ML15321A235: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 1: Line 1:
{{Adams
#REDIRECT [[DCL-15-130, Diablo Canyon, Units 1 and 2 - Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term]]
| number = ML15321A235
| issue date = 11/02/2015
| title = Diablo Canyon, Units 1 and 2 - Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term
| author name = Allen B S
| author affiliation = Pacific Gas & Electric Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000275, 05000323
| license number = DPR-080, DPR-082
| contact person =
| case reference number = DCL-15-130
| package number = ML15321A264
| document type = Letter, Response to Request for Additional Information (RAI)
| page count = 41
}}
 
=Text=
{{#Wiki_filter:The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Pacific Gas and Electric Company Barry S. Allen Canyon Power Plant Vice President, Nuclear Services Mail Code 104/6 P. 0. Box 56 November 2, 2015 PG&E Letter DCL-15-130 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03. "Application of Alternative Source Term" Avila Beach, CA 93424 805. 545. 4888 Internal:
691.4888
 
==References:==
: 1. PG&E Letter DCL-15-069, License Amendment Request 15-03, "Application of Alternative Source Term," dated June 17, 2015 (ADAMS Accessi.on No. ML 15176A539)
: 2. PG&E Letter DCL-15-105, Supplement to License Amendment Request 15-03, "Application of Alternative Source Term," dated August 31, 2015 (ADAMS Accession No. ML 15243A363)
: 3. Email from NRC Project Manager Siva P. Lingam, "Diablo Canyon 1 and 2 -Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term per 1ffCFR 50.67 (TAC Nos. MF6399 and MF6400),"
dated October 1, 2015 Dear Commissioners and Staff: Pacific Gas and Electric (PG&E) Letter DCL-15-069, "License Amendment Request 15-03, 'Application of Alternative Source Term,"' dated June 17, 2015, and supplemented by PG&E Letter DCL-15-105, "Supplement to License Amendment Request 15-03, 'Application of Alternative Source Term,'" dated August 31, 2015, submitted License Amendment Request (LAR) 15-03, "Application of Alternative Source Term." On October 1, 2015, the NRC Radiation Protection and Consequence Branch (ARCB) requested (Reference
: 3) additional information required to complete the review of LAR 15-03. PG&E's responses to the ARCB staff's questions are provided in the Enclosure.
A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance CaUaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
The Enclosure, Attachments 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Document Control Desk November 2, 2015 Page2 PG&E Letter DCL-15-130 Attachment 1 provides Input Data for the EN-113 Dispersion Model, the description of input contained in the EN-113 User's Manual, the input files for the Unit 1 Exclusion Area Boundary (EAB), Unit 2 EAB, and the Units 1 and 2 Low Population Zone dispersion model runs. Attachment 2 summarizes the description of the Release-Receptor cases and the associated input/output file names. Attachment 3 provides various data files in response to the NRC requests for information.
Attachment 4 provides various plant drawings.
Because the information contained in the drawings may be useful to adversaries, PG&E requests that Attachment 4 be withheld from public disclosure under 1 O CFR 2.390. This information does not affect the results of the technical evaluation or the no significant hazards consideration determination previously transmitted in PG&E Letters DCL-15-069 and DCL-15-105.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter. This letter includes no revisions to existing regulatory commitments.
If you have any questions, or require additional information, please contact Mr. Hossein Hamzehee at (805) 545-4720.
I state under penalty of perjury that the foregoing is true and correct.
Executed on November 2, 2015. Sincerely,
!37 . s: AtL---Barry S. Allen Vice President, Nuclear Services A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance Callaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
The Enclosure, Attachments 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Document Control Desk November 2, 2015 Page3 mjrm/4557150307101 Enclosure*
cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Administrator PG&E Letter DCL-15-130 Thomas R. Hipschman, NRC Senior Resident Inspector Siva P. Lingam, NRR Project Manager Gonzalo L. Perez, Branch Chief, California Dept of Public Health A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance Callaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
ENCLOSURE ARCB Response 1 Enclosure PG&E Letter DCL-15-130 Enclosure PG&E Letter DCL-15-130 PG&E Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, "Application of Alternative Source Term" NRC Request for Additional Information General 1. The licensee used the NRG-accepted ARCON96 dispersion model (based on NUREGICR-6331, Rev. 1 as implemented by Regulatory Guide (RG) 1.194) to estimate onsite impacts to the Unit 1/Unit 2 Control Rooms (CRs) as well as the . Technical Support Center (TSC). The licensee included the TSC pursuant to Supplement 1 to NUREG-0737 (Clarification of TM/ Action Plan Requirements
-dated January 1983) and RG 1. 183. There are 58 source-receptor pairs evaluated for each unit.
* PG&E Response This request for additional information (RAI) is a statement of fact. No response is necessary.
NRC RA/ General 2. The licensee used a (presumably) proprietary dispersion model referred to as EN-113 (Atmospheric Dispersion Factors),
which is said to implement provisions in* RG 1. 145 for accident releases and from RG 1. 111 for routine releases, to estimate short-term relative concentrations (X/Qs) and long-term (annual average)
X/Qs at the Exclusion Area Boundary (EAB) and the outer boundary of the Low Population Zone (LPZ) similar to the NRC-accepted PAVAN andXOQDOQ dispersion models, respectively.
Unlike PAVAN andXOQDOQ,
: however, the EN-113 code runs on hourly meteorological data and has, among other things, the ability to directly calculate XIQ values for the intermediate, short-term averaging intervals (i.e., 2-8 hours, 8-24 hours, 1-4 days, and 4-30 days). Because of conflicting discussions within the application package.
it is not clear at this stage of the review how these provisions were implemented for this LAR. The licensee also cites other facilities where this code has been used and approved by the NRG staff. The licensee will need to provide justification for the use of the EN-113 code at the DCPP. PG&E Response The following clarifies the discussion in Section 5.1 of Attachment 4 of License Amendment Request (LAR) 15-03:
* Regulatory Guide (RG) 1.145 provides the methodology to establish the 0-2 hour (hr) X/Q, as well as the intermediate, short-term averaging time period X/Qs, (i.e., 2-8 hrs, 8-24 hrs, 1-4 days, 4-30 days) -RG 1.145 calls out use of RG 1.111 methodology (which focusses on developing "long term, annual average" X/Qs). 2 Enclosure PG&E Letter DCL-15-130
* Short term (accident) ground level release X/Qs were developed for DCPP using RG 1.145, Revision 1 methodology, using CB&I computer code EN-113 utilizing 2007 through 2011 hourly average meteorological data.
* Intermediate averaging time X/Qs were developed for DCPP using RG 1.111, Revision 1 methodology, using CB&I computer code EN-113, utilizing logarithmic interpolation between the 0-2-hr and the annual average X/Q values. The "sliding average" methodology was not used for DCPP (see Section 5.1 of LAR 15-03), although the capability was discussed in Section 3.0, Attachment 4 of LAR 15-03.
* EN-113 calculates all of the X/Qs (0-2 hr, 2-8 hrs, 8-24 hrs, 1-4 days, 4-30 days) using hourly average meteorological data.
* EN-113 follows RG 1.145 methodology which intrinsically means that the intermediate, short-term averaging time period X/Qs are* developed using RG 1.111 methodology
* EN-113 has the capability to calculate the intermediate, short-term averaging time period X/Qs using a) sliding average methodology OR b) logarithmic interpolation between the 0-2 hr and the annual average X/Q values.
* For DCPP, the EN-113 logarithmic interpolation methodology option was chosen to establish the intermediate, short-term averaging time period X/Qs
* PG&E is asking for NRC approval for use of EN-113 for development of accident X/Qs. The LAR does not address normal operation routine releases.
As justification for the usage of EN-113, Section 5.1 of Attachment 4 of LAR 15-03 provides
'a summary of how RG 1.145 methodology was implemented by EN-113 including the applicable equations used and the key assumptions made to ensure conservative results.
