ML020920654
| ML020920654 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 03/20/2002 |
| From: | Repka D Duke Energy Corp, Winston & Strawn |
| To: | Kelber C, Rubenstein L, Austin Young Atomic Safety and Licensing Board Panel |
| Byrdsong A | |
| References | |
| +adjud/rulemjr200506, 50-369-LR, 50-370-LR, 50-413-LR, 50-414-LR, ASLBP 02-794-01-LR, RAS 4194 | |
| Download: ML020920654 (37) | |
Text
RA-5 4qi4 WINSTON & STRAWN 35 WEST WACKER DRIVE CHICAGO, ILLINOIS 60601-9703 43 RUE DU RHONE 1204 GENEVA, SWITZERLAND 38TH FLOOR 333 SOUTH GRAND AVENUE LOS ANGELES, CALIFORNIA 90071-1543 DAVID A. REPKA (202) 371-5726 drepka@winston.com 1400 L STREET, N.W.
WASHINGTON, D.C. 20005-3502 (202) 371-5700 FACSIMILE (202) 371-5950 www.winston.com March 20, 2002 Ann Marshall Young, Chairman Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 200 PARK AVENUE NEW YORK, NEW YORK 10166-4193 21 AVENUE VICTOR HUGO 75116 PARIS, FRANCE DOCKETED USNRC April 1, 2002 (11:39AM)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Dr. Charles N. Kelber Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Lester S. Rubenstein Administrative Judge 4760 East Country Villa Drive Tucson, Arizona 85718 Re:
In the Matter of Duke Energy Corporation McGuire Nuclear Station, Units 1 and 2 Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-369-LR, 50-370-LR, 50-413-LR. 50-414-LR
Dear Administrative Judges:
In accordance with our obligation to keep the Atomic Safety and Licensing Board and parties informed of new and material developments,1 and as we indicated during the status conference call of March 13, 2002 (Tr. 742-43), we have enclosed two documents dated March 2
14, 2002, incorporating information provided by Duke Energy Corporation ("Duke") to the I
See Duke Power Co. (William B. McGuire Nuclear Station, Units 1 and 2), ALAB-143, 6 AEC 623, 625 (1973).
2 The March 14, 2002 document entitled "Information Provided by Duke Energy Corporation Related to Severe Accident Mitigation Alternatives in Its License Renewal Application for the McGuire Nuclear Station, Units 1 and 2 (TAC Nos. MB2021 and MB2022)" is available in ADAMS at accession number ML020740318. The March 14, 2002 document entitled "Information Provided by Duke Energy Corporation Related to Severe Accident Mitigation Alternatives in Its License Renewal Application for the Catawba Nuclear Station, Units 1 and 2 (TAC Nos. MB2031 and MB2032)" is available at accession number ML020740179.
VINSTON & STRAWN Administrative Judges March 20, 2002 Page 2 NRC Staff. The information was provided in response to teleconferences with the NRC Staff on February 7, 2002 and February 25, 2002, as a follow-up to the Request for Additional Information ("RAP') responses submitted by Duke on January 31, 2002 (for McGuire Nuclear Station) and February 1, 2002 (for Catawba Nuclear Station).
The RAI responses related generally to the license renewal-related Severe Accident Mitigation Alternatives ("SAMA")
Analysis Final Reports for the McGuire and Catawba stations, which were submitted in the license renewal Environmental Reports for those facilities. Thus, these supplemental responses are potentially relevant to BREDL/NIRS Consolidated Contention 2.
The enclosed copies of these two documents are printed from the final electronic file currently available in ADAMS. Although the NRC's cover memorandum for each of the documents indicates the availability of certain data files provided by Duke as attachments to the documents,3 the data files included in ADAMS currently do not include all of the information that Duke submitted with its RAI responses. Accordingly, for the convenience of the parties, Duke has provided paper copies of the attachments in question, based upon its original submittal to the NRC.
Sincerely, David A. Repka Counsel for Duke Energy Corporation cc:
Service List (w/Enclosure)
Page 1 of the NRC cover memorandum for the McGuire document refers to the data files as "Attachment 3;" page 1 of the NRC cover memorandum for the Catawba document refers to the data files as "Attachment 2."
March 14, 2002 NOTE TO:
File FROM:
James H. Wilson, Senior IsIJHWilson Environmental Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation.
SUBJECT:
INFORMATION PROVIDED BY DUKE ENERGY CORPORATION RELATED TO SEVERE ACCIDENT MITIGATION ALTERNATIVES IN ITS LICENSE RENEWAL APPLICATION FOR THE CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (TAC NOS. MB2031 AND MB2032)
As followup to the NRC request for additional information dated December 10, 2001, related to the staff's environmental review for Catawba license renewal and the Duke Energy Corporation (Duke) response dated February 1, 2002, the staff held two telephone conferences with Duke.
In a telephone conference call held on February7, 2002, Duke provided additional information to supplement its Catawba Nuclear Station Severe Accident Mitigation Alternatives (SAMA)
Analysis Final Report, submitted in the environmental report (ER) for Catawba license renewal. summarizes the questions asked by the staff, as well as Duke's responses. Duke is currently using Revision 2b to the Catawba PRA, but has not submitted this information to the NRC elsewhere. Attachment 2 is the printout of 2 data files containing the Catawba release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities Another telephone conference call was held on February 25, 2002, to further supplement information in the Catawba ER and the material provided after the February 7, 2002, telephone conference. Attachment 3 summarizes the questions asked by the staff, as well as Duke's responses.
The Duke Energy Corporation (Duke) provided the information in the designated attachments to the NRC staff via e-mails dated February 13 and March 14, 2002. Because the staff may rely on some of this information in its environmental review of Duke's application for renewal of the Catawba Nuclear Station, Units 1 and 2, licenses, this information is being docketed and made publicly available.
Docket Nos. 50-413 and 50-414 Attachments: As stated
March 14, 2002 NOTE TO:
File FROM:
James H. Wilson, Senior /s/JHWilson Environmental Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation.
SUBJECT:
INFORMATION PROVIDED BY DUKE ENERGY CORPORATION RELATED TO SEVERE ACCIDENT MITIGATION ALTERNATIVES IN ITS LICENSE RENEWAL APPLICATION FOR THE CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (TAC NOS. MB2031 AND MB2032)
As followup to the NRC request for additional information dated November 19, 2001, related to the staff's environmental review for Catawba license renewal, and the Duke Energy Corporation (Duke) response dated January 29, 2002, the staff held two telephone conferences with Duke.
