ML093170217
| ML093170217 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/10/2009 |
| From: | Morris J Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML093170217 (25) | |
Text
4 V Duke Energy Carolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station / CN01 VP 4800 Concord Road York, SC 29745 803-831-4251 803-831-3221 fax November 10, 2009 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Technical Specifications (TS) and/or Bases Sections:
3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation 3.3.3, Post Accident Monitoring (PAM)
Instrumentation 3.5.4, Refueling Water Storage Tank (RWST) 3.6.6, Containment Spray System License Amendment Request for Emergency Core Cooling System (ECCS)
Water Management Initiative
References:
Letters from Duke to NRC, same subject, dated September 2,
- 2008, June 18, 2009, July 8,
- 2009, August 13,
- 2009, and September 8, 2009 The September 2, 2008 reference letter requested a license amendment pursuant to 10 CFR 50.90 to revise the Unit 1 and Unit 2 T.S and associated Bases to allow manual operation of the Containment Spray System and to revise the upper and lower limits on the RWST.
The June 18, 2009, July 8, 2009, August 13,
- 2009, and September 8, 2009 reference letters responded to four sets of Requests for Additional Information (RAIs) and supplemented the September 2, 2008 original submittal.
On October 2, 2009, the NRC electronically transmitted an additional RAI.
The purpose of this letter is to formally respond to this RAI.
The attachment to this letter contains our RAI response.
The format of the response is to restate the RAI question, followed by our response.
A001
/oI~
www. duke-energy. com
U.S. Nuclear Regulatory Commission Page 2 November 10, 2009 There are no regulatory commitments contained in this letter or its attachment.
Pursuant to 10 CFR 50.91, a copy of this letter and its attachment is being sent to the designated official of the State of South Carolina.
If you have any questions or require additional information, please contact L.J. Rudy at (803) 701-3084.
Very truly yours, Ja Morris LJR/s Attachment
U.S. Nuclear Regulatory Commission Page 3 November 10, 2009 James R. Morris affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
James Subscribed and sworn to me:
1//
/ t I Date Notary ublic My commission expires:
Date SEAL
U.S. Nuclear Regulatory Commission Page 4 November 10, 2009 xc (with attachment):
L.A.
Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85
- Atlanta, GA 30303 G.A. Hutto, III Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.H. Thompson (addressee only)
Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 G9A Rockville, MD 20852-2738 S.E. Jenkins Section Manager Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
- Columbia, SC 29201
U.S. Nuclear Regulatory Commission Page 5 November 10, 2009 bxc (with attachment):
R.D.
Hart L.J. Rudy M.E.
Patrick R.L. Gill, Jr.
Document Control File 801.01 RGC Date File ELL NCMPA-1 NCEMC PMPA
Attachment Response to NRC Request for Additional Information Attachment Page 1
On October 2, 2009, the NRC electronically transmitted the following RAIs:
- 1. In Section 3.2.4, "Equipment Qualification" of the license amendment request (LAR) the licensee states that as a result of the proposed modifications, the environmental accident profiles based on a loss of coolant accident (LOCA) scenario for areas located inside containment and the annulus were revised. Provide a comparison of the environmental accident profiles (before and after the modifications) for inside containment and the annulus as well as a discussion on any differences in the profiles. In addition, provide a discussion on how the existing EQ profiles are bounding.
Duke Response:
The following information is taken from approved engineering calculation CNC-1381.05-00-0239, "Environmental Qualification (EQ) Equipment Evaluation For Containment Profile Revisions Due To ECCS Water Management Initiatives" (Revision 0),
which evaluated the differences between the current environmental accident profiles and the revised environmental profiles proposed for the Catawba ECCS Water Management project.
For ease of NRC review, relevant tables and figures contained within the calculation, as well as the list of references contained within the calculation, are included in this response.
To support the equipment evaluations of this calculation, a
temperature profile curve consisting of the new "Lower Cont (ECCS WM)"
curve, the "Lower Cont (Bounding Curve)", the new "Upper Cont (ECCS WM)"
curve, the new "Sump Temp (ECCS WM)"
curve, and the "Annulus (ECCS WM)"
curve was used.
This figure is provided as Figure B-6A and Figure B-6B in Appendix B, and this temperature response curve (labeled "EQ Equip Evaluation Curve") serves as the overall profile for the equipment evaluations provided in Appendix C.
In developing the "EQ Equip Evaluation Curve" in Figure B-6A and Figure B-6B, it is noted that each of the sub-curves to the composite "EQ Equip Evaluation Curve" have different periods in time where they each have the highest peak temperature compared to the other sub-curves.