Also included is a discussion of the selection process of the appropriate X/Q values for the 0-2 hour averaging time and intermediate period averaging times. As noted in Section 3.0 of Attachment 4 of LAR 15-03, EN-113 has been used in prior alternative source term (AST) licensing applications (e.g., Fort Calhoun Power Station [ML013030027]),
and its results accepted by the NRC. As depicted in Attachment 8 of LAR 15'."03, the proposed update of Section 2.3.2 oft.he Updated Final Safety Analysis
'Report (UFSAR) reflects the use of the EN-113 computer code to provide short-term (i.e., accident) dispersion estimates.
It includes the same level of detail as is provided in Attachment 4 of LAR 15-03. NRC RA/ General 3. The licensee has updated the meteorological data set used to make its related XIQ estimates (i.e., a more recent 5-year period of record (POR) consisting of data for calendar years 2007 through 2011 ). Data and summaries through Rev. 20 (November 2011) of the Updated Final Safety Analysis Report (UFSAR) -latest available on NRR's V:\ drive -are based on various 2-or 3-year PORs, which
* appear to be associated with the initial submittal for this facility.
The purpose 3 Enclosure PG&E Letter DCL-15-130 of some of those summaries appears to be related to the complicated meteorological conditions that characterize this coastal site, which includes complex terrain.
It is riot clear at this stage of the review how (or iO these previous studies.
and the issues previously considered to be important as addressed by those studies.
relate to the dispersion modeling analyses performed for this LAR. PG&E Response The referenced meteorological studies in the UFSAR with respect to X/Qs were provided by PG&E within the original license application since it pre-dated the availability of the NRC guidance documents.
The previous meteorological studies conducted at DCPP in the 1970s are not related to the X/Q dispersion modeling/analyses in support of LAR 15-03. The X/Q analyses supporting LAR 15-03 followed the current NRC guidance available in RG 1.145, Revision 1, and uses the updated meteorological data set (i.e., a more recent 5-year period of record (POR) consisting of data for calendar years 2007 through 2011 ). NRC RA/ Meteorological (Met} Data -Offsite Impacts 1. Need Met data for calendar years 2007 thru 2011 a. Sequential hourly file(s) formatted in accordance with Appendix A to Revision 1 of RG 1.23 or equivalent with proper explanation;
: b. Explanation of any data formatting differences between RG 1.23 (Appendix A) and as input to EN-113 dispersion model; \ c. Whether Met data is input to the EN-113 dispersion model as a concatenated 5-year data set or run as individual years and if the latter how the modeling results are interpreted.
PG&E Response
: a. The 2007 through 2011 sequential hourly file(s),
formatted in accordance with RG 1.23, Revision 1, Appendix A are provided in the following five Excel files in the enclosed Attachment 3 data disc:
* NRC07
* NRC08
* NRC09
* NRC10
* NRC11 b. The RG 1.23, Revision 1, Appendix A format is different than that used in EN-113. 4 ----------------
Enclosure PG&E Letter DCL-15-130 The RG 1.23, Revision 1, Appendix A format is focused on an h_ourly presentation, i.e., it provides all parameter values on an hourly basis on one line. Thus each line presents the wind speeds, wind directions, temperatures, etc. for the upper level, intermediate, and lower level tower measurements followed by other parameters such as temperature difference and solar radiation for that
* hour. _This is repeated for each hour in the day and each day of the year. The EN-113 format is focused on a daily presentation, i.e., 24 hourly values for each parameter of interest is presented on a line. Each parameter has a code associated with it such as "111" for 10-meter wind speed and "112" for 10-meter Wind_ direction.
Thus, hourly values for each parameter are provided on a daily basis and repeated for each day of the year. Both formats record the days on a Julian day basis (i.e., Days 1 -365). c. The 2007 through 2011 onsite meteorological data are utilized by the EN-113 dispersion model as concatenated 5-year data set. NRC RA/ Meteorological (Met} Data -Offsite Impacts 2. Joint frequency distributions (JFDs) of wind speed and wind direction by atmospheric stability class for indicated 5-year POR or, if EN-113 was run for individual years, JFDs for each year and for the composite 5-year POR; PG&E Response As noted in PG&E response to NRC Radiation Protection and Consequence Branch . (ARCB) RAl-2 (General) above, PG&E used hourly average meteorological data to develop the offsite atmospheric dispersion factors.
JFDs of wind speed and wind direction by atmospheric stability class for the indicated 5-year POR have not been submitted to NRC since JFDs were not used to support LAR 15-03. NRC RA/ Meteorological (Met} Data -Offsite Impacts . 3. Bases for determining hourly stability class and if different methods were used 1 ' throughout the data set(s) (e.g., depending on wind speed as suggested by UFSAR Table 2.3-41) an accounting of such hours when implemented and an explanation for having done so; PG&E Response The hourly stability classes were based on the vertical temperature difference methodology (i.e., delta T) identified in RG 1.23, Revision
: 1. Temperatures were measured at an upper level of 76 meters and a lower level of 10 meters on the tower. 5 Enclosure PG&E Letter DCL-15-130 The delta T method was used to type stability class throughout the entire concatenated 5-year data base. NRC RA., Meteorological (Met) Data -Offsite Impacts 4. Summary of data recoveries by year and for the 5-year POR for individual Met parameters and as composite recovery of concurrent wind speed, wind direction, and atmospheric stability class for the same periods; PG&E Response As depicted in Attachment 8 of LAR 15-03, the proposed update of Section 2.3.2 of the UFSAR reflects the use of the 2007 through 2011 onsite meteorological data for the calculation of accident diffusion estimates.
The summary of data recoveries for this period, in percent, is provided in the table below: Meteorological Parameter 2007 2008 2009 2010 2011 2007-2011 1 O m wind direction 99.2 96.9 91.0 91.3 95.2 94.7 1 O m wind speed 99.2 96.9 91.0 91.3 93.8 94.4 Stability Class 99.2 '96.9 91.0 91.3 95.2 94.7 76 m wind direction 99.1 96.8 90.8 90.9 95.2 94.6 76 m wind speed 99.1 96.8 90.8 91.3 92.4 94.1 Composite 99.1 96.8 90.8 90.9 92.4 94.0 The data recovery for each year of the 2007 through 2011 period and the entire 2007 to 2011 period meet or exceed the "greater than 90 percent data recovery" guidance identified in RG 1.23, Revision 1 . . NRC RA/ Meteorological (Met) Data -Offsite Impacts 5. (Part 1) Whether any data substitution was implemented to supplement data 'recovery over the indicated 5-year POR and, if so, an accounting of hours and parameters substituted, 6
PG&E Response Enclosure PG&E Letter DCL-15-130 The following table summarizes the data substitutions for the DCPP Primary Tower for the period 2007 through 2011. Substitution Summary 2007 2008 2009 2010 2011 Totals Day/Time Day/Time Day/Time Day/Time Day/Time Substituted Hrs Substituted Hrs Substituted Hrs Substituted Hrs Substituted Hrs 100/1230-98/1545-29/1945-123/1100-5/1015-113/1245 312 111/1700 313 30/0030 5 133/1345 242 11/1345 148 276/1245-143/1230-121/0000-305/0000-83/1400-299/1030 550 153/1530 243 135/1645 353 313/0200 194 90/1115 166 154/1115-314/1330-95/1145-157-0145 63 315/0930 20 106/1315 266 157/1445-145/1415-158/2230 32 145/1800 4 159/1230-216/1145-228/0700 1651 221/0815 117 229/1330-262/1000-229/2330 10 282/0030 471 230/0730-287/0945-All Parameters Substituted 239/0700 216 291/1345 100 Total 862 Total 2528 Total 358 Total 456 Total 1272 Total Hrs Substituted 5476 J Hrs in year 8760 Hrs in year 8784 Hrs in year 8760 Hrs in year 8760 Hrs in year 8760 Total Hrs 5 year period 43824 Percent Percent Percent Percent Percent Total Percent Substituted 9.84%_ Substituted 28.78% Substituted 4.09% Substituted 5.21% Substituted 14.52% Substituted 12.50% 7 NRC RA/ Meteorological (Met) Data -Offsite Impacts Enclosure PG&E Letter DCL-15-130
: 5. (Part 2) an explanation of why any substitutions were necessary, and the source of such data; and PG&E Response The DCPP Primary Tower is taken out of service for calibration approximately every six months per Equipment Control Guideline (ECG) surveillance requirement (SR) 40.1.2. Each calibration period lasts from two to three weeks in duration.
