3F1196-01, Forwards Rev 23 to Crystal River Unit 3,FSAR Which Satisfies Requirements of 10CFR50.71(e)(4) & Includes Matl Which Describes Organization,Mods or Changes to CR-3 That Have Been Implemented as of End of Refuel 10

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Forwards Rev 23 to Crystal River Unit 3,FSAR Which Satisfies Requirements of 10CFR50.71(e)(4) & Includes Matl Which Describes Organization,Mods or Changes to CR-3 That Have Been Implemented as of End of Refuel 10
ML20134L508
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/18/1996
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134L512 List: ... further results
References
3F1196-01, 3F1196-1, NUDOCS 9611210056
Download: ML20134L508 (3)


Text

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Florida Egger

. O ?nl November 18, 1996 3F1196-01 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001

Subject:

Final Safety Analysis Report, Revision 23

Reference:

1.

NRC to FPC letter, dated March 6, 1996, 3N0396-03 2.

FPC to NRC letter, dated October 28, 1996, 3F1096-22

Dear Sir:

Florida Power Corporation (FPC) is submitting one original and ten copies of Revision 23 to the Crystal River Unit 3 (CR-3) Final Safety Analysis Report (FSAR). This FSAR revision satisfies the requirements of 10 CFR 50.71(e)(4) and includes material which describes the organization, modifications, or changes to CR-3 that have been implemented as of the end of Refuel 10 which was completed on May 17, 1996.

For exampla, Changes to the CR-3 Quality Program are discussed in Section 1.7 including those audit schedule changes approved by the NRC in Reference 1.

Section 3.12, Cycle 11, adds a description of the fuel loaded into CR-3 for the current cycle.

Section 6.1, Emergency Core Cooling Systems, and Section 7.1.3, Engineered Safeguards Actuation System, have been revised to reflect plant changes required to resolve Small Break LOCA issues.

Section 9.3, Spent Fuel Cooling System, has been revised to be consistent with License Amendment No.135 regarding fuel storage capacity and thermal performance of the system in various operational configurations.

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U. S. Nuclear Regulatory Commission November 18, 1996 3F1196-01 Page 2 of 3 Section 9.6, Fuel Handling Equipment, has been revised to be consistent with License Amendment No.154 for fuel enrichment increase to 5 weight %.

FSAR Tables 8-1 and 8-2 describe the Emergency Diesel Generator automatic and manually connected loads for Emergency Diesel Generator ""A" and Emergency Diesel Generator "B", respectively. The data in these tables have not been provided in this FSAR revision because the calculations necessary to produce the entries are still being developed. The data for this table are under development and are not necessary in Mode 5.

Therefore, the To Be Determined (TBD) status of the data in this table does not impact the operability of the Emergency Diesel Generators as described in CR-3 ITS 3.8.2, AC Sources-Shutdown. The data in these tables will be provided in a separate FSAR revision that will occur before CR-3 restarts (enters Mode 4) from the Fall 1996 Outage.

Other changes to the FSAR which result from modifications and other activities taking place during the current outage will be provided in another FSAR revision that will be submitted no later than six months after the restart from the Fall 1996 Outage.

Please note that some of the replacement pages do not change revision level. FPC has changed the printer fonts which results in a relocation of the text on the page. Text that has moved from one page to another because of the font changes are indicated with a change bar in the right margin and a revision level change 1

on that page.

The copy of the FSAR required by 10 CFR 50.4 for the NRC resident inspector will be provided to the Senior Resident Inspector through FPC's internal controlled documentation distribution system.

Sincerely, M.

eard, Jr.

Senior Vice President Nuclear Operations PMB/JWT Attachments xc:

Regional Administrator, Region II Senior Resident Inspector NRR Project Manager 1

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U. S. Nuclear Regulatory Commission November 18, 1996 3F1196-01 Page 3 of 3 j

STATE OF FLORIDA COUNTY OF CITRUS P. M. Beard, Jr. states that he is the Senior Vice President, Nuclear Operations j

for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached i

hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

P. M. Beard, Jr.

Senior Vice President Nuclear Operations

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P. M. Beard, Jr., personally known to me. Subscribed and sworn to befor me, a Notary Public in and for the-State and County above named, this /A.

ay of November, 1996.

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Notary Public (signature)

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