For example, the "Lower Cont (ECCS WM)"
curve has the highest temperature profile from the start of the accident simulation until 35.0 seconds, at which time the "Sump Temp (ECCS WM)"
curve Attachment Page 2
exceeds the "Lower Cont (ECCS WM)"
curve.
Following this transition, the "Upper Cont (ECCS WM)"
curve peaks followed by the "Lower Cont (ECCS WM)"
curve, the "Lower Cont (Bounding Temp)'" curve, and finally the "Annulus (ECCS WM)"
curve completes the overall profile.
curve is a long duration profile which extends the previously defined EQ profile curves for the Reactor Building locations in the EQCM (Reference 11).
As noted in Reference 8, the calculation for the Annulus temperature return response is via an extrapolation of the containment values provided in Reference 7.
This is considered a bounding and conservative approach.
Reference 9 also includes a bounding straight line approximation for the Lower Containment temperature response.
For additional reference, supplemental calculations in Reference 9 have shown that a more natural, lower, long term return response for Lower Containment can be expected in 1,001,400 seconds (i.e.
11.60 days).
For the purpose of the equipment evaluations, the "EQ Equip Evaluation Curve" consists of the highest temperature value from each of the ECCS Water Management calculation sub-curves for each time instance described above with an extra 5.0°F of margin added for conservatism.
The inclusion of the Containment sump temperature and Annulus temperature response curves to supplement the Lower Containment curve adds margin to this evaluation based on its extra thermal content as shown in Figure B-5A and Figure B-6A.
Development Of EQ Envelope Curve:
The "EQ Equip Evaluation Curve" developed as part of this calculation will serve as the EQ Envelope Curve once the final plant modifications and supporting activities associated with the ECCS Water Management initiatives are implemented.
The Catawba EQCM (Reference 11) will be updated to incorporate this curve along with the new profiles generated by NGO Safety Analysis and NGO Radiological Engineering.
This curve is considered to be bounding and conservative with respect to the environmental profiles for equipment locations within the Reactor Building via the incorporation of the highest temperature values of all locations and the straight line approximations for the long term Lower Containment and Annulus temperature responses.
As noted in Attachment Page 3
the development of this curve, 5.0°F of margin was added to the overall profile for additional conservatism, and based on the results of this calculation, the curve is an acceptable measure in comparing the respective qualification levels / profiles for EQ-related equipment located within the Reactor Building.
The above information details the development of a composite environmental curve which was used to both compare the existing environmental curves against those being proposed for the Catawba ECCS Water Management project and evaluate against the documented test profiles for EQ equipment.
In some cases, the proposed ECCS Water Management profiles exceeded current approved profiles for the Containment and Annulus locations.
- However, the equipment was evaluated using the composite "EQ Equip Evaluation Curve" which included the highest temperature values from all curves for all times plus additional margin.
This approach is considered to be bounding for both the existing and new revised profiles.
- 2.
The licensee states in Section 3.2.4, "Equipment Qualification" that the current steam line break containment analysis bounds the plant response with proposed modifications based on the use of a computer code. Explain why post-steam line break temperatures in the annulus were not calculated assuming the proposed modifications were in place.
Duke Response:
The input taken specific to a design basis accident for calculation of post-accident temperatures in the annulus consists of the post-accident containment conditions, namely containment pressure and containment compartment temperatures.
As stated in Section 3.2.4 of the original submittal (Page 22 of Attachment 1),
"It was determined that the current steam line break containment analysis bounds the plant response with the proposed modifications (refer to the discussion in Section 3.2.1 under the heading Large Steam Line Break Containment Response)".
This precludes the need to calculate the annulus temperatures for the steam line break with the proposed modifications presumably in place.
The basis for the conclusion that the current steam line break analysis bounds the plant response with the Attachment Page 4
proposed modification...
"' is discussed in Section 3.2.1.
Additional details of this basis are provided in the response to Question 4.
- 3.
In Section 3.2.9 of the LAR, the licensee stated that for ice condenser plants, the increase in containment pressure resulting from the elimination of containment spray would be limited. Explain what is meant by a limited increase in containment pressure and provide the values of containment pressure before and after the modifications.
In addition, provide a discussion of the impact of increased containment pressure as a result of the modifications.
Duke Response:
Section 3.2.9 of the LAR discusses the impact of the proposed modification to the results of the peak fuel cladding temperature LOCA analysis presented in UFSAR Section 15.6.5.
Unlike the UFSAR Chapter 6.2 peak containment pressure analysis, the peak clad temperature LOCA analysis uses a minimum containment pressure response as an input to minimize the steam enthalpy credited in the analysis.
This minimizes the energy content of the steam and helps ensure a conservative peak clad temperature result.
The minimum containment pressure analysis typically assumes maximum flow from two trains of containment spray at a minimum temperature.
