IR 05000416/1982044
| ML20058C230 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/25/1982 |
| From: | Jape F, Andrea Johnson, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C214 | List: |
| References | |
| 50-416-82-44, NUDOCS 8207260295 | |
| Download: ML20058C230 (4) | |
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'o UNITED STATES
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4, NUCLEAR REGULATORY COMMISSION g
e REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303
Report No. 50-416/82-44 Licensee:
Mississippi Power and Light Company Jackson, MS 39205 Facility Name: Grand Gulf Docket No. 50-416 Licenses No. CPPR-118 Inspection at Grand Gulf site near Port Gibson, Mississippi Inspectors:
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A. H. Johnson h/c25/85 id A OTVM M. Thomas
Date ' Signed hg_se b
Approved by:
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F. Jape' Section Chief //
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Date Signed
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Engineering Inspection 'Brandh Division of Engineering and Technical Programs SUMMARY Inspection on June 1-4,10-12, and 21-22,1982 Areas Inspected i
This routine, unannounced inspection involved 116 inspector-hours on site in the areas of preoperational test results review and open items.
Results Of the two areas inspected, no violations or deviations were identified.
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8207260295 820628 PDR ADOCK 05000416 G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- C. K. McCoy, Plant Manager
- J. W. Yelverton, Site QA Manager
- J. C. Roberts, Startup Supervisor
- R. A. Ambrosino, Assistant Plant Manager Other licensee employees contacted included test supervisors.
NRC Resident Inspector
- A. G. Wagner, SRI
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 4, 12, and 22, 1982, with those persons indicated in paragraph 1 above.
The licensee acknowledged the inspectors comments and findings.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preoperational Test Results Evaluation The inspectors reviewed the test results and licensee acceptance for the following preoperational tests:
a.
1C91PT01, Rev. 2, NSSS Process Computer Preoperational Test b.
1C88-ST03, Rev. 2, NSSS Piping: Preoperational Monitoring c.
1017PT03, Rev.1, Ventilation Radiation Monitoring Preoperational Test d.
1E51PT01, Rev.2, Reactor Core Isolation Cooling Preoperational Test e.
1G41PT01, Rev.1, Fuel Pool Cooling and Cleanup Preoperational Test f.
IP42PT01, Rev.1, Component Cooling Water System Preoperational Test
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IP53PT01, Rev. 2, Instrument Air Preoperational Test h.
IP65PT01, Rev.1, Smoke Detection System 1.
1P71AT01, Rev.1, Plant Chilled Water Acceptance Test j.
IP75PT01, Rev.1, Standby Diesel Generators Preoperational Test k.
IP75PT02, Rev.
1, Standoy Diesel Generator Fuel Oil System Preopera-tional Test 1.
1P75PT03, Rev.1, Standby Diesel Generator Starting Air System Preop-erational Test m.
IP75PT04, Rev.
1, Standby Diesel Generator Integrated Sequencing Preoperational Test n.
1P81PT03, Rev. 1, High Pressure Core Spray Diesel Generator Integrated Test o.
1P81PT04, Rev.1, HPCS D/G Prototype Qualification Test p.
1R20PT01, Rev. 1, 480 VAC Preoperational Test q.
1Z92PT01, Rev.1, Emergency D. C. and Control Room Lighting r.
1821PT01, Rev.1, Nuclear Boiler System Preoperational Test s.
1C71PT01, Rev.1, Reactor Protection System Preoperational Test t.
1E71PT01 Rev.1 Integrated ECCS and LOP Preoperational Test u.
1P41PT01, Rev.1, Standby Service Water Preoperational Test v.
1T48FT01, Rev.1, Standby Gas Treatment System Preoperational Test w.
1F41ST01, Rev. 1, Reactor Vessel Flow-Induced Vibration Testing Prior to Fuel Load x.
IP44AT01, Rev. 1, Plant Service Water / Radial Wells System Acceptance Test The inspectors reviewed the results of the above tests to verify the following:
a.
Individual test steps and data sheets were properly initialed and dated.
b.
Data sheets were completed.
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c.
Changes to procedures were made in accordance with pertinent require-ments.
d.
Test changes did not change the basic objective of the test.
e.
Test deficiencies were identified.
The inspector noted minor discrepancies during the results review, which were discussed with licensee representatives and resolved prior to the exit meeting.
Within the areas inspected, no violations or deviations were identified.
6.
Review of Open Items a.
(Closed) IFI 50-416/82-19-03, Incorporation of Design Changes into the Preoperational Tests.
The inspector resolved his question and no licensee action is required, therefore, this item is closed.
b.
(Closed) PRD 82-04, Standby Diesel Generator Starting Air Receiver Sensing Line not Seismically Supported.
The inspector reviewed the comoleted construction work permits (CWP) and had no further questions, therefore, this item is closed.
7.
Startup Procedures The inspector obtained the following startup procedures for review in the regional office:
a.
1-C11-SU-05-0, Rev. 2, Control Rod Drive System - Open Vessel b.
1-C11-SU-05-H, Rev.1, Control Rod Drive System - Heatup c.
1-C91-SU-13-0, Rev.1, Process Computer d.
1-000-SU-99-0U, Rev.1, Plateau Procedure - Open Vessel e.
1-000-SU-99-HU, Rev. 2, Plateau Proceaure - Heatup f
1-F41-SU-34-H, Rev.1, Reactor Internal s Vibration Measurement - Heatup g.
1E61 ST01, Rev.
1, Hydrogen Analyzer Heat Trace and Igniter Special Test h.
1-000-SU-33-H, Rev.1. Drywell Piping Vibration - Heatup i.
1-C51-SU-10-0, Rev.1, SRM/IRM Overlap
l-000-5U-04-0, Rev.1, Full Core Shutdown Margin Demonstration k.
1-000-SU-03-0, Rev. 2, Fuel Loading - Open Vessel 1.
1-C51-SU-06-0, Rev. 2, SRM Performance m.
1-000-SU-17-H, Rev.1, System Expansion - Heatup n.
1-000-SU-02-0, Rev.1, Radiation Monitoring - Open Vessel o.
1-000-SU-01-0, Rev. 2, Chemical and Radiochemical - Open Vessel Testing