IR 05000416/1978016
| ML20147C595 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/07/1978 |
| From: | Crowley B, Herdt A, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20147C587 | List: |
| References | |
| 50-416-78-16, 50-417-78-16, NUDOCS 7812180353 | |
| Download: ML20147C595 (6) | |
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. UNITED STATES
[ t>* af oot 'o,f NUCLEAR REGULATORY COMMISSION REGloN il
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Report Nos.-
50-416/78-16 and 50-417/78-16
. Docket Nos.:.50-416 and 50-417-
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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
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Jackson,.' Mississippi 39205 Facility Name:
Grand Gulf Nuclear Station, Units 1 and 2 Inspection at:
Grand Gulf and Jackson, Mississippi.
Inspection. conducted: October 10-13, 1978 Inspectors:
J. K. Rausch B. R proley-
Reviewed by:
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'A.
R. Herdt, Chief Bat'e Projects Section Reactor Construction and Engineering Support Branch l
Inspection Summary l_nspection on-October 10-13, 1978 (Report Nos. 50-416/78-10 n
and.50-417/78-16)
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. Areas Inspected:
QA program implementation; licensee's follow of Part 21
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event reports and Inf ormation Circular 78-08; and pre-service inspection on Unit 1 reactor vessel. The-inspection involved 22 inspector-hours on site.
by two NRC inspectors.
Results: No items of noncompliance or deviations were disclosed.
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781318o353 k
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RII Rpt. Nos. 50-416/78-16 and 50-417/78-16 1-1
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DETAILS 1 Prepared by:
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,'N f~ - Projects Secti6n.K.7Rausch,P/incipalInspector Date
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Reactor Construction and Engineering Support Branch
. Dates of Inspection:
e ober 12-13, 1978 Reviewed by:
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'l~7~78 A. R. Herdt, Chief Date Projects Section Reactor Construction and Engineering Support Branch
1.
Pe'rsor s Contacted a.
Mississippi Power and Light Company (MP&L)
- T. E. Reaves, Jr., Manager of Quality Assurance (QA)
P. W. Sly, QA Field Supervisor J. C. Fuller, QA Representative W.- M. Gardner, Civil'QA Representative
- F.
Kellan, Licensing b.
Contractor Organization Bechtel Power Corporation (Bechtel)
D. M. Lake, Field Construction Manager
- Denotes those present at the exit interview.
2.
Licensee Actions on Previous Inspection Findings No previous inspection findi;.gs were examined.
3.
Unrer.olved items There were no new unresolved items identified during this inspection.
4.
Independent Inspection Effort The inspector examined various areas of Units 1 and 2 to observe construction' work and related activities in progress, to inspect the general state of. cleanliness and housekeeping, and to examine the inplace storage' conditions of mechanical and electrical equipmen._
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RII Rpt 'Nos. 50-416/78-16 at
'7/78-16 I-2 noncompliance or deviations were identified.
. No i t ei
5.
Licenst
"ollow of Control Switch Installation Without Locking ng, Part 21 Report by G.E.
G.E. 2dentified and updated to the licerree by letter on July 20, 1978, information supplied earlier to the NRL. The licensee then formally
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requested.th'at G.E. supply a corrective action report and include MP&L on the. distribution list for all correspondence relating to the Part 21 reportable deficiency.
On August 15, 1978, MP&L submitted a final report to identify the corrective action to be taken. This item will remain open until it has been ascertained that applicable switches are equipped with locking rings and that rings were installed per written instructions. This is identified as IFl 416/417/78-16-01.
c No items of noncompliance or deviations were identified.
6.
Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants, IE Circular 78-08, Units 1 and 2 The contents of_ the subject IE Circular were discussed with the licensing manager at the MP&L corporate of fice.
The licensee was reminded that although no written response to this circular itself is required, a determination as to applicability of the qualification items identified by the circular should be made for the Grand Gulf Plant. The licensee advised that a review had been made of the subject matter but could not identify that any review or other action had been documented for the records.
The licencee agreed to obtain a letter from Bechtel to evidence their review and evaluation. This item will be t reated as IF1416/417/78-16-02, IE Circular 78-08, 7.
Management Interviews The inspector met with the licensee representatives (denoted in paragraph 1) at the' conclusion of the inspection on October 13, 1978, at the Corporate office. Discussion included the Part 21 event report on the G.E. control switch locking rings and the inf ormation circular 78-08.
