ML20236M116
| ML20236M116 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/31/1987 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20236M039 | List: |
| References | |
| NUDOCS 8708100476 | |
| Download: ML20236M116 (6) | |
Text
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MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: R.V. LOWER SHEl.L COPPER CONTENT: 0.07 WT5 j e NICKEL CONTENT: 0.5R_WT5 l INITIAL RTNDT: 50 7 RT AFTER 9 IFPY: 1/4T, 116.4 I NDI 3/47, 108.3 1 CURVES APPLICABLE FOR EATUP RATES UP TO 100 F/HR FOR 'IHE SERVICE PERIOD UP TO 9 EFPY AND CONTAINS MARGINS CF 107 AND 60 PSIG FOR POSSIBLE INSTRIMENT ERRORS 2500 ggggggggggg; j j j j j LEAK TEST LIMITS 'ewJ l I I r I r r 2250 l i l \\ l I 4 I i 1 I I I l I l 1 I f 2000 f f CRITICAUTi 05tfT' ~ I 1 I J BASED ON W/HR b- [ [ HEATUP CURVE I 1750 UNACCEPTABLE / . / OPERATION r i / i i! Iii I I I I I II II I I I I CRITICAUTY usiT', g.1500 HEATUPRATESUP / / / BA ON /HR p UR 2 TO 1007/HR s ,I / p s f f g w x r i r i N / / ACCEPTABLE A g.1250 HEATUP RATES UP w si f OPERATION um TO 607/HR.--s f f f f m r i w f1000 l / c '~ / / / f h 2 s' 4 /,/ / CRITICALITY LIMIT E 750 f BASED ON INSERVICE l g / / HYDROSTATIC TEST TEMPERATURE (261 F) / / / FOR THE SERVICE PERIOD 500 UP TO 9 EFPY 250 00 50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERAT'URE (DEC.F) ( REACTOR COOLANT SYSTDi HEAH'P LIMITATIONSAPPLICABLEFORTHEFIRST9EFPY.%/ii UPRATED To-3!ir?SFMWt. -:L".T"".".iT::0 LT TO 100 3%5 FIGURE 3.4-2 CALLAWAY - UNIT 1 3/4 4-30
~~ ~ ~ MATERIAL PROPERTY BASIS CONTRG LING MATERIAL: R.V. LOWER SHELL COPPER CONTENT: 0.07 Wr5 NICKEL CONTENT: 0. Wr5 INITIAL RTNDT: .50 'RT AFTER 9 EFPY: 1/4T, 116.4 F g 3/4T, 108 3 F CURVES APPLICABLE FOR C00LDOWN RATES UP TO 10b"F/HR FO SERVICE PERICD UP TO 9 EFPY AND CONTAINS MARGINS T 107 AND 60 PSIO FOR POSSIBLE INSTRtMENT ERRORS 2500 i I J 2250 i a l 2000 l } 1750 ,i a I ( 1500 -UNACCEPTABLE oj. OPERATION [ w / 1250 h I ACCEPTABLE e j r OPERATION f~1000 r 2 B 750 j
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j. 1. '} s ) ~ REACTOR COOLANT SYSTEM hk j ,.C.. ' \\... ', ' BASES l PRESSURE / TEMPERATURE LIMITS (Continued) 2. These limit lines shall be calculated periodically using methods provided below. 3. The secondary side of the steam generator must not be pressurized above i 200 psig if.the temperature of the steam generator is below 70*F. 4 The pressurizer heatup and cooldown rates shall not exceed 100*F/h and 200*F/h, respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 583*F. 5. System pres 4rvice hydrotests and in-service leak and hydrotests shall be performed at pressures in accordance with the. requirements.of ASME Soiler and Prassure Vessel Code, Section XI. The fracture toughness properties of the ferritic materials in th'e reactor vessel are determined in accordance with the 1972 Winter Addenda to Section III of the ASME Boiler and Pressure Vessel Code. Heatup and cooldown limit curves are calculat using the most miting at the end of geffe - -,) valueofthenil-ductilityreferencetemperatur,gT i N0 f tive full power years (EFPY) of service life. he X EFP service li c; at the 1 loca ion in the core region j /, is chosen such that the limiting RTHDT I.the limiting unirradiated material. The selection l S is greater than the RTNDT of such a limiting RT assures that all components in the Reactor Coolant NDT System will be operated conservatively in accordance with applicable Code requirements. The reactor vessel materials have been tested to determine their initial Reactor NOT; the results of these tests are shown in Table B 3/4.4-1. RT operation and resultant fast neutron (E greater than 1 MeV) irradiation can cause an increase in'the RT Therefore, an adjusted reference temperature,, HDT. based upon the fluence and copper content and phosphorus content of the material in question, can be predicted using Figure B 3/4.4-1 and largest value of ART computed by either Regulatory Guide 1.99, Revisio {, Ef fects of NOT Residual Elements on Predicted Radiation Damage to Reacto essel Materials," or the Westinghouse Copper Trend Curves shown in Figure B 3/4.4-2. The heatup and cooldown limit curves of Figures 3.4-2 3.4-3 include predicted adjust-at the end FPY as well as adjustments for ments for this shif t in RTNOT possible errors in the pressure and temper e sensing instruments. Values of ART determined in this manner may be used until the results NOT from the material surveillance program, evaluated according to ASTM E185, are available. Capsules will be removed in accordance with the requirements of ASTM E185-73 and 10 CFR Part 50, Appendix H. The surveillance specimen withdrawal ) CALLAWAY - UNIT 1 B 3/4 4-7 - - - - - - ~ . _ _ _ _ _ _ _ _ _. _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}