ML20198S567
| ML20198S567 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/24/1997 |
| From: | Raghavan L NRC (Affiliation Not Assigned) |
| To: | Richard Anderson FLORIDA POWER CORP. |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9711140054 | |
| Download: ML20198S567 (7) | |
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'!9' Mr. Roy A. Anderson Senior Vice President
. Nuclear Operations Florida Power Corporation ATTN: Managor, Nuclear Licensing -
r Crystal River Energy Complex (SA2A) 15760 W. Power Line Street
- Crystal River, Florida 34428 6708
SUBJECT:
CRYSTAL RIVER NUCLEAR GENERATING PLANT UNIT 3 - USI A-46 Audit
Dear Mr. Anderson:
During the week of November 3,1997, the NRC staff will be performing an audit to verify FPC's implementation of the USl A-46 program. Specifically, the staffs audit will focus on determining if the A 46 program was completed and documented in accordance with FPC's commitments in the plant specific procedures for CR-3 docketed on September 16,1994, and will evaluate the open issues identified in the staffs safety evaluation, dated May 2,1996.
Enclosed is a copy of the staffs ".udit plan. -If you have any questions regarding this matter, please write or call me at (301) 415-1471.
Sincerely, 0.NgiIova!1hrkekM5hadpers for l
Project Directorate ll 3 Division of Reactor Projects - l/ll Office of Nuclear Reactor Regulation Docket No. 50-302 a
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Enclosure:
USl A-46 Audit Plan g
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- Distribution 0 Docket File Public CR-3 Reading B. Boger 32
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October 24, 1997 Mr. Roy A. Anderson Serlor Vice President l
Nt., lear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER NUCLEAR GENERATING PLANT UNIT 3 - USl A-46 Audit
Dear Mr. Anderson:
During the week of November 3,1997, the NRC staff will be performing an audit to verify FPC's implementation of the USl A-46 program. Specifically, the staffs audit will focus on determining if the A-46 program was completed and documented in accordance with FPC's commitments in the plant specific procedures for CR 3 docketed on September 16,1994, and will evaluate the open issues identified in the staffs safety evaluation, dated May 2,1996.
Enclosed is a copy of the staffs Audit plan. If you have any questions regarding this matter, please write or call rne at (301) 4151471.
Sincerely, L. Raghavan, Project Mdnager Project Directorate ll-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
USl A 46 Audit Plan cc: See next page I'
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Mr. Roy A. Anderson CRYSTAL RIVER UNIT N0. 3 t
Florida Power Corporation l
CC' Mr. R. Alexander Glenn Corporate Counsel Mr. Robert E. Grazio. Director Florida Power Corporation Nuclear Regulatory Affairs (SA2A)
MAC-A5A Florida Power Corporation P.O. Box 14042 Crystal River Energy Complex
'St. Petersburg, Florida 33733-4042 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Charles G. Pardee, Director Nuclear Plant Operations (NA2C)
Senior Resident Inspector Florida Power Corporation Crystal River Unit 3 Crystal River Energy Complex U.S. Nuclear Regulatory Comission 15760 W. Power Line Street 6745 N. Tallahassee Road Crystal River, Florida 34428-6708 Crystal River, Florida 34428 Mr. Bruce J. Hickle. Director Mr. John P. Cowan Director, Restart (NA2C)
Vice President, Nuclear Production Florida Power Corporation (NA2E)
Crystal River Energy Complex Florida Power Corporation 15760 W. Power Line Street Crystal River Energy Complex Crystal River, Florids 34428-6708 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Robert B. Borsum framatome Technologies Inc.
Mr. James S. Baumstark 1700 Rockville Pike, Suite 525 Director, Quality Programs (S*.20)
Rockville, Maryland 20852 Florida Power Corporation Crystal River Energy Complex Mr. Bill Passetti 15760 W. Power Line Street Office of Radiation Control Crystal River, Florida 34428-6708 Department of Health and Rehabilitative Services Regional Administrator, Region II 1317 Winewood Blvd.