If the minimum containment pressure analysis were to be performed without containment spray flow, the pressure results would be expected to increase.
Since the ability of containment spray to condense steam in lower containment is limited during the first few minutes of a LOCA, the containment pressure difference would be small.
There are currently no plans to incorporate the proposed modification into the minimum containment pressure analysis as the current analysis will remain bounding.
Thus, no quantitative assessment is necessary.
The peak clad temperature LOCA analyses would also need to be re-analyzed in order to quantify the impact of the change.
The net impact of the change would be a slightly higher steam enthalpy during the 15.6.5 LOCA analyses which would be a credit in the peak clad temperature analysis.
The impact of the change would appear as a decreased fuel cladding temperature result relative to the 10 CFR 50.46 criterion.
Attachment Page 5
- 4. Provide a detailed explanation how it was concluded that the current steam line break analysis bounds the plant response with the proposed modification to remove the automatic containment spray actuation logic, as stated in Section 3.2.1 under "Large Steam Line Break Containment Response."
Duke Response:
The current steam line break analysis is a relatively short term analysis that examines the period of time during which superheated conditions may exist in lower containment.
The duration of this analysis is not sufficient to include the actuation of the containment air return fans.
The parameter of concern for this analysis is the lower containment vapor temperature.
The lower containment temperature response for the current steam line break analysis is affected by the steam released from the break, ice condenser drain flow, and the passive heat structures.
The current steam line break analysis does not allow liquid from containment spray in upper containment to enter lower containment.
Thus, the analysis does not consider the timing of the containment spray actuation, various equipment delay times, containment spray header fill time, and delays associated with liquid accumulation on the refueling deck and in the refueling canal prior to liquid entering the drains to lower containment.
All of these phenomena are conservatively bounded by preventing liquid from upper containment from entering lower containment.
Since liquid entering upper containment due to containment spray actuation does not affect the current analysis results in lower containment, the proposed modification to extend the time when the containment spray pumps start will not affect the steam line break analysis results.
- 5.
Confirm that the EQ components remain qualified for the changes in containment spray operation in the LAR.
Duke Response:
The following information is taken from approved engineering calculation CNC-1381.05-00-0239, "Environmental Qualification (EQ)
Equipment Evaluation For Containment Profile Revisions Due To ECCS Water Management Initiatives" (Revision 0),
which evaluated the EQ equipment for the Attachment Page 6
revised environmental accident profiles proposed for the Catawba ECCS Water Management project.
For ease of NRC review, relevant tables and figures contained within the calculation, as well as the list of references contained within the calculation, are included in this response.
For the equipment reviews, a search was performed for all equipment listed in the Passport Portal J Equipment Database (EDB) using the search criteria of ACTIVE or DESIGN equipment located within the Reactor Building designated as either RX1 or RX2 (Reactor Building),
CV1 or CV2 (Containment Vessel),
or AN1 or AN2 (Annulus).
The results of this equipment search were reduced to include only equipment designated as EQ Related = "H" (HARSH) or noted to be required by Regulatory Guide 1.97.
This list is provided in the calculation as Attachment 1.
From this list of EQ-related equipment located with the Unit 1 or the Unit 2 Reactor Buildings, Table 1 was developed, and it summarizes the various equipment types (i.e.
Manufacturer, Model Number) which are required for this review.
Table 2 summarizes the Reactor Building equipment types for this review listed to meet the requirements of Regulatory Guide 1.97.
Table 3 summarizes the various equipment types which are located at or below the defined submergence level of 562.0 feet due to sump level.
The qualification references for each equipment type listed in Table 1 and Table 2 are located in their respective Environmental Qualification Maintenance Manual (EQMM) section.
The qualification report was reviewed for each equipment type, and copies of the respective test results /
test profiles have been included in Attachment 4 (Reference 13).
The bounding environmental profiles for the equipment located within Containment and the Annulus areas are for a Loss Of Coolant Accident (LOCA) scenario and are listed in the Catawba Environmental Qualification Criteria Manual (EQCM)
(Reference 11).
The equipment evaluations for this calculation encompass the revised profiles provided in (Reference 7, Reference 8, and Reference 9),
the existing EQCM profiles in Attachment 3 (Reference 11),
and the individual equipment qualification reference information in Attachment 4 (Reference 13).
It should also be noted that the equipment evaluation curves provided in Appendix C utilize the logarithmic scale profile for the -"EQ Equip Evaluation Curve" (i.e.
Figure B-6A) to remain consistent with the various vendor test result profiles and Attachment Page 7
test results.
The above information details the development of the equipment search performed as part of calculation CNC-1381.05-00-0239 (Revision 0) to evaluate EQ equipment against the composite "EQ Equip Evaluation Curve".
