ML20195H658: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:_
~
1 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 l
DOCKET NO. 50-302/ LICENSE NO. DPR-72 l
l l
i ATTACHMENT LICENSE AMENDMENT REQUEST #221, REVISION 2 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM i
i Proposed Technical Specification Change Page l
l 9811240067 981117 DR ADOCK 050003 2 i
I
 
-... ~.
.-.. -..... -. -. _ -. - - -. -.. ~. -.. - -
.. ~. -
=-... -.-
Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued) 5.
.For first span "B" 0TSG pit-like IGA, a summary of analyses performed to determine if estimated leakage based on the projected end-of-cycle perce9t throughwall distribution-exceeds the leak limit (dete'rmined from the licensing basis dose calculation for the main steamline break) for the next operating cycle.
6.
A deterministic assessment for the first span "B" 0TSG pit-like IGA.
Results of 0TSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant
'l operation. This report shall provide a description of investigations conducted to determine cause of the tube l
degradation and corrective measures taken to prevent recurrence.
I II I I
I l
l l
L i'
i Crystal River Unit 3 5.0-29A Amendment No.
4
-,}}

Latest revision as of 18:16, 10 December 2024

Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic
ML20195H658
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/17/1998
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20195H655 List:
References
NUDOCS 9811240067
Download: ML20195H658 (2)


Text

_

~

1 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 l

DOCKET NO. 50-302/ LICENSE NO. DPR-72 l

l l

i ATTACHMENT LICENSE AMENDMENT REQUEST #221, REVISION 2 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM i

i Proposed Technical Specification Change Page l

l 9811240067 981117 DR ADOCK 050003 2 i

I

-... ~.

.-.. -..... -. -. _ -. - - -. -.. ~. -.. - -

.. ~. -

=-... -.-

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued) 5.

.For first span "B" 0TSG pit-like IGA, a summary of analyses performed to determine if estimated leakage based on the projected end-of-cycle perce9t throughwall distribution-exceeds the leak limit (dete'rmined from the licensing basis dose calculation for the main steamline break) for the next operating cycle.

6.

A deterministic assessment for the first span "B" 0TSG pit-like IGA.

Results of 0TSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant

'l operation. This report shall provide a description of investigations conducted to determine cause of the tube l

degradation and corrective measures taken to prevent recurrence.

I II I I

I l

l l

L i'

i Crystal River Unit 3 5.0-29A Amendment No.

4

-,