ML20031C006
| ML20031C006 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/30/1981 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20031B997 | List: |
| References | |
| NUDOCS 8110060422 | |
| Download: ML20031C006 (4) | |
Text
,
4 DOCKET NO. 50-213 ATTACHMENT 1 HADDAM NECK PI M PROPOSED REVISIONS TO TECHNICAL SPECIFICATTMc f
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Basic:
The allowable pressure-temperature relationships for the specified heatup and cooldown rates of the reactor coolant system were calculated in accordance with Appendix G in Section III of the ASME Boiler and Pressure Vessel Code. The minimum full pressurization limits to be applied during hydro-static and leak testing of the reactor coolant system were de-rived in accordance with Appendix G to ASME III and Regulatory Guide 1.99 Revision 1.
The system leakage test and system hy-drostatic test pressure limitations are based on paragraph IS-522 of the Winter 1972 Addenda to ASME Section XI.
The total stress of a component in the reactor coolant system is the combined stress caused by internal pressure and by thernal gradients. The Appendix G approach specifies that the allowaole total stress intensity factor (K 1) at any time during heatup and cooldown cannot be greater than that shown on the KIR curve (Reference 1) for the metal temperature &t that time.
The derived operating limit curves (Figt..cs 3.4-2, 3.4-3, 3.4-4, 3.4-5, 3.4-6 and 3.4-7) contain explicit safety factors of 2.0 and 1.25 (addit-ional conservatism above code requirements) on stress intensity factors induced by pressure and temperature gradients, respr.ctively.
Allowable pressure temperature relationships for both steady-state and finite heatup and cocidown rates were generated assuming the presence of code reference 1/4 T deep flaw at either the ID or OD of the reactor vessel. Finally, a composite ev1ve was constructed based on a point-by-point comparison of the steady state and finite heatup ard cooldown data. At any given temperature, the allowable pressura is tsken to be the lesser of the two values taken from the curves ur.dur consideration. The composite curve was then adjusted to allow for possible errors in the pressure and temperature sensing instruments.
The criticality limit is defined as the minimum full pressurization temperature plus 400F when reactor is critical.
The heatup, cooldown and hydrostatic and leak testing operating limits were based on the adjrsted trend curve (Reference 2),
derived from surveillance Capsule A and F results. The projected RT shif t will be verified periodically by the reactc,r vessel NDT surveillance program.
The heatup and cc ildown rates of 200 F/hr of the pressurizer and 100 i/hr for heat 9 and cooldown of the steam generators are specified since they are both design limits to maintain stresses in these vessels within acceptable design limits.
A temperature difference of 2000F between the pressurizer and reactor coolant system in specified to maintain thermal stresses within the surge line below design limits.
Temperature requirements for pressurization of the pressurizer and steam generators correspond with DTT measured for each material of each component.
3-6
References:
1.
ASME Boiler and Pressure Vessel Code,Section III, 1972 Summer t.ddenda, Appendix G.
2.
T..R.
Mager, S. A. Legge, S.-E. Yanichko and S. L. Anderson, "Heatup and Cooldown Limit Curves for Normal Operation for Connecticut Yankee Reactor Pressure Vcssel, April 15, 1973.
3.
PVRC Bulletin No. 175/ August, 1972, "PVRC Recommendations on Toughness Requirements 'or Ferritic Materials", August, 1972.
4.
W. Hazelton, S. L. Anderson and S. E. Yanichko, " Basis for Heatup and Cooldown Limit Curves", WCAP-7924, July, 1972.
5.
ASME Boiler and Pres _ tre Vessel Code,Section XI, Winter 1972 Addenda.
6.
Regulatory Guide 1.99 Revision 1.
m 3-7
s 12 EFPY 15 EFPY 2200 SYSTEM HYDROSTATIC TEST PRESSURE (P=2160)
CONNECTICUT YANKEE LIMIT CURVES FCP.
HYDROSTATIC AND LEAK TESTING FOR SYSTEM LEAKAGE TEST PRESSURE (P=2000)
MINIMW MINEW SYSM 1800.
- EFPY HYDRO TEMP LEAK TEST TEMP 12 296*F 287'F 15 331*F 322*F SAFE
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- WHEN 12 EFPY IS REACHED THE OPERATION m
O 1400-15 EFPY CURVE IS TO BE USED 8
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1000" a
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s BELOW 70*F PRESSURE IS NOT TO EXCEED 500 PSIG ESSURIZER & PR N RY SIDE OF STEAM 600 GENERATOR AIAXIMUM PRESSURE FOR RHR SYSTEM OPERATION (350 paig)
\\ MINIMUM PRESSURE FOR RCP OPERATION (300 psig)
~200~
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100 200 300 400 500 600 REACTOR COOLANT TEMPERATURE (*F)
FIGURE 3.4-l'