML19253C487 (8) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMIS$10N n
E REGION 11
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101 MARIETTA ST N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303
.....
Report Nos. 50-416/79-23 and 50-417/79-23 Licensee: Mississippi Power and Light Company Jackson, Mississippi Facility Name:
Grand Gulf Nuclear Station Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR 119 Inspection at Grand Gu f sit near Port Gibson, Mississippi Inspected by:
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Approved by:
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A. R. Herdt, Tection Chief, RC&ES Branch Dhte Sigded SUMMARY Inspection on September 25-28, 1979 Areas Inspected This routine unannounced inspection involved 27 inspector-hours onsite in the areas of safety related pipe welding and inspection activities; safety related structures welding activities; safety relief valve radiographic film review; and followup of an item of noncompliance.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
1503 333 7912050
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DETAILS 1.
Persons Contacted Licensee Employees
- J. C. Fuller, Acting QA Field Supervisor
- H. D. Morgan, Construction Supervisor
- S. F. Tanner, QA Representative
- R. A. Courtney, QA Representative D. D. Little, QA Representative Other Organizations Bechtel Power Corporation (Bechtel)
- J. W. Yelverton, QA Engineer
- J. R. Valdez, QA Engineer General Electric Company (GE)
- R. R. Zrubek, Site Manager
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 28, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (416/79-07-01): Failure to follow approved procedures and draw;ngs during installation welding of safety related structures. The MP&L letter of response dated June 1, 1979, has been
"iewed and determined to be acceptable by Region II. The inspector held da..'Msions with MP&L and Bechtel QA personnel and examined the corrective actions as stated in the letter of response. The inspector concluded that MP&L had determined the full extent of t'te subject noncompliance, performed the necessary survey and followup action s to preclude recurrence of similar circumstances. The corrective actions identified in the letter of response have been implemented.
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. A new unresolved item identified during this inspection is discussed in paragraph 6.
1503 334
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-2-
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5.
Independent Inspection Effort (Units 1 and 2)
The inspector conducted a general inspection of the Unit I containment a.
and Units 1 and 2 auxiliary building areas to observe activities such as filler metal control, material storage and pipe handling activities.
b.
Preservice inspection is being conducted in accordance with the ASME Boiler and Presse.e Vessel Co.3 Section XI, 1974 edition plus addenda.
through the summer of 1975 and the Appendix III portion of the winter 1975 addenda. The applicable procedure for ultrasonic-testing (UT) of piping is UT-14-380, Rev.
0," Procedure for Ultrasonic Examination of Nuclear Piping Systems for Preservice and Inservice Inspection".
The inspector observed portions of 45* UT inspection of Unit I weld nos.
1D21-15-8-1 and IB21-15-8-2 for conformance to code and procedure requirements.
Installation of safety related piping is being performed in accordance c.
with the ASME Boiler and Pressure Vessel Code Section III, 1974 edition with no addenda, The inspector observed root and second pass welding of Unit 2 weld no. 2 of ISO M-2348S for conformance to code and procedure requirements in the areas of weld identification, weld procedure used, physical appearance of weld, welder identification and control of filler metal.
d.
Unit 1 Recirculation System inlet nozzles are being replaced in ac-cordance with the ASME Boiler and Pressure Vessel Code Section XI, 1974 edition plus addenda through summer 1975 and GE Specification 21A2042, Rev.
3.
The inspector observed automatic welding of nozzle
'"C" for conformance to code and procedure requirements.
No items of noncompliance or deviations were identified.
6.
Reactor Coolant System Safety Relief Valve Radiographic Film Review (Unit 1)
This inspection was performed at the request of NRC: Region IV Vendor Inspection Branch.
Reactor Coolant System Safety Relief Valves are manu-factured for Grand Gulf by G. Dikkers and Co. N. V. (Dikkers) in Hengelo, Netherlands under contract to General Electric Company (GE).
The Grand Gulf FSAR, Chapter 5, Appendix 5A requires manufacture in accordance with the ASME Boiler and Pressure Vessel Code Section III, 1974 edition plus addenda through Summer 1976. At the tim-of this inspection MP&L had received forty Dikkers valves but had not accepted the valves through receipt inspection since portions of required documentation had not been received. The i apector verified this through review cf Material Receiving Report Nos. GPD-124 and GPD-9034. Radiographs had only been received for the twenty Unit 1 valves.
The inspector selectively reviewed radiographic 1503 335
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film for nine Unit I valves. The inspector did not review allof the film available for each valve (approximately 80 film each). Radiographic require-ments isr these valves includes the following:
a.
ASME Section III (1) NB-2571
" Cast pressure retair.ing materials shall be examined by radiographic methods,"
(2) NB-2573.1
"The radiographic methas shall be in accordance with ASTM E-94-68 Recommended Practice for Radiographic Testing and E-142-72 Controlling Quality of Radiographic Testing.
." and
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"The extent of radiographic coverage shall be of the r.iaximum feasible volume.
."
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(3) NB-2753.2(b)
"For those areas where relatively uniform thick-nesses occur, the mirimum film density shall be 1.5 for single viewing and 2.0 for composite viewing of multiple film exposures.
,
(4) NB-2573.2(d)
"The radiographie quality level shall be 2-4T for section thicknesses up to and including 3/4 inches and 2-2T for section thicknesses greater than 3/4 inches".
