IR 05000416/1978019
| ML19263B451 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/11/1978 |
| From: | Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B445 | List: |
| References | |
| 50-416-78-19, 50-417-78-19, NUDOCS 7901180266 | |
| Download: ML19263B451 (5) | |
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AT L ANT A, GEORGI A 30303 s, w.... f Report Nos. : 50-416/78-19 and 50-417/78-19
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Docket Nos..
50-416 and 50-417 License Nos. : CPPR-118 and CPPR-119
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Categories: A2 and A2 Licensee: Mississippi Power and Light Company P. O. Box 1640 Jackson, Mississippi Facility Name: Grand Gulf Nuclear Station, Units 1 and 2 Inspection at: Grand Gulf, Mississippi t
Inspection conducted: November 28 - December 1,1978 Inspector:
W. P. Ang Reviewed by:\\
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J. C. Bryant, Chief ate (
Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch InspecQon_ Summa.ry Inspec_ tion on November 28 - December 1, 1978 J eport_Nos. 50-416/78-19 and 50,-417/78-19)
Areas Inspected: Unit I reactor vessel internals - observation of work and quality related records; safety related pipe support and restraint systems.
The inspection consisted of 22 inspector-hours onsite by one hTC inspector.
Results: No items of noncompliance or deviations were identified.
790118O M
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RII Report Nos. 50-416/78-19 and 50-417/78-19 I-1
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DETAILS I Prepared by:
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W. P. Ang, Mechanical Engineer Date Engineering Support Section No.1 Reactor Construction and Engineering Support Branch Dates of Inspection: November 28 - December 1,1978 Reviewed by:
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,nm J. C. Bryant, Qbief
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Dats
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Engineering Support Section No.1 Reactor Cons * ruction and Engineering Support Branch 1.
Persons Contacted MississippiPowerandLightkapany(MPL)
a.
- T. E. Reaves, QA tianager
- W. Edge, QA Representative
- P. W. Sly, QA Field Supervisor
- D. D. Little, Mechanical QA Representative
- D. F. Mahoney, Mechanical QA Representative b.
Bechtel Power Corporation (Bechtel)
- R. L. Scott, Project QA Manager
- J. R. Valdez, QA Engineer
- D. W. Strohman, QA Engineer
- G. D. Brodeur, Assistant Piping Engineer J. Trammel, Procurement, Supplier Quality Site Representative c.
B. C. Patterson, Installation and Service Engineering (ISE)
Site Manager D. Orr, Installation and Service Engineer T. Sigman, QC Engineer, Nuclear Engineering Division (NED)
- Denotes attendance at exit interview.
- Denotes participation in the exit by telephone.
2.
Licensee Actions on Previous Inspection Findings Licensee actions on previous inspection findings were not reviewed during this inspectio.-
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RII Report Nos. 50-416/78-19 and 50-417/78-19 I-2 3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain they are acceptable items, items of noncompliance, or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 7.
4.
Independent Inspection Effort A walk-through inspection of the react'r plant (Units 1 and 2) was performed.
General work practices, housekeeping and inplace storage of components were observed.
Construction progress was noted. No items of noncompliance or deviations were identified.
5.
Reactor Vessel Internals - Observation of Work and Work Activities (Unit 1)
This is a follow-on inspection to khose reported on inspection report Nos. 50-416/78-03 and 50-416/78-14. The completed shroud installation and partially completed core support plate installation were inspected.
"In-core Housing" work was also observed. The inspector noted that prerequisites of GE installation instruction no. 22A4304 requiring installation of bottom head thermocouples and bottom head drain line insulation prior to installation of "In-Core Housing" had not been accomplished.
However, the GE-NED QC engineer informed the inspector that this was not a technical problem.
GE NED (San Jose, Ca. ) had provided telephone concurrence to this. Field deviation disposition requests were prepared by the GE-NED field representative to correct the procedure for Grand Gulf.
Furthe rmore, the GE-ISE site manager indicated that the controlling work document known as the " traveller" would in the future include signoff spaces for prerequisites to assure that no prerequisites are overlooked.
