ML20137R867

Forwards Request for Addl Info Re BWR Feedwater Nozzle Cracking Analysis.Addl Info Requested within 45 Days of Ltr Receipt to Complete Review

ML20137R867
Person / Time
Site:	FitzPatrick
Issue date:	11/20/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
NUDOCS 8512060101
Download: ML20137R867 (4)

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November 20, 1985 DISTRIBUTION C Docket File, ~

Docket No. 50-333 'NRC'~PDR Local PDR ORB #2 Rdq 4 Thompson OELD Mr. John C. Brons SNorris Senior Vice President - 4 Abelson Nuclear Generation ELJordan Power Authority of the State JPartlow of New York BGrimes 123 Main Street ACRS (10)

White Plains, New York 10601 Gray File

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION -

BWR FEEDWATER N0ZZLE CRACKING ANALYSIS Re: James A. FitzPatrick Nuclear Power Plant We have reviewed your submittal dated August 20, 1983 concerning the analysis of feedwater nozzle cracking at FitzPatrick and have identified the need for the enclosed additional information to enable us to complete our review.

We request that you provide us with the r.ecessary information within 45 days of receipt of this letter.

i The reporting and/or recordkeeping requirements contained i'n this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by/

$$k20ggggggggggj33 Domenic B. Vassallo, Chief S PDR Operating Reactors Branch #2 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page DL RB#2 0 ) DL:0RB#2 S  : as HA son DVassallo 11/q/85 11/#/85 11/f8/85

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Mr. John C. Brons James A. FitzPatrick Nuclear i Power Authority of the State of New York Power Plant ,

cc:

Mr. Charles M. Pratt Mr. Jay Dunkleberger Assistant General Counsel Division of Policy Analysis Power Authority of the State and Planning of New York New York State Energy Office 10 Columbus Circle Agency Building 2 New York, New York 10019 Empire State Plaza Albany, New York 12223 Resident Inspector's Office U. S. Nuclear Regulatory Commission Regional Administrator, Region I Post Office Box 136 U.S. Nuclear Regulatory Commission Lycoming, New York 13093 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. A. Klausman Mr. Radford J. Converse Vice President - Quality Assurance Resident Manager Power Authority of the State 4 James A. FitzPatrick Nuclear of New York Power Plant 10 Columbus Circle Post Office Box 41 New York, New York 10019 Lycoming, New York 13093 Mr. J. A. Gray, Jr. Mr. George Wilverding, Chairman Director - Nuclear Licensing - BWR Safety Review Comnittee Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street White Plains, New York 10601 White Plains, New York 10601 Mr. Robert P. Jones, Supervisor Town of Scriba R. D. #4 Oswego, New York 13126 -

Mr. Leroy W. Sinclair Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Mr. M. C. Cosgrove Quality Assurance Superintendent James A. Fitz'atrick Nuclear Power Plant -

Post Office Box 41 Lycoming, New York 13093 i - -- - ,

1 REQUEST FOR ADDITIONAL INFORMATION REGARDING BWR FEEDWATER N0ZZLE CRACKING ANALYSIS JAMES A. FITZPATRICK NUCLEAR POWER PLANT i By letter dated August 20, 1985, the licensee submitted three reports concerning the analysis of feedwater nozzle cracking for the FitzPatrick facility. The following is a Request for Additional Information related to each of these reports.

! A. " James A. FitzPatrick Nuclear Power Station Feedwater Nozzle Fracture Mechanics Analysis to show Compliance with NUREG-0619,"

General Electric (GE), NEDC-3G799-P/DRFB13-109-3, December 1984.

'1. Page 3-1 It is unclear how 27 and 28 startup/ shutdown events were obtained from Figure 3-1 and reference 2 respectively. It is also unclear whether the startup data shown in Tables 3-1 through 3-3 were used in the analysis. Provide a more detailed discussion on the calculation and application of the thermal events / cycles in the analysis.

2. Page 4-1 f

The report stated that the heat transfer coefficients were taken i

from the GE analysis (NEDE-21812). Justify the fact that the generic heat transfer coefficients used in the GE analysis satisfy the plant i specific conditions at FitzPatrick.

j. 3. Page 5-1 The report stated that pressure stresses require a scaling factor ~

based on a three-dimensional analysis. Cite the reference for the

, three-dimensional analysis in the report. Provide the scaling factor l and the justification for using it in the analysis.

l l B. "Feedwater Nozzle Rapid Cycling Fatigue Analysis James A. FitzPatrick i Nuclear Power Plant," General Electric, MDE-21-0185/DRFB13-109-3, January 1985. -

1. Page 9 Cite the reference for the GE feasibility study that was mentioned.

This study indicated that seal refurbishment which includes restoration of the initial seal radial gap and axial gap is preferred. This new concept results in a lower number of seal refurbishments and better feedwater nozzle protection than that offered by.the GE analysis.

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2. Page 21 The two curves in Figure 5-1 show that the new seal refurbishment concept has a higher usage factor than that of the original seal e refurbishment concept. Explain why the new seal refurbishment l concept is preferred if it results in a higher usage factor.

C. " Effects of Reactor Water Cleanup Reroute on Feedwater Nozzle Fatique l Usage James A. FitzPatrick Nuclear Power Plant," General Electric, MDE-22-0185/tRFB13-109-3, January 1985.

1.  ? age 8 The report stated that reactor water cleanup (RWCU) flow is a small portion of the total feedwater flow.

Provide the flow rate of RWCU and feedwater system under startup, shutdown, and scram conditions.

2. Page 13 The evaluation presented in NEDE-21821 showed that the largest improvement in the crack initiation usage factor would be achieved by rerouting RWCU, i.e., a reduction in usage factor from 0.70 to 0.46; however, in the FitzPatrick analysis, the reduction in usage factor is from 0.814 to 0.801. Explain the fact that the FitzPatrick analysis has such a low reduction compared to the NEJE-21821-02 results.

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