Table 1, Table 2, and Table 3 detail the various equipment types (i.e.
manufacturer and model number) obtained from this search.
The calculation documents an equipment evaluation performed for the following equipment types (listed in same order as documented within the calculation):
EQ Equipment:
- Rotork MOV Actuators
- Limitorque MOV Actuators
- Combustion Engineering Incore Thermocouple Cables
- TEC Valve Acoustic Monitoring / Accelerometer System
- Sorrento (General Atomics) High Range Radiation Monitors
- Gamma-Metrics Neutron Flux Monitoring System
- Joy / Reliance Fan Motors D.
G. O'Brien Electrical Penetration Assembly
- Conax Electrical Penetration Assembly
- Conax RTDs
- RDF RTDs
- Minco RTDs
- Duke Energy Commercial Grade Items (Terminal Box /
Enclosures and Potting / Sealant Materials)
Barton Pressure Switches (Inside Containment Models)
- Namco EA-180 Limit Switches
- Solon Pressure Switches (Inside Containment Models)
GEMS LS-57761 Level Switches Barton 764 And 763 Series Transmitters Rosemount 1153B And 1154 Series Transmitters
- GEMS XM 54853 Level Transmitters
- ASCO NP8316 Series Solenoid Valves
- Valcor V70900-39, V70900-65, V526,
& V573 Series Solenoid Valves
- Westinghouse Hydrogen Recombiners Attachment Page 8
I
.I Regulatory Guide 1.97 Equipment:
- Burns Engineering RTDs
- Combustion Engineering Incore Thermocouples
- Conax RTDs
- Magnetrol Level Switches
- Namco EA-180 Limit Switches
- Rochester Signal Conditioners
- Rosemount 1151 & 3.051 Series Pressure Transmitters Sorrento (General Atomics) Area Radiation Monitors
- Tobar Pressure Transmitters
- Veritrak Pressure Transmitters
- Weed Pressure RTDs Generic Support Equipment:
Cables
- Splice / Tape Materials
- Connectors Based on the review and evaluations documented within calculation CNC-1381.05-00-0239 (Revision 0),
all EQ equipment located within the Containment and Annulus locations for Catawba Nuclear Station remain qualified for the revised environmental profiles proposed for the Catawba ECCS Water Management project.
The following is the documented conclusion section from the calculation:
Per the review provided in this calculation, the specific EQ equipment discussed in this calculation and located within various areas of the Reactor Building at Catawba Nuclear Station remain qualified for their respective applications.
The revised profiles as a result of the pending ECCS Water Management initiatives have been evaluated against all EQ-related electrical equipment located in the Reactor Building and equipment required to function per Regulatory Guide 1.97, and there is no adverse impact on the existing qualifications.
This calculation and its contained EQ evaluations serve as an input in the License Amendment Request (LAR) process in support of the ECCS Water Management initiatives and related plant modifications.
Attachment Page 9
Tables, Figures, and List of References from Calculation CNC-1381.05-00-0239 (Revision 0)
(Question 1 and Question 5 Responses)
Attachment Page 10
CNC-1381.05-00-0239, Rev. 0 Page 7
Of 24 Environmental Qualification (EQ) Equipment Evaluation For Containment Profile Revisions Due To ECCS Water Management Initiatives By:
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located with the Unit 1 or the Unit 2 Reactor Buildings, Table 1 was developed, and it summarizes the various equipment types (i.e. Manufacturer, Model Number) which are required for this review. Table 2 summarizes the Reactor Building equipment types for this review listed to meet the requirements of Regulatory Guide 1.97. Table 3 summarizes the various equipment types which are located at or below the defined submergence level of 562.0 feet due to sump level.
Table 1 Consolidated Equipment Manuftiturer & Milodel Number List For Reactor Buildin Equipment Types Taken From Passport Portal J (EO = "H" (H-arsh))
MANUFACTURER EQ MASTER NAME:
MODEL NUMBER:
REFERENCE:
ROTORK NAl Series MOV Actuators EQMM-1393ý01-Ao1-00 LIMITORQUE SBD / SMB MOV Actuators EQMM-1393.01-A02-00 CCI Pressurizer PORVs EQMM-1393.01-A06-01 COMBUSTION Incore Thermocouple Cables EQMM-1393.01-C01-00 ENGINEERING (Westinghouse)
TEC / ENDEVCO Valve Acoustic Monitoring
" EOMM-1393.01-F01-00 Accelerometer System SORRENTO High Range Radiation Monitors EQMM-1393.01-F02-00 (General Atomics)
GAMMA-METRICS RCS Series Detector & Junction Box EQMM-1393.01-F04-00
.(Neutron Flux Monitoring System)
JOY / RELIANCE Fan Motors EQMM-1393.01-GO1-00 D. G. O'BRIEN Electrical Penetration Assembly EQMM-1393.01-J01-00 CONAX Electrical Penetration Assembly EQMM-1393.01-J02-00 CONAX RTDs EQMM-1393_01-K0t-00 RDF CORP RTDs EQMM-1393.01-K03-01 EQMM-1393_01-K03-02 MINCO RTDs EQMM-1393_01-K04-00 DUKE/CGD.