These calibration periods represent the majority of the time that data substitution was necessary.
Additionally, in 2008 the DCPP Primary Tower was taken out of service for replacement due to damage inflicted by a boom truck. During 2011, in addition to calibrations, some instruments on the Primary Met Tower needed replaced, resulting in increased unavailability.
Primary Met Tower Backup Met Tower (parameter substituted) 10M Temperature 10M Temperature 76-1 OM Delta T 60-1 OM Delta T 46-10M Delta T None 1 OM Wind Speed 1 OM Wind Speed 76M Wind Speed 60M Wind Speed 1 OM Wind Dfrection 1 OM Wind Direction 76M Wind Direction 60M Wind Direction Data substitution techniques were employed using back-up tower data when primary tower data were missing during calibrations and unscheduled meteorological monitoring outages.
Stability class from the back-up tower was calculated from temperature difference measurements at the 60-meter and 10-meter levels. NRC RA/ Meteorological (Met} Data -Offsite Impacts 6. Comparisons between the indicated 5-year POR and the PORs reflected in the current (or previous)
UFSAR to establish the long-term representativeness of the 2007 through 2011 POR from an atmospheric dispersion standpoint.
PG&E Response Regulatory Position C.3.1 of RG 1.194 states that "the size of the data set used in the X/Q assessments should be sufficiently large such that it is representative of long-term meteorological trends at the site. The NRC staff considers 5 years of hourly observations to be representative of long-term trends at most sites." Therefore, the 8 Enclosure PG&E Letter DCL-15-130 2007 through 2011 onsite meteorological data base is sufficient in length to establish long-term representativeness from an atmospheric dispersion standpoint.
NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 1. Need Met data for calendar years 2007 thru 2011 a. Sequential hourly file(s) formatted in accordance with NUREGICR-6331 (PNNL-10521) (Rev. 1). b. Note that the cover sheet for Appendix A to Attachment 4 of the LAR submittal package (see Part 2 of 8. ML 15176A528) states that "ftlhe on-site meteorological data input to ARCON96 (January 1, 2007 through December
: 31. 2011 ), in the ARCON96 input data format. is embedded below)",
followed by a list of the five individual calendar years. The phrase "is embedded below" suggests that this Met data may have already been provided with the LAR submittal package.
If already in hand, copies of those files should be provided to my attention at NROIDSEAIRHMB1/RMOT.
and a separate request for that data is not necessary.
PG&E Response
: a. The 2007 through 2011 sequential hourly file(s),
formatted in essentially the same format (with some differences in spacing) as NUREG/CR-6331 Revision 1, are provided in the following five Excel files in the enclosed Attachment 3 data disc:
* DCPP _Primary_2007 (DIT 50503441-02-00).xls
* DCPP _Primary_2008 (DIT 50503441-02-00).xls
* DCPP _Primary_2009 (DIT 50503441-02-00).xls
* DCPP _Primary_2010 (DIT 50503441-02-00).xls
* DCPP _Primary_2011 (DIT 50503441-02-00).xls I Note: Unavailable data for the given hour period is indicated by a "999." b. It appears that due to the scanning approach used to package LAR 15-03 prior to submittal to the NRC, the meteorological data in ARCON96 format that were embedded in Appendix A of Attachment 4, were inadvertently omitted.
NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 2. If different from the sequential hourly Met data sets input to the EN-113 dispersion model, bases for determining hourly stability class and if different methods were 9 Enclosure PG&E Letter DCL-15-130 used throughout the data set(s) (e.g., depending on wind speed as suggested by UFSAR Table 2.3-41) an accounting of such hours when implemented and an explanation for having done so; PG&E Response The sequential hourly meteorological data input into ARCON96 to determine the onsite atmospheric dispersion factors are the same as the sequential hourly meteorological data input into the EN-113 dispersion model; the only difference being the format of the data that is input into the respective computer codes. NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 3. Atmospheric stability class appears to have been based, at least in part, on the temperature difference between the 76-and 10-m measurement levels on the primary Met tower. Except for the Unit 1 and Unit 2 Plant Vent release scenarios (Release Height= 74.1 m), all other source release heights for estimating CR and TSC impacts are no greater than 32.0 m (and most are less than that height).
Explain the basis for not having defined atmospheric stability based on the temperature difference between the 46-and 10-m measurement levels on the primary Met tower for those release scenarios with source-receptor pairs within that 46-to 10-m surface boundary layer. This comment also applies to the Met data input to the EN-113 dispersion modeling analyses to estimate impacts at the EAB and LPZ. *
* PG&E Response The DCPP licensing basis for stability class has always been based on the temperature difference (delta-T) of the 10-meter and 76-meter measurements.
The 91 JFD tables currently presented in UFSAR Section 2.3 provide stability classes from delta-T data based on the 76-meter to 10-meter difference, and there is no reference made to the 46 meter to 10 meter delta-T.
Stability class based on the 46-meter to 10-meter delta-T values has never been a part of the DCPP licensing basis. At the time of the original license when Safety Guide 23 was in force, PG&E as well as NRC, may have likely focused on the parenthetical statement "plant vent height" when locating meteorological instrumentation to determine stability
'classes for atmospheric dispersion factors.
At that time, Regulatory Position C.(2) of Safety Guide 23 stated that " ... the upper set should sense wind speed and direction and temperature at the height of release of radioactive material (plant vent height) but should be positioned not less than 30 meters above the lower sensor height."
In accordance with the current plant licensing basis and design, the primary meteorological tower is instrumented to provide temperature difference between the 10 Enclosure PG&E Letter DCL-15-130 76-meter and 10-meter elevations and the 46-meter and 10-meter elevations, and the backup meteorological tower is instrumented to provide temperature difference between the 60-meter and 10-meter elevations.
Additionally, Section 5.6.1 of DOE-HDBK-1216-2015, "DOE Handbook Environmental Radiological Effluent Monitoring and Environmental Surveillance,"
states that "If a vertical temperature difference (i.e., /1T//1z) is used along with solar radiation to determine atmospheric stability, the temperature difference should be determined over an interval of sufficient thickness to avoid undue influence of the ground (typically at least 50 meters).
The temperature monitoring levels should be selected and spaced such that the profile is representative and characterizes the magnitude of atmospheric turbulence at the potential release height(s)."
Thus, the 46-meter to 10-meter levels is deemed insufficiently distant from each other to provide a vertical temperature difference that would support a valid stability class methodology.
Accordingly, it is PG&E's position that the delta-T used to determine stability class at DCPP to all short-term (accident) atmospheric dispersion factors is in accordance with its current licensing basis, as well as current regulatory
: guidance, with respect to recommended locations for temperature instrumentation to determine stability class. ' NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 1. Need input files for EN-113 model runs along with a key explaining file format and identification of model input parameters so that equivalent input data files can be developed for NRG staff confirmatory modeling runs using NRG-accepted PA VAN dispersion model. PG&E Response Attachment 1 provides the description of input contained in the EN-113 User's Manual and the input files for the Unit 1 EAB, Unit 2 EAB and the Units 1 and 2 LPZ dispersion model runs. NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 2. Since this appears to be the first use of the EN-113 dispersion model at the DGPP and the licensee indicates that the code's provisions implement certain guidance from RG 1. 145 and RG 1. 111, provide documentation that demonstrates the equivalency of EN-113 results to the output from the NRG-accepted PAVAN and XOQDOQ dispersion models, which implement the guidance in RGs 1. 145 and 1.111, respectively, with the understanding that EN-113 operates on sequential
, 11 ------
Enclosure Letter DCL-15-130 hourly Met data whereas the PA VAN and XOQDOQ dispersion models operate on JFDs of wind speed and wind direction by atmospheric stability class. PG&E Response As noted in PG&E response to RAI 2 in the General section, Section 5.1 of Attachment 4 of LAR 15-03 which provide the technical assessment supporting the application, and Attachment 8 of LAR 15-03 which provides the proposed update of Section 2.3.2 of the U FSAR, both reflect the use of the EN-113 computer code to provide short-term (accident) dispersion estimates.