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RII Rpt. Nos. 50-416/78-16 and 50-417/78-16 11-1 DETAILS ]]
Prepared by:
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B. R. Crowley, Meta 11urgic/a1 Engineer Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection:
October 10-13, 1976 Reviewed t
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T. E. Conlon, Chief 6 ate Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted Mississippi Power and Light Company (MP&L)
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T. E. Reaves, Jr., Manager of QA kP. W. Sly, QA Field Supervisor
- D. L. Hunt, Assistant Maintenance Supervisor hS. F. Tanner, QA Representative b.
Contractor Organizations General Elect ric Installat ion and Service Engineering b2 vision TihSEl B. E Husband, NDE Supervisor and 151 Coordinator H. F. Fedick, ISI Supervisor R. E Edwards, QC Supervisor D. Kerr, Level 11 Examiner J. Albanese, Level 11 Examiner
- Denotes those present at the exit interview.
2.
Licensee Actions on Previous Inspection Findings Actions on prev:ous 1indings were not examined during this inspect ion 3.
Unrepolved 1tems
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Ril Rpt. Nos. 50-416/78-16 l
and 50-417/78-16 11-2 No unresolved items were identified during this inspection.
4.
Preservice inspection - Review of Procedures (Unit 1)
The inspector reviewed the preservice inspection procedures indicated below relative to the reactor vessel to determine whether the procedures were consistent with regulatory requirements and licensee commitments.
The preservice examination is being perf ormed in accordance with the ASME Boiler and Pressure Vessel Code,- Section XI, 1974 Edition and addenda through the Summer of 1975 with more re.it rict ive and definitive requirements of the
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Winter of 1975 and Summer of 1976 addenda.
The f ollowing procedures were reviewed:
GG2]A3800AB, Rev. 1, " Ult rasonic Examination of Reactor Pressure Vessel Welds" GG21A3814AA, Fev. 3, " Remote Ultrasonic Examination of Reactor Pressure f
Vessel Welds and Base Material" GG2]A3815AA, Rev. 1, " Evaluation of Ultrasonic Indications in Reactor Pressure Vessel Welds"
"I&SE Southern Region Inservice Inspection Quality Asst rance Manual",
Set tions 10 and 17 These procedures were reviewed in the areas of:
a.
Procedure approval, requirements f or qua1ifacation of NDE Personnel, and procedure scope b.
Procedure technical content relative to type of apparatus, ext ent of coverage, calibration requirements, size and frequencies of search units, beam angles, methods of compensation f or metal distance t raveled by ultrasonic beam, reference level for monitoring discontinuities, method of demonstrating penetration, limits for evaluation and recording of indications, method of recording significant indications, and accept ance limits Compilation of requiud records (
in the areas inspected, no items of noncompliance or deviations were identified.
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Rll Rpt. Nos. 50-416/78-16 j
and 50-417/78-16 11-3 5.
Preservice Inspection - Observation of Work and Work Activities
{._ Unit 1)
The inspector observed the preservice activities described below to determine whether these activities were being perf ormed 2n accordance with regulatory requirements and licensee procedures. See paragraph 4. above for the applicable code and procedures.
Personnel qualification records for one Level 1, one Lev-1 II, and one a.
Level 111 examiner were reviewed.
b.
In process ultrasonic examination, including portions of the calibration sequence were observed for reactor vessel vertical seam BG l
on GE drawing 762E399, " Vessel Weld Identification Layout" The j
inspection was compared with the applicable procedures in the f ollowing areas:
(1) Use of specified type of apparatus (2) Extent of coverage and scanning technique
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(3) Calibration method including frequency and use of required calibration block (4) Size and f requencies of send units (5)
Beam angles and DAC curves
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(6) Definition of reference level f or monitoring discontinuities (7) Demonst ration of penetration (8) Limits for evaluating and recording indications (9) Method of recording significant indications (10) Acceptance limits (11) Use of instruction manual or program procedure (12) Personnel thoroughly f amiliar with inspection system (13) Examination provision f or 100*4 volumetric coverage (14) Continuco:,
recording of reproducible data v2th accurate orientatlon of the ref er(nce points In the areas inspected, no items of noncompliance or deviations were 2dentified.
6.
Exit Interview The inspec tor met with licensee representat ives denoted in paragraph I at the conclusion of the inspectson and summarized the scope and Iindings of the inspection. The inspection included review of procedures and observat ion of work f or the Unit I reactor vessel preservice inspection. The lic ensee had no comment s or quest ions.