Terminal Boxes EQMM-1393.01-M01-00 BARTON 581A-0 Pressure Switches EQMM-1393.01-NO1-O0 (Inside Containment Models)
EQMM-1393.01-N01-01 NAMCO EA-180 Limit Switches EQMM-1393.01-N03-00 EQMM-1393.01-N03-01 SOLON 7PSW-Series Pressure Switches FQMM-1393.01-N04-00 (Inside Containment Models)
GEMS LS-57761 Level Switch EQMM-1393.01-N09-00 BARTON 764 Transmitter EQMM-1393.01-PO1-O0 EQMM-1393.01-PO1-02
.BARTON 763 Transmitter EQMM-1393.01-PO1-01 ROSEMOUNT 11538 Series Transmitter EQMM-1393.01 -P02-02 EQMM-1393.01-P02-03 ROSEMOUNT 1154 Series Transmitter EQMM-1393.01-P02-04 GEMS/DELAVAL XM 54853 Level Transmitter EQMM-1393.01-P04-00 ASCO NP8316 Series SOVs EQMM-1393.01-Q01-01 VALCOR V70900-65 Series SOVs EQMM-1393.01-Q03-01 VALCOR V70900-39 Series SOVs EOMM-1393.01-003-02 VALCOR V526 / V573 Series SOVs EQMM-1393.01-Q03-03 WESTINGHOUSE Hydrogen Recombiner EQMM-1393.01-RO1-00 (Removed From EQ Program)
CNC-1381.05-00-0239, Rev. 0 Page 8
Of 24 En virontmental Qualification (EQ) Equipment Evaluation For Contaitnment Profile Revisions Due To ECCS Water Management Initiatives By:
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Table 2 Consolidated Eauipment Manufacturer & Model Number List For Reactor Buildin.g Eauitment Tvnes Taken From Passport Portal.1 (Regulatorv Guide 1.97 Eauipment)
MANUFACTURER REG. GUIDE 1.97 NAME:
MODEL NUMBER:
CATEGORY:
BURNS RTDs 3
ENGINEERING COMBUSTION Incore Thermocouples 1
ENGINEERING (Westinghouse)
CONAX RTDs 2
MAGNETROL 804 Series Level Switches 3
NAMCO EA-180 Limit Switches 1
ROCHESTER Signal Conditioners 2
ROSEMOUNT 1151 Series Transmitters 3
ROSEMOUNT 3051 Series Transmitters 3
SORRENTO RD-1 Area Radiation Monitors 3
(General Atomics)
TOBAR Pressure Transmitters 3
VERITRAK Pressure Transmitters 3
WEED RTDs 2
Table 3 Consolidated.Equ__ipment manufacturer & Model Number List For Inside Containment Equipment List Taken From Passport Portal.1 (Below Flood Level 0f562. 0 Elevation) 0 MANUFACTURER NAME:
MODEL NUMBER:
BURNS RTDs ENGINEERING COMBUSTION Incore Thermocouple Cables ENGINEERING (Westinghouse)
DUKE / CGD Terminal Boxes GEMS LS-57761 Level Switch GEMS/DELAVAL XM 54853 Level Transmitter LIMITORQUE SBD / SMB MOV Actuators MAGNETROL 804 Series Level Switches MINCO RTIDs NAMCO EA-180 Limit Switches ROSEMOUNT 1154 Series Transmitters ROSEMOUNT 3051 Series Transmitters ROTORK NA1 Series MOV Actuators VALCOR V70900-39 Series SOVs VALCOR V70900-65 Series SOVs 0
APPENDIX B FIGURE B-5A LONG TERM EQ REACTOR BUILDING TEMPERATURE RESPONSE MASTER PROFILE (ALL AREAS COMBINED)
(Logarithmic Time Scale).
250
-Lower Cont (ECCS WM)
Lower Cont (Calculated Long Term)
Lower Cont (Bounding Temp)
Lower Cont (Current DB) (EQCM)
Upper Cont (ECCS WM)
Upper Cont (Bounding Temp)
Sump Temp (Calculated Long Term)
,)nn 0
I-ni I-.
