ML19347C050

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Discusses Mod of Cycle 5 License Application to Reflect Only NRC Approved Methodologies.Submits List of Sections Changed by Mod & Sections That Will Not Be Affected by Proposed Change
ML19347C050
Person / Time
Site: Calvert Cliffs Constellation icon.png
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)


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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

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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

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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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