In a telephone conference call held on February7, 2002, Duke provided additional information to supplement its Catawba Nuclear Station Severe Accident Mitigation Alternatives (SAMA)
Analysis Final Report, submitted in the environmental report (ER) for Catawba license renewal. summarizes the questions asked by the staff, as well as Duke's responses. Duke is currently using Revision 2b to the Catawba PRA, but has not submitted this information to the NRC elsewhere. Attachment 2 is the printout of 2 data files containing the McGuire release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities Another telephone conference call was held on February 25, 2002, to further supplement information in the Catawba ER and the material provided after the February 7, 2002, telephone conference. Attachment 3 summarizes the questions asked by the staff, as well as Duke's responses.
The Duke Energy Corporation (Duke) provided the information in the designated attachments to the NRC staff via e-mails dated February 13 and March 14, 2002. Because the staff may rely on some of this information in its environmental review of Duke's application for renewal of the Catawba Nuclear Station, Units I and 2, licenses, this information is being docketed and made publicly available.
Docket Nos. 50-413 and 50-414 Attachments: As stated Accession no: 1. Note to file, w/att(s) 1, 2 and 3 only: ML020740179 Accession no: 2. Aft. 3: ML DISTRIBUTION:
Environmental R/F JHWilson RPalla JTappert SUttal RI
- See previous concurrence DOCUMENT NAME: G:\\RPRP\\Catawba\\SAMA\\Docketing note-SAMA.wpd OFFICE PM:RLEP SCSB SC:RLEP NAME JHWilson*
RPalIa*
JTappert*
DATE 03/14/02 03/14/02 03/14/02 OFFICIAL FILE COPY Harty (PNNL)
Documentation of Information Provided in Teleconference held on February 7, 2002
- 1.
Provide the release category matrix for the baseline risk study and for the sensitivity case used to develop the response to RAI 4.
RESPONSE: In determining the risk impact based on the NUREG/CR-6427 weighted value of 34% for early containment failure probability, the Catawba PRA Revision 2b release category matrix (RCM) is modified by reallocating only the release category frequencies for those PDSs identified as SBOs in the RCM such that the early containment failure probability is 34%. From the Catawba PRA Revision 2b analysis the fast station blackout PDSs are 8PI, 8PS, 14PI, 14PS and 20PI, and the slow station blackout PDSs are 4PI, 4PS, 7PI, 7PS, 15PI and 15PS (note that small containment isolation failures are included since some of these PDSs end up in early containment failures) - a description of the PDSs can be found in the section 6.1 of the Catawba IPE report. The early containment failure frequencies in the RCM (RC501 and RC502) were increased proportionally.
Attached (Attachment 2) is a data file containing the Catawba release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities
.2.
Provide an approximate estimate of the costs associated with implementing the following 2 SAMAs at the Duke plants, broken down by general cost categories, such as engineering, materials, labor, administrative, or equivalent. It is our expectation that: (1) all equipment/hardware would be non-safety related, (2) procedures and any related training would be developed and maintained in accordance with existing plant practices applicable to the severe accident management guidelines, (3) no licensee submittals or changes to the FSAR or technical specifications would be involved.
RESPONSE
Option 1 - (a severe accident management procedure to power a subset of the igniters
[e.g., one train] from a portable generator or equivalent ac-independent power source.
This change would not address backup power to air return fans. [The generator need not be dedicated or pre-staged if there is sufficient time to locate, position, and connect it prior to the onset of core damage, e.g., several hours in the frequency-dominant SBO.])
This potential modification would require a 50.59 review which may result in changes to the design and additional costs not contained in the present estimate. This option does not provide for tornado protection of the generating source and is not seismically designed. Seismic and tornado are significant contributors to the overall SBO CDF.
Including such features to the design would significantly increase the cost of the option.
Engineering
$5,000 Materials
$50,000 Installation Labor
$110,000 Maint and Operations
$40,000 TOTAL
$205,000 Option 2 - (a severe accident management procedure to power a subset of the igniters plus one air return fan from an ac-independent power source)
This potential modification would require a 50.59 review which may result in changes to the design and additional costs not contained in the present estimate.This option does not provide for tornado protection of the generating source and is not seismically designed. Seismic and tornado are significant contributors to the overall SBO CDF.
Including such features to the design would significantly increase the cost of the option.
Engineering
$50,000 Materials
$210,000 Installation Labor
$240,000 Maint and Operations $40,000 TOTAL
$540,000
- 3.
Provide the basis for the cost estimates provided for the following 2 SAMAs, and a specific dollar value or range of dollar values (in lieu of the general statement ">1$M"):
(1) Install automatic swap-over to high pressure recirculation, and (2) Install automatic swap to RV cooling/other unit RN system upon loss of RN.
RESPONSE
From Page 7-8 of the Watts Bar SAMA report (reference NUREG-0498, Supp. 1), an alternative considered in the cost benefit analysis was:
"Category I - Improve Availability of ECCS Recirculation - Install automatic high-pressure recirculation (1.4): automate the alignment of ECCS recirculation to the high-pressure charging and safety injection pumps. This would reduce the potential for related human errors made during manual realignment."
On Page 7-9 of the above mentioned report, Table 7.4 (Summary of Value/Impact Study Results) provides the cost estimate for this alternative to be on the order of $2.1 million.
This cost estimate applies to both SAMAs (1) and (2).
ATTACHMENT 2 (Catawba base release category matrices)
C1 1 R12 R13 R14 R21 R20 C0 C0 C0 C0 C303 RC304 RC05 R3 0
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0.01 0.005 0
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0.01 0.009 0
0.01 0.00851 0
0.0049 0
0.00431 0
0 0
0 0.891 0.009 0.45 0.000045 0
0 0
0 0
0 0.891 0.009 0.802 0.0081 0
0 0.891 0.009 0.77 0.000077 0
0 0
0.0297 0
0 0
0.0262 0
0 0
0 0 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 0
0 0
0 0
0 0
0 0
0 0.00369 0
0.00324 0
0
Documentation of Information Provided in Teleconference held on February 25, 2002 Provide a description of the assumptions on which the risk reduction for the 3rd diesel was based (i.e.., diverse but not seismic), and the types of sequences/failures that would not be addressed by the 3rd (non-seismic) diesel.
