ML20209F257
| ML20209F257 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/09/1999 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20209F261 | List: |
| References | |
| TAC-M83685, NUDOCS 9907150281 | |
| Download: ML20209F257 (4) | |
Text
has y
UNITED STATES s
B NUCLEAR REGULATORY COMMISSION
?g WASHINGTON, D.C. 20656-0001
. /
. Udly 9,1999 Mr. James W. Langenbach, Vice President
' and Director, TMl GPU Nuclear, Inc.
P.O. Box 480
- Middletown, PA 17057
SUBJECT:
REVIEW OF THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMl-1)
INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE)
SUBMITTAL (TAC NO. M83685)
Dear Mr. Langenbach:
On June 28,1991, the NRC issued Generic Letter (GL) 88-20, Supplement 4, " Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - Title 10 CFR 50.54(f) along with NUREG-1407, " Procedural and Submittal Guidance," requesting that licensees perform individual plant examinations of external events to identify plant-specific vulnerabilities to severe accidents and report the.results to the Commission together with any licensee-determined improvements and corrective actions. You responded to GL 88-20, Supplement 4 by lotter dated December 29,1994. On January 8,1998, the staff issued a request for additional information related to your GL response, to which you responded by letter dated April 24,1998. Enclosed is the NRC Staff Evaluation Report (SER) of its review of your submittals. Also included with the SER are the contractor's Technical Evaluation Reports
. (TERs) in the seismic and fire areas and the staff's TER in the high winds, floods and other external events (HFO) area.
On the basis of these reviews, the staff concluded that the aspects of selsmic; fires; high winds; floods; and other extemal events were adequately addressed. The staff's review findings are summarized in the enclosed SER, and the' details of the contractor's and staff's findings in their TERs appear in attachments to the SER.
For the seismic analysis, your staff used a seismic probabilistic risk analysis (PRA)
' methodology to assess the capacity of plant structures and equipment to withstand beyond
. design basis earthquakes and to estimate the frequency of seismic sequences. Your staff estimated the total seismic core damage frequency (CDF) to be 8.4E-5 per year using the revised Lawrence Livermore National Laboratory (LLNL) hazard curve and 3.2E-5 per year using the Electric Power Research Institute (EPRI) hazard curve. High confidence of low probability of failure (HCLPF) values of critical equipment were also estimated for a majority of equipment and found to be higher than 0.3g which is the NUREG-1407 criterion for
\\
focused-scope plants. For the fire analysis, your staff performed plant walkdowns, flre area i
screening, and frequency quantification of fire sequences for fires in unscreened fire areas using the. fire-induced vulnerability evaluation (FIVE)/PRA method. Your staff estimated the
- 4 o\\I}
fire-induced CDF to be 2.4E-5 per year. For the HFO analysis, your staff used the, progressive screening approach described in NUREG-1407 in judging the safety significance of HFO events. Your staff estimated the CDF values due to high winds and external floods to be 7.4E-7 per year and 8.1E-5 per year, respectively. The CDF estimates due to chemical release events and air transportation events were found to be 1.6E-7 per year and 4.0E-7 per year, p**J&!Mfy [
SC HLF fftNTER CDPV
J.Lan0:nbich July 9, 1999 r:sp:ctiv:ly. The totil CDF dus to int:rnal ev:nts, including internal floods, was estimat:d by your st:tff to ba 4E-5 p:r y:ar.
Your staff defined a potential seismic vulnerability for TMI-1 to be any seismically induced core damage sequence greater than 1E-4 per year or any containment bypass or large early containment failure greater than 1E-6 per year. Using this criterion, your staff did not identify any seismic vulnerabilities.
Your submittals have addressed Generic Safety issue (GSI)-103, " Design for Probable Maximum Precipitation (PMP)," GSI-57, " Effects of Fire Protection System Actuation on Safety-Related Equipment," Unresolved Safety issue (USI) A-45, " Shutdown Decay Heat Removal Requirements," and the Sandia Fire Risk Scoping 3tudy (FRSS) issues as explicitly requested in Supplement 4 to Generic Letter 88-20 and its associated guidance in NUREG-1407. On the basis of the IPEEE review, the staff concludes that the TMI-1 IPEEE process is capable of identifying the most likely severe accidents and severe accident vulnerabilities and, therefore, that the TMI-1 IPEEE has met the intent of Supplement 4 to Generic Letter 88-20, and considers the above issues resolved for TMI-1.
In addition, the TMI-1 IPEEE submittals contain some specific information that addresses the external event aspects of certain other GSis (GSI-147, " Fire-induced Alternate Shutdown / Control Room Panel Interactions," GSI-148, " Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156, " Systematic Evaluation Program (SEP)," and GSI-172,
" Multiple System Responses Program (MSRP)." The specific information associated with each issue is identified and discussed in the enclosed SER. Based on the review of the information
- contained in the submittals, the staff considers that your process is capable of identifying potential vulnerabilities associated with these issues. On the basis that no vulnerabilities associated with the external events aspects of these issues were identified at TMl-1, the staff considers GSI-147 and GSI-148 and the IPEEE-related portions of GSI-156 and GSI-172 resolved for TMI-1.