(5) NB-2573.3(a)
" Location markers, such as lead numbers or letters, which shall appear as radiographic iraages on the film, shall be placed on the casting.
"
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b.
ASTM E94-68 (1)
13.1
"The selection and placement of penetrameters should conform to Method E142."
(2)
14.2
"The image of the location markers for the coordination of the part with the film should appear on the film.
."
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c.
ASTM E142-72 (1)
4.1
"The quality of all levels of radiographic testing shall be determined by a penetrameter.
"
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(2)
4.1.4 - "The rectangular penetrameter shall be identified with a number made of lead.
"
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(3)
7.1
"One penetrameter shall represent an area witbin which radiographic densities do not vary more than -15 or +30 percent.
At least one penetrameter per radiograph, exposed simultaneously with the specimen, shall te used.
"
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-4-
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(4)
8.1
"The image of the location markers for the coordination of the part with the film shall appear on the film, without inter-fering with the interpretation".
Contrary to the above requirements the following discrepancies were noted:
a.
Film identification and penetrameters located in such a manner as to interfere with the interpretation of the area of interest
,
b.
Film density below the minimum requirement of 1.5.
Film density within the area of interest not within -15 to +30 percent c.
of the film density at the penetrameter.
d.
Location markers not shown on film.
e.
Penetrameter size not shown on film.
f.
Edge of part not shown on film due to radiation scatter, sometimes called " washout" or " burn-out".
g.
Idnetification not on film.
h.
Radiographic quality level dees not meet 2-2T.
Discrepancy a. was noted to be a general practice and was present on most film reviewed. The remaining discrepancies noted by specific film are as follows:
Valve No.
Part Film No.
View Discrepancy Q1B21-F041 Cover
-
-
b. (density 1.42)
S/N 160795 and g.
"
Cap LW390 42-39 d. (no. 38)
38-35
"
Body JW704
e.
"
"
JW705 8-14, c.
9-15
"
"
JW710
b. (density 0.93)
and f.
Q1B21-F041 Cap LW466 28-29-h.
S/N 160796 30,24-
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-5-
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Valve No.
Part Film No.
View Discrepancy
"
Body KW485 3-4-5 c.
"
"
KW486 8-14, c.
9-15 Q1B21-F041 Body KW475 9-15, b. (density 0.83)
.
S/N 160797 10-16 11-7 Q1B21-F047 Body KW503 8-14 c.
S/N 160805 9-15
"
"
KW508 9-15 b.(density 0.68)
10-16 11-17 Q1B21-F047 Body KW611 8-14 c.
S/N 160806 9-15
"
"
"
9-15 b.(density 0.74)
10-16 11-17
"
"
KW616 25-26 f.
Q1B21-F047 Body KW351 8-14 c.
S/N 160807 9-15
"
"
"
9-15 b. (density 0.96)
10-16 11-17 Q1B21-F051 Body KW722 8-14 c. and S/N 160811 7-15 d. (no. 8)
Q1B21-F051 Body KW 722 9-15 b. (density 0.81)
S/N 160811 10-16 11-17 Q1B21-F051 Body KW362 8-14 b. (density 1.12)
S/N 160812 9-15
"
"
"
9-15 b. (density 0.87)
10-16 11-17
"
"
KW363 25-26 f.
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Part Film No.
View Discrepancy.
Q1B21-F051 Body KW402 12-18 b. (density 1.36)
S/N 160814 13-19
"
"
"
8-14 b. (density 9-15 1.27) and d.
(no. 8)
'
"
"
9-15 b. (density 0.62)
10-16 11-17
"
"
KW411
h.
It should be noted that the specific radiographic procedure, shooting sketches, valve drawings and acceptance radiographic standards were not available on-site during the film review. Therefore, the radiographs wtre not evaluated for acceptance / rejection and the above findings are considered to be preliminary. MP&L has initiated Corrective Action Request Number 236 to GE for corrective action and eveluation for reportability to NRC. This is Unresolved Item 50-416, 417/79-23-01 " Radiographic film discrepancies for reactor coolant safety relief valves."
No items of noncompliance or deviations weneidentified.
7.
Safety Related Piping (Welding) - Observiation of Work and Work Activities (Unit 1)
The applicable code is identified in paragraph 5.c.
The inspector observed welds at various stages of completion for conformance to procedure and code requirements in the areas of weld Identification, weld procedure used, physical appearance, welder identification, QC verification and control of filler metal. Welds observed included Weld No. 4 of ISO M-1335 (inter-mediate welding), Weld No. 2 of ISO M-1335 (root welding) and Weld No. 24 of ISO M-1348R (final welded and contour ground).
No items of noncompliance or deviations were identified.
8.
Safety Related Structures (Welding) - Observation of Work and Work Activities (Unit 1)
Safety related structures (supports) are being installed in accordance with the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF 1974 edition pluu the Summer 1974 addenda as required by Design Specification for Fabrication of Structural Steel for Pipe Supports, Restraints and Anchors-Nuclear Service, 9645-M-300.6, Rev.19. The inspector observed welding for conformance to code and procedure requirements in the areas of 1503 339
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weld identification / location, use of applicable weld procedure and use/ control of specified weld material. Welding was observed on a seismic tubing support per Drawing No. FSK-I-0126-091-V, Rev. I and Class 1 pipe support Q1E12-G015-H06.
No items of noncompliance or deviations were identified.
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