RESPONSE: Section 4.3 of the SAMA submittal (see Attachment H of the Environmental Report) provides a discussion of how the seismic and non-seismic initiators were treated separately in the SAMA analysis. The reason for separating out the seismic from non-seismic initiators in the SAMA analysis is that for the seismic initiator extensive plant damage is expected to occur resulting in failures of multiple pieces of equipment/components. Therefore, to mitigate such an event would require substantial upgrades to the plant systems seismic ruggedness. The CDF reductions reported in the SAMA submittal are for the non-seismic initiating events.
The intent of our estimation of the risk reduction associated with the installation of a third diesel was to maximize the potential benefit by assuming that the third diesel was perfectly reliable, no random failure modes and no common cause connections to the essential diesels. This was to be accomplished by setting the existing diesel generator failure modes to 0 in the cutset file thus eliminating all blackout sequences. In practice, we did this by identifying and setting to 0 the dominant failure modes of the diesel generators, as described in Attachment H of the Environmental Report. Some residual CDF related to diesel failures did remain in the solution. The SAMA analysis estimated the change in CDF from installation of a third diesel to be 1.6E-05. This change comes from the reduction in the CDF contributions from the non-seismic initiators (turbine building flood, LOOP, all consuming turbine building fire, tornado initiators, etc.).
Remember that the seismic considerations were addressed independently. This reduction is approximately 89% of the estimated benefit (-1.8E-05) if every single diesel generator failure event had been set to 0 rather than simply addressing the dominant contributors. The change in CDF provided in the SAMA submittal provides a reasonable estimate of the reduction expected by a highly reliable and diverse alternate ac power source.
The intent was to present a change in CDF consistent with the complete elimination of all diesel generator failure modes, perfect reliability and diversity.
- 2.
Provide a description of the additional risk reduction that would be achieved by making the 3rd diesel seismic, and the types of sequences/failures that not be addressed by the 3rd (seismic) diesel.
RESPONSE: A sensitivity study has been conducted to evaluate the impact that a third diesel could have on the seismic results. No cost estimate has been developed for providing a seismically qualified diesel. As was done for the non-seismic analysis, the random failure modes of the diesels were removed form the model. The resulting change in CDF is approximately 4E-07. The seismic results are dominated by seismic failures in the 4 kV power system for which improving diesel generator availability provides no benefit.
- 3.
Provide the expected risk reduction for the dedicated power line from the nearby hydro station (i.e., equivalent to adding a 3rd (seismic?) diesel), and the supporting rationale (i.e., that the HCLPF for hydro stations would typically be less than for a seismic diesel).
RESPONSE: A dedicated and tornado protected line from the Wylie hydro-electric station could provide a CDF reduction similar to the estimate provided for the third diesel in the SAMA analysis. However, the result does not address potential common cause failure of the hydro-electric station as a result of the same tornado that causes the loss of offsite power to occur. The seismic fragilities of the hydro-electric plant would be expected to be lower than most of the essential systems at Catawba.
- 4.
Provide a brief description of the SAMA on which the $205K and $540K estimates were based. This information is needed in order to put the various cost elements (engineering, materials, installation labor, and maintenance) in perspective. The response should clarify whether the SAMA/cost estimates: assume the generator is dedicated? pre-staged? would be located inside or outdoors?; include the cost of a pad or enclosure building? power cables (and their approximate length)? installing disconnects? routine surveillance and maintenance costs for remaining plant life?
RESPONSE: The design requires an installed dedicated diesel because powering of the igniters needs to occur prior to the onset of core damage. The diesel is located outdoors for ventilation and exhaust considerations. Initiation and operation of the diesel will occur prior to the onset of core damage and thus will be covered by the emergency operating procedures rather than the severe accident management guidelines which are entered after core damage occurs.
The cost estimates provided assumed one new dedicated diesel generator set, prestaged and located outside on a concrete pad for each station. No enclosure was included in the estimate. Approximately 900 feet of cable and nine circuit breakers would need to be installed and are included in the cost estimate. Initial procedure development costs were included in the cost estimate. However, ongoing routine surveillance and maintenance costs were not included. Also, this cost estimate does not include tornado protection of the diesel generator set nor does it include any seismic design.
- 5.
Based on information provided in response to RAI 6c and RAI 8 (Table 8-3), it appears that installation of a watertight wall, if it achieves the same risk reduction as "manning the SSF 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day", may be cost beneficial. In this regard, please:
- a. Provide the estimated risk reduction (CDF and person-rem) and averted risk benefit for the alternative SAMA involving installation of a watertight wall. Describe which sequences/failure modes are eliminated by the SAMA, and which ones would remain.
RESPONSE: To estimate the maximum benefit associated with installing a watertight wall around the 6900/4160V Iransformers the same methodology implemented in the SAMA submittal is used here. This alternative has the potential to significantly reduce the risk associated with severe accident sequences involving turbine building flood initiators. Therefore, it is assumed that the installation of this watertight wall would completely eliminate the turbine building flood initiator severe accident sequences from the cut set file. To determine the maximum risk reduction possible for this alternative the turbine building flood initiator was set to 0 in the cut set file. The maximum estimated CDF reduction is 1.4E-05 per yr with a person Rem risk reduction of 12.4 person-Rem.
Based on these risk reduction values, over the 46-year current and license renewal period the maximum estimated benefit is approximately $1.1 million (averted public exposure = $3.4E+05, averted onsite cleanup cost = $2.1 E+05, averted onsite exposure cost = $6.8E+03, averted offsite property damage cost = $7.0E+04, and averted power replacement cost = $4.5E+05).
The estimate of the benefit provided above is based, as is the SAMA submittal, on Revision 2b of the Catawba PRA. Catawba has recently installed reactor coolant pump seals that use o-ring materials that perform better at high temperature. This plant modification is expected to reduce the probability of a reactor coolant pump seal LOCA following a loss of seal cooling. Since a large fraction of the core damage sequences initiated by the turbine building flood involve seal LOCAs, the modification will reduce the CDF contribution form the flood and consequently reduce the change in CDF associated with the construction of a watertight wall. A sensitivity study has been performed to estimate the impact of the new seals on the benefit calculation.
Considering the performance of the new seals, the change in CDF associated with the construction of the wall is estimated to be 1 E-05. The estimated benefit is less than
$870,000 with a person Rem risk reduction of 15.1 person-Rem.
- b. Provide a description and breakdown of the major costs that contribute to the estimated cost of $500K to install a watertight wall.
RESPONSE: The estimated cost to install this modification in one Catawba unit is
$250K The estimated cost breakdown is $75K for engineering, $25K for materials,
$150Kfor installation labor. Ongoing costs (i.e., maintenance of a sump pump) have not been included in this estimate. These cost estimates are for scoping purposes only and are subject to change.
