IR 05000416/1981040

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IE Insp Repts 50-416/81-40 & 50-417/81-17,on 810928-1001.No Noncompliance Noted.Major Areas Inspected:Work Packages for Nis Owner Data Repts,Previous Insp Findings & Meeting to Review Preservice Insp Program
ML20032D154
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 10/19/1981
From: Coley J, Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20032D149 List:
References
50-416-81-40, 50-417-81-17, NUDOCS 8111130441
Download: ML20032D154 (5)


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UNITFD STATES

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NUCLEAR REGULATORY COMMISSION o

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REGION 11

101 MARIETTA ST., N.W., SUITE 3100 o,

ATLANTA, GEORGIA 30303

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Report Nos. 50-416/81-40 and 50-417/81-17 Licensee: Mississippi Power and Light Company Jackson, MS 39205 Facility Name: Grand Gulf Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Grand Gulf site near Port Gibson, Mississippi Inspector:

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g Date Signed to

/ 0 - /'/ - S l J. L. ColeyT Accompanying Personnel:

J. J. Blake, Region II Martin Hum, NRC/NRR A. R. Herdt, Region II

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J. F. Cook, NRC Consultant Approved by:

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A. R. Herdt, Section Chief Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division t

SUMMARY Inspection on September 28 - October 1,1981 Areas Inspected This routine, announced inspection involved 50 inspector-hours on site in the areas of review of work packages for NIS Owner's Data Reports (Unit 1), previous inspection findings (Unit 1), independent inspection (Unit 1) and NRC/ licensee meeting to review preservice inspection program (Units 1 and 2).

Results Of the four areas inspected, no violations or deviations were identified.

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REPORT DETAILS 1.

Persons Con.tacted Licenseo Employees:

G. Rodgers, Site Manager, Construction

  • J. W. Yelverton, QA Field Supervisor
  • J. G. Cesare, Supervisor of Licensing

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C. K. McCoy, Plant Manager, Operations

  • S. M. Pruitt,' Inservice Inspection (ISI) Coordinator

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  • S. F. Daugherty, Senior Plant Quality Representative
  • J. M. Kelly, QA Specialist

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Other Organizations

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E. Edwards, ISI Service Manager, General Electric

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NRC Resident Inspector J.

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  • A. G. Wagner

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  • Attended exit interview

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2.

Exit' Interview

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The inspection scope and findings were summarized on October 1,1981 with those persons indicated in paragraph I above. The inspector described the j

areas inspected and discussed in detail the inspection findings listed below:

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(0 pen) Unresolved Item 416/81-40-01 and 417/81-17-01:

UT weld volume

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coverage when performing full vee path examinations paragraph 8.a.

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(0 pen) Unresolved Item 416/81-40-02 and 417/81-17-02:

Qualification of

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ultrasonic indications as geometric reflectors paragraph 8.b.

3.

Licensee Action on Previous Inspection Findings a.

(Closed) Unresolved Item 416/81-11-02: Lack of licensee audits of-NDE performance during preservice inspection.

The inspector reviewed approximately 12 monitoring audits of the PSI program performed by _

plant quality _ personnel. These audits dealt primarily with ultrasonic testing (UT) since the majority of the inspections performed during the period of 1979 through 1981 were UT.

In addition, General Electric (GE) supervisors vere required to conduct biweekly surveys utilizing checklist of the work performance of GE NDE examiners in each NDE discipline.

The inspector is satisfied that the above mentioned monitoring / audits performed were adequate to provide assurance of the adequacy of examinations performed in the PSI program.

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b.

(0 pen) Unresolved Item 416/81-11-03: Visual examination of pressure retaining bolting for preservice inspection is questionable. This item dealt with the failure of the licensee to perform a visual examination of B-G-1 and B-G-2 items prior to installation. The licensee had intended to inspect the bolting in the installed condition, however the inspector pointed out that for B-G-2 Category items visual inspection was to be perfornied prior to installation. The licensee's position was that removal of pressure retaining bolting 2" and less in diameter for visual examination is not required as this bolting had already received a more stringent examination (magnetic particles) prior to "N" stamp'ng of the particular Section III part or component.