The referenced sections of LAR 15-03 describe how EN-113 follows the methodology of RG 1.145, Revision 1, induding the equations used and the selection of the appropriate XIQ values for the 0-2 hour averaging time and intermediate averaging times. EN-113
* uses the RG 1.111 Revision 1 methodology guidance to calculate the annual average XIQ used for the intermediate averaging times calculation.
Thus, the methodology used by PG&E to determine the short-term (accident) dispersion estimates are equivalent to that used by NRG-accepted PAVAN and XOQDOQ dispersion models, which also implement the guidance in RGs 1.145 and 1.111, respectiyely.
* NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 3. Confirm whether the XIQ values for the 0-to 2-hour averaging time and the other intermediate averaging intervals (i.e., 2-8 hours, 8-24 hours, 1-4 days, and 4-30 days) and annual average are determined as sliding averages or interpolated between the 0-to 2-hour and annual average X!Qs. The text in different parts of the application package appears to be inconsistent such that it is not clear which *approach has been used and Which discussions may only be intended to describe the capabilities of the EN-113 dispersion model. PG&E Response The 0-2 hr X/Q calculation followed the methodology in RG 1.145, Revision 1, and the annual average X/Q calcylation followed the methodology in RG 1.111, Revision
: 1. The XIQ values for the 0-2-hr averaging time and the other intermediate averaging intervals (i.e., 2-8 hrs, 8-24 hrs, 1-4 days, and 4-30 days) were determined by logarithmic*
interpolation between the 0-2-hr and annual average X/Qs. Only hourly average meteorological data is used as input in EN-113. For additional detail see* PG&E response to RAI 2 in the 'General' section.
12 ----------
NRC RAJ ARCON96 Dispersion Model Input I Output Files 1. Need input and output files for all ARCON96 model runs. PG&E Response Enclosure PG&E Letter DCL-15-130 The ARCON96 input/output files are provided in in the enclosed Attachment 3 data disc. Attachment 2 summarizes the description of the Release-Receptor cases and the associated input/output file names. NRC*RAI ARCON96 Dispersion Model Input I Output Files 2. In addition to Figure A-1 in Appendix A to Attachment 4 of the LAR submittal
: package, need legible drawings of all structures used to determine building related parameters as input to the ARCON96 model runs, as well as drawings that illustrate release and receptor heights.
This comment also applies to the EN-113 dispersion modeling analvses if building wake has been accounted for as part of those analyses.
PG&E Response The following drawings are provided in in the enclosed Attachment 4 data disc: Drawinq No Sheet Rev. Title Filename 57727<2> Equipment Location; Plan at Elevation
: 1. 41. 140'-0";
Aux., Containment and Fuel DWG 57727-1 (r41}.pdf Handlinq Bldqs. 57729<2> 1 12 Equipment Location; Section A-A Auxiliary DWG 57728-1 (r12}.pdf Building 57732<1>'2> Mechanical; Equipment Location; Section 1 17 'E-E' -Auxiliary, Turbine & Fuel Handling DWG 57732-1 (r17}.pdf Buildings l 59353(2) 1 10 Mechanical; Air Conditioning Area "K" DWG 59353-1 (r10}.pdf Elev. 154'-6" Auxiliary Building 101942'1><2> [Local Instrument Panel Index; Coordinate-3 35 Column Line Cross Reference sheet] DWG 101942-3 (r35}.pdf (note that the drawinq has no title block) 438040\"'I 1 43 Civil; Finished Grading Plan; Plant Area DWG 438040-1 (r43).pdf 438042\<!)
1 27 Civil; Finish Gradinq Plan; Plant Area DWG 438042-1 (r27).pdf 443115<2> 1 10 Architectural; Ladder Details; Exhaust Vent DWG 443115-1 (r10}.pdf Containment Structure 471124\<!)
1 11 Civil; Plot Plan DWG471124-1 (r11).pdf 500059<2> 1 15 Piping & Mechanical; Area G, GW and GE; DWG 500059-1 (r15}.pdf Plan at Elevation 140'-0" 501551<2> 1 9 Piping & Mechanical; Areas GE & GW; DWG 501551-1 (r9}.pdf Plan Above El. 140'-0" 508911<2> 1 9 Mechanical; Outdoor Storage Tanks; DWG 508917-1 (r9}.pdf Pipinq Modification; Sections 13 Drawing No Sheet Rev. 511155<2> 1 16 512905<2> 1 22 663071<2> 129 6 lJFSAR Figure 2.1-2 11 UFSAR Figure 2.1-15 22 Title Mechanical; Plans & Sections; Air Conditioning Control Room Pressurization Fan Arrangements; Area "A" Elevation 140'-0" Mechanical; Plans, Sections, and Schedule; Onsite Technical Support Center and Laboratory Refueling Water Storage Tank; Elevation and Orientation Details Site Plan and Gaseous/Liquid Effluent Release Points Low Population Zone (Historical)
Enclosure PG&E Letter DCL-15-130 Filename DWG 511155-1 (r16).pdf DWG 512905-1 (r22).pdf DWG 663071-129 (r6).pdf UFSAR Figure 2.1-2.pdf UFSAR Figure 2.1-15.pdf (1): Drawings 101942 and 57732 were used to develop cross-sectional building areas to account for building wake effect in ARCON96 and EN-113. (2): Note: These drawings are considered Security Sensitive and should be withheld under 10 CFR 2.390. 14 Input Data for EN-113 Dispersion Model EN-113 Input Description 1 Enclosure Attachment 1 PG&E Letter DCL-15-130 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGR.t\H OOCUt.tENTAUON s*roNE & WBBSTBR SECTION:
V OPR&\TING INSTRUCTIONS REVISED DATE: I). Selection of Type of Calculation and Output Format READl !nput Data Card l (UA4,3A4}
CLIENT -Client's name (left-justified).
JOBNO -Job Number (left-justified).
Card 2 (11A4,SA4)
SITE -Site Name (left-justifiud).
-Ca 1.culal:ion nu111ber.
Gat"d 3 (4I5,F5.0,I5)
ISTART -Start date (on) (year ancl Julian date) if othet' than start of data. ISTOP -Stop date (after) (year and Julian date) if other than end of NDYSDT -Numbet' of days input data. HETSTB -Method of determining stability d.ass: 1 -Radiation index (WBAN tape)
(llM) (3A4) 2 -Split sigma {3 and 4 or 5 below) 3 -Delta temperatur0 (must have DllT) 4 -Wind direet!on t:'ange 5 -Wind direc:tlon standard deviation.
DRT -Height: difference for delta t:cmpera t:m:e: If temperature is in deg F then DHT must be ln feet U:
is in <leg C t:ben DIIT must bo in l'.leters.
IREDIS -Rcdist-e:l'oution of CALMS switch: 0 -:Preyfous good wind di tection 1 -Cal111 speed -1. 5 mph speed class sector frequency distri button 2 -Calm speed -t. 5 mps (3 *. 3557 mph) speed class sector frequency distribution 1118.ke Device tl available.
Card 4 (9(2X,A3),2I5)
ID -Met data three.-character ID: ID(l) -Wind speed ID(2) -Wind direction.
!D(3) -Temperature
!0(4) -Wind direction range ID(S) -Wlnd dir:ect:ion standard deviation tD(6) -Delta temperature t0(7) -Wind speed (upper levd) !0(8) -Wind direction (upper level) ID(9) -Temperature (upper 2
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM OOCUMSN!Ar!ON sroNE & wessrER EN-113 SECrtoN:
v OPERArtNG INSrRUCUONS REV!SEI>
DArE: PAGE 5 ISPUNr -Wind speed units indicator:
tf input data is ill mph, ISPUNI' is 0 If input: data ls in
!SPUNr is l If input data is i.n rnps, ISPUNr is 2. IfPtnir -temperature units indicator:
If input data is .in F, IrPUNr is 0 If input data is in Deg c, I!PUNr is 1. PARMUL -Parameter Mulcipliet:
PARMUL(l)
-Wind speed Uefault t.O ?ARMUL(2)
-Wind direction Default 1.0* PARMUI.(3)
-!elllperatute Default 1.0 PARMUL( 4) -Wind direction range Oefault 1.0 PARMUL(S)
-Wind direction standard deviation Normally 0.1 PARMUL(6)
-Delta tempeJ;ature Default 1.0 PARi.'1.UL(7)
-Wind speed (upper level) Default 1.0 PARMUI.(8)
-Wind direction (upper level) 'Dafault t.O PARMUJ.{9)
-!emperature (upper level) Default 1.0. rPGRAD -Specified tempei:atur:e gradients (6) for specific toimr height differentials to be used to determine stability classes (hourly data LE apecified.gt'ad:tent seta stability class). Specified gradient should include parameter multiplier.