- 6.
Provide a breakdown of the Catawba SBO CDF in terms of internal events, seismic, fire, flood, tornado, etc.
RESPONSE
INTERNAL INITIATOR Core Damage Freq. (per yr) 71 Peactor Trip 1.6E-08 a2 Loss of Load 1.0E-09 r3 OOP 1.6E-06 T4 ss of Main Feedwater 1.1E-09 r9 loss of RN 9.3E-09 l1 Loss Of 4160 V Essential Bus 9.6E-08 FTB Turbine Building Flood 1.3E-05 EXTERNAL INITIATOR Core Damage Freq. (per yr)
FACTB ll Consuming TB Fire 1.7E-07 CBLR Cable Room Fire Causes A Loss Of CCW 1.8E-08 FETB TB Fire Initiating Event 1.5E-09
'CR ontrol Room Fire Causes A Loss Of KC 1.0E-08 SEISMIC leismic 8.4E-06 FORNF4 Plant Struck By F4 Or F5 Tornado 4.E-07 FORNSW ornado Causes LOOP 1.5E-06
March 14, 2002 NOTE TO:
File FROM:
James H. Wilson, Senior /slJHWilson Environmental Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation.
SUBJECT:
INFORMATION PROVIDED BY DUKE ENERGY CORPORATION RELATED TO SEVERE ACCIDENT MITIGATION ALTERNATIVES IN ITS LICENSE RENEWAL APPLICATION FOR THE MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TAC NOS. MB2021 AND MB2022)
As followup to the NRC request for additional information dated November 19, 2001, related to the staff's environmental review for McGuire license renewal, and the Duke Energy Corporation (Duke) response dated January 29, 2002, the staff held two telephone conferences with Duke.
In a telephone conference call held on February7, 2002, Duke provided additional information to supplement its McGuire Nuclear Station Severe Accident Mitigation Alternatives (SAMA)
Analysis Final Report, submitted in the environmental report (ER) for McGuire license renewal. summarizes the questions asked by the staff, as well as Duke's responses. Duke is currently developing Revision 3 to the McGuire PRA, but has not submitted this information to the NRC elsewhere. Attachment 2 is a McGuire PRA Revision 3 results summary. Attachment 3 is the printout of 2 data files containing the McGuire release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities.
Another telephone conference call was held on February 25, 2002, to further supplement information in the McGuire ER and the material provided after the February 7, 2002, telephone conference. Attachment 4 summarizes the questions asked by the staff, as well as Duke's responses.
The Duke Energy Corporation (Duke) provided the information in the designated attachments to the NRC staff via e-mails dated February 13 and March 13, 2002. Because the staff may rely on some of this information in its environmental review of Duke's application for renewal of the McGuire Nuclear Station, Units 1 and 2, licenses, this information is being docketed and made publidy available.
Docket Nos. 50-369 and 50-370 Attachments: As stated
March 14, 2002 NOTE TO:
File FROM:
James H. Wilson, Senior Is/JHWilson Environmental Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation.
SUBJECT:
INFORMATION PROVIDED BY DUKE ENERGY CORPORATION RELATED TO SEVERE ACCIDENT MITIGATION ALTERNATIVES IN ITS LICENSE RENEWAL APPLICATION FOR THE MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TAC NOS.
MB2021 AND MB2022)
As followup to the NRC request for additional information dated November 19, 2001, related to the staff's environmental review for McGuire license renewal, and the Duke Energy Corporation (Duke) response dated January 29, 2002, the staff held two telephone conferences with Duke.
In a telephone conference call held on February 7, 2002, Duke provided additional information to supplement its McGuire Nuclear Station Severe Accident Mitigation Alternatives (SAMA) Analysis Final Report, submitted in the environmental report (ER) for McGuire license renewal. Attachment 1 summarizes the questions asked by the staff, as well as Duke's responses. Duke is currently developing Revision 3 to the McGuire PRA, but has not submitted this information to the NRC elsewhere. Attachment 2 is a McGuire PRA Revision 3 results summary. Attachment 3 is the printout of 2 data files containing the McGuire release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities.
Another telephone conference call was held on February 25, 2002, to further supplement information in the McGuire ER and the material provided after the February 7, 2002, telephone conference. summarizes the questions asked by the staff, as well as Duke's responses.
The Duke Energy Corporation (Duke) provided the information in the designated attachments to the NRC staff via e-mails dated February 13 and March 14, 2002. Because the staff may rely on some of this information in its environmental review of Duke's application for renewal of the McGuire Nuclear Station, Units 1 and 2, licenses, this information is being docketed and made publicly available.
Docket Nos. 50-369 and 50-370 Attachments: As stated DISTRIBUTION:
Environmental R/F JHWilson RPalla JTappert SUttal RHarty (PNNL)
Accession nos.
- 1. Note to file, Att(s) 1, 2, and 4: ML020740318
- See previous concurrence DOCUMENT NAME:
G:\\RPRP\\McGuire\\Docketing note-SAMA.wIpd OFFICE PM:RLEP SCSB SC:RLEP NAME JHWilson*
RPalla*
JTappert*
DATE 03/14/02 03/14/02 03/14/02 OFFICIAL FILE COPY
Documentation of Information Provided in Teleconference held on February 7, 2002
- 1.
Provide the core damage frequency estimates from Rev 3 of the McGuire PRA, broken out by the major contributors in a way that they can be directly compared to the Rev 2 results reported in Section 4.1 of the ER, and in the response to RAI la. Please be certain to include the frequencies of the following events: transients, LOCAs, internal flood, ATWS, SBO/LOOP, SGTR, and ISLOCA. A further break down by internal events, external events, and combined would be helpful.
RESPONSE: (See McGuire PRA Revision 3 results summary - Attachment 2)
- 2.
Provide the release category matrix for the baseline risk study and for the sensitivity case used to develop the response to RAI 4.
RESPONSE: In determining the risk impact based on the NUREG/CR-6427 weighted value of 58% for early containment failure probability, the McGuire PRA Revision 2 release category matrix (RCM) is modified by reallocating only the release category frequencies for those PDSs identified as SBOs in the RCM such that the early containment failure probability is 58%. From the McGuire PRA revision 2 analysis the fast station blackout PDSs are 8PI and 14PI, and the slow station blackout PDSs are 4PI, 7PI, 7PS, and 15PI (note that small containment isolation failures are included since some of these PDSs end up in early containment failures) - a description of the PDSs can be found in the section 6.1 of the McGuire IPE report. The early containment failure frequencies in the RCM (RC501 and RC502) were increased proportionally.
