3F0992-02, Submits Info to Verify Seismic Adequacy of Equipment in Older Plants,Per Suppl 1 to GL 87-02.Licensing Basis Earthquake Magnitude Will Be Reviewed to Determine If Safety Can Be Enhanced by Changing to More Appropriate SSE

Submits Info to Verify Seismic Adequacy of Equipment in Older Plants,Per Suppl 1 to GL 87-02.Licensing Basis Earthquake Magnitude Will Be Reviewed to Determine If Safety Can Be Enhanced by Changing to More Appropriate SSE

ML20105A652
Person / Time
Site:	Crystal River
Issue date:	09/04/1992
From:	Beard P FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0992-02, 3F992-2, GL-87-02, GL-87-2, NUDOCS 9209170150
Download: ML20105A652 (3)

Text

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-September 4, 1992 3F0992-02 U. S. Nuclear Regulatory Commission Attn: Document Control Desk-Washington, D.C, 20555

Subject:

Generic letter 87-02, Supplement 1 Verification of Seismic Adequacy of Equipment in Older Operating

' Nuclear Plants -

References:

A. Generic letter 87-02, dated February 19, 1987 (3N0287-39) >

-B.- Generic letter 87-02, Supplement 1, dated May 22, 1992 (3N0592-20)

C. FPC letter to NRC, December 19, 1991 (3F1291-01)

D. Generic Letter 88-20, Supplement 4, . dated June 28, 1991 (3N0691-23)

Dear Sir:

ReferenceE A encouraged utilities to participate in a generic program to accomplish seismic verification. As a result, the Seismic Qualification Utility ,

Group (SQUG) develo3ed the Generic Implementation- Procedure. (GIP) for Seismic Verification of nuclear plant equipment. .In Reference B, the NR: Staff issued a final Supplemental- Safety Evaluation Report (SSER)Lon Revision 2 of the. GIP.

The.lettce requests that Florida Power Corporation -(FPC) provide to the NRC, within 120-days, .a description of FPC's plans for resolution of USI A 46 for Crystal River 3 (CR-3). This letter responds to that request. -This letter also supplements:FPC's response.(Reference C).to Generic letter 88-20,' Supplement 4 (Reference _D).for-that~ portion related to seismic issues.

SEISMIC PROGRAM COMMITBDt{I As part of its program for resolution of USI A 46, FPC is planning to establish-a formal: seismic design basis-pregram applicable to all safety related equipment.

JA1 Seismic-. Steering Committee was -formed in March of this -year to define the overall scope of-the program tnd direct the effort. The following elements will

' be- included.--in the development of this_ program.

-o FPC will review the licensing 1 basis earthquake magnitude- to determine if-safety can be . enhanced by' changing' to a more appropriate Safe Shutdown Earthquake. - Consideration will be given to both the safety benefits of womme mm ff 4,04 7 ---y ,,,,,,,,,,,,,__, y

4

.-U. S. Nu: lear Regulatory Commission 3F0992-02 Page-2 enhanced seismic ruggedness and the potential operational and safety benefits of less rigid system supports.

o FPC will evaluate the benefits of updating from a 2 dimensional to 3 dimensional earthquake. This would be more consistent with current engineering and licensing practice.

o FPC will review the current licensing basis damping coefficients to determine if it would be more appropriate to use higher or lower values for some components or structures.

o FPC will review the current design basis floor spectra to determine if they contain a minimal, sufficient, or an excessive degree of conservatism.

o FPC will also review the current "falldown" criteria for non-safety related l piping, conduit, cable trays, ductwork, lighting and equipment. The current I guidance was put in place in 1984 and has created inconsistencies in the l

plant with items installed before that. These inconsistencies will be evaluated.and eliminated through clarified guidance or plant modifications.

o The program development will consider alternative means of demonstrating seismic qualification and a refined definition of how seismic qualification relates to Technical Specification OPERABILITY.

The result of this effort will be a formalized seismic licensing basis and design guide for Crystal River 3. This program will also include the developmen, of a plant specific procedure, based on the GIP, for verification of the seismic adequacy of the safe shutdown equipment installed at CR-3. This procedure will be used in a plant walk-down to resolve USI A-46 for Crystal River 3.

SCHEDULE Work will begin on the program during the 4th quarter of 1992. A formal response to the NRC on seismic issues will be submitted by June 30, 1993. This submittal will include detailed information on floor spectra and the plant specific walkdown procedure, based on the GIP, to be used for resolution of USI A-46 and the. seismic portion of the IPEEE. The walkdown is currently scheduled to be conducted in 1995 and the report will be submitted to the NRC by December 31, 1995.

Sincerely, P. H.-Beard, Jr.

Senior Vice President Nuclear Operations PMB/AEF:

xc: Regional Administrator, Region 11 NRR Project Manager Senior Resident Inspector 1

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. .-. = .

- ATTACHMENT TO LETTER NO. 3F0992-02 STATE OF FLORIDA COUNTY OF CITRUS P. M. Beard, Jr. states that he is the Senior Vice President, Nuclear Operations 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 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.

i P. M. Beard, Jr.

l Senior Vice Presider..

l Nuclear Operations Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this #Aday of September,1992.

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"/Notary Public L2 Notary Public, State of Florida at Large, Notary Public state of Tiwida My Commission Expires: Er Commission ispires o<t. 11.1994 w e. i .,, , i .., . . . . . n . .

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