ML19319C778

Forwards Request for Addl Info Re Util 770414 Request for Relief from ASME Code Requirements Re Inservice Insp

ML19319C778
Person / Time
Site:	Crystal River
Issue date:	06/14/1977
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Rodgers J FLORIDA POWER CORP.
References
TAC-04548, TAC-4548, NUDOCS 8003040739
Download: ML19319C778 (4)

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, 5 ',, v. ray,.y:f ycur re'ucst for relief fram certain f&E Code racJira-r,:nts fer inscreice inspcctica et Crystal River l' nit " 2.s described in

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ENCLOSURE-l_

REQUEST FOR ADDIT.'ONAL INFOR."ATION

-FLORIDA POWER CORPORATION tlMI'AL RWER U.m T I:0. 3 '

O(TCTET iM:3ER 50-3LT2-1.

' Referring to Category B-D, Reactor Mozzles, describe the preservice inspection (base line) which has been performed.

' Indicate the' volume of weld and base material examined in

-each of the nozzles.

2-Clarify the alternate examinaticn proposed in lieu of the ASME Section XI requirement for examination of the inlet and cutlet nozzles.

Specifically, clarify the statement " Examine bott, cutlet nozzles plus accessible portion of vessel weld, sitell to fiange, from flange surface by end of firs; third of the interval."

Estimate the volume of each nozzle and weld to be examined, and relate the test method to the base line

. inspection.

The FSAR implies that nozzle welds will be inspected from outside the vessel.

If this is the case, removal of the core barrel shculd not be required.

Explain.

3.

Referring to Category B-G-2, the Code requires visual examination of 100"; of the CRDM bolts and nuts to head flange during each inspection interval with the bolting either in place or removed.

The licensee pro?osed changing the examination to 100'; of the bolts and nuts in 10'; df the peripheral CRDM

-lecation with the bolts removed.

State whether accesst iimit-ations prevent visual inspection of the remaining bolts in place to the extent necessary to verify absence of bolt failure or major distress.

rigure 4-4 ff the FSAR shows a sdpport skirt attached to the reactor vessel.

erovide a detailed descriptica of the vessel supports, and tn,e proposed inservice examination procedure to ccmply with Category B-H,Section XI requirements.

5.

The preservice inspection of Crystal River Unit "o.

3 was conducted to.confera to the general requirements of the AS:'.E Code,Section XI,1971 Edition, including Addenda through Summer 1972.

Provide information to show the weld area and extent of volumetric examina~ tion conducted during the pre-service; inspection on each Category B-J weld for which relief is requested.

Indicata deviation in the proposed alternate examination from the preservice inspection, n

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6.

Gecmetry' and design of the system is cited as Justifictricn

'for using surface _ (dye penetrant) in lieu of volumetric

. examination _for welds in Category B-K-1, " Integrally Welded Supports for-Piping, Valves and Pumps." Provide typical.; eld joint details of: integrally welded supports for which

- alternate _inspecticn is proposed.

Describe the extent of preservice inspection that was per-7.

formed on Class 2 ccmponents for which relief is recuested.

. Provide better de.'inition (in terms: of percentage weld area /

volume'excmir.ed) where ccmmitments are made to do a "best effort" scan.

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