Attached (Attachment 3) is a data file containing the McGuire and Catawba release category matrices (RCMs) used in the PRA analyses and the modified RCMs assuming the NUREG/CR-6427 weighted early containment failure probabilities
- 3.
Provide an approximate estimate of the costs associated with implementing the following 2 SAMAs at the Duke plants, broken down by general cost categories, such as engineering, materials, labor, administrative, or equivalent. It is our expectation that: (1) all equipment/hardware would be non-safety related, (2) procedures and any related training would be developed and maintained in accordance with existing plant practices applicable to the severe accident management guidelines, (3) no licensee submittals or changes to the FSAR or technical specifications would be involved.
RESPONSE
Option 1 - (a severe accident management procedure to power a subset of the igniters
[e.g., one train] from a portable generator or equivalent ac-independent power source.
This change would not address backup power to air return fans. [The generator need not be dedicated or pre-staged if there is sufficient time to locate, position, and connect it prior to the onset of core damage, e.g., several hours in the frequency-dominant SBO.])
Attachment I This potential modification would require a 50.59 review which may result in changes to the design and additional costs not contained in the present estimate. This option does not provide for tornado protection of the generating source and is not seismically designed. Seismic and tornado are significant contributors to the overall SBO CDF.
Including such features to the design would significantly increase the cost of the option.
Engineering
$5,000 Materials
$50,000 Installation Labor
$110,000 Maint and Operations
$40,000 TOTAL
$205,000 Option 2 - (a severe accident management procedure to power a subset of the igniters plus one air return fan from an ac-independent power source)
This potential modification would require a 50.59 review which may result in changes to the design and additional costs not contained in the present estimate.This option does not provide for tornado protection of the generating source and is not seismically designed. Seismic and tornado are significant contributors to the overall SBO CDF.
Including such features to the design would significantly increase the cost of the option.
Engineering
$50,000 Materials
$210,000 Installation Labor
$240,000 Maint and Operations
$40,000 TOTAL
$540,000
- 4.
Provide the basis for the cost estimates provided for the following 2 SAMAs, and a specific dollar value or range of dollar values (in lieu of the general statement ">1$M"):
(1) Install automatic swap-over to high pressure recirculation, and (2) Install automatic swap to RV cooling/other unit RN system upon loss of RN.
RESPONSE
From Page 7-8 of the Watts Bar SAMA report (reference NUREG-0498, Supp. 1), an alternative considered in the cost benefit analysis was:
"Category I - Improve Availability of ECCS Recirculation - Install automatic high-pressure recirculation (1.4): automate the alignment of ECCS recirculation to the high-pressure charging and safety injection pumps. This would reduce the potential for related human errors made during manual realignment."
On Page 7-9 of the above mentioned report, Table 7A (Summary of Value/Impact Study Results) provides the cost estimate for this alternative to be on the order of $2.1 million.
This cost estimate applies to both SAMAs (1) and (2).
McGuire PRA Revision 3 results summary Initiator Core Damage
% of CDF SEISMIC 8.9E-06 19.3%
TORNSW 1.5E-06 3.3%
FIRES 6.3E-06 13.7%
Internal Floods 5.4E-06 11.7%
Transients 2.8E-06 6.2%
LOCAs 1.9E-05 40.4%
RPV Rupture 1.OE-06 2.2%
SGTR 5.3E-07 1.1%
ATWS 5.3E-07 1.1%
ISLOCA 9.8E-07 2.1%
Total CDF 4.6E-05 1 SBO Frequency 1.OE-05 22.2%
Seismic 7.4E-06 Tornado 1.5E-06 LOOP 1.3E-06
- 1. This is the CDF found in the official results file, summing the contributors as listed in this table provides a slightly higher number due to round-off error.
ATTACHMENT 3 (McGuire base release category matrices)
U.uIuz 0.0107 0.000922 0.00882 0.00107 0.000874 0.00882 0
0 0
0 0
0.00106 0.00106 0
0 0
0 0.000534 0.00107 0.000981 0
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0.000081 0.00884 0
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0 0.00851 0.000946 0
0 0
0 0.00851 0.000946 "1.U/-Uo 1.16E-05 5.83E-05 0.000981 1.07E-07 0.000107 0.000981 0
0 0
0 0
5.39E-06 5.39E-06 0
0 0
0 5.34E-08 1.16E-06 0.000109 0
0 0
0 0
0 0
0 0
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0 0
0 0
9.91 E-06 0.000982 Wd.Oor--VU 0.000103 8.9E-06 8.51 E-05 1.07E-05 8.43E-06 8.51 E-05 0
0 0
0 0
1.07E-05 1.07E-05 0
0 0
0 0.000543 1.08E-05 0.899 0
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7.23E-06 6.93E-05 9.88E-09 1.12E-07 5.63E-07 9.46E-06 1.07E-09 1.03E-06 9.46E-06 0
0 0
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5.44E-08 5.44E-08 0
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0 5.43E-08 1.17E-08 0.0999 0
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8.84E-07 7.7E-06 0 0 0
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0.892 0.0991 0
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0.884 0.0982 0
0.009 0
0 0.899 0
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0.009 0
0 0.009 0
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0 0.0999 0
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0 0.001 0
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0.001 0
0 0.001 0
0.01 0
0 0.000903 0
0 0.00077 U
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0
RC40 RC02 C0 C0 RC0
-4 RC0 C407 RC083 C61ýR52 R61 R62-C6-
ý64" C0 0
0 0
0 0
0 0
0 0.0257 2.82E-05 0
0 0
0 0
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0 0
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0.0257 2.82E-05 0.0446 0.000451 0.0404 0.000408 0.000448 0
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0 0.24 0.00217 0.111 0.0202 0.00541 0.0171 0.00111 0
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1/40 0
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0.00259 2.84E-06 0
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0.186 0.0016 0.221 0.0404 0.0108 0.0342 0.00223 0
0 0
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0 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000493 4.51E-06 0.218 0.223 0.00213 0.00217 0.0022 0
0 0
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0.891 0.099 0.009 0.000999 0
0 0
0 0.000493 4.51E-06 0
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0 0 4.95E-08 5E-10 0
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0 0.000259 2.85E-07 0.4 0.00404 0.0409 0.000413 0.00404 0
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0 0.000493 4.51E-06 0
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0 0 0.000542 5.24E-06 0.0873 0.000882 0.000852 8.61 E-06 0.000882 0
0 0
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0 0
0.891 0.0989 0.00899 0.000999 0
0 0
0 0.000542 5.24E-06 0
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0 0 0.000259 2.85E-07 0
0 0
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0 0 0.000259 2.85E-07 0.0799 0.000807 0.00818 8.26E-05 0.000807 0
0 0
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0 0
0 0
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0 4.95E-08 5E-10 0
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0 0
0 0 4.95E-08 5E-10 0
0 0
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0 0
0 0
0 0
9.9E-08 1E-09 0.803 0.00812 0.0786 0.000794 0.00812 0
0 0
0 0
0 0
0 0.158 0.00164 0.242 0.0707 0.00217 0.0067 0.00244 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 4.99E-06 5.05E-08 0
0 0
0 0
0 0
0 0
0 0
0 0 9.99E-06 1.01 E-07 0.0874 0.000883 0.000786 7.94E-06 0.000883 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000493 4.51E-06 0.873 0.00882 0.00852 8.61 E-05 0.00882 0
0 0
0 0
0 0
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0 0
0 0
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0 0
0 0
0 0
0 0
0.0794 0.000301 0
0.748 0
0.0724 0
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0.139 0.00697 0.102 0.315 0.00991 0.0304 0.0021 0
0 0
0 0
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0.0902 0
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0 0.139 0.00697 0
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0.255 0.00394 0.188 0.0365 0.00784 0.0252 0.00367 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
RC0 R67 R
C608 RC0
-C0tC73 R74 RC801
~RC8 ' 2.
