ML19220B919
| ML19220B919 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/30/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904270658 | |
| Download: ML19220B919 (3) | |
Text
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Dockat So. 50-320 70ss A. Moore, Assistant Director f or Light Water Reactors, Grcup 2 Directorate of Licensing METROPOLITAN EDISON COMPANY, M MTT2 ISIMD, UNIT 2 (OL),
DCCI?T 50. 50-320 Plant Nane: Three Mila Island, P2it 2 Suppliers: Babcock ~ Wilcos; Burns and Roe Docket 5tnber: 50-320 Responsible Branch and Project Manager:
L'*R 2-2 ; 3. Washburn Requested Coc:platien Date: August 2, 1974 Description of Response: Questions - First Round (Q-1)
Revieu Status: Infernation Requested Information t,ulnitted by the appt b nt in the FSAR has bee.n reviewed by the Materiala Engineering Branch, Directorate of Licensing. Adequate responses to the ene%ed request for additional infoncation are required before vu can eceplete our evaluation. In order to untain the current schadule, the applicant should respond to this request by October 18, 1974.
yp ige = t E'
R. R. Maccary, Assistant Director for Ing1 earing Directorate of Licensing Pnelnttura Materials ?ngineering Br w h Request for Addir % =1 Information (Q-1) 6 cc v/ enc 1:
DISTRI3CTION:
S. H. Hnnuer, DET.A Docket File (50-320)
- 7. Schroedel, L L Read.ing File A. Ginsbusso, L MTE3 Tiles W. G. Mcdonald, L S. Varga, L
[ D ;r'a, t 79'O4270658 S. S. Pavlichi, L 84-041 W. s. saze1too, L K.. G. Hoge, L L:F"E3 L:MIIB[M
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_7] A. /74 7/.3 Q74__ _ _7/fJ/74_ _ _1/W/ 74 Form AEC.313 (Re. M3) AZCM O240 2 v. s. sow s== m s.=v..imv as ca rse as i,n. sa s ee
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12.1 Frovide a list of any cold worked sustenitic stainless steels, (4.2.2) precipitation hardening stainless steels er hardenable martensitic stainless steels having yield strengths greater than 90,0C0 psi used for cenponents of the reactor vessel internals. If any such steels are used, provide assurance that they will be cenpatib'.e with :he reac:cr ecolant.
12.2 In Sectica 5.2.3.3 of the FSAR ycu s: ate that the reacecr (5.2.3.3) ccolant in.ulatica is all retal reflective insulation. Describe t.u.,.
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chloride, fluoride, and silicate centent.
Indicate the degree of corfor:ance with Regulatory Guide 1.36, "Nenne:alli:
Therral Insulatica for Austenitic Stainless Steel," da:ed February 23, 1973.
Include detailed infcr:atica en the nature or w...e c,.,,.,,(a) c a,s.
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this respect are the types of cements that are field =ixed for applica:ica.
12.3 In Section 5.2.4.3 of the FSAR ycu state that Appendix G :o (5.2.4.3)
Sectica III was used as a guide in estabitshing operating p r e s s t.,.e c..,r e, a..,,., 1 e
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Provide us a copy of the report, 3ra-100'.6, er :he information contained in the report, for our review and evaluation.
In addition, the temperature-pressure licitations for core operation cust confern to the requirements of Appene.a.x u.
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(5.2.4.4) lance progra: to ASTM E-155-73 and A.ppendi,. H, 10 CFI 50 and p,o,.,4.; e,3t - < :<
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12-2 12.7 Ycu state in Section 5.2.7.3 cf the FSAR that the taximun (5.2.7.3) total leakage rate is 30 gp. The total allewable leakage rate should be changed to 10 gp to cenicr to the value stated in Technical Specifica icn 3.1.6.1.
-- 12. 8 Inservice inspectica require =ents for AS"I Code Class 2 (5.2.3) cc=ponen:s shcu'.d cceply with the ainter 1972 ?.ddenda to Section XI.
The prcgrl: far Code Class 2 cc penents shculd include a table in the !cchnical Specificaticas using the forrat of Table ISC-261 cf the " inter 1972 Addenda. Since the design has beau already established, the vol=:e:ric and surface examinations of selected cceponents and areas of Code Clars 2 safe:2 related systems shculd be ccnducted to the extent practical.
12.9 Provide sufficient infor:atica about your preposed inservice (5.2.8) inspection pregra: for Class 3 cc penents to indicate that the progra: will provide a degree of assurance of syste:
integrity cc: parable to the progran recc=cended in Regula: cry Guide 1.51, " Inservice Insnection of ASMZ Code Class 2 and 3 Nuclear ?cwer Plant C =penents," May 1973.
12.10 Te=perature-pressure limitaticas for heatup, cccidevn, core (16.3.1.2) operation and inservice hyd:ctests.shculd be de:errined in accordance with the equire=ents of Appendi: C of the Su= er 1972 Addenda cf Sectica III of the ASMZ Code and Appendix G of 10 CFR 50.
The folicwing infor:atica is recuired before we can evaluate your Technical Specificaticns in this area.
, (1) Frevide the basis for the heatup and cocidcwn licit curves, Figures 3.1.2-1 and 2.
This should include s p e c s.a.a,.a._--
...e oe,3...as.
mm.a., o e.a
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elements such as cepper, phosphorus, and va-'"'"- which affect fracture toughness preperties, should be provided.
(2) Specifica:icn 3.1.2.1, "Hydrotests," refers to Specitica:ica 2.2 for pressure lici:ations when there are fuel asse:blies in the vessel. Specifica:icns 2.2 and 3.1.2.] should also pre side temperature limita:icns ea...,..,.- 2n a--,.a.,..
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..u paragraph 3-2410 of 1.ppendi.. G 0.\\iMZ Io11er 2nd Pressure 7essel Ccde, dectica III.84-043 e