I-0 5
i 1 lf iu'J
.I-,-
1 UU 50 I.E-i00 I.E+02 I.E-'03 I.E+04 I.E+05 I.13+/-07 I.E+06 I.E+01 TIME (SECONDS)
CNC-1381.05-00-0239, Rev. 0 Environmental Qualification (EQ) Equipment Evaluation For Containment APPENDIX B Profile Revisions Due To ECCS Water Mananement Initiatives Page B9 By:
6:-ý Checked:'10i3ý,
250 APPENDIX B FIGURE B-5B LONG TERM EQ REACTOR BUILDING TEMPERATURE RESPONSE MASTER PROFILE (ALL AREAS COMBINED)
(Linear Time Scale)
Lower Cont (ECCS WM)
Lower Cont (Calculated Long Term)
- Lower Cont (Bounding Temp)
Lower Cont (Current DB) (EQCM)
Upper Cont (ECCS WM)
Upper Cont (Bounding Temnp)
.SumpTemp (Calculated Long T'erm)
W I-0 200 150 L
K S.
ý::'
100 50 I.E+00 SEF+06 I.E+06 2.E+06 3.E+06 TIME (SECONDS) 4.E+06 6.E+06 CNC-1381.05-00-0239, Rev. 0 Environmental Qualification (EQ) Eguipment Evaluation For Containment APPENDIX B Profile Revisions Due To ECCS Water Management Initiatives Page B10 B y: 'ý '-
Checked,ý-fl;j,S
APPENDIX B FIGURE B-6A LONG TERM EQ REACTOR BUILDING TEMPERATURE RESPONSE EQ EVALUATION CURVE (Logarithmic Time Scale) 250
-Lower Cont (ECCS WM)
- - - Lower Cont (Bounding Temp)
Upper Cont (ECCS WM)
EQ Equip Evaluation Curve 1-I-
z 200 150 100 50 ;,
I.E+00
- -1 I.E+/-05 I.E+06 I.E+07 I.E+01 1.E+02 I.E+03 1E+04 TIME (SECONDS)
CNC-1381.05-00-0239, Rev. 0 Environmental Qualification (EQ) Equipment Evaluation For Containment APPENDIX B Profile Revisions Due To ECCS Water Management Initiatives Page B111 By.
6:2!2:
Checkedý
APPENDIX B FIGURE B-6B LONG TERM EQ REACTOR BUILDING TEMPERATURE RESPONSE EQ EVALUATION CURVE (Linear Time Scale) 250 200 0
150 100 50 I.E+00
-Lower Cont (ECCS WM)
- Lower Cont (Bounding Temnp)
Upper Cont (ECCS WM)
EQ Equip Evaluation Curve 5.E+06 I.E+06 2.E+06 3.E+06 TIME (SECONDS) 4JE+06 CNC-1381.05-00-0239, Rev. 0 Environmental Qualification (EQI) Equipment Evaluation For Containment APPENDIX B Profile Revisions Due To ECCS Water Manaaement Initiatives Page B12 By: 6 Checked f3
CNC-1381.05-00-0239, Rev. 0 Page 2
Of 24 By:-w-Environmental Qualification (EQ) Equipment Evaluation For Containment Checked:
A Profile Revisions Due To ECCS Water Management Initiatives 7"
S F. RELATED SAR CRITERIA:
Catawba Updated Final Safety Analysis Report: (Revision 12). Dated 04/24/2006 Chapter 3, Section 3.11 Chapter 6, Engineered Safety Features Chapter 15, Accident Analysis G.
REFERENCES:
- 1.
PIP C-04-5738.Details Issues Related To ECCS Sump Water Into Incore Instrumentation Room
- 2.
PIP C-06-6395 Details Issues Related To NRC GSI-191 Recommendations
- 3.
PIP C-07-01840 Details Issues Related To Annulus Temperature Increase Due To ECCS Water Management Activities
- 4.
PIP C-07-02451 Details Issues Related To Elevated Sump Water Temperature & Associated Effects Due To ECCS Water Management Activities
- 5.
Nuclear System Directive (NSD) 303 Environmental Qualification Program (Revision 4)
Dated 02/26/2004 S
- 6.
Equipment List Search Results (EQ="H" HARSH Or Required By Reg. Guide 1.97) For Inside Containment Or Annulus Equipment From Passport Portal J (ATTACHMENT 1)
- 7.
Calculation CNC-1 552.08-00-0390 Long-Term Containment Response - Manual NS Initiation (Revision 0) Dated 05/23/2007 (Selected Pages Included As ATTACHMENT 2)
- 8.
Calculation CNC-1227.0.0-00-0103 Analysis Of Post LOCA Secondary Containment Transient Response Using CANVENT (Revision 1) Dated 07/12/2007 (Selected Pages Included As ATTACHMENT 2)
- 9.