RC0 C0 6 C0 C0 0
0 0
0 0
0 0
0.0849 0.00943 0.87 0.000087 0
0 4.53E-06 0.000391 3.95E-06 0.00945 9.54E-05 9.33E-05 9.42E-07 0.0763 0.00848 0.782 7.82E-05 0
0 0.000202 5.43E-05 0.000167 0.0129 0.00415 0.00013 0.000041 0.051 0.00567 0.523 0.00528 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.0895 0.00994 0.897 8.97E-05 0
0 0,000405 0.000109 0.000334 0.0258 0.00829 0.00026 8.21E-05 0.0407 0.00453 0.418 0.00422 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00225 2.15E-05 2.19E-05 0.0245 0.025 0.000247 0.000252 0.045 0.005 0.448 0.00227 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00009 0.0999 0.0009 9E-08 0.899 8.99E-05 0
0 0
0 0
0 0
0 0
0 0
0 0
4.08E-05 0.000412 4.16E-06 0.0489 0.000494 0.000494 4.99E-06 0.0449 0.00499 0.449 4.49E-05 0
0 4.08E-05 0.000412 4.16E-06 0.0489 0.000494 0.000494 4.99E-06 0.0449 0.00499 0.449 4.49E-05 0
0 0
0 0
0 0
0 0
0.09 0.00999 0.899 0.00009 0
0 8.91 E-06 8.6E-06 8.69E-08 0.0098 9.89E-05 9.89E-05 9.99E-07 0.081 0.00899 0.809 0.000081 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.045 0.0549 0.45 0.000045 0.449 4.49E-05 8.15E-06 8.25E-05 8.33E-07 0.00979 9.89E-05 9.88E-05 9.98E-07 0.0809 0.00899 0.809 8.09E-05 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00009 0.0999 0.0009 9E-08 0.899 8.99E-05 0
0 0
0 0
0 0
0.045 0.055 0.45 0.000045 0.45 0.000045 0.000082 0.000794 8.02E-06 0.098 0.00099 0.00099 0.00001 0
0 0
0 0
0 0.00071 2.19E-05 6.72E-05 0.0271 0.0086 0.000274 8.63E-05 0.0428 0.00476 0.428 0.00433 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.09 0.01 0.9 0.00009 0
0 8.92E-06 7.94E-06 8.02E-08 0.0098 0.000099 0.000099 0.000001 0.081 0.009 0.81 0.000081 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
8.91 E-05 0.000086 8.69E-07 0.098 0.00099 0.000989 9.99E-06 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00716 0 0.000693 0
0.0912 0 0.000873 0
0 0
0 0
0 0.037 0.000204 0.00358 0.0125 0.0383 0.000256 0.00451 0.022 0.00645 0.232 0.00234 0.0357 0.00036 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.00457 0.000136 0.00249 0.0217 0.00685 0.000423 0.000784 0.0296 0.00956 0.344 0.00348 0.0558 0.000564 0
0 0
0 0
0 0
0 0
0 0
0 0
ATTACHMENT 3 (McGuire modified release category matrices)
RC101 C10 RC0 C04 R21 R202
~'20 RC20 RC1 R32 R33 R34 RC305 RC0 0.0102 1.02E-06 9.88E-05 9.88E-09 0
0 0
0 0
0 0
0 0
0 0.0107 1.16E-05 0.000103 1.12E-07 0
0 0
0 0
0 0
0 0
0 0.000922 5.83E-05 8.9E-06 5.63E-07 0
0 0
0 0
0 0
0 0
0 0.00882 0.000981 8.51 E-05 9.46E-06 0
0 0
0 0.883 0.0981 0.00851 0.000946 0
0 0.00107 1.07E-07 1.07E-05 1.07E-09 0
0 0
0 0
0 0
0 0
0 0.000874 0.000107 8.43E-06 1.03E-06 0
0 0
0 0
0 0
0 0
0 0.00882 0.000981 8.51E-05 9.46E-06 0
0 0
0 0.883 0.0981 0.00851 0.000946 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.891 0.099 0.009 0.001 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.000891 0.000099 0.899 0.0999 0
0 0.00106 5.39E-06 1.07E-05 5.44E-08 0
0 0
0 0
0 0
0 0
0 0.00106 5.39E-06 1.07E-05 5.44E-08 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.891 0.099 0.009 0.001 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.000534 5.34E-08 0.000543 5.43E-08 0
0 0
0 0
0 0
0 0
0 0.00107 1.16E-06 1.08E-05 1.17E-08 0
0 0
0 0
0 0
0 0
0 0.000981 0.000109 0.899 0.0999 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00099 0
0.999 0
0 0
0 0
0 0
0 0
- 0.
