ML20080Q819
| ML20080Q819 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/05/1983 |
| From: | Nix H GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NED-83-500, TAC-52115, TAC-52483, NUDOCS 8310170183 | |
| Download: ML20080Q819 (6) | |
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Gocry a Powcr Compey 333 P<eont Avenue
,; gy Attarta Georia 30~ sod Teirphone 494 526 6526 Ma+rsg Act$ess Po'.t Omco Box 4545 b
Atianta. Gwrga 30302 Georgia Power
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Fower Generation Department NED-83-500 October 5, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HA'ICH NUCLEAR PIANT UNIT 2 PLANS FOR REACIOR CODIANT PRESSURE BOUNDARY PIPING REPIACENENT IN UPC04ING OUIAGE Gentlenen:
By confirmatory order dated July 8,1983, the NRC required that Georgia Power Cmpany (GPC) provide plans for additional inspections of repaired and unrepaired recirculation systen stainless steel piping welds dt* ring the present fuel cycle at Plant Hatch Unit 2.
In addition, that order required GPC to subnit plans for corrective actions and/or modifications at least three months before the start of the next refueling outage.
Exanination plans which counitted to performing inspections om selected piping welds in the Recirculation Systen and Residual Heat Removal (RHR)
Systen were subnitted to NRC by our letter dated August 5,
1983.
The examinations were to be performed during an outage scheduled to begin no later than December 31, 1983.
In lieu of performing the comnitted inspections, GPC has decided to replace the affected stainless steel piping and hereby requests relief fra performing those inspections.
GPC continues to believe that the weld repairs would be fully effective for at least five years and views the replacanent of piping to be an econmic decision rather than a safety concern.
Pursuant to the requirenents of the confirmatory order, GPC hereby provides notification to NRC that plans are being developed for the replacenent of the main recirculation stainless steel piping during an outage tentatively scheduled to begin in January 1984.
Although the det. ailed planning is not yet cmplete, the following is a brief stmnary of the current piping replacenent plans:
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Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 October 5, 1983 Page 'lvo (1) Work Description ne job will consist of cutting the old piping, rsmoving it frm contalment, and welding the new piping in place. 'n e work will be done with all fuel removed fra the reactor vessel, the fuel pool gates in place, and the water level lowered as requirad inside the vessel.
Due to obstructions within the drywell, it is anticipated that a significant amount of structural steel, ventilation equipnent and docting, and electrical quipnent and cable will be 1 moved to provide access for the piping work. Job controls will aisure that any cructures or aquipnent which are reoved are properly restored prior to restarting the unit after work cmpletion.
(2)
Project Organization
Description:
%e job will be performed under the direction and control of a dedicated project organization.
%e Project Manager at GPC has overall responsibility for the job.
Engineering support is being provided by Southern Cmpany Services Incorporated (SGI) through a dedicated engineering staff under an assigned project lead engineer.
SGI will provide engineering services fra their hm e offices and will also provide on-site full shift engineering coverage for the job.
%e reoval/ installation work will be performed by Newport News Industrial (INI). NNI performed a similar task at Niagara Mohawk's Nine Mile Point Plant.
Support services groups will be assigned to the project for its duration to assure continuity of support.
%ese suppo.-t groups will include Quality Assurance, Quality control, Health Physics, and others as needed.
(3)
Design
%e new piping to be utilized will be Nuclear Grade type 316 stainless steel with 0.02% maximm carbon content and nitrogen controlled between 0.06% and 0.10%.
An evaluation of the existing safe-end materials has revealed that they are constructed of a low carbon stainless steel and do not require replacment.
700775'
GeorgiaPbwu A Director of Nuclear Reactor Regulation Attention: Mr. John F, Stolz, Chief Operating Reactors Branch No. 4 October 5, 1903 Page W ree he new Recirculation Syste piping configuration will be slightly different fra the existing syste in that the existing 22-inch header end caps will be eliminated. This is accmplished by using a 22 x 12 inch reducer and a long tangent elbow to replace the old header, outboard risers, and end cap assably.
