ML20028H038

Lists Issues to Be Addressed During Meeting Re NRC Bulletin 88-008 on Thermal Stresses in Piping Connected to RCS

ML20028H038
Person / Time
Site:	Prairie Island
Issue date:	09/27/1990
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Parker T NORTHERN STATES POWER CO.
References
IEB-88-008, IEB-88-8, NUDOCS 9010050273
Download: ML20028H038 (5)

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NUCLE AR REGUL ATORY COMMISSION i 1, W AstDNGTON, D c 20s%

d September 27, 1990 8

-g....3 Docket Nos. 50-282 and 50-306 1

o Mr. T. M. Parker, Manager Nuclear Support Service Northern States Power Company-414 Nicoliet Mall.

Minneapolis, Minnesota 55401

SUBJECT:

RESPONSE TO BULLETIN 88-08

" THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS" RELATED TO THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NOS. 1 AND 2.

By letter dated September 30,-1988 and June 2, 1989 you provided results of stress analyses of the piping systems existing at the Prairie Island Nuclear Generating Plant Units Nos. I and 2.

The results-of analyses are in response-to our Bulletin 88-08 dealing with thermal stresses in pipes connected to reactor coolant system.

The purpose of this letter is to request a meeting-with cur staff te discuss an evaluation of your response.

We request this meeting.to take place at the NRC within 30 days from this letter date, and the specific time and date to be coordinated by telecon.

Our review of your response identified the following issues that you should address during the meeting.

1.

There is no experimental assurance that the lift check-valve in the auxiliary spray-line does not experience chattering under very low fluid flows, 2.

'The. alternating ~ stresses should be based on the material properties for stainless steel of ANSI B31.1, since all piping in these plants were initially designed ander this code.

The mean coefficients of-

,1 thermal expansion are different from those in ASME.Section III, 1983.

3.

The fatigue lives should be calculated based on the ASME Section-III fatigue data at the mean temperature of the " tee" connection.

4.

The time to crack initiation depends-on the age of the plant.

The licensee has not addressed this item, but staff calculations indicate that crack initiation time decreases significetly with plant age.

5.

The NUTECH procedure is based on.:nethodology which was initially applied by GE to the evaluation 'of cracking in BWR feedwater nozzles.

Although we find this methodology acceptable, and it

appears to be applicable'to the " tee" connection, there are a number

'l of uncertainties such that the actual margin of safety in this application cannot be ascertained without extensive experimental verification.

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L E.n lThnlicerisee has prorcsed perforr:ing' the -llDE of +tbe-_ weld jiinling the.

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6uxiliary sprsy.-.litie to ithe _" tee"! tonnect ion.

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linitiates.s Itltherefore. appears--that the entire " tee"Tshould be

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llSP hasistatedithat'.the isolation' valves!are boundary / valves in the-

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local: leak = rate test which is perfornied.dur,ing each refueling' outage?

_on,the cha'rging' line. containment _ penetratiorG It'is not clear;that;.

thisitest can quentify:the. interrcl leakage occurring thru _the valves.:.

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This licensee has proposed' performing the NDE of. the weld joining:the F

auxiliary sprayiline'to the " tee" connection. ;From-the NUTECH analysis and-procedure it-is+not clear where the cracking actually:

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initiates.H It.therefore appears =that~the entire " tee" should be examined and no.t only the weld.-

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Sincerely,.

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'DominicC.Dilanni, Project l Manager Project Directorate III-1 Division of Reactor Projects -:III.,

IV, V-& Special Projects 3 Office of' Nuclear Reactor RegulationL

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Gerald Charnoff, Esq.

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Dr. J. W. Ferman Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155 Mr. E. L. Watzl, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55009 Joseph G. Maternowski-tssister.t Attorney _ General Environmental Prctection Division Suite-200 520 Lafayette Road St. Paul, Minnesota 5515E U.S. Nuclear Regulatory Commission Resident Inspector's Office 1719 Pakonede Drive East Uelch, Minnesota 550P,9 Regional Adninistrator, Pegion III U.S. Nuclear Regulatory Commission Office of Executive Director for Operaticos

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The licensee has proposed perforodng the NDE of the weld joining the auxili6ry sprey line to the " tee" connection, froc, the liUTECH analysis 6 tid procedure it is nct clear where the crecHog 6ctually.

i initietes, it therefore appears that the entire " tee" should be' l

exeniried and not only the weld.

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fiSP.has stated tb61 the isolation valves 6re boundary v61vts in the L

1ccel le6L rete test which is perforned'during each refueling out69e on-the ch6tging '11r.t- (ontainntr.t penetr6 tion.

It is not clear that this test cari e,uor.tify the interr.tl.le6Lege occurring thru.the valves..

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