ML19347C050
| ML19347C050 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 10/07/1980 |
| From: | Lippold W BALTIMORE GAS & ELECTRIC CO. |
| To: | Conner E Office of Nuclear Reactor Regulation |
| References | |
| NFM80-200, NUDOCS 8010160513 | |
| Download: ML19347C050 (2) | |
Text
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B ALTIMORE G AS AND ELECTRIC COMPANY P. O. B O X 1475 B A LTIM O R E. M A R Y L A N D 2120 3 J
NUCLEAR POWER DEPARTMENT October 7, 1980 I
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NFM80-200 l
- J Lp TO:
Mr. E. L. Conner, USNRC FROM:
W. J. Lippold, BG&E
SUBJECT:
CALVERT CLIFFS UNIT 1 CYCLE 5 LICENSE APPLICATION As we discussed on 10/3, CE has begun work on modifying the Unit 1, Cycle 5 1
license apolication to reflect only NRC approved methodologies. However, j
as we also discussed, much of the infomation in the 9/22 license application will not change. Suninarized below is a list of sections which will change and a list of sections which will not change.
I LIST OF SECTIONS WHICH WILL CHANGE l
6.0 (TORC instead of CETOP will be used) 7.0 Transient Analysis 7.1.1 CEA Withdrawal l-7.1.a Excess Load 7.2.1 Loss of Flow 7.2.3 CEA Orop 7.2.4 Asymetric Steam Generator Transients 7.3.4 Seized Rotor Event i
9.0 Modifications to Technical Specifications (keyed to Table 1, j
Summary of Technical Specification Changes) i Change No.
4 1
5 through 11
]
25 27 through 30 Appendix B (FIESTA will be deleted)
LIST OF SECTIONS WHICH WILL NOT CHANGE j
1.0)(exceotCycle4shutdownwindowchangesfrom 2.0 )
10,600-11,600 to 10,600-11,800 MWD /T) f 3.0 )
4.0 5.0 (except shutdown window changes to 10,600-11,800 VAD/T) i
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T0: Mr. E. L. Conner, USNRC October 7, 1980 l
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NFM80-200 ;
i LIST OF SECTIONS WHICH WILL NOT CHANGE (Continued) 7.0 Transient Analysis j
7.1.2 1
7.1.3 j
7.1.5
]
7.1.6 7.1.7 t
7,f,g..
i i
7.2.2 l
7.3.1 (except Table 7.3.1-2:
" Fraction of Fuel Having at least j
Incipient Centerline Melting" changes from.04 to.08 due to typo) j 7.3.2 (assumes Appendix C will be reviewed and approved) 7.3.3 i
8.0
)
9.0 Modifications to Technical Specifications (keyed to Table 1 l
Summary of Technical Specification changes) l Change No.
Change No.
1 2
33 AS/GPT 3 AS/GPT 34 AS/GPT l
4 35 through 47 j
12 13 AS/GPT AS/GPT s assumes approval of 14 through 24 Asymmetric Steam Generator i
26 Trip (Appendix C) i 31 AS/GPT i
32 10.0 j
11.0 Appendices A
C
{
D i
E i
j In addition, several Technical Specification sections not mentioned above i
may change due to a general squeezing of operating parameter envelops.
This reflects the margin lost by the deletion of FIESTA and Statistical Combination of Uncertainty methodologies.
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W. J.'Lippol f
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j Nuclear Fuel Management WJL:st i
cc:
A. E. Lundvall J. A. Tiernan l
JPS/ JAM /MEB/SAS/JBC/J0W/ File: Licensing - Reload Fuel j
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