IR 05000416/1979019
| ML19256E130 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/17/1979 |
| From: | Herdt A, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256E129 | List: |
| References | |
| 50-416-79-19, 50-417-79-19, NUDOCS 7910290141 | |
| Download: ML19256E130 (4) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION n
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o 101 MARIETTA ST., N.W., SUITE 3100
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Report Nos. 50-416/79-19 and 50-417/79-19 Licensee: Mississippi Power and Light Company Jackson, Mississippi Facility Name: Grand Gulf Nuclear Station, Units 1 and 2 Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Grand Gulf Site near Port Gibson, Mississippi N K. Van Doo n
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?!/7[J9 Inspector: h, [
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Date Signed Approvedpy:
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- Uste' Sip,ned 9//7/79 A. R. Herdt? Section Chief, RCES Branch SUMMARY Inspection on August 29-31, 1979 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours onsite in the areas of preservice inspection program, procedures and observation of work.
Results No items of noncompliance or deviations were identified.
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s DETAILS 1.
Persons Contacted Licensee Fa; ' ces
- J. C. Fuller, Acting QA Field Supervisor
- D.
L. Hunt, Plant Quality Supervisor
- H. D. Morgan, Constructim Supervisor
- S. F. Tanner, QA Represectative
- S. M. Pruitt, Plant Quality Representative Other licensee employees contacted included two engineers and three techni-CianS.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 31, 1979 with those persons indicated in Paragraph 1 above. The threeinspector followup items described in paragraphs 5 and 8 were discussed in detail.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preservice Inspection - Review of Program (Units 1 and 2)
Mississippi Power and Light Company (MP&L) has contracted with General a.
Electric Installation and Service Engineering Division (I&SE) for services to plan, perform and document the preservice examination.
Preservice examination is being performed in accordance with the ASME Boiler and Pressure Vessel Code (BPVC)Section XI,1974 edition plus addenda through the Summer of 1975 and the Appendix III portion of the Winter 1975 addenda. Bechtel Power Corporation (Bechtel) has develop-ed the " Technical Specification for Inservice Inspection',' M-189.0 which includes preservice inspection requirements. Bechtel also serves as technical consultant to MP&L for the preservice inspection pro; ram.
I&PE has developed a qualitf assurance manual and the " Grand Gulf Nucle.r Station Preservice Examination Plan for Class 1, 2, and 3 Piping Systems and Associated Components." Included in this plan is the manual piping UT procedure, " Procedure for Ultrasonic Examination of Nuclear Piping Systems for Preservice and Inservice Inspection",
UT-14-380, Rev. 0; the " Identification and Marking Plan for Class 1 and 2 Piping Welds", Rev. I and the "Preservice Examination Matrix for Class 1, 2 and 3 Piping Systems and Associated Components", dated 122/ 006
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-2-o September 15, 1979. The applicable MP&L administrative procedure is
"Preservice and Inservice Inspection, Safety Related", 01-S-07-10, Rev. O.
In addition, the MP&L Operations QA Manual is applicable ta preservice inspection. The inspector reviewed the above listed docu-ments to determine whether appropriate procedures / instructions were provided and requirements were being met in the following areas:
licensee approvals; QA organization; general QA requirements such as specification of quality requirements, control of program deviations, quality documentation and identification of components / systems covered by the program; establishment and control of work procedures to insure control of special processes; control of corrective acticn; document control; control of examination equipment; quality recorus; qualifica-tion of personnel; and senpe of the preservice inspection.
b.
The inspector noted on August 39, 1979 that pipe / fitting longitudinal seam welds were not shown on weld isometric drawings presently includ-ed in the PSI program. Portions of these welds are required to be inspected per ASME (BPVC),Section XI.
The licensee informed the inspector that isometrics were in the prccess of being updated and longitudinal seam welds are being included as part of the updating process. Until it can be verified that these welds wil' be included on the isometrics this will remain open as inspector followup item 50-416,417/79-19-01, " Incorporation of Longitudinal Seam Welds on PSI Isomecrics".
c.
On August 29, 1979 the licensee informed the inspector that the use of Appendix III of the ASME BPVC,Section XI, Winter 1975 addenda for UT inspection had not been approved by NRC to date. The inspector reviewed MP&L letter AECM-78/77 dated November 3, 1978 which was submitted to the NRC requesting approval of use of the above Appendix. The letter also submitted the Class 2 piping system e;emptions to NRC (NRR) for approval. The licensee indicated that the appendix was essentially in accordance with the Summer 1978 addenda and when this addenda is authorized by NRC the program will be updated to the later addenda.
At this time the new prc.3 ram will be submitted to NRC for approval.
Authorization for use of the Summer 1978 addenda by incorporation into 10 CFR Part 50, Section 50.55a is presently in the approval process at NRC. MP&L has issued Discrepancy and Correction Report Number 1146 as a tracking document until NRC approval is obtained. The licensee was informed that this item will remain open until final NRC approval is obtained, verifying this appro val and reviewing the updated program for conformance to the lattr code and any additional requirements required by NRC. This is inspector followup item 50-416,417/79-19-02,
" PSI Program Approval".
No items of noncompliance or deviations were identified.
6.
Preservice Inspection - Review of Procedures (Units 1 and 2)
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The applicable code is identified in paragraph 5.
The inspector reviewed the " Procedure for Ultrasonic Examination of Nuclear Piping Systems for i22/
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-3-o Preservice and Inservice Inspection", UT-14-380, Rev. O for confromance to Code and NRC requirements.
It snould be noted that the procedure was reviewed for conformance to Appendix III of the Winter 1975 addenda to ASME,Section XI which has not been approved to date by NRC (s e paragraph 5) and is therefore subject to further review.
Thia procedure was reviewed in the areas of procedure approvals; personnel
. qualification requirements; procedure scope; requirements for records such as results, data sheets, equipmen' data, calibration data sheets, calibra-tion blocks and couplant material, and technical requirements such as type of apparatus (including frequency range, linearity and signal attenuation accuracy), extent of coverage, scanning rate, scanning directions, calibra-tion requirements, size and frequency of transducers, beam angle, DAC curves, reference and scanning levels, methods of demonstrating penetra-tion, methods of evaluating and recording indications and acceptance limits.
No items of noncompliance or deviations were identified.
7.
Preservice Inspection - Observation of Work and Work Activites (Unit 1)
The applicable Code is identified in paragraph 5.
The inspector observed 45 shear wave ultrasonic testing (UT) of 18-inch Residual Heat Removal System Weld No. FW-28.
The weld inspection was observed to ascertain whether the following requirements were met: available UT procedure complied with for all technical attributes, specified UT equipment used, examination personnel knowledgeable of method and equipment, proper qualification level of personnel using equipment and accurate recording of results and equipment data. The inspector also reviewed qualification records of one Level II inspector and certification records of UT equipment used, calibration blocks and couplant.
No items of noncompliance or deviations were identified.
8.
Item of Concern On August 28, 1975 a former employee of the Grand Gulf site expressed concerns to the inspector about inadequacies of the welder qualification program for certain non-safety-related piping. Since the concerns were limited to non-safety-related piping, the MP&L Plant Quality and Field QA management personnel were notified of the concerns. These personnel assured the inspector that the area would be reviewed and a copy of the report would be forwarded to NRC:RII.
This item will be carried as inspection followup item 416-417/79-19-03, Welder Qur'.ification Program in Certain Non Safety Related Piping.
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