L-2002-176, Supplemental Response to NRC Request for Additional Information Related to the Staffs Review of Severe Accident Mitigation Alternatives
| ML022410053 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/26/2002 |
| From: | Jernigan D Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2002-176 | |
| Download: ML022410053 (5) | |
Text
0 I=IL Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 August 26, 2002 L-2002-176 10 CFR 54 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Supplemental Response to NRC Request for Additional Information Related to the Staff s Review of Severe Accident Mitigation Alternatives for St. Lucie Units I and 2 By letter dated June 25, 2002, FPL provided its response to the NRC Requests for Additional Information (RAIs) regarding the St. Lucie Units 1 and 2 License Renewal Application (LRA) Environmental Report Severe Accident Management Alternatives. Due to an administrative error in Table 1-1, "Breakdown in Internal CDF Sorted by Initiating Events," FPL's response to Questionl.c has been revised. Attachment 1 to this letter contains the revised response to Question 1.c. FPL has evaluated the revision to Table 1-1 and determined that there was no impact on the validity of the SAMA studies.
Should you have any further questions, please contact S. T. Hale at (772) 467-7430.
D. E. Jem'niga Vice President St. Lucie Plant DEJ/STH/hlo Attachment (1) an FPL Group company
-A c) 8ý
L-2002-176 Page 2 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Supplemental Response to NRC Request for Additional Information Related to the Staff's Review of Severe Accident Mitigation Alternatives for St. Lucie Units 1 and 2 STATE OF FLORIDA COUNTY OF ST. LUCIE
) ) ss
)
D. E. Jernigan being first duly sworn, deposes and says:
That he is Vice President - St. Lucie of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge,11 rmation and belief, and that he is authorized to execute the document on behalf-6f sayl Licensee.
Subscribed and sworn to before me this ZO day of
- icJA-*Z,."
2002.
Name of Notary Public (Type or Print)
D. E. Jernigan is personally known to me.
Leslie I Whitwell
?
MYCOMMISSION # D0020212 EXPIRES
-May 1Z 2005 BONDED THRU TROY FAIN INSURANCE, INC.
L-2002-176 Page 3 cc:
U.S. Nuclear Reqiulatory Commission, Washington, D.C.
Program Director, License Renewal and Environmental Impacts Project Manager - St. Lucie License Renewal Project Manager - St. Lucie U.S. Nuclear Regulatory Commission, Regqion II Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Other Mr. Robert Butterworth Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32399-1050 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, FL 32399-1741 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, FL 34982 Mr. Jim Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE Tower Drive Stuart, FL 34997 Mr. Alan Nelson Nuclear Energy Institute 1776 I Street NW Suite 400 Washington, D.C. 20006
L-2002-176 ST. LUCIE UNITS I AND 2 DOCKET NOS. 50-335 AND 50-389 ATTACHMENT 1 SUPPLEMENTAL RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION TO THE STAFF'S REVIEW OF THE SEVERE ACCIDENT MANAGEMENT ALTERNATIVES (SAMA) FOR ST. LUCIE UNITS I AND 2 QUESTION 1..c The SAMA analysis appears to be based on the current version of the "living" PSA model for internal events, which is a modification to the original Individual Plant Examination (IPE) that was reviewed by the U. S. Nuclear Regulatory Commission (NRC). Please provide the following:
- c.
a breakdown of the internal event CDF for each unit by initiating event, specifically, Loss of Offsite Power (LOOP), General Transients, Station Blackout, ATWS, Loss-of-Coolant Accidenta (LOCAs), Interfacing System LOCA (ISLOCA), and Steam Generator Tube Rupture (SGTR), and other internal events initiators (please specify). Also, confirm the total of 2.99x1 0- per reactor year for Unit 1 and 2.44x1 0" per reactor year, for Unit 2, respectively.
Response to Question I.c This response supercedes the response to Questionl.c provided in FPL Letter L-2002-124 dated June 25 in its entirety.
- c.
Individual sequences associated with various Plant Damage States (PDSs) were quantified separately and then totaled, yielding frequencies of 2.99E-05 per reactor year and 2.44E-05 per reactor year (including ISLOCA) for Unit 1 and Unit 2, respectively. An alternate quantification based on an "OR" gate containing all PDS sequences produced frequencies of 2.86E-05 per reactor year and 2.43E-05 per reactor year, respectively.
The following is based on the one-top PDS results. The individual sequence for various PDSs were used for Level 3 analysis.
Table 1-1 Breakdown of Internal CDF Sorted by Initiating Events Initiating Event Frequency (per Year)
Unit I
Unit 2 Loss of Offsite Power/Station Blackout' 4.63E-06 2.67E-06 Transients 2 4.55E-06 1.84E-06 Anticipated Transient Without Scram 8.23E-07 3.31 E-07 Loss-of-Coolant Accident 8.22E-06 7.82E-06 ISLOCA 2.89E-06 5.64E-06 SGTR 9.58E-07 2.78E-07 Internal floods 5.OOE-07 5.OOE-07 Others 3 6.03E-06 5.22E-06 Total CDF 2.86E-05 2.43E-05 Notes:
- 1. Loss of Offsite Power sequences are predominantly Station Blackout sequences.
- 2. General Transients include Reactor Trip, Loss of Main Feedwater, and Excessive Feedwater.
- 3. See list of other initiators below.
Page 1 of 2
L-2002-176 Other initiators include:
Loss of 4KV Bus 1A2 Loss of 4KV Bus 1 B2 Loss of 6.9KV Bus 1A1 As Initiator Loss of 6.9KV 1B1 As Initiator Loss of Component Cooling Water (CCW)
Loss of DC Bus 1A Loss of DC Bus 1B Loss of Instrument Air Loss of Intake Cooling Water (ICW)
Loss of 120VAC Instrument Bus 1MA Loss of 120VAC Instrument Bus 1MB Loss of 120VAC Instrument Bus IMC Loss of 120VAC Instrument Bus 1 MD Seal LOCA Initiating Event (IE) (Loss of CCW Not Related to LOCCWIE or LOICWIE) - All RCPs Seal LOCA IE (Loss of CCW Not Related to LOCCWIE or LOICWIE) - One RCP Steamline Break Upstream of SG A Main Steam Isolation Valve (MSIV)
Steamline Break Upstream of SG B MSIV Steamline Break Downstream of the MSIVs Spurious Main Steam Isolation Signal Spurious Safety Injection Actuation Signal Transient Induced by Power Operated Relief Valve (PORV) Opening with Pressurizer (PRZR) Transmitter (XMTR) Failing Hi PORV 1404 Transient Induced by PORV Opening with PRZR XMTR Failing Hi PORV 1402 Loss of Turbine Cooling Water (TCW)
Page 2 of 2