ML20196C303

From kanterella
Revision as of 06:28, 9 December 2021 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Notice of Withdrawal of Application for Amend to Facility Operating License.Amend Would Revise CR3 TS Re Decay Heat Removal Requirements in Mod 4
ML20196C303
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/24/1998
From: Wiens L
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20196C298 List:
References
NUDOCS 9812020027
Download: ML20196C303 (2)


Text

- .. .-. _ _ _ . . _ . _-. -

, . l l

l 7590-01

)

UNITED STATES NUCLEAR REGULATORY COMMISSION l I

FLORIDA POWER CORPORATION DOCKET NO. 50-302 NOTICE OF WITHDRAWAL OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (the Commission) has granted a request by the Florida Power Corporation (FPC) to withdraw its October 31,1997, application for an amendment to Facility Operating License No. DPR 72, issued to FPC for operation of the Crystal River Nuclear Generating Unit 3 (CR3) located in Citrus County, Florida. Notice of consideration of i

issuance of this amendment was published in the Federa/ Registeron November 12,1997 l

l (62 FR 60735).

The proposed amendment would have revised the CR3 Technical Specifications (TS) relating to decay heat removal requirements in Mode 4. The proposed modification would have revised the TS and associated Bases to require in Mode 4, one operable emergency feedwater l l

(EFW) train and associated equipment, including the EFW tank, emergency feedwater initiation and control ar,tuation instrumentation for EFW, post accident monitoring instrumentation, and the turbine bypass vaives. Additionally, the TS and associated Bases would have been revised to require in Mode 4, a low-pressure injecton (LPI) train, dedicated to the borated water storage tank, and to reflect that the available loops for decay heat removal do not include this dedicated LPI train. Editorial changes would also have been made to clarify the description of Mode 4 accidents requiring emergency core cooling system injection, and to revise the title of TS limiting condition for operation 3.7.5.

9812O20027 901124 l PDR ADOCK 05000302 l P PDR l l

1 I

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

l 2

FPC's letter of November 18,1998, informed the staff that the request was being withdrawn because the NRC staff had indicated that the subject of reactor decay heat removal l

requirements during Mode 4 operation would be treated as a generic industry issue. In this letter, FPC committed to continue to maintain administrative controls for the additional equipment and capability to remove decay heat identified in the October 31,1997, request during Mode 4

, operation of CR-3. '

For further details with respect to this action, see the application for amendment dated

October 31,1997, and FPC's withdrawal letter dated November 18,1998, which are available for public inspection at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC and at the local public document room located at the Coastal Region Library,8619 W. Crystal Street, Crystal Rwer, Florida.

Dated at Rockville, Maryland, this 24 th day of November 1998.

For the Nuclear Regulatory Commission f

Leonard A. Wiens, Senior Project Manager Project Directorate II-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation o

s i

J e , , , . . - -,-- - . wr - m- - ,-, w *,e