The inspector con-curred that technically magnetic particle examination was superior and asked to see MT records for bolted flanges that the licensee had installed on Unit 1.

The above magnetic particles ir.spection reports were not available for review at this time. This item will be reviewed on a subsequent inspection, c.

(0 pen) Violation 416/81-20-02: Inadequate inspection activities. This item dealt with failure of Atwood Morrill to properly bend locking devices on valves B21F0288 and B21F028C. The inspector stated in this i

violation that the licensee's planned inspection program did not verify design safety features such as locking devices, since this was the

vendor's responsibility.

The licensee took exception to the inspec-tor's statement and referenced Chapters 4.23 and 5.11 of the Checkout and Turnover Organization (CTO) Manual as the necessary requirements for inspection of locking devices.

This inspector reviewed both references and found them inadeqaate for insuring locking Avices would be properly installed. In addition, the licensee has not noti-fied the vendor in writing of the discrepancy. The inspectsr requested that the licensee amend the response to this item to address the inspector's concerns stated above.

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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraphs 8.a and 8.b.

5.

Independent Inspection Effort (Unit 1)

The inspector conducted a general inspection of the reactor building and auxiliary building to observe construction progress and construction activities such as welding, welding material control, housekeepi,g and storage.

Within the areas inspected, no violations or dev'.~ ions were identified.

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6.

Review of NIS-1 Owners Data Reports (Unit 1)

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Mississippi Power and L'ght Company (MP&L), in accordance with the require -

ments of ASME Section XI Code, Article IWA-6000, submitted copies -to >

Region II of NIS-1 Owner's Data. Reports for repairs, replacements,- and

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modifications that had been performed on Grand Gulf Unit 1 on June 3,1981.

The following ASME Section XI repairs, replacements, and modifications were-performed:

1.

Feedwater Safe-end Replacement NIS-1-00001; 2.

Recirculation Discharge Block Valve Modification NIS-1-00002; 3.

Feedwater Nozzle 30 AZ(N4A) Repair NIS-1-00003; 4.

CRD Return Line Nozzle Capping NIS-1-00004; 5.

Recirculac on Inlet Nozzle Safe-end Replacement NIS-1-00005.

The repairs, replacements, and modifications were performed by GE under contract to MP&L and Bechtel Power Corporation, using procedures meeting the requirements of ASME Section XI 1974 Edition, up to and including the Summer 1975 Aduenda.

The inspector reviewed the comp!ated work packages containing the original NIS-1 Owner's Data Reports and procedures used in the ASME Section XI repair, modification or replacement activity, as well as final examination results, for NIS-1 items 00003, 00004, and 00005 above.

Within the areas inspected, no violations or deviations were identified.

7.

Inspector Followup Items (Unit 1)

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(Closed) Inspector Followup Item 416/81-11-01: Preservice inspection program clarifications and corrections.

Based on recent meetings between NRR in Washington and MP&L, it was decided to use GE isometrics to review the GGNS Preservice Program.

Therefore, the use of the Preservice Program Abstract for NRC review of the GGNS PSI program, will no longer be needed. Paragraph 8 of this report describes certain clarifications Region II has requested as a result of a NRR, IE, MP&L, and GE review of GGNS PSI program conducted on September 30 and October 1, 1981. Region II concerns as a result of this meeting will continue to be tracked by unresolved items 416/81-40-01; 417/81-17-01; 416/81-40-02 and 417/81-17-02.

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(0 pen) Inspector Followup Item 416/81-11-04, Records of qualification test specimen do not identify built-in defects. GE had not completed corrective action on this item. GE stated that when their corrective action is complete Region II will be notified and verification can be performed in Norcross, Georgia.

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(Closed) Inspector Followup Item 416/81-20-01:

Effectiveness of QC monitoring checklists. The inspector reviewed QC monitoring checklists from June 1981 until the present and found that the licensee is presently making effective use of the QC monitoring checklist.-

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8.