U.S. Nuclear Regulatory Commission Tallahassee, Flor.ida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Attorney General -
Department of Legal Affairs Mr. Kerry Landis The Capitol U.S. Nuclear Regulatory Comission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Comunity Affairs 2740 Centerview Drive Tallahasseee Florida 32399-2100 Chairman Board of County Comissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245 3. -
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Enclosure i
Plan for Performing Plant Specific Audli Review of the Licensee's Implementation of the Resolution for USI A-46 Program at Crystal River Nuclear Generating Plant Unit 3 (CR 3)
Week of November 3 7,1997 1.
Pulpose:
De purpose of the audit review is to verify that the licensee's implementation of the USI A-46 program was completed and oocumented in accordance with the licensee's f
commitments in the Plant Specific Procedure for CR-3, Rev.1, docketed on September -
16,1994 (CR 3 PSP), supplemented by the NRC staffs Safety Evaluation on CR-3 Criteria and Procedures, dated May 2,1996.
I 2.
Audit Team:
4 The audit team will be led by a member from Mechanical Engineering Branch (EMEB)
P and include one member from Civil Engineering & Geoscience Branch (ECGB). A contractor from Brookhaven National Laboratory will participate in this audit.
i Note: Conduct of the audit has been coordinated with the NRR project manager, Region
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II, and the Resident Inspectors.
3.
Maior Activities:
Nate: Prior to the site visit, the audit team has reviewed the licensee's summary report 4
and responses to the staffs request for additional information.
l he major elements of the audit tea n activities are identified below:
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o 2-(1)
Review overall program implementation.
(2)
Review resolution of all open issues documented in the staffs Safety Evaluation dated May 2,1996.
(3)
Discuss the licensee's response, dated March 27 and August 1,1997, to the staffs request for additional information (RAls), dated January 28,1997.
(4)
Rt. view the licensee's general approach for equipment anchorage seismic adequacy verification in accordance with the criteria and procedures delineated in Section 4.4 of GIP-2.
(5)
Select sample equipment items fmm the safe shutdown equipment list included in the licensee's correspondence in item (3) above and from the licensee's Seismic Evaluation Report, Rev. O, docketed on January 2,1996. The sample will include, but not limited to, equipment from the following two special categories: (a) equipment considered to have met the applicable GIP-2 caveats, and (b) equipment listed in the seismic evaluation outlier summary table. For the selected equipment, the aucit team will verify, by reviewing the detailed documentation and/or walkdown inspection, the seismic adequacy of these equipment items by focusing on the following aspects, as applicable:
a.
Verify that the licensee has conectly applied or interpreted applicability of the GIP-2 caveats wherever the GlP 2 Bounding Spectrum or Generic Equipment Ruggedness Spectra were used as the basis for seismic capacity. Emphasis will be given to verifying that the seismic review engineers have considered all GIP-2 caveats before deciding on their applicability.
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Verify that the licensee has correctly determined and compared equipment seismic capuity and demand.
I c.
Verify that the licensee has correctly determined equipment anchorage
- adequacy.
6 d.
Verify that the applicable caveats for each equipment category are met and l
there are no unusual design details which are not addressed by the
. equipment caveats, and which could compromise the seismic adequacy of the equipment.
e.
Verify that no seismic interaction concerns exist.
f.
Verify adequate resolution of equipment outliers (including the schedule for resolution), and/orjustification provided for not resolving outliers based on safety implications and impact on licensing basis requirements.
(6)
Review, by sampling, the relay portion of the program to verify that essential relays that affect equipment in Safe Shutdown E<1uipment List (SSEL) have been addressed and evaluated for functionality during and after the safe shutdown earthquake (SSE) in accordance with the gensal framework of criteria establi6ed in the staffs Safety Evaluation dated May 2,1996.
N (7)
Review, by sampling, the tanks and heat exchanger portion of the program to verify that criteria and procedures delineated in EPRI Report NP-5228, Revision 1, Volume 4, were adequately implemented.
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Review, by sampling, the seismic adequacy of the cable and conduit raceways, including supports, in accordance with the CR 3 original design criteria and Procedures.
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