ML19220C322
| ML19220C322 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/05/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| 740306, NUDOCS 7904300387 | |
| Download: ML19220C322 (3) | |
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Voss !. Moore, Assistant Director for Light Wa ter Reactors. Group 2 Directorate of Licensing MI*RCPOLIT/Ci EDISCN CC'GA';Y
~RREE MILE ISla.D - U'!!T 2 - ACC2?TX'CI' R 7IEW, DOCTH NO. 50-320
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Plant Kane: Three File Island, Unit 2
, f. 'r Suppliers: nabccck a Vilcox; Burns & Roe Jociet :iumber:
50-320 Respcnsible 3 ranch ard Project Manager: LW2 2-2; r. '4ashburn
?.cquested Cccpletion Date: March 5,.1974 Description of 2esponse: Acceptance Review Review Status: Complete In accordance with the schedule for Acceptance Review, February 14, 1974, Washburn to "R A/D's, the Materials Engineering Branch, Directorate of Licensing, has conducted an Acceptance Review of the subject applicatien.
The following is a si m e y of cur review of the ?SAR.
a.
Areas of Review:
Oct. 1972 F"AR & Tech Spe:
SAR Standard MTE3 Areas of Reviev Sections Format neviewed 5.2.3.1 Material specifications 3.2.3.1. Table 5.2-11 5.2.3.2 Co=patibility with reacter coolant 5.2.3.2, Table 5.2-12 5.2.3.3 Coc:patibility with external insulation and envirornental atmosphere 5.2.3.3 5.2.3.4 Chemistry of raactor coolant
- 5. 2.3.4, 7,f 3 /. 5 5.2.4.1 Comp 11ance with code requirements 5.2.4.1 Table 5.2-1
.5.2.4.2 Acceptable fracture energy levels 5.2.4.2 5.2.4.3 Operating limitations during haatup, cooldown, and hydrotest 5.2.4.3, TS 3.1.2 5.2.4.4 Material surveillance program 5.2.4.4 5.2.4.5 Capability to anneal 5.2.4.5 5.2.5' Austanitic stainless steel 5.2.5 5.2.6 ru=p flyvleels 5.2.6, 5.5.1.5 5.2.7 ROF3 leakage detection systems 5.2.7, TS 3.1.6 5.2.3 Inservice inspection program 5.2.3, TS 4.2 b.
Guides and Othe-Require:unta Used:
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(1) Stancard Format SAR Guide, dated October 1972; (2) 10 CT-2, 50. A&. M den C
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Tichard C. DeYoung
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Mfz Section.II. Enised fracture toughness r 21e: Eur:ncr Addet.da,197":, including appendix G:
(4)
A5'C Section '(I, Inservice Inenmtlan, 197' Editten.1972 *!intar Adderd.a. and 1973 Su=:.cr Addenda; (3) ASr' hecificati. n 105-73, surveillance Pren:r :
(6) Regulatory Guide 1.14, Funo Flywheels,
(7) Regulaterv Gide 1.31, Rev.1, Control cf S tainless S teel Weldine:
(S) Re;ulatorf Guide 1.36, :fornetallic Thernal Insulation for Austarmtic Stainless Steel:
(9) Regulatory Guide 1.44, Centrol of the Use of Sensitized Stainlass S teel:
(10) Regulatory Guida 1.45, RC?3 Leakage Detection Syste.;
(11) Regulatory Guide 1.51 Inservice Inspectica for Class 2 & 3 Componants.
c.
Additional Infornation Required:
Additional infor=ation vill be needed in the areas of:
Inservice Inspection of Code Class 2 & 3 systems, Inservice Testing of Code Class 1, 2, and 3 Punps and 'Talves, and conformance to Regulatory Ouide 1.14 Reactor Coolant Punp Flywheel Integrity.
d.
Assessnent of Acceptabi' ity:
The 7SAR contains appre: inately 75% of the Materials Engineer 1rg Branch's required infon.ation.
e.
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Conclusion:==
We find the infornation sub::dtted in the JSAR sufficlently cenplete that an evaluation can be perferned with ers round of quagens.
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R. R. Maccary, Assistant Director for Erg N ering Directorate of Licenair4 cc:
S. E. Hanauer, DETA J. M. Hendria, L A. Gianbusso, L V. G. Mcdonald, L S. Varga, L K. Kniel, L B. Washburn, L S. S. Pawlicki, L V. S. Hazelton, L r) 7.A fl
-*u M. E. Fairtile, L jfrEB:L /,yh-. 5 "I
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.y M3Fairtile/g LPn reiten SSPaw d carv
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r METECPOLITA'; EDISC: C CYP A.'~f THREE MILE ISL.C;D, U'!IT 2 DCCKET NO. 50-3!C PRELIMINARY REQUEST FCR ADDITICNAL I';7CRMTION MATERIALS ENGINEERING EPU!CH, L REACTC? CCCL.C;T SYSTE'4 Inservice Ins ection Procram of ASME Ccde Class 2& 3 Cceronen ts Frovide s f ficient infor:ation about your proposed ESF inservice inspecticn program to indicate that the program will provide a degree of assurance of sys te= integrity comparable to the program recc : ended in Regulatory Guide 1.51, " Inservice Inspection of ASME Code Class 2 and 3 huclear Power Plant Ccapenents," May 1973.
Inservice Tes tin 2 of Pures and Valves Provide your program for the inservice tes ting of pumps and valves that are part of ASME Eciler and Pressure Vessel Ccde,Section III, Class 1, 2, and 3 safety related systems. Furnish sufficient infer ation to indicate that the pump tes t progra= follows the provisions of ASME Section XI, Su=er 1973 Addenda, Subsection IWP, and that the valve test progras follows Subsec tion I'A'.
Identify all pumps and valves in the program. The component identification cay be either in tabular form or ref erence P&I drawings, or a ecebination of each nethed. Each valve identity should also include the IW7-2101 Category designation.
F1.aheel Inteeritv Provide sufficient information about the primary coolant pu=p-=otor flywheels to indicate the da. gree of flywhael integrity ce= parable to the program ree-c = ended in Regulatory Guide 1.14, " Reactor Coolan Pu=p Flywheel Integrity."
Ce tober 27, 1971.
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