Grand Gulf Nuclear Site Preservica Inspection ' Program Meeting (Units 1 and 2)

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l On September 30 and October 1,1981, a meeting was conducted at Grand Gulf with NRC/NRR, NRC/IE, -MP&L and GE te discuss GGNS PSI program.

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following topics were discussed by the above:

(1) Summary of NRC/NRR and MP&L August 6, meeting

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(2) Applicant's summary of PSI program and submittal

.(3) Relief request (4) Exemption application.

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(5) Class II _alection (6) Review of reactor vessel PSI report (7)' Resolution of detailed questions on PSI Abstract

i (8) Review of procedures and results

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(9) Demonstration of procedures l

'(10) Summary and conclusions It is our opinion that this meeting was beneficia, and has provided for a-

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better understanding of GGNS PSI program and also of NRC inspection and enforcement issues. There were, however, several areas in GGNS PSI program

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that NRC felt MP&L should clarify. This report Will only deal with clarift--

cations requested by Region _II.

a.

GE examiners performed a UT demonstration of Procedure - UT-14-380, Revision 1, on weld joint No. 62-8-3 (MP&L System No.-1G35G002). This weld joint.was an eight-inch schedule 80 pipe to elbow. The GE exam-

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iners first tried to. inspect this. weld joint using a half vee examina-

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tion and. scanning from both sides of -the weld. This technique would not inspect the weld volume due to the thin' pipe wall and the large

weld reinforcement. The examiners then conducted the examination as it had been performed during preservice. This technique consisted of a full vee examination from the pipe side of the weld on one surface.

The inspector noted during this inspection that i f the half vee

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j inspection could not be performed then the full vee inspection would

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have to-include calibration and examination for a minimum to the 12/8ths vee path and possibly to' the 16/8ths vee path in order to

inspect the weld volume and the heat effective Lane on the far side of

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the weld.

Paragraph 6.2.5.1 of. GE's Procedure UT-14-380, Revision -1, however, stated in p' art; "when the calibration block size pt mits

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l the 12/8ths vee path (2nd ID notch) appears et the 6th major division."

l This qualifying statement cannot be applied to the 12/8th vee path

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calibration since this vee point. is essential. GE's representative stated, that to his knowledge GE does not have a calibration block that

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the 12/8th vee path.could not be obtained, however this would be veri-fied and the qualifying statement would be taken out of paragraph

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6.2.5.1 since it would also contradict calibration requirements for the 12/8th vee path noted in paragraph 6.2.5.3 when calibration

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standards equal to or -exceed -inch thickness. The licensee should also review other UT procedures to determine if deletion of this quali-fying statement would also be applicable. This item was-reported to the licensee. as unresolved item 416/81-4^-01 and 417/81-17-01: UT weld volume coverage when performing full vee path examinations.

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The inspectors review: of preservice UT examination records revealed that geometric indications were recorded as required in paragraph 6.3.3 and paragraph _6,3.3.1 of GE's Procedure UT-14-380, Revision 1.

These paragraphs, however gave no guidance on how to qualify UT indications n a geometric reflector in accordance with Section IWB3514.5 of the 1977 Edition of the ASME Code. UT records _ reviewed by the inspectors revealed that the only qualifying requirement GE used was if -the-indication could be detected intermittently around the weld joint. The inspectors noted that cracks, lack of root penetration and lack of fusion at the root could also occur intermittently around the. root.

'The Winter 1975 Addenda of the 1974 Edition of the ASME Code and the 1977 Edition of the ASME Code states in part:

"The presence of a geometric reflector shall be noted for the record.

To qualify an ultrasonic indication as a geometric reflector, the following requirements shall be met.

(1) The area' containing the geometric reflector shall be.

examined and interpreted in accordance with Appendix III.

(2) The presence of geometric reflectors shall be confirmed either by review of 'the fabrication drawings of-the pipe.

weld edge-preparction, the nondestructive examination records, or supplenental examination results.

(3) Supplemental-examination methods shall be used, if necessary, to confirm the presence of geometric reflectors."

This item was reported to the licensee &s unresolved item 416/81-40-02 and 417/81-17-02: Qualification of ultrasonic indications as geometric reflectors, b

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