ML17264A815
| ML17264A815 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/31/1997 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9702110454 | |
| Download: ML17264A815 (5) | |
Text
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REGULATOI INFORMATION DISTRIBUTIONa'.STEM (RIDE)
ACCESSION NPR:9702110454 DOC.DATE: 97/01/31 NOTARIZED: NO FACIL!50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
Project Directorate I-1 (PD1-1)
(Post 941001)
SUBJECT:
Provides util response to 9GC924 request for SW heat exchanger thermal performance test reviews
& plans for completing initial thermal performance test program.
DISTRIBUTION CODE:
IEOID COPIES RECEIVED:LTR I ENCLj SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET G
05000244 05000244 E
RECIPIENT ID CODE/NAME
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1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
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January 31, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Letter from Lawrence T. Doerflein, NRC, to Robert C.
- Mecredy, RGE,
Subject:
"NRC Integrated Inspection Report 50-244/96-06 and Notice of Violation", dated September 24, 1996 R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear M=. Vissing:
The purpose of this letter is to provide the RG&E response to the subject letter's request for service water heat exchanger thermal performance test reviews and our plans for completing the initial thermal performance test program.
This response is provided in Attachment A.
Very truly yours, Attaqhment REJK444 Robert C.
Mec edy xc:
Mr. Guy Vissing (Mail Stop 14C7)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector j ~ /
9702110454 970i3i PDR ADOCK 05000244 P
Attachment A The initial test program for Ginna was intended to perform three annual tests.
During Engineering review ofthe performance test results, occasional data anomalies were apparent for some ofthe heat exchangers.
It was decided that additional tests would be performed for these heat exchangers as necessary.
A total of56 performance tests have been completed, covering 17 safety-related heat exchangers served by service water.
The completion status ofthe initial test program is as follows:
A.
Standb Auxilia Feedwater SAFW Pum Room Coolers A and B The initial test program for SAFW pump room coolers A and B included three performance tests - one each during 1992, 1993, and 1994.
Subsequent to the 1993 test, preliminary analysis ofthe test data, indicated that the coolers may require maintenance.
A non-conformance report was initiated which resulted in maintenance cleaning and gasket replacement in these coolers. A test was completed in 1994 after this maintenance.
The data from all three tests has been evaluated and documented in one test report, The conclusion ofthis test report is that the SAFW Pump Room Coolers were able to perform their safety-related heat transfer function.
Evaluation ofthe test data has proven inconclusive in establishing a periodic long term testing frequency; therefore, an additional thermal performance test willbe completed during the spring of 1997.
B.
S entFuelPool SFP HeatExchan erB The initialtest program for SFP HXB included four performance tests - one each during 1993, 1994, 1995 and 1996.
Test reports have been completed for the 1993, 1994, 1995, and 1996 tests.
Based on Engineering analysis ofinitial program test results (1993 - 1995 tests), new temperature instrumentation was permanently installed and an improved test methodology was employed for the 1996 test. Test accuracy was greatly improved. The 1996 test report has concluded that the actual fouling ofthis heat exchanger is significantly below the design value and that this heat exchanger is capable ofperforming its intended safety-related heat transfer function.
The initial test program for this heat exchanger is considered complete, and a long term periodic test frequency has been established.
Page 1 of 3 NRC RESP.DOC
Attachment A C.
CRFCMotorCoolersA B C and D The initial test program for CRFC motor coolers A, B, C, and 0 included four performance tests - one each during 1992, 1993, 1994, and 1995.
CRFC motor coolers were replaced with new coils in 1992.
The data from all four tests has been evaluated and documented in test reports.
The conclusion ofthese test reports is that the CRFC MCs were able to perform their safety-related heat transfer function.
Evaluation ofthe test data has proven inconclusive in establishing a periodic long term testing frequency; therefore, an additional thermal performance test willbe completed during the 1997 outage.
D.
Containment Recirculation Fan Coolers CRFC A B C and D The initial test program for CRFCs A, B, C, and D included this~ performance tests - one each during 1993, 1994, and 1995.
CRFCs A, B, C, and D were replaced with new enhanced design coils in 1993.
The enhanced design included a slight increase in heat transfer capacity.
The 1993 test was completed after replacement ofthe coils.
The data fmm all three tests has been evaluated and documented in test reports.
The conclusion ofthese test reports is that the CRFCs were able to perform their safety-related heat transfer function. For the 1995 test, analysis ofthe data for the "A"and "C" CRFCs concluded that these heat exchangers may have had fouling factors higher than design values; therefore, additional analyses were performed to evaluate the effect on the plant of these higher fouling factors.
The conclusion ofthe additional analyses was that the CRFCs would have been capable ofremoving sufficient heat to maintain the plant within analyzed and licensed conditions.
Analysis ofthe data for the 1994 test concluded inconsistencies in the test data precluded meaningful analysis ofthe data.
Therefore, the operability ofthe CRFCs for 1994 has been judged acceptable based on interpolation of the 1993 and 1995 test results and analysis.
Evaluation ofthe test data has proven inconclusive in establishing a periodic long term testing frequency; therefore, an additional thermal performance test willbe completed during the 1997 outage.
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NRC-RESP.DOC
Attachment A E.
Diesel Generator G Jacket Water Heat Exchan ers A and B and Lube Oil Coolers A and B The initial test program for DG Jacket Water/Lube Oil Coolers A and B included three performance tests - one each during 1992, 1993, and 1994.
The data from these tests has been evaluated and documented in test reports.
The conclusion ofthese test reports is that the coolers met their design requirements and would have been able to perform their intended safety-related heat transfer function.
Each ofthe DG coolers was re-tubed during the 1996 outage, thus restoring the coolers to an essentially clean condition (0 fouling) and restoring margin to their thermal performance.
A baseline thermal performance test was completed following the tubing replacement.
The test data is currently being evaluated and is scheduled for completion by the end ofFebruary 1997.
Evaluation ofthe test data has proven inconclusive in establishing a periodic long term testing frequency. A further assessment wilibe made when the 1996 test data analysis is completed.
An additional test ofthese heat exchangers is planned in 1997.
F.
Com onent Coolin Water CCW HeatExchan ers A and B The initial test program for CCW HXA and B included three performance tests - one each during 1993, 1994, and 1995.
The data from all three tests has been evaluated and documented in test reports. For 1993 and 1994, data analysis concluded that the CCW HXs were capable ofperforming their safety-related heat transfer function. For 1995, data analysis concluded that the "B"HX was capable ofperforming its safety-related heat transfer function. Analysis ofthe data for the "A"heat exchanger concluded that this HXmay have had a fouling factor higher than the design value; therefore, additional analyses were performed to evaluate the effect on the plant ofthe high fouling factor for the "A"HX. The conclusion ofthe additional analyses was that the "A"HXwould have been capable ofremoving sufficient heat to maintain the plant within analyzed and licensed conditions.
Preliminary analysis oftest data indicated there was a possibility ofdegraded heat transfer capability; therefore, CCW HXA and B were eddy-current inspected and cleaned during the 1996 outage.
Evaluation ofthe test data has proven inconclusive in establishing a periodic long term testing frequency; therefore, an additional thermal performance test willbe completed during the 1997 outage.
Page 3 of 3 NRC-RESP.DOC