Desired gradient of -3.0 and parameter multiplier of 0.1. should. give rPGRAD of -30. tf all are set to ioro default classes of -1,9, -t.7, -1.5, -0.), l.5 and 4.0 deg C/100 will be used. REJ.D2 Int>ut Data Ca.rd 5 lREi'lP RE LS ID Cat'd 6 !SrIY'P WPLUB S!KHr srKDIA (15, 11A4) Release {X/Q) (D/Q) -Release point and calculation type switch: (1) gl:'ound (2) efo*mted (3) ground (4) Qlavated
?oi.nt ID ( lef t-jus tHied) (IS,FtO.O,SFS.0,2FlO.O,Il 1I4IS,2F5.0)
-Station t:ype l -nuclear, 2 -fossil (llA4) fossil -No more than t:i;.-o do1mwJ.nd distances when calculating hourly and .11.nnual averages together.
ran downwind distances calculating annual averages only. -Stack gaa flow. -
holght. -Scack exit: diame.ter.
(lb/hr) (f C:) (ft:)
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRA.o\I' DOCUC18Nl'ArION srom:: & W&BSrBR 1m-113 SECUON: ,, Ol'ERArING rnsra.ucrIONS REVISED DAI'E: GAS VE!. rs HLID WFUE:L H.VAT .. UE !S!RLN !CALM ucu ucs Card 7 ISECVG MESHr IAECSG IBWEFP PAGE 6 -Stack exit velocity
-Stack exit temperature
(&deg;F). -
mixing L!O height (Geters).
-Fuel f1ow (Lucas and Moore Plume Rise) (lb/hr).
-Heat value of fuel (Lucas and Moore) (Btu/hr).
-Calculilta hourly averages from straight line Oil log-log paper: (0) -no ealculation
( positive number) -Limiting index of l.)0 loop, . Wtll calcul.ate averages with straight lines scarting at. land going to the limit (!SrRLN),
Must make the 1-hour average calculation and the annual calculation at the same t1111e. If the 1-hour, 50 percent x/Q 11alues is t:o be used, 6et the left-inost digit to 1.
the 50 percent equal risk value is used. (lEQSO) -Switch to allow wind speed or height corrected lrlnd speed to be reset to calm speed if wind apeed falls below calm speed: Default (0) -W/S reset: (1) -W/S not: reset. -Unstable and neutral W/S height correction factor (Stabilities A -D) Default UCU Q 1.0. -Stable W/S height correction factor (Stabilities E -G) Default UCS 1.0. (7IS,2(3X,7tl),3IS,2F5,0)
-Sector average:
0 -with 1 -
cotrection.
-Height of wind speed meaaurement (ft).
= O, Speed modification with height not made (ASHE). -Dispersion coefficient:
0 -AEC (POLYN) Gtfford1s l -S&W {SIGY, SIGZ) rurner' g 2 -AEC (POL'!ND)
Dasert. -Building effect (short-term):
0 -Not used (if not o. t:'ead Cards 9 and 10) l -Meandering plume GJethod.
If stability E, F or G and wind speed LE 2.5 mph, 2*Pt*S!GY*SIGZ is increased four times. 2 -AEC method (Sagendorf) yjQ = l/(U*(PI*S!GY*SIGZ+c*A))
3 -Sigma Squared method :(/Q = l/(PI*U*SlGY*S!GZ)
SIGY (SIGY**2+C*A/PI)**0.5 S!GZ = (SIGZ**2+c*A/?.I)**0.5 4
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM OOCUMENrArION sroNE & 1masr1m BN-113 sncrroN:
v oPERAl'ING REVISED DAl'E: IrOPO . lXERIN IS!GMA ISrABY !SrABZ NHR624 PAGE 7 4 -A.bbey Plume Meander method, CPRlM must be specified.
If CPRIM = O.O, there is no building wake effect 5 -Rancho Seco ( '77) building wake l.'llennder.
Number of directions
"'11th inputted topographic dat;a . (l-16): 0 -
topography Terrain adjustment factor selection switch (annual).
If input data cards are needed, they will be read in by Subroucine
!8RAIN after all other READ2 Cards. (0) -No adjustment
( l) Plain '(2) -Desert ( 3) -Plain (4) -Desert (S) -Valley (input data (6) -Coast (7) -
valley (point) (point) (curve) (curve) required see Card 30 below) (B) -Raad in data for (5, 6, and 7) (9) -Read only sil:e-specific ground release factors (10) -Re*ld only site-specific eleN<ltcd release factors (11) -Read both site-specific ground and elevated release factors.
(Input of this dat:a is i.n the same format as topographic
.input, 16 directions and up . to. 12 doi;,-nwind dis ta.nee a. Reading sequence f.3 the same as Cards 30 -32; ground first and elevated second.)
(12) -Use site specific ground-level release recirculation factors in calculation.
(13) -Use site elevated release recirculation f'actol:'s
.1.n calcul.ation.
-*sigma printout print control:
0 -no printout 1 -printout.
-Horizontal di.spersion coefficient:
.selo?ctio11 array. rhe seven locations of this array represent stability claesoe A -G. By inserting a nurnber l -7 in a 1ocatton the sigma curve ( l
* 7) will be used tor that particular stability clasi;. If the array is left blaok, the normal sigma cur'1os f.i"ill be used for ehe stability classes.
Set to (1). Vertical ciispersio11 coefficient selection
:a.rray.
Other .. cooments are the surne as ISfABY above. Number of hours to be slid for 72-hour sliding average, NumbQr of houra to be slid for 624-hour sliding average.
NRR72 and NRR624 default to 1 if not values used must di11ide 72 or 624 without remainder.
5 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENrArION sroNE & WEBSrER EN-113 sgcn:ON:
v OPERA.UNG REVISED DArE: PAGE 8 L!HXQR x/Q l!lnit write switch: 0 -no pt:intout t -printout.
(Supply XQLIM values Card 8A.) PRGHRS -Number of hours intermittent (purga) release.
(must not be set to 0.0)
-Wind speed below whlch recirculation fraction
-will be applied Nora:
and R?CWSP used only for intermittent release calculation which mui;t he.ve special GNCHIQ and ourCHQ subroutines.
Card 8 JHRARY (7IS,5F5.0,15X,15) rime period control:
1 a 16 72 24 (6I5) 624 1000 1000 0 Fossil 1 3 8 Blank or zero -no calculation 1000 -Annual Average (one level of winds), 2000 -Annual Average (use upper level winds if to elevated shift ts to be made) JHRARY(l)
If used, can only be for JHRARY(2-5)
Nuclear JHRAR'l(6)
Nuclear JHRARY(2-4)
Fossil JHRARY(S)
Fossil NOrESt l hout. 1001 or*2001 ground to elevated shift (Regulat-0ry Guide l.111 pt'1Jporations) using l or 2 levels of wlnds. 3001 or 400t same as above plus aeronynamic downwash.
If used can range tt'orn 2 to 624 hrs If used can only be 1000, 1001, 2000 or 2001 If used can range from 2 to 624 hrs If used can only be 1000 or 2000 l. Any a*Terage of S hours or less ...,ill uae term equat:!ons.
: 2. ro obtain only undecayed annual x/Q printout use 1001 or 2001 as a control.