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.891 0.099 0.009 0.001 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.891 0.099 0.009 0.001 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.99 0
0.01 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.892 0.0991 0.00813 0.000903 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.000081 9.91 E-06 7.23E-06 8.84E-07 0
0 0
0 0
0 0
0 0
0 0.00884 0.000982 6.93E-05 7.7E-06 0
0 0
0 0.884 0.0982 0.00693 0.00077 0
0
RC401 R0402 RC0 RC0 R46 RC40 0
0 40 RC408 RC0I C0 C0 C0 RC60 RC04 C0 0
0 0
0 0
0 0
0 0.0257 2.82E-05 0
0 0
0 0
0 0
0 0
0 0
0 0
0.0257 2.82E-05 0.0446 0.000451 0.0404 0.000408 0.000448 0
0 0
0 0
0 0
0 0.576551 0.00557 0.111 0.0202 0.00541 0.0171 0.00111 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00259 2.84E-06 0
0 0
0 0
0 0
0 0
0 0
0 0 0.574991 0.005529 0.221 0.0404 0.0108 0.0342 0.00223 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000493 4.51E-06 0.218 0.223 0.00213 0.00217 0.0022 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.891 0.099 0.009 0.000999 0
0 0
0 0.000493 4.51E-06 0
0 0
0 0
0 0
0 0
0 0
0 0 4.95E-08 5E-10 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.000259 2.85E-07 0.4 0.00404 0.0409 0.000413 0.00404 0
0 0
0 0
0 0
0 0.000259 2.85E-07 0.4 0.00404 0.0409 0.000413 0.00404 0
0 0
0 0
0 0
0 0.000493 4.51E-06 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000542 5.24E-06 0.0873 0.000882 0.000852 8.61 E-06 0.000882 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.891 0.0989 0.00899 0.000999 0
0 0
0 0.000542 5.24E-06 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000259 2.85E-07 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000259 2.85E-07 0.0799 0.000807 0.00818 8.26E-05 0.000807 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 4.95E-08 5E-10 0
0 0
0 0
0 0
0 0
0 0
0 0 4.95E-08 5E-10 0
0 0
0 0
0 0
0 0
0 0
0 0
9.9E-08 1E-09 0.803 0.00812 0.0786 0.000794 0.00812 0
0 0
0 0
0 0
0 0.573246 0.005834 0.242 0.0707 0.00217 0.0067 0.00244 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 4.99E-06 5.05E-08 0
0 0
0 0
0 0
0 0
0 0
0 0 9.99E-06 1.01 E-07 0.0874 0.000883 0.000786 7.94E-06 0.000883 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 0.000493 4.51E-06 0.873 0.00882 0.00852 8.61E-05 0.00882 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.0794 0.000301 0
0.748 0
0.0724 0
0 0
0 0
0 0
0 0 0.549733 0.028588 0
0.2835 0.00991 0.0304 0.0021 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.32852 0
0.0902 0
0 0
0 0.552706 0.028744 0
0 0
0 0
0 0
0 0
0 0
0 0 0.571893 0.010682 0.188 0.0365 0.00784 0.0252 0.00367 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
~RC606_
RC607
~RC608 RdCTOI
?RC702
- R70
- hC704, R6CO T1 -- R802 -RC90~1 jRC902 RC903~ RC904t 0
0 0
0 0
0 0
0.0849 0.00943 0.87 0.000087 0
0 4.53E-06 0.000391 3.95E-06 0.00945 9.54E-05 9.33E-05 9.42E-07 0.0763 0.00848 0.782 7.82E-05 0
0 0.000202 5.43E-05 0.000167 0.0129 0.00415 0.00013 0.000041 0.051 0.00567 0.18305 0.00528 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.0895 0.00994 0.897 8.97E-05 0
0 0.000405 0.000109 0.000334 0.0258 0.00829 0.00026 8.21 E-05 0.0407 0.00453 0.02508 0.00422 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00225 2.15E-05 2.19E-05 0.0245 0.025 0.000247 0.000252 0.045 0.005 0.448 0.00227 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00009 0.0999 0.0009 9E-08 0.899 8.99E-05 0
0 0
0 0
0 0
0 0
0 0
0 0
4.08E-05 0.000412 4.16E-06 0.0489 0.000494 0.000494 4.99E-06 0.0449 0.00499 0.449 4.49E-05 0
0 4.08E-05 0.000412 4.16E-06 0.0489 0.000494 0.000494 4.99E-06 0.0449 0.00499 0.449 4.49E-05 0
0 0
0 0
0 0
0 0
0.09 0.00999 0.899 0.00009 0
0 8.91 E-06 8.6E-06 8.69E-08 0.0098 9.89E-05 9.89E-05 9.99E-07 0.081 0.00899 0.809 0.000081 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.045 0.0549 0.45 0.000045 0.449 4.49E-05 8.15E-06 8.25E-05 8.33E-07 0.00979 9.89E-05 9.88E-05 9.98E-07 0.0809 0.00899 0.809 8.09E-05 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00009 0.0999 0.0009 9E-08 0.899 8.99E-05 0
0 0
0 0
0 0
0.045 0.055 0.45 0.000045 0.45 0.000045 0.000082 0.000794 8.02E-06 0.098 0.00099 0.00099 0.00001 0
0 0
0 0
0 0.00071 2.19E-05 6.72E-05 0.0271 0.0086 0.000274 8.63E-05 0.0428 0.00476 0.00856 0.00433 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.09 0.01 0.9 0.00009 0
0 8.92E-06 7.94E-06 8.02E-08 0.0098 0.000099 0.000099 0.000001 0.081 0.009 0.81 0.000081 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
8.91 E-05 0.000086 8.69E-07 0.098 0.00099 0.000989 9.99E-06 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.00716 0 0.000693 0
0.0912 0 0.000873 0
0 0
0 0
0 0.037 0.000204 0.00358 0.0125 0.0383 0.000256 0.00451 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0.00457 0.000136 0.00249 0.0217 0.00685 0.000423 0.000784 0.0296 0.00956 0.02064 0.00348 0.0558 0.000564 0
0 0
0 0
0 0
0 0
0 0
0 0
Documentation of Information Provided in Teleconference held on February 25, 2002
- 1.
Provide a description of the assumptions on which the risk reduction for the 3rd diesel was based (i.e.., diverse but not seismic), and the types of sequences/failures that would not be addressed by the 3rd (non-seismic) diesel.
