ML20010G595

Requests Generic Relief from Hydrostatic Test Requirements of Article Iwc 5000 of ASME Section XI While Performing Work on Main Feedwater Piping Between Steam Generators & First Upstream Isolation Valves.Response Requested by 811015

ML20010G595
Person / Time
Site:	Crystal River
Issue date:	09/14/1981
From:	Baynard P FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
3-091-10, 3-91-10, TAC-04548, TAC-24576, TAC-4548, TAC-46976, NUDOCS 8109220274
Download: ML20010G595 (3)

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?9fM!Df)E RoEQp ecs30 Florida Power C O d PO R A T IO N September 14,1981 File:

3-B-4

1. 3-091-10 O f v

Mr. John F. Stolz E

Operating Reactors Branch No. 4 N

Division of Operating Reactors l~

q hC U.S. Nuclear Regulatory Commission d

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Subj ect: Crvstal River Unit No. 3

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M Docket No. 50-302

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D Operating License No. DPR-72 N

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Relief from ASME Pressure Testing Code

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Dear Mr. Stolz:

The current Inservice Inspection Program at Crystal River Unit 3 is based on ASME Section XI, 1974 Edition through Summer 1975 Addenda.

This letter is to advise you that Florida Power Corporation has determined that a portion of the ASME Section XI Code, concerning " System Pressure Testing" of systems following modifications, repairs, or replacements, is nat feasible for use at Crystal River Unit 3.

Therefore, Florida Power Corporation requests generic relief from the hydrostatic test requirements 4 Article IWC 5000 of ASME Section XI while work is being performed on the main feedwater piping between the steam generators and the first up-stream isolation valves (see attached).

For example, plans have been made to remove and replace a drain valve (FWV-183) during the Fall 1981 Refueling Outage at CR-3.

In this case, conforming to the code is impractical since it would involve pressurization of the steam side of the steam generators. The attendant problems this could cause make this procedure highly urdesirable (e.g., additional main-tenance on the main steam stop check valves, possible water in the turbine).

Additional concerns include unnecessarily degrading steam generator "B" in addition to damage caused by loose parts of the burnable poison rods.

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/ I 8109220274 010914 PDR ADOCK 05000302 p

PDR m.icias vome Jeui inirty-fourth Straat South e P O Box 14042. St. Petersburg Fiorda 33733 e 813-866-5151

I Page'.2 Mr. John F. Stolz-U.S. Nuclear Regulatory Comnission September 8, 1981

~Although modification, repair,or replacement work on the subject section of -

main feedwater piping can not be hydrostatically-tested while maintaining isolation of steam generators.for test purposes, a rigorous non-destructive examination (NDE) program will be carried out for all necessary welds.

N1oridaLPowerCorporationmaintainsthepositionthattheintentoftheASME Code requirement can be met through the-NDE program for the subject feedwater-:

j pipings ection. We consider this to be-a high priority item: and, therefore, l

. request that-your-response be issued.as soon as possible or no-later than f

October 15, 1981.; This will facilitate scheduling of work to be performed

-i during our upcoming refueling' outage.

Very truly yours, FLORIDA POWER CORPORATION A&(

Pwi T

atsy Y. Baynard Manager Nuclear Support Services j

KFP:cmd' i

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