ML20058E198
| ML20058E198 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/22/1982 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8207280093 | |
| Download: ML20058E198 (4) | |
Text
e PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET F).O. BOX 8699 PHILADELPHIA. PA,19101 SHIELDS L. D A LTROFF attern c en o CTioN July 22, 1982 Re:
Docket No. 50-278 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
At the request of Mr. M. Fairtile of your staff, we are pleased to provide the following additional information in support of our recent license amendment application for modification of Minimum Critical Power Ratio (MCPR) limits.
Question 1:
Why did the original Peach Bottom 3, Reload 4, license amendment application MCPR limits differ from the calculated values documented in General Electric document Y1003J01A20, " Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3, Reload No. 4"?
Response
The option B MCPR limits contained in the Peach Bottom 3, Reload 4 license amendment application were arbitrarily increased (in the conservative direction) for cycle exposures from beginning of cycle 5 to end of cycle 5 minus 2000 MWD /t.
The slight increase was employed to reduce the need for future cycle dependent revisions to the Technical Specifications in order to accommodate future refuelings in accordance with the provisions of 10CFR50.59.
t B207280093 820722 00l PDR ADOCK 05000278 P
s Mr. John R. Stolz, Chief Page 2 Question 2:
Supply the calculational results for the Feedwater Controller Failure event for the end of Cycle 5 exposure point.
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Response
The calculational results are given in the attached Table 1.
Should you have any questions or require any additional information, please do not hesitate to contact us.'
Very truly yours, u'
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.i TABLE 1 PEACH BOTTOM 3 RELCAL h (CYCLE $)
RELOAD LICENSING SUBMITTAL Y1003J01A20 FEVISION 1 ADDITIONAL INFORMATION 9
CORE-WIDE TRANSIENT ANALYSIS RESULTS ($.2.1) 4 4
Core CPR Power Flow Q/A Psl Pv PTA &
Plant Transient Exposure M
M
(% NBR)
(% NBR)
(psig)
(psig) 8x8 8x8R P8x8R
Response
Feedwater Controller Failure EOC$
10h.$
100 h07 126 1163 1203 0.22 0.22 0.25 Figure 5a 11.
CYCLE MCPR VALUES (5.2)
EOC$-1000 MWD /t to E006 Option A Option B PTA/
PTA/
Pressurization Events 8x8 8x8R P8x8R 8x8 8x8R P8x8R Feedwater Controller Failure 134 13h 1 37 1.28 1.28 1 31 4
1 July 21, 1982 1
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