ML19319D263
| ML19319D263 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/08/1977 |
| From: | Pawlick S Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130902 | |
| Download: ML19319D263 (4) | |
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,' HEM)RANDUMlFOR:' John F. Stolz, Niief '
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Light Water Reactors Branch No.1 Division.of Profect itansge ent FRCit:
- 3. S..Pawlicki, Chief itaterials Engineering Branch
SUBJECT:
CRYSTAL RIVER, UNIT NO. 3 (CL) REQUEST T02 M 1VER OF CERTAIN ASME CODE SECTION XI INSErC CE IHS?ECTION
_ REQUIREMEiiT5.- TAC 4543 (MS)
Plant Mra: Crystal River, Unit Mc. 3 (OL)
Dochet huncer:
50-302 Responsible Sranen:
LWR No. 1 Project Manager: - J. Angelo, X27391
. Description of Recuest: _Reviets and evaluate the licensce's ret.iest for waiver of certain requireacnts of the ASME
-Section XI CodeL cn intervice. inspection as i
described lin licensce's letter dated
.~ April 14,1977. Also, provide, as appropriate, F
.a safety evaluation :uppertir.g any vatver that may be granted from the requirements of d, m. -
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". The Haterials: Integrity Section of'the Materials Engineering. Branch 1hasJ reviewed the recuest-for rdM from certain ASME Code 01974. Edition,-
-o 7 including Sux:ct 1975 Mdanda." Inservice Inspectica requirements fcr Nr 2.UCrystal River Unit
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.e Insufficient information is provided by tha licensee for an evaluation of the request at this time. _We have prepared a-list of questions to
. clarify the information.
Our questions are attached.'
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.5. S.iPawlicki, Chief
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Enclosure:
As stated cc w/anc1:
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT NO. 3 (OL)
DOCKET NUMBER 50-302 REQUEST FOR WAIVER OF REQUIREMENTS OF SECTION XI ASME CODE (TAC-4548) 121.0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121.1 Referring to Category B-0, Reactor Nozzles, describe the preservice inspection (base line) which has been performed.
indicate the volume of weld and base material examined in each of the nozzles.
121.2 Clarify the alternate examination proposed in lieu of the ASME Section XI requirement for examination of the inlet and outlet nozzles.
Specifically, clarify the statement " Examine both outlet nozzles plus accessible portion of vessel weld, shell to flange, from flange surface by end of first 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 frcm outside the vessel.
If this is the case, removal of the core barrel should not be required.
Explain.
121.3 Referring to Category B-G-2, the Code reouires visual examinati n of 100% of the CRDM bclts and nuts to head flange during each inspection interval with the bolting either in place or removed.
The licensee proposed changing the examination to 100% of the bolts and nuts in 10% of the peripheral CRDM location with the bolts removed.
State whether access limit-ations prevent visual inspection of the remaining bolts in place to the extent necessary to verify absence of bolt failure or major distress.
121.4 Figure 4-4 of the FSAR shows a support skirt attached to the reactor vessel.
Provide a detailed description of the vessel supports, and the proposed inservice examination procedure to comply with Category B-H,Section XI requirements.
121.5 The pr'eservice inspection of Crystal River Unit No. 3 was conducted to conform to the general requirements of the ASME Code,Section XI,1971 Edition, including Addenda through Summer 1972.
Provide information to show the wald area and extent.of volumetric examination conducted during the pre-service inspection on each Category B-J weld for which relief is requested.
Indicate deviation in the proposed alternate exam.ination from the preservice inspection.
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,, 121.6 Geometry and design of the system is cited as justification for using surface (dye penetrant) in lieu of volumetric examination for welds in Category B-K-1, " Integrally Weldad Supports for Piping, Valves and Pumps." Provide typical weld joint details of integrally welded supports for which alternate inspection is proposed.
121.7 Describe the extent of preservice inspection that was per-formed on Class 2 components for whicS relief is requested.
Provide better definition (in terms of percentage weld area /
volume examined) where commitments are made to do a "best effort" scan.
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