This completes the staff's review of GL 88-20, Supplement 4, for the Three Mile Island Nuclear Station, Unit 1 and TAC No. M83685. If you have any questions, please call me at (301) 415-1402.
Sincerely, original signed by:
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
' Staff Evaluation Report cc w/ encl: See next page DISTRIBUTION:
_ Docket FHet PUBLIC GHill(2)
PDl-1 R/F ACRS TColburn TClark ARubin OGC RNorsworthy (RCN)
EChelliah DCoe CWoods TSchiltz, EDO MOprendek, Rl PEselgroth, RI DOCUMENT NAME: G:\\PDI-2\\TMI-1\\SE83685.WPD To receive a copy of this document, indicate in the box:
"C" - Copy without attachment / enclosure "E" = Copy w,ith, attachment / enclosure "N" - No copy i
0FFICE PDI-1/PM %ul PDI-1/LfQ,iF[P*" 7 PDI-1/SC jjl l
NAME TColburn/rsl '
TClark i P"T & (6 SBajwa
/1 ug DATE 9/ Q /99 iM 7/4 /99
' / 9 /99 8
0FFICIAb RECORD COPY k.
F F
'J. Langenbach respectively. The total CDF due to internal events, including internal floods, was estimated by your staff to be 4E-5 per year.
i l
Your staff defined a potential seismic vulnerability for TMI-1 to be any seismically induced core i
damage sequence greater than 1E-4 per year or any containment bypass or large early containment failure greater than 1E-6 per year. Using this criterion, your staff did not identify any seismic vulnerabilities.
Your submittals have addressed Generic Safety issue (GSI)-103, " Design for Probable Maximum Precipitation (PMP)," GSI-57," Effects of Fire Protection System Actuation on 1
Safety-Related Equipment," Unresolved Safety issue (USI) A-45, " Shutdown Decay Heat l
Removal Requirements," and the Sandia Fire Risk Scoping Study (FRSS) issues as explicitly requested in Supplement 4 to Generic Letter 88-20 and its associated guidance in NUREG-1407. On the basis of the IPEEE review, the staff concludes that the TMI-1 IPEEE process is j
capable of identifying the most likely severe accidents and severe accident vulnerabilities and, therefore, that the TMI-1 IPEEE has met the intent of Supplement 4 to Generic Letter 88-20, l
and considers the above issues resolved for TMI-1, l
In addition, the TMI-1 IPEEE submittals contain some specific information that addresses the external event aspects of certain other GSis (GSI-147," Fire 'nduced Alternate Shutdown / Control Room Panel Interactions," GSI-148, " Smoke Control and Manual
' Fire-Fighting Effectiveness," GSI-156, " Systematic Evaluation Program (SEP)," and GSI-172, j
" Multiple System Responses Program (MSRP)." The specific information associated with each I
issue is identified and discussed in the enclosed SER. Based on the review of the information contained in the submittals, the staff considers that your process is capable of identifying potential vulnerabilities associated with these issues. On the basis that no vulnerabilities associated with the external events aspects of these issues were identified at TMl-1, the staff considers GSI-147 and GSI-148 and the IPEEE-related portions of GSI-156 and GSI-172 resolved for TMI-1.
This completes the staff's review of GL 88 20, Supplement 4, for the Three Mile Island Nuclear Station, Unit 1 and TAC No. M83685. If you have any questions, please call me at (301) 415-1402.
Sincerely, M
Timothy G. Co urn, Senior Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Staff Evaluation Report cc w/ encl: See next page l
Three Mile Island Nuclear Station, Unit No.1 cc:
l Michael Ross Director, O&M, TMI Robert B. Borsum GPU Nuclear, Inc.
B&W Nuclear Technologies
. P.O. Box 480 Suite 525 Middletown, PA 17057 1700 Rockville Pike Rockville, MD 20852 John C. Fomicola Director, Planning and David J. Allard, Director RegulatoryAffairs Bureau of Radiation Protection GPU Nuclear, Inc.
PA Dep. of Environmental Protection l
100 Interpace Par 1<way P.O. Box 8469 Parsippany, NJ 07054 -
Harrisburg, PA 17105-8469 l
Jack S.Wetmore Dr. Judith Johnsrud Manager, TMl Regulatory Affairs National Energy Committee GPU Nuclear, Inc.
Sierra Club P.O. Box 480 433 Orlando Avenue Middletown, PA 17057 State College, PA 16803 Ernest L. Blake, Jr., Esquire Peter W. Eselgroth, Region i Shaw, Pittman, Potts & Trowbridge U.S. Nuclear Regulatory Commission 2300 N Street, NW.
475 Allendale Road Washington, DC 20037 King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Cour1 house Harrisburg, PA 17120 l
Chairman Board of Supervisors of LondonderryTownship R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 RegionalAdministrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406