RESPONSE: Section 4.3 of the SAMA submittal (see Attachment K of the Environmental Report) provides a discussion of how the seismic and non-seismic initiators were treated separately in the SAMA analysis. The reason for separating out the seismic from non-seismic initiators in the SAMA analysis is that for the seismic initiator extensive plant damage is expected to occur resulting in failures of multiple pieces of equipment/components. Therefore, to mitigate such an event would require substantial upgrades to the plant systems seismic ruggedness. The CDF reductions reported in the SAMA submittal are for the non-seismic initiating events.
The intent of our estimation of the risk reduction associated with the installation of a third diesel was to maximize the potential benefit by assuming that the third diesel was perfectly reliable, no random failure modes and no common cause connections to the essential diesels. This was to be accomplished by setting the existing diesel generator failure modes to 0 in the cutset file thus eliminating all blackout sequences. In practice, we did this by identifying and setting to 0 the dominant failure modes of the diesel generators, as described in Attachment K of the Environmental Report. Some residual CDF related to diesel failures did remain in the solution. The SAMA analysis estimated the change in CDF from installation of a third diesel to be 8.4E-06. This change comes from the reduction in the CDF contributions from the LOOP and tornado initiators.
Remember that the seismic considerations were addressed independently. This reduction is approximately 92% of the estimated benefit (-9.OE-6) if every single diesel generator failure event had been set to 0 rather than simply addressing the dominant contributors. The change in CDF provided in the SAMA submittal provides a reasonable estimate of the reduction expected by a highly reliable and diverse alternate ac power source.
The intent was to present a change in CDF consistent with the complete elimination of all diesel generator failure modes, perfect reliability and diversity.
- 2.
Provide a description of the additional risk reduction that would be achieved by making the 3rd diesel seismic (i.e., 1.3E-61y), and the types of sequences/failures that would not be addressed by the 3rd (seismic) diesel.
RESPONSE: A sensitivity study has been conducted to evaluate the impact that a third diesel could have on the seismic results. No cost estimate has been developed for providing a seismically qualified diesel. As was done for the non-seismic analysis, the random failure modes of the diesels were removed form the model. The resulting seismic CDF reduction is 1.3 E-06. The seismic results are dominated by seismic failures in the 4 kV power system for which improving diesel generator availability provides no benefit.
- 3.
Provide the expected risk reduction for the dedicated power line from the nearby hydro station (i.e., equivalent to adding a 3rd (seismic?) diesel), and the supporting rationale (i.e., that the HCLPF for hydro stations would typically be less than for a seismic diesel).
RESPONSE: A dedicated and tornado protected line from the Cowan's Ford hydro electric station could provide a CDF reduction similar to the estimate provided for the third diesel in the SAMA analysis. However, the result does not address potential common cause failure of the hydro-electric station as a result of the same tornado that causes the loss of offsite power to occur. The seismic fragilities of the hydro-electric plant would be expected to be lower than most of the essential systems at McGuire.
- 4.
Provide a brief description of the SAMA on which the $205K and $540K estimates (from the February 7, 2002, telephone conference) were based. This information is needed in order to put the various cost elements (engineering, materials, installation labor, and maintenance) in perspective. The response should clarify whether the SAMA/cost estimates: assume the generator is dedicated? pre-staged? would be located inside or outdoors?; include the cost of a pad or enclosure building? power cables (and their approximate length)? installing disconnects? routine surveillance and maintenance costs for remaining plant life?
RESPONSE: The design requires an installed dedicated diesel because powering of the igniters needs to occur prior to the onset of core damage. The diesel is located outdoors for ventilation and exhaust considerations. Initiation and operation of the diesel will occur prior to the onset of core damage and thus will be covered by the emergency operating procedures rather than the severe accident management guidelines which are entered after core damage occurs.
The cost estimates provided assumed one new dedicated diesel generator set, prestaged and located outside on a concrete pad for each station. No enclosure was included in the estimate. Approximately 300 feet of cable and three circuit breakers would need to be installed and are induded in the cost estimate. Initial procedure development costs were included in the cost estimate. However, ongoing routine surveillance and maintenance costs were not included. Also, this cost estimate does not include tornado protection of the diesel generator set nor does it include any seismic design.
These cost-estimates are for scoping purposes only and are subject to change.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of:
DUKE ENERGY CORPORATION (McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 and 2)
) )
)
)
)
)
)
)
Docket Nos.
50-369-LR 50-370-LR 50-413-LR 50-414-LR CERTIFICATE OF SERVICE I hereby certify that copies of "Information Provided by Duke Energy Corporation related to Severe Accident Mitigation Alternatives in Its License Renewal Application for the McGuire Nuclear Station, Units 1 and 2" and "Information Provided by Duke Energy Corporation Related to Severe Accident Mitigation Alternatives in Its License Renewal Application for the Catawba Nuclear Station, Units 1 and 2" in the above captioned proceeding have been served on the following by deposit in the United States mail, first class, this 2 0 th day of March, 2002.
Ann Marshall Young, Chairman Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (e-mail: amy@nrc.gov)
Dr. Charles N. Kelber Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (e-mail: cnk@nrc.gov)
Office of Commission Appellate Adjudication U.S. Nuclear Regulatory Commission Washington, DC 20555 Lester S. Rubenstein Administrative Judge 4760 East Country Villa Drive Tucson, Arizona 85718 (e-mail: lesrrr@msn.com)
Office of the Secretary U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Rulemakings and Adjudications Staff (original + two copies)
(e-mail: HEARINGDOCKET@nrc.gov)
Adjudicatory File Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, DC 20555 1
Susan L. Uttal, Esq.
Office of the General Counsel U.S. Nuclear Regulatory Commission Washington, DC 20555 (e-mail: slu@nrc.gov)
Mary Olson Director of the Southeast Office Nuclear Information and Resource Service 729 Haywood Road, 1-A P.O. Box 7586 Asheville, NC 28802 (e-mail: nirs.se@mindspring.com)
Paul Gunter Nuclear Information and Resource Service 1424 16th Street, NW Washington, DC 20026 (e-mail: pgunter@nirs.org)
Janet Marsh Zeller Executive Director Blue Ridge Environmental Defense League P.O. Box 88 Glendale Springs, NC 28629 (e-mail: BREDL@skybest.com)
Donald J. Moniak Blue Ridge Environmental Defense League P.O. Box 3487 Aiken, SC 29802-3487 (e-mail: donmoniak@earthlink.net)
Jared K. Heck Office of the General Counsel, 0-15D21 U.S. Nuclear Regulatory Commission Washington, DC 20555 (e-mail: jkh3@nrc.gov)
David A. Repka Counsel for Duke Energy Corporation 2
252062.1