ML17250B195

Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept

ML17250B195
Person / Time
Site:	Ginna
Issue date:	06/05/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
RTR-NUREG-1344 GL-89-08, GL-89-8, NUDOCS 9006130305
Download: ML17250B195 (5)

Text

J ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9006130305 DOC.DATE: 90/06/05 NOTARIZED: NO DOCKET "

FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3

SUBJECT:

Responds to GL 89-08, "Erosion/Corrosion Induced Pipe Wall Thinning."

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL .ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 5 5 INTERNAL: NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTS B1 1 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC B 1 0 OGC/HDS2 1 0 ~G ILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAFEEl CONTACT THE DOCUMENT CONTROL DESK ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

ICi ////// /////S/8 Igl // ////I/////II/I ROCHESTER, ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, 7EEEPHONE AREA COOK 7IK 546.2700 June 5, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Response to Generic Letter 89-08 Erosion/Corrosion Induced Pipe Wall Thinning dated May 2, 1989 R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In the July 21, 1989, RGE letter relative to NRC Generic Letter 89-08, we stated that the following items would be implemented prior to the completion of our 1990 Refueling Outage:

Review and revise our Erosion/Corrosion Monitoring Program (described in USNRC Bulletin 87-01 response transmittal from R. W. Kober to W. T. Russell, dated 9/8/87) as necessary. The revision would include the development of formalized procedures and/or

.administrative controls to assure that erosion/

corrosion does not result in unacceptable degradation of the structural integrity of high energy carbon steel piping system". The revised program would include use of the NUMARC program or another equally effective program.

RG&E has completed the following:

The existing RG&E Erosion/Corrosion Program has been reviewed and revised as follows:

RG&E has developed an Erosion/Corrosion Program for single and two phase systems consistent with the requirements of NUREG-1344 and NUMARC Erosion/Corrosion report, dated June ll, 1987. This program is documented in the Ginna Station Erosion/Corrosion Program Manual, April 1990.

900bi30306 90060 PDR ADOCK 05000244 PDC

The RG&E Erosion/Corrosion Program Manual includes the following:

1) Frequency of Inspection Criteria

2) Acceptance Criteria

3) Inspection/Expansion Criteria

4) Repair/Replacement Criteria

5) Corrective Action The following are included in the controlled RG&E Erosion/Corrosion program:

1) A list of systems for inclusion in the program has been identified. These systems include Main Steam, Condensate, Feedwater, Steam Generator Blowdown, Extraction Steam, Turbine Gland Steam, Gland Sealing Water and Moisture Separator Reheater system piping. CHEC/CHECMATE analyses have been performed for the systems.

2) The results of CHEC/CHECMATE analyses were combined with historical data, and a list of those components most susceptible to Erosion/Corrosion wear was developed. This list of components defines the scope of the E/C monitoring program for Ginna. From this list, a population of components were identified for examination during the 1990 Refueling Outage. Where the acceptance criteria were not met, corrective actions in the form of repairs and replacements were implemented. Other components will be scheduled for inspection during successive outages as a function of wear rates and conformance to acceptance criteria.

Although the program described above has been implemented, RG&E has not yet fully completed the administrative procedures.

Currently, RG&E procedures are being developed to administratively control and implement the developed program.

The procedures will define functional group responsibilities and interactions and administrative control of the program.

The procedures for process control and administrative control will be completed by 10/30/90 and will be fully in effect to be utilized for the 1991 Outage inspection.

Very truly yours, Robert C. Mec y Division Manager Nuclear Production

xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

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