The licensee agreed to the inclusion of prerequisites on the " traveller."
No items of noncompliance or deviations were identified.
6.
Reactor Vessel Internals - Review of Quality Records (Unit 1)
This is a follow-on inspection to the inspection reported on inspection report No. 50-416/77-3. Applicable portions of the following instruc-tions and drawings were reviewed:
GE DVG 762E639 Rev. 2 - Shroud GE DWG 762E541 Rev. 7 - Vessel and Components GE DWG 105D5435 Rev. 4 - Hardware - Core Plate GE Instruction 22A4978 Rev. 2 - Core Plate Stud Tensioning
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RII Report Nos. 50-416/78-19 and 50-417/78-19 I-3 GE Instruction 21A3513 Rev. 8 - Vessel and Components GE Instruction 22A4304 Rev. 0 - Reactor System The following quality related records were reviewed to ascertain that QA activities relative to handling, installation and inspection were being accomplished and to confirm that installation is in accordance with specifications and procedures:
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GE Traveller S-T Rev.1 - Shroud Installation GE Traveller CP-IL Rev. O Core Plate Installation GE Traveller ICH-T Rev. 0 - In-Core Housing MPL QA Inspection Report 78/44 - Installation of Reactor Internals MPL QA Inspection Report 78/49 - GE Storage Requirements MPL Quality Surveillance Inspection Report Dated 2/11/77 -
Hoisting, Rigging and Transporting Items Nuclear; Handling, Rigging and Installation of RPV No items of noncompliance or deviations were identified.
7.
Safety-Related Pipe Support and Restraint Systems (Unit 1)
Safety-related pipe support and restraint system's procedures and drawings were reviewed to ascertain that they had been approved by authorized liciasee personnel.
The procedures and drawings were prepared and approved by Bechtel, the architect / engineers, rather than the licensee. MPL does perform surveillances on Bechtel. MPL Quality Surveillance Inspection Reports of December 6,1976 and February 10, 1976 were reviewed. The following Bechtel specifications and instruc-tions were reviewed to ascertain compliance with NRC requirements and licensee commitments:
Bechtel Design Specification 9645-M-204.0 Rev.18 Bechtel Mechanical Standard 9645-MS-16 Rev.13 Bechtel Design Specification 9645-M-300.0 Bechtel QC Instruction No. 9.1-20 Rev. 3 Bechtel Construction Work Plan / Procedure WP/P-P-5 Rev. 1 Ten mechanical snubbers that were fully inspected and acceptable for installation, according to the licensee, were selected and inspected for smoothness of shaf t travel and unit activation. The ten snubbers are:
20,000 # Rating: International Nuclear Safeguards (INS)
Corporation Serial Nos. 07259, 07263-1978 3000 # Rating INS Serial Nos. 07217, 07068, 11507-1978 750 # Rating INS Serial Nos. 07265, 07058, 07095, 07087, 07057-1978
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k RII Report Nos. 50-416/78-19 and 50-417/78-19 I-4 One 750 # snubber (serial No. 07087) did not operate smoothly and had a tendency to bind when the shaft was slowly moved. The two 20,000 #
snubbers could not be activated by sudden movement of the shaft. The inspector requested to see the test results or certificate of compliance for similar tests specified on INS procedure 1003 and approved and implemented by Bechtel as specification 9645-d-300.0-QS-26.1-2-0.
Bechtel informed the inspector that the records were not on the site.
The acceptability of the one 750 # snubber and the two 20,000 # snubbers could not be confirmed. The licensee indicated that the acceptability of the snubbers would be investigated and the test results or certifi-cate of compliance would be made available for future inspections.
Consequently, this item has been identified as an unresolved item, 50-416/78-19-01.
Except for the unresolved item mentioned above no items of noncompliance were identified.
t 8.
Exit Interview e
An exit interview was held at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection of reactor vessel internals work and records, safety-related pipe supports and restraints systems, and the reactor plant walk-through inspection.
The unresolved item on paragraph 7 was discussed. The licensee commit ted to investigate the unresolved item fully and to have the necessary records available for future inspections.