3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments

From kanterella
Jump to navigation Jump to search

Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments
ML20196E806
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/21/1999
From: Roderick D
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0699-08, 3F699-8, GL-96-06, GL-96-6, TAC-M96800, NUDOCS 9906290011
Download: ML20196E806 (2)


Text

.y Fl2rida Power S' ' FPmm?

8*l%4*E.L onn June 21,1999 3F0699-08 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Updated Information Regarding Response to NRC Generic Letter 96-06,

" Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions" (TAC No. M96800)

References:

1. FPC to NRC letter 3F0197-05, dated January 27,' 1997, "120 Day Response to NRC Generic Letter 96-06, ' Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions'"
2. FPC to NRC letter 3F1097-05, dated October 17,1997, " Final Report on NRC Generic Letter 96-06, ' Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions'"

Dear Sir:

The purpose of this letter is to provide updated information to the Florida Power Corporation (FPC) response to Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions." The FPC response to GL 96-06 is currently under review by the NRC.

In References 1 and 2, FPC provided the response to GL 96-06 and the status of resolution activities for Crystal River Unit 3 (CR-3). Included was a listing of reactor building penetrations, and associated relieving devices, that were modified as a result of GL 96-06 implementation to address the potential for overpressurization of isolated, fluid filled piping \

i sections. The relieving devices for the affected penetrations have also been added to Final D

Safety Analysis Report (FSAR) Table 5-4, " Reactor Building Mechanical Penetration Information."

FPC is currently developing a plant modification under 10 CFR 50.59 that will change the previously listed relieving device for some of the penetrations. The plant modification will v

,I install relief valves in place of the existing expansion chamber / rupture disc or rupture disc h configuration for some penetrations. This change is needed to address recent premature \

failures of several rupture discs. The relief valves will be sized to provide adequate protection for overpressurization of these penetrations. Therefore, the conclusions provided in our response to GL 96-06 are unchanged. The plant modification will be reflected in the FSAR update as required by 10 CFR 50.71(e).

'~

9906290011 990621 PDR ADOCK 05000302 P PDR CRYSTAL RIVER ENERGY COMP' LEX: 15760 W. Power Line Street Crystal River, Florida 34428-6708 * (352) 795 4 486 A Florida Progress Company l

o <

'U.S. Nuclear Regulatory Conunission 3F0699-08 '

Page 2 of 2-FPC has' performed operability evaluations and taken appropriate actions for the rupture disc failures - to ensure that each penetration continues to ' have adequate post-accident overpressurization protection. Therefore, , the affected penetrations have adequate overpressurization protection with either the currently installed expansion chambers / rupture discs or with the planned installation of relief valves. Either method of overpressure protection meets the intent of GL %06.

This letter establishes no new regulatory commitments. If you have any questions regarding this submittal, please contact Mr. Sid Powell, Manager, Nuclear Licensing at (352) 563-4883.

cerely, Daniel L. Roderick, Director Nuclear Engineering & Projects .

DLR/dah xc: Regional Administrator, Region II NRR Project Manager Senior Resident Inspector t

L