-Plume Use Equation: 1 -Bolland Equation Eq 4.1, Briggs 1969) 2 -Lucas and Hoore (HVALUE) 3 -Optimized 6
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENTATION STONE & WEBSTER EN-113 SECTION:
,, OPERATING rnSTRUCTIONS REV!SED DATE: 4 -Opt11nized Csanady 5 -Clarke 6 -'Sriggs 7 -2/3 Law 8 -Zero ?tume Rise 9 -Spadfied Plume Rise (PLUMRS) 10 -Rriggs (Revised 1970) 11 -Rolland (C:q 4.1, Turner's Wot'kbook) 12 -Briggs (Revised 1972) PAGE 9 1.3 -Briggs ('Rr:l.ggs
-Sagendorf, Non-Buoyant Plume) 14 -Briggs (Revised 1975). The fol lowing parar:netet"s (X) are needed for the equat.ton number at the top: N l 2 3 4 5 6 7 8 9 10 11 WFUEL -x -------W.FLIJF:
-x x,-x x -x x GASl/EL
* x x x -x TSS x x x x x x x --x x STKllT -x --x x -x ---STl<DIA x x x -x 'l'A x x x x x x x --x x WNDSPD x x x x x x x --x x RVALUE -x -------where \.IFIJeL
"' Fue.l Flow WFT,tre = Flue Gas Flow GASVEL
* Stack Gas Exit Velocity TSS = Stack Gas Eidt Teoperature STKHT "' Stack Height STKDIA = Stack Exit Diameter TA = knblent Air Temperature H11DSPD = \Hnd Speed HVALUE = Heat Value of :'uel. Specified Plu:ne Rise (ft). 12 -x -x --x x x --x x x 14 x -x --x :< -WFUEL WFLUR GASVEL TSS STKHT STKDIA TA WNDSPD HVA1UE PLTP.iRS CAL::t.\C
-fiT!nd speed (::iph) assigned to calm observ<ltion for accident x/Q calculation.
Stop 6, i.f needed and not given. CALMAN -Wind speed (mph) assigned to calm observation for annual yJQ calculation.
Stop 6, if needed and not given. -Building height wake effecc. (long-turm)
(Annual).
If zero defaults to l.ong-tem ground release (11eter:s).
(NOTE: BRT must be eero when SPDBWE is -3
* 0. ) 7 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENt'ArION srmra & WEBSL'ER SECl'!ON:
v Ol;>ERArING lNS!R.UCrrocrn RK'JISE:D OAl'E: PAGE 10 Sl?DBWE Ground to ele*1ated release shift: attd stack downwnsh switch (annual).
Zero (0) -??o shift or downwash.
-.Pos!.t:lva
-SPDBt.JB is wind speed (mph) below which shift from ground to release will be made. (Staclt 'height (SrKHr) must: be specified.)
-Negative
(-1.0) t:o elevated proportional shift (Regulatory Guide 1.111 2B) is made. (Stack gas exit (GASV8L) and (Sl'KH!)
must be specified.)
-Negative
(-3.0) -Aerodynamic downwash Guide 1.111, F..q (5) 1s used). (Stack diameter (S l'KDIA),
(SrlCIIr) and (GASVEL) must: be apecified.)
-Negative
(-2.0) -will apply aerodyrui!ll!.c downwaah
(-3.0) to elevated portion of ground to ele*1ated release (-1.0). lAJDIR -Adjacent doW"tlwlnd disl:ilnce switch (short-term only); (0) -Card St\ XQLnt Card 9 not used, {GT.O) -used. (2El0.0)
(Card not needed if Array containing lower and upper x/Q *1alues for and ootwecn which, the d1tte, time and meteorology (speed, direction and vertical stability class) are printed out. READ2 will limit release potnts to the first zero time period and the LPZ distances.
tf all r:aeteotology is desired, set the. lower limit = O.O and uppeT limit 1.0 or greater.
(3F5.0) (Card not needed if WSP&#xa3;ED -Wind speed above which building effect w!ll be considared (mph). C -Constant (0.5 CPRIM -Const:ant used in Abbey ?lume Meander method, CPRIH .. O.O removes bu1ld1ng waka effect, Card 10 (16F5.0)
(Card not needed U IBWEFF .. O.) A -Building wake effect area by df.rection:
l -wind fro1n the nol.*t:h
-ai*ea on the south side of building.
Card 11 (16"F5.0)
D!SrrE -Sita boundary distance by direction (metet's): 1 -wind north.-distance south of release point. 8 ---------------
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENTATION STONE & WEBSTER EN-113 SECTION:
V OPERATWG INSTRUCTIONS REVISED DATE: PAGE 11 Card 12 -(16FS.O)
DISLPZ -Low population zone boundary distance by direction (meters): l -wind from north -distance south of. release point. NOTE: For Cards 10, 11 and 12, if the values eor all directions are the: same, punch the value in location (l) and 99999 in location (2). Card 13 (I5110F5.0) IDSLP -Number oE downwind distances other than site boundary or low population zone bou1\dary.
DISTAN -Downw1ud distances (1-10) {meters)
Cards 14 -29 (I5,12PS.O)
(Cards not needed 1f ITOPO=O)
IDR -Wind direction index* -
blo"1ing from (l-16). TOPORT Ground elevation obo*1e stack basa downwind Erorn the point (feet). (If IDR "" l (1101.'th),
elevation should be those south o.f the refousc point.) Cards 30 -32 (12,6(!2,2F5.Q)/2X,6(I2,2F5.0)/2X,4(I2,2F5.0))
* These data cat'ds will be read in by Subroutine TERAUl when the ITER!N Em! t:c.h is set to 3, 4 or ;. INUM IDRA UISTHX XQMlIT.T
-
of conrUtion groups
-Winrl direction identification (l -wind from north). (Direction not given means no adju5traent.)
-Downwind distance (mJ.les) bi!yond i*hich no adjustments are made. For up-valley sot distance to 1000.0. x/Q adjustment value.
* Typic.al values are --Down-Valley XQ!1ULT "" 5 XQMUtT == 1.5 XQMULT = l DISTM.'{
* 20 Hiles DISTHX = 1000 DISTitX = 1000 -
-Cross-Valley 9
Unit 1 EAB EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE Pacific Gas & Electric Company GROUND LEVEL (X/Q) CALCULATION NUMBER 14078104-C-M-00002 Diablo Canyon Nuclear Power Plant Unit 1 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 1 I START I STOP NDYSDT METS TB DHT IREDIS 87001 91365 1826 3 100.0 2 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL(9) 0.10 1.00 1.00 1.00 1.00 0.10 **********
READ2 (6.8) INPUT DATA**********