In addition, the new riser piping will be of a one-piece design to reduce the nmber of welds sployed in the systs.
%e stainless steel portions of the Class 1 RHR Syste piping and the nonisolable portion of the Class 1 Reactor Water Cleanup Systs piping are also scheduled to be replaced during the Recirculation Syste piping reolacment.
We piping material and the new design are being supplied by General Electric Cm pany.
(4) Analyses:
Stress analysis will be performed after the design is finalized and will be fully docmented at that time.
It is expected that the new piping design will reduce the stresses on the piping.
Other analyses such as syste hydraulic characteristics, seismic effects, etc. that may be affected by the new piping gemetry will also be evaluated.
(5) Health Physics:
A full ALARA evaluation will be performed and reasonable steps will be taken to reduce radiation exposures and containation.
(6) Mockups:
Full-scale mockups will be utilized as training aids as demed appropriate.
%is is expected to reduce radiation exposure and reduce outage time by prmoting improved efficiency.
%ese piping replacment plans will be described in greater detail in a report scheduled to be provided to the NRC by mid-Novmber. A draft outline of that report is attached.
% e outage schedule and piping replacment plans were discussed with NRC Region II and NRR managment personnel in a meeting at GPC's offices on Septaber 28, 1983.
700775
GeorgiaPbwer d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 October 5, 1983 Page Four Please be advised that proposed Technical Specification changes to accomodate piping replacanent are forthcaning.
Your cooperation is requested to review and approve the proposed changes in a timely manner to avoid the schedular impact on this voluntary major piping replacenent.
GPC is willing to meet with the NRC staff to discuss our planning /replacanent status and to answer any questions the staff may have.
Should you desire such a meeting, please contact this office.
Sincerely yours, i'
444 --C*
H. C. Nix, Jr.
General Manager JAE/Jt%4nb Attachnent xc:
L. T. Gucwa Senior Resident Inspector J. P. O'Reilly (NRC-Region II) 5 700nS
. Georgia Power A 2
ATTACF9ENT PROPOSE 0 OUTLINE REPORT ON RECIRCULATION PIPIbG REPLACEMENT AT HATCH UNIT 2
1.0 INTRODUCTION
1.1 Purpose 1.2. Scope 1.3 Future Reports
2.0 DESCRIPTION
OF WORK 2.1 Work Sequence 2.2 Advance Preparations and Job Preplanning 2.3 Interference Removal 2.4 Defueling/ Fueling 2.5 Drywell Restoration 2.6 System Testing for Startup 3.0 PROJECT DESCRIPTION 3.1 Overall Organization 3.2 Project Management 3.3 Engineering 3.4 Contractor 3.5 Support Services 3.5.1 Quality Control 3.5.2 Health Physics 3.5.3 Cor.sultants 3.5.4 Licensing 3.5.5 Authorized Nuclear Inspector 4.0 DESIGN DESCRIPTION (To address methods, physical geometry, supports, etc.)
5.0 ANALYSES (To address hydraulic, stress, seismic effects, etc.)
6.0 HEALTH PHYSICS CONTROLS 6.1-ALARA Evaluation 6.2 Airborne Contamination Controls 6.3 Contaminated Material Controls Outside Containment
-7.0 WASTE DISPOSAL 7.1 Waste Minimization 7.2 Piping Disposal uns
GeorgiaPbwer A PROPOSED OUTLINE Page 2 of 2 REPORT ON RECIRCULATION PIPING REPLACEMENT AT HATCH UNIT 2 r
8.0 PIPING INSULATION 9.0 CODES Am STANDAROS 10.0. INSPECTIONS-11.0 TRAINING 11.1 Mockup Training 11.2 Welder Qualification 11.3 Health Physics 12.0 TEMPORARY FACILITIES 12.1 Drywell Ventillation 12.2 Training 12.3 Health Physics 13.0 TECHNICAL SPECIFICATIONS 13.1 Temporary 13.2 Permanent 14.0 SAFETY ANALYSIS 4
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