ML20236J143

Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits

ML20236J143
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1998
From:	GENERAL PUBLIC UTILITIES CORP.
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ML20236H176	List: ML20236H174 ML20236H208 ML20236H264 ML20236J143
References
NUDOCS 9807080061
Download: ML20236J143 (2)

Text

Based on the predicted RTer after 17.7 effective full power years of operation, the pressure / temperature limits of Figure 3.1-1 and 3.1-2 have been established by FTl calculation, reference No. 7, in accordance with the requirements of 10 CFR 50, Appendix G. Also, see Reference 4. The methods and criteria employed to establish the operating pressure and temperature limits are as described in BAW-10046A, Rev. 2. The protection against nonductile failure is provided by maintaining the coolant pressure below the upper limits of these pressure temperature limit curves.

The pressure limit lines on Figure 3.1-1 and 3.1-2 have been established considering the following:

a. A 25 psi error in measured pressure.

b. A 12 F error in measured temperature.

c. System pressure is measured in either loop.

d. Maximum differential pressure between the point of system pressure measurement and the limiting reactor vessel region for the allowable operating pump combinations.

The spray temperature difTerence restriction, based on a stress analysis of spray line nozzle is imposed to maintain the thermal stresses at the pressurizer spray line nozzle below the design limit.

Temperature requirements for the steam generator correspond with the measured NDTT for the shell.

REFERENCES (1) UFSAR, Section 4.1.2.4 " Cyclic Loads" (2) ASME Boiler and Pressure Code,Section III, N-415 (3) BAW-1901, Analysis of Capsule TMI-lC, GPU Nuclear, Three Mile Island Nucle:.; Station -

Unit 1, Reactor Vessel Materials Surveillance Program (4) BAW-1901, Supplement 1, Analysis of Capsule TMI-lC, GPU Nuclear, Three Mile Island Nuclear Station - Unit I, Reactor Vessel Materials Surveillance Program, Supplement 1 Pressure - Temperature Limits.

(5) BAW-2108, Rev.1, B&WOG Materials Committee Report " Fluence Tracking System" (6) GPU Nuclear calculation No. C-1101-221-E520-013 Rev.1,"TMI-l Reactor Vessel Welds Fluence, RTrrs and RTwr per R.G.1.99 R-2, Pos. No.1 (7) FTI calculation No. 32-5001065-01,"TMI-l P/T Limits," March 1998.

3-5 Amendment No. 29, !31, M7,1,76 9807080061 980630 PDR ADOCK 05000219 P PDR

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r ATTACHMENT I 1920-98-30236 DOC ID. 32-5001065-01 CALCULATION

SUMMARY

SHEET (CSS)

FRAMATOhm TECHNOLOGY TMI-l P/T LIMITS l

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