IRETYP RELSID(ll) 1 GROUND LEVEL (X/Q) ISTTYP 1 WFLUE 0. STKHT 0.00 ISECVG MESHT IAECSG IBWEFF 1 0 0 5 JHRARY(6) 1 0 0 0 WSPEED C CPRIM 0.00 0.50 0.00 A(l6) STKDIA 0.00 ITO PO 0 0 GASVEL 0.00 ITERIN 1 1001 JOBN0(3) 14078101 CALCNU(5) 14078104-C-M-00002 ELEVATED CONDITIONS SPEED 0 1. 00 TS 0. I SIGMA 0 IPLM!1Q 8 DIR 0 1. 00 HLID 0. PLUMRS 0.0 TEMP ISPUNT ITPUNT 0 0 1 1. 00 0.00 0.00 WFUEL 0. ISTABY ISTABZ 0000000 0000000 CAL MAC CAL MAN BHT 0.5 0.3 66.5 2 14078104 TPGRAD(6) 0.00 0.00 HVALUE ISTRLN 0. 0 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 0.00 0.00 I CALM ucu ucs 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE (16) 830.0 830.0 780.0 780.0 750.0 750.0 750.0 750.0 730.0 730.0 740.0 740.0 890.0 890.0 920.0 830.0 DISLPZ (16) 0.0 o.o 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 IDSLP DISTAN(lO) 0 0.0 0.0 0.0 0.0 0.0 0.0 o.o 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 4.000 2 4.000 10 3 4 5 6 7 8 9 10 11 12 13 14 15 16 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 ---
11 Enclosure Attachment 1 PG&E Letter DCL-15-130 Unit 2 EAB EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE CALCULATION NUMBER 14078101-ME-003 Pacific Gas & Electric Company GROUND LEVEL (X/Q) Diablo Canyon Nuclear Power Plant Unit 2 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 2 ISTART ISTOP NDYSDT METSTB DHT IREDIS 87001 91365 1826 3 100.0 2 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL (9) 0.10 1. 00 1. 00 1. 00 1. 00 0.10 **********
READ2 (6. 8) INPUT DATA **********
IRETYP RELSID (11) 1 GROUND LEVEL (X/Q) ISTTYP WFLUE STKHT STKDIA GASVEL 1 0. 0.00 0.00 0.00 ISECVG MES HT IAECSG IBWEFF ITO PO ITERIN 1 0 0 5 0 1 JHRARY (6) 1 0 0 0 0 1001 WSPEED c CPR IM 0.00 0.50 0.00 A(16) 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE (16) 730.0 730.0 740.0 780.0 780.0 780.0 DISLPZ (16) 0.0 0.0 0.0 0.0 0.0 0.0 IDS LP DISTAN (10) 0 0.0 0.0 0.0 0.0 0.0 JOBN0(3) 14078101 CALCNU(5) 14078101-ME-003 ELEVATED CONDITIONS SPEED DIR TEMP I SPUNT IT PUNT 0 0 0 0 1 1. 00 1. 00 1. 00 0.00 0.00 TS HLID WFUEL 0. 0. 0. I SIGMA ISTABY ISTABZ 0 0000000 0000000 IPLMEQ PLUMRS CALMAC CAL MAN BHT 8 0.0 0.5 0.3 66.5 2745.0 2745.0 2745.0 2745.0 2745.0 830.0 830.0 830.0 830.0 820.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 4.000 2 4.000 12 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 14078101 TPGRAD (6) 0.00 0.00 0.00 0.00 HVALUE ISTRLN I CALM ucu ucs 0. 0 2 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 820.0 870.0 870.0 850.0 730.0 0.0 o.o 0.0 0.0 0.0 3 4 5 6 7 8 9 10 11 12 13 14 15 16 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4. 000 4.000 4.000 4.000 4.000 4. 000 13 Enclosure Attachment 1 PG&E Letter DCL-15-130 I
Unit 1/2 LPZ EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE CALCULATION NUMBER 14078101-ME-003 Pacific Gas & Electric Company GROUND LEVEL (X/Q) Diablo Canyon Nuclear Power Plant Unit 1 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 1 ISTART ISTOP NDYSDT METSTB DHT IREDIS 87001 91365 1826 3 100. 0 1 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL(9) 0.10 1. 00 1. 00 1. 00 1. 00 0.10 **********
READ2 (6. 8) INPUT DATA **********
IRETYP RELSID(ll) 1 GROUND LEVEL-(X/Q) ISTTYP WFLUE STKHT STKDIA GASVEL 1 0. 0.00 0.00 0.00 ISECVG MES HT IAECSG IBWEFF ITO PO IT ERIN 1 0 0 5 0 1 JHRARY(6) 1 0 0 0 0 1001 WSPEED c CPR IM 0.00 0.50 0.00 A(16) 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE(16) 9650.0 9650.0 9650.0 9650.0 9650. 0 9650.0 DISLPZ (16) 0.0 0.0 o.o 0.0 0.0 0.0 IDS LP DISTAN(lO) 0 0.0 0.0 0.0 0.0 0.0 JOBN0(3) 14078101 CALCNU (5) 14078101-ME-003 ELEVATED CONDITIONS SPEED DIR TEMP I SPUNT IT PUNT 0 0 0 0 1 1. 00 1. 00 1. 00 0.00 0.00 TS HLID WFUEL 0. 0. 0. ISIGMA ISTABY ISTABZ 0 0000000 0000000 IPLMEQ PLUMRS CALMAC CAL MAN BHT 8 0.0 0.5 0.3 66.5 2745.0 2745.0 2745.0 2745.0 2745.0 9650. 0 9650.0 9650.0 9650.0 9650.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 1.250 2 1.250 14 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 14078101 TPGRAD(6) 0.00 0.00 0.00 0.00 HVALUE ISTRLN I CALM ucu ucs 0. 0 2 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE _ IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 9650.0 9650.0 9650.0 9650.0 9650.0 0.0 0.0 0.0 0.0 0.0 3 4 5 6 7 8 9 10 11 12 13 14 15 16 1.250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1.250 1. 250 1. 250 15 Enclosure Attachment 1 PG&E Letter DCL-15-130 Release-Receptor Cases 1 Enclosure Attachment 2 PG&E Letter DCL-15-130 File Name dccase01 dccase02 dccase03 dccase04 dccase05 dccase06 dccase07 dccase08
 
dccase09 dccase10 dccase11
 
dccase12 dccase13 dccase14 dccase15 dccase16 dccase17 dccase18 dccase19 dccase20
 
dccase21 dccase22 dccase23 dccase24 dccase25 dccase26 dccase27 dccase28
* dccase29 TABLE 1: Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Post-Accident LOCA Radioloaical Releases Description of Release-Receptor Cases. XIQ (sec/m3) 0-2 hours 2 -8 hours 8 -24 hours 1 -4 davs 4-30 davs Unit 1 CB Edge to Unit 1 CR Normal Intake 1.28E-03 7.12E-04 2.87E-04 2.90E-04 2.84E-04 Unit 1 CB Edge to Unit 1 CR Emergency Intake 4.11 E-04 2.30E-04 9.62E-05 8.69E-05 7.03E-05 Unit 1 CB Edge to Unit 2 CR Emergency Intake 1.67E-04 7.95E-05 2.63E-05 2.81 E-05 2.34E-05 Unit 1 CB Edge to CR Center 8.85E-04 4.43E-04 1.75E-04 1.77E-04 1.65E-04 Unit 1 PV to Unit 1 CR Emergency Intake 5.59E-04 3.38E-04 1.32E-04 1.12E-04 8.38E-05 Unit 1 PV to Unit 2 CR Emergency Intake 2.26E-04 1.48E-04 5.40E-05 5.47E-05 4.45E-05 Unit 1 PV to CR Center 1.26E-03 8.96E-04 3.44E-04 3.44E-04 2.99E-04 Unit 1 RWST Vent to Unit 1 CR Emergency Intake 3.27E-04 1.90E-04 7.13E-05 6.99E-05 5.76E-05 Unit 1 RWST Vent to Unit 2 CR Emergency Intake 2.10E-04 9.83E-05 3.73E-05 3.53E-05 2.86E-05 Unit 1 RWST Vent to CR Center 1.07E-03 4.86E-04 1.99E-04 1.75E-04 1.43E-04 Unit 2 CB Edge to Unit 2 CR Normal Intake 1.96E-03 9.42E-04 4.48E-04 3.98E-04 3.18E-04 Unit 2 CB Edge to Unit 1 CR Emergency Intake 1.70E-04 1.06E-04 4.23E-05 3.81E-05 2.95E-05 Unit 2 CB Edge to Unit 2 CR Emergency Intake 3.85E-04 1.47E-04 5.94E-05 5.84E-05 4.84E-05 Unit 2 CB Edge to CR Center 1.08E-03 5.46E-04 2.47E-04 2.12E-04 1.68E-04 Unit 2 PV to Unit 1 CR Emergency Intake 2.03E-04 1.29E-04 5.13E-05 4.32E-05 3.19E-05 Unit 2 PV to Unit 2 CR Emergency Intake 5.71 E-04 2.96E-04 1.20E-04 