Calculation DPC-1 552.08-00-0033 Long Term EQ Containment Temperature Response For LOCA AndSLB (Revision 2) Dated 07/20/2007 (Selected Pages Included As ATTACHMENT 2)
- 10. Calculation CNC-1 552.08-00-0314 Large-Break LOCA Containment Response With Asyummetrical Initial Ice Distribution (Revision 6) Dated 05/23/2007 (Selected Pages Included As ATTACHMENT 2)
- 11.
Catawba Manual CNLT-1 780-03.03 Catawba Nuclear Station Environmental Oualification Criteria Manual ('EQCMV) (Revision 25) Dated 01/29/2007 (Selected Pages Included As ATTACHMENT 3)
S
- 12. Catawba Manual CNLT 1780-03.02 Catawba Nuclear Station Response To NUREG-0588 (Revision 7) Dated 01/26/1988 (Selected Pages Included As ATTACHMENT 3)
CNC-1381.05-00-0239, Rev. 0 Page 3
Of 24 By:
Environmental Qualification (EQ) Equipment Evaluation For Containment Checked:
Profile Revisions Due To ECCS Water Management Initiatives
- 13.
Equipment Manufacturer Qualification Test Profiles (Selected Pages Included As ATTACHMENT 4)
- 14.
Email To Chris Abernathy From Mark Costello Dated 05/08/2007. Documenting Radiological Conditions Based On Water Management Initiatives (Included In ATTACHMENT 5)
- 15.
Email To Chris Abernathy From Andy Gullion Dated 06/21/2007 Documenting Equipment Below 562' Submergence Level (Included In ATTACHMENT 5)
- 16. Email To Chris Abernathy From Eugene Pisarskiy Dated 07/09/2007 Documenting Equipment Model Types For Radiation Monitors (Included In ATTACHMENT 5)
- 17.
Email To Chris Abernathy From Mary Edmunds Dated 07/18/2007 Documenting Sump Level Values Spreadsheet (Included In ATTACHMENT 5)
- 18.
Email To Chris Abernathy From John Edwards Dated 07/12/2007 Documenting Final Annulus Temperature Profile & Electronic Spreadsheet (Included In ATTACHMENT 5)
- 19.
Email To Chris Abernathy From Raymond Chow Dated 07/20/2007 Documenting Final Containment Temperature Profiles & Electronic Spreadsheet (Included In ATTACHMENT 5)
- 20. Email To Chris Abernathy From Raymond Chow Dated 07/23/2007 Documenting The Use Of Cold Leg Break Analyses For Evaluation & Sump Temperature Values (Included In ATTACHMENT 5)
- 21.
Email To Chris Abernathy From Raymond Chow Dated 07/24/2007 Documenting The Calculation Reference For Current Design Profiles (Included In ATTACHMENT 5)
- 22. EPRI Report NP-1 558 A Review Of Equipment Aging Theory And Technoloy. September 1980. (Selected Pages Included As ATTACHMENT 4)
- 23. EQMM Document EQMM-1393.01-AO1-00 Rotork AA] Electric Motor Acluators (Revision
- 9) Dated 04/24/2007
- 24. EQMM Document EQMM-1393.01-A02-00 Limitorque Actuators SA4B/,SBD/SB Inside &
Outside Containmen (Revision 13) Dated 03/19/2007
- 25.
EQMM Document EQMM-1393.01-A06-01 Control Components, hnc. Pressurizer PORVs (Revision 1) Dated 07/14/1998
- 26.
EQMM Document EQMM-1393.01-CO1-00 Combusrion E-,wineerin,' (Vestinghoulse)
Thermocouple Cable (Revision 2) Dated 06/18/2003
- 27.
EQMM Document EQMM-1393.01-FO1-00 Technologv For Eneruv (TEC) Flow,Monitor (Revision 3) Dated 01/23/2002
CNC-1381.05-00-0239, Rev. 0 Page 4
Of 24 By:
Environmental Qualification (EQ) Equipment Evaluation For Containment Checked:
Profile Revisions Due To ECCS Water Management Initiatives
- 28.
EQMM Document EQMM-1 393.01 -F02-00 Sorrento (General Aitomics) Radiation Monitors (Revision 1) Dated 04/13/1 992
- 29.
EQMM Document EQMM-1 393.01 -F04-00 Gamma-Metrics Neutron Flux Detectors (Revision 2) Dated 08/28/2003
- 30. EQMM Document EQMM-1393.01-G01-00.1o_/Reliance Fan Motors (Revision 6) Dated 03/19/2007
- 31.
EQMM Document EQMM-1 393.01 -JO1 -00 D. G. O'Brien Electrical Penetration Assemblies (Revision 0) Dated 01/23/1991
- 32. EQMM Document EQMM-1393.01 -J02-00 Conax Electrical Penetration Assemblies (Revision 3) Dated 10/12/2005
- 33. EQMM Document EQMM-1393.01 -KO1-00 Conax Resistance Temperature Detectors (RTDs)
(Revision 2) Dated 02/26/2003
- 34.
