3F0694-01, Updates Status of Remaining Unimplemented GSIs Identified in NRC

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Updates Status of Remaining Unimplemented GSIs Identified in NRC
ML20069Q615
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/22/1994
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-043, REF-GTECI-075, REF-GTECI-124, REF-GTECI-A-35, REF-GTECI-EL, REF-GTECI-NI, TASK-043, TASK-075, TASK-124, TASK-43, TASK-75, TASK-A-35, TASK-OR 3F0694-01, 3F694-1, NUDOCS 9406280063
Download: ML20069Q615 (3)


Text

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June 22, 1994 3F0694-01 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Status of Generic Safety Issue (GSI) Implementation

Reference:

1. NRC to FPC letter, 3N0490-29, dated April 25, 1990
2. FPC to NRC letter, 3F0690-10, dated June 21, 1990
3. NRC to FPC letter, 3N1190-11, dated November 26, 1990

Dear Sir:

Reference 1 requested Florida Power Corporation (FPC) provide information for Crystal River Unit 3 (CR-3) on the implementation status of generic safety issues (GSIs) resolved with the imposition of requirements or corrective actions. The FPC response (Reference 2) and subsequent discussions with the NRC Staff resulted in issuance of Reference 3, which contained the NRC list of unimplemented GSIs for CR-3. The purpose of this letter is to update the status of the remaining unimplemented GSIs identified in Reference 3.

On December 20, 1993, the NRC issued Amendment 149 " Improved Technical Specifications" to the CR-3 Operating License. This Amendment incorporated the additional requirements in the CR-3 Technical Specifications necessary to close GSI No. 75 (MPA No. B090), " Item 4.3, Reactor Trip System Reliability-Technical Specification Changes", GSI No. 75 (MPA No. B091), " Item 4.4, Reactor Trip System Reliability", and GSI No. A-35 (MPA No. B023) " Adequacy of Offsite Power Supplies".

l CRYSTAL RIVER ENERGY COMPLEX

  • 15760 W, Power Line Street
  • Crystal River e Floride 34428-6708 * (904)795-6486

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9406280063 940622 PDR ADOCK 05000302 -?ik ) ,

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r U. S. Nuclear Regulatory Commission i . 3F0694-01 i Page 2 i

. I The Multi-Plant Actions (MPAs) associated with GSI No. 75 requested Technical i Specification changes to assure functionality of the reactor trip breaker shunt i trip mechanism and Reactor Protection System silicon controlled rectifiers (SCR).  ;

These changes are addressed in ITS Specification 3.3.4 " Control Rod Drive Trip Devices." The CR-3 specific terminology for the SCRs described in the MPA is electronic trip assembly (ETA) relay. GSI No. A-35 requested Technical Specifications be added for degraded voltage relays and the associated -

instrumentation. These changes are addressed in ITS Specification 3.3.8

" Emergency Diesel Generator Loss of Power Start." l The other GSIs identified in Reference 3 have been previously implemented and  !

this information transmitted to you under separate cover letter. Refer to the Attachment to this letter. Therefore, FPC considers the implementation status .

of all GSIs requested in Reference I to be complete for CR-3 with the issuance i of Amendment 149. Future updates to NUREG 1435 should reflect this status.

Sincerely, f gdhdttt'l ~~

P.M. Beard,Jr.E Senior Vice President Nuclear Operations ,

t PMB/BPW:ff 1 Attachment  :

xc: Regional Administrator, Region II Senior Resident Inspector NRR Project Manager  ;

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,- 3F0694-01 Page 3 j

Attachment to 3F0694-01 ,

i Status of Generic Safety Issues (GSI). Identified  !

in NRC to FPC letter dated November 26, 1990 i

GSI N0. IllLE CLOSURE DOCUMENTATION REFERENCES ,

43 Reliability of Air Systems FPC to NRC letter, 3F0591-08, dated >

May 30, 1991.

NRC to FPC letter, 3N0891-05, dated 'l August 8, 1991.  ;

75 Salem ATWS Item 2.2.2, FPC to NRC letter, 3F0491-10, dated  !

Vendor Interface for April 30, 1991.  ;

Safety-Related Components NRC to FPC letter, 3N1090-20, dated October 30, 1990.

75 Item 4.3, Reactor Trip FPC to NRC letter, 3F1093-12, dated l System Reliability-TS October 15, 1993. ,

Changes  !

NRC to FPC letter, 3N1293-30, dated December 20, 1993. ,

75 Item 4.4, Reactor Trip FPC to NRC letter, 3F1093-12, dated System Reliability October 15, 1993.

NRC to FPC letter, 3N1293-30, dated  :

December 20, 1993.

124 Auxiliary Feedwater FPC to NRC letter, 3F0692-22, dated l System Reliability 1 June 25, 1992. i i

~A-35 Adequacy of Offsite Power FPC to NRC letter, 3F1093-12, dated '

Supplies October 15, 1993.

NRC to FPC letter, 3N1293-30, dated December 20, 1993.

1 FPC considers GSI 124 implementation to be complete for CR-3. NRC's June-6,1994 request for information relating to the current functional status of Feedwater Pump 7 are being addressed separately. ,

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