1.04E-04 8.19E-05 Unit 2 PV to CR Center 1.13E-03 7.08E-04 2.85E-04 2.39E-04 1.70E-04 Unit 2 RWST Vent to Unit 1 CR Emergency Intake 1.91E-04 1.21E-04 4.58E-05 4.39E-05 3.53E-05 Unit 2 RWST Vent to Unit 2 CR Emergency Intake 3.29E-04 1.61E-04 6.10E-05 5.53E-05 4.45E-05 Unit 2 RWST Vent to CR Center 1.07E-03 5.80E-04 2.18E-04 2.19E-04 1.79E-04 Unit 1 140' Leakage to Unit 1 CR Normal Intake 6.84E-03 3.08E-03 1.21E-03 1.12E-03 8.75E-04 Unit 1 140' Leakage to Unit 1 CR Emergency Intake 3.75E-04 2.33E-04 9.12E-05 8.45E-05 6.62E-05 Unit 1 140' Leakage to Unit 2 CR Emergency Intake 2.55E-04 1.25E-04 4.42E-05 4.38E-05 3.55E-05 Unit 1 140' Leakage to CR Center 3.22E-03 1.42E-03 5.54E-04 5.20E-04 4.21E-04 Unit 1 PL to Unit 1 CR Normal Intake 4.90E-03 3.45E-03 1.37E-03 1.37E-03 1.28E-03 Unit 1 PL to Unit 1 CR Emergency Intake 8.20E-04 5.40E-04 2.15E-04 1.87E-04 1.43E-04 Unit 1 PL to Unit 2 CR Emergency Intake 2.58E-04 1.54E-04 4.95E-05 5.26E-05 4.48E-05 Unit 1 PL to CR Center 2.59E-03 1.81 E-03 7.29E-04 7.15E-04 6.64E-04 Unit 2 140' Leakage to Unit 2 CR Normal Intake 6.71 E-03 3.12E-03 1.21E-03 1.22E-03 1.02E-03 2
File Name dccase30 dccase31 dccase32
 
dccase33 dccase34 dccase35 dccase36 dccase37
* dccase38 dccase39 dccase40 dccase41 dccase42 dccase43 dccase44 dccase45 dccase46 Notes: File names CR CB PV 140' Leakage RWST PL TABLE 1 : Input I Output File Names. Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Post:. Accident LOCARadiological Releases Description of Release-Receptor Cases Unit 2 140' Leakage to Unit 1 CR Emergency Intake Unit 2 140' Leakage to Unit 2 CR Emergency Intake Unit 2 140' Leakage to CR Center Unit 2 PL to Unit 2 CR Normal Intake Unit 2 PL to Unit 1 CR Emergency Intake Unit 2 PL to Unit 2 CR Emergency Intake Unit 2 PL to CR Center Unit 1 PV to Unit 1 CR Normal Intake Unit 2 PV to Unit 2 CR Normal Intake Unit 1 CB Edge to Unit 2 CR Normal Intake Unit 2 CB Edge to Unit 1 CR Normal Intake Unit 1 PV to Unit 2 CR Normal Intake Unit 2 PV to Unit 1 CR Normal Intake Unit 1 140' Leakage to Unit 2 CR Normal Intake Unit 1 PL to Unit 2 CR Normal Intake Unit 2 140' Leakage to Unit 1 CR Normal Intake Unit 2 PL to Unit 1 CR Normal Intake = Input (.rsf), Output (.log) = Control Room = Containment Building
=Plant Vent = Containment Penetration (GE Area) = Refueling Water Storage Tanks =Containment Penetration (GW/FW Area) Or 2 hours 2.28E-04 3.97E-04 3.16E-03
 
3.55E-03 2.28E-04 8.64E-04 2.21 E-03 1.67E-03 1.51E-03 6.52E-04 6.93E-04 9.10E-04 7.88E-04 2.24E-03 1.38E-03 2.14E-03 1.22E-03 3 XIQ (sec/m3) 2 -8 hours 8 -24 hours 1 -4 days 4-30 days 1.60E-04 6.25E-05 5.52E-05 4.21E-05 1.76E-04 6.93E-05 6.44E-05 5.27E-05 1.85E-03 7.17E.:.04 6.84E-04 5.43E-04 1.19E-03 4.82E-04 4.56E-04 3.03E-04 1.62E-04 6.58E-05 5.43E-05 3.99E-05 4.23E-04 1.50E-04 1.48E-04 1.20E-04 1.17E-03 4.?0E-04 3.90E-04 2.61E-04 1.22E-03 4.90E-04 4.90E-04 4.44E-04 9.41E-04 3.86E-04 3.23E-04 2.23E-04 3.51E-04 1.51E-04 1.49E-04 1.37E-04 3.84E-04 1.67E-04 1.42E-04 1.0SE-04 6.57E-04 2.68E-04 2.62E-04 2.45E-04 4.86E-04 2.01 E-04 1.69E-04 1.17E-04 1.15E-03 3.98E-04 3.89E-04 3.20E-04 9.83E-04 3.92E-04 3.88E-04 3.65E-04 1.39E-03 5.72E-04 4.83E-04 3.62E-04 6.26E-04 2.53E-04 2.12E-04 1.41 E-04 TABLE 2 -Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for FHA File Name dcfhc1 dcfhc2 dcfhc3 dcfhc4 dcfhcS dcfhc6 dcfhc7 dcfhc8 dcfhc9 dcfhc10 dcfhc11 dcfhc12 dcfhc13 dcfhc14 dcfhc15 dcfhc16 dcfhc17 . dcfhc18 dcfhc19 dcfhc20 Notes: File names CR FHB EH Radiological Releases Description of Release-Receptor Case Unit 1 FHB to Unit 1 CR Normal Intake Unit 1 FHB to Unit 2 CR Normal Intake Unit 1 FHB to Unit 2 CR Emergency Intake Unit 1 FHB to CR Center Unit 1 EH to Unit 1 CR Normal Intake Unit 1 EH to Unit 2 CR Normal Intake Unit 1 EH to Unit 2 CR Emergency Intake Unit 1 EH to CR Center Unit 2 FHB to Unit 1 CR Normal Intake Unit 2 FHB to Unit 2 CR Normal Intake Unit 2 FHB to Unit 1 CR Emergency Intake Unit 2 FHB to CR Center Unit 2 EH to Unit 1 CR Normal Intake Unit 2 EH to Unit 2 CR Normal Intake Unit 2 EH to Unit 1 CR Emergency Intake Unit 2 EH to CR Center Unit 1 FHB to Unit 1 CR Emergency Intake Unit 2 FHB to Unit 2 CR Emergency Intake Unit 1 EH to Unit 1 CR Emergency Intake Unit 2 EH to Unit 2 CR Emergency Intake =Input (.rsf), Output (.log) = Control Room = Fuel Handling Building
= Equipment Hatch 4 XIQ (sec/m3) 0 -2 hours 6.98E-03 2.93E-03 2.56E-04 3.78E-03 2.61E-02
 
2.88E-03 2.64E-04 5.51E-03 2.72E-03 6.98E-03 2.49E-04 3.7.1 E-03 2.49E-03 2.51E-02 2.49E-04 5.19E-03 3.31 E-04 3.50E-04 4.36E-04 4.68E-04 File Name dcmssv02 dcmssv03 dcmssv04 dcmssv05 dcmssv07 dcmssvOB dcmssv10 dcmssv11 dcmssv12 dcmssv13 dcmssv15 dcmssv16 dcmssv18 dcmssv19 dcmssv20 dcmssv21 dcmssv23 dcmssv24 dcmssv25 dcmssv26 dcmssv27 dcmssv28 dcmssv29 TABLE 3 Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Radiological Releases from MSSVs/ADVs/MSLB Description of Release-Receptor Cases X/Q (sec/m3) 0 -2 hours 2 -8 hours 8 -24 hours 1 -4 days 4-30 days Unit 1 MSSVs to Unit 1 CR Normal Intake NIA NIA NIA NIA NIA Unit 1 MSSVs to Unit 2 CR Normal Intake 4.29E-03 2.76E-03 1.04E-03 1.06E-03 9.46E-04 Unit 1 MSSVs to Unit 2 CR Emergency Intake 3.14E-04 1.53E-04 5.12E-05 5.29E-05 4.38E-05 Unit 1 MSSVs to CR Center 1.39E-02 7.40E-03 2.38E-03 2.56E-03 2.15E-03 Unit 2 MSSVs to Unit 1 CR Normal Intake 3.87E-03 2.42E-03 9.89E-04 8.17E-04 6.09E-04 Unit 2 MSSVs to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 MSSVs to Unit 1 CR Emergency Intake 2.89E-04 1.91E-04 7.45E-05 6.62E-05 5.08E-05 Unit 2 MSSVs to CR Center 1.22E-02 8.10E-03 3.27E-03 2.76E-03 2.08E-03 Unit 1 ADVs to Unit 1 CR Normal Intake NIA NIA N/A NIA NIA Unit 1 ADVs to Unit 2 CR Normal Intake 4.30E-03 2.79E-03 1.05E-03 1.06E-03 9.49E-04 Unit 1 ADVs to Unit 2 CR Emergency Intake 3.13E-04 1.54E-04