EQMM Document EQMM-1393.01-K03-01 RDF Resistance Temperature Detectors (RTDs)
(Revision 2) Dated 01/31/2002
- 35.
EQMM Document EQMM-1393.01-K03-02 RDF Resistance Temperature Detectors (RTDs)
(Revision 5) Dated 11/24/2003
- 36.
EQMM Document EQMM-1393.01-K04-00 Minco Resistance Temperature Detectors (RTDs)
(Revision 4) Dated 03/23/2004
- 37. EQMM Document EQMM-1393.01-MO1-00 Duke Ener,-. Commercial Grade/Approved Vendor Items (Revision 1) Dated 10/25/2004
- 38. EQMM Document EQMM-1393.01-NO 1-00 Barton 580 Series Pressure Switches (R VLIS)
(Revision 1) Dated 09/06/1995
- 39.
EQMM Document EQMM-1393.01-NO1-01 Barton 580A Series Pressure Switches (Revision
- 5) Dated 05/07/2007
- 40. EQMM Document EQMM-1393.01-N03-00 Njamco EA-180 Limit Switches (Revision B-G)
(Revision 4) Dated 01/26/2006
- 41.
EQMM Document EQMM-1393.01-N03-01 Namco EA-180 Limit Switches (Revisions H Or Later) (Revision 7) Dated 03/02/2007
- 42. EQMM Document EQMM-1 393.01-N04-00 Solon Pressure Switches (Inside Containment)
(Revision 3) Dated 06/14/2007 O
- 43. EQMM Document EQMM-1 393.01 -N09-00 GEMS LS-57761 Level Switches (Provided Bi NLI) (Revision 0) Dated 02/02/2007
CNC-1381.05-00-0239, Rev. 0 Page 5
Of 24 By:
c,-e Environmental Qualification (EQ) Equipment Evaluation For Containment Checked: t Profile Revisions Due To ECCS Water Management Initiatives 7
- 44.
EQMM Document EQMM-1 393.01-P01-00 Barton 764 Differential Pressure Transmitlers (Revision 2) Dated 05/22/2007
- 45.
EQMM Document EQMM-1 393.01 -P01-01 Barton 763 Differential Pressure Transmiters (Procured From Westinghouse) (Revision 1) Dated 05/22/2007
- 46.
EQMM Document EQMM-1393.01-PO1-02 Barton 764 Differential Pressure Transmitters (Procured From Westinghouse) (Revision 1) Dated 05/22/2007
- 47.
EQMM Document EQMM-1393.01-P02-02 Rosemount 1153B Pressure Transmilters (Revision 5) Dated 05/07/2007
- 48.
EQMM Document EQMM-1393.01-P02-03 Rosemount 1153D Pressure Transmiulers (Revision 6) Dated 01/26/2006
- 49.
EQMM Document EQMM-1393.01-P02-04 Rosemount 1154 Pressure Transmilters (Revision 6) Dated 01/26/2006 50- EQMM Document EQMM-1393.01-P04-00 GEMS Level Transmitters (Revision 4) Dated 11/18/1998
- 51.
EQMM Document EQMM-1393.01-QO1-01 ASCO NP 8316 Series Solenoid Valves (Revision
- 12) Dated 03/19/2007
- 52. EQMM Document EQMM-1 393.01 -Q03-01 Valcor 1170900-65,Series'Solenoid Valves (Revision 6) Dated 05/07/2007
- 53.
EQMM Document EQMM-1393.01-Q03-02 Valcor 1'70900-39 SeriesSolenoid Vah,es (Revision 4) Dated 01/26/2006
- 54.
EQMM Document EQMM-1393.01-Q03-03 Valc"r V'526 & V.5 73 Series Solenoid Valves (Revision 15) Dated 04/27/2006
- 55.
EQMM Document EQMM-1393.01-RO1-00 iVestinihouse Electric t-I,drogeen Recombiners (Revision 2) Dated 05/21/2007
- 56. CD Copy Of Electronic Files For Calculation (Uncontrolled Copy Provided In ATTACHMENT 6)
H. ASSUMPTIONS:
This calculation evaluates equipment in support of future plant modifications due to ECCS Water Management activities. It is assumed that all currently installed equipment has been evaluated against the current environmental conditions inside the Containment or Annulus either during the initial development and issuance of Catawba's Response to NUREG-0588 (Reference 12) or as part of the EQ review and verification processes established in NSD-303 for Modifications and/or EDM-601 for Design Changes. The term "current" in relation to this assumption corresponds to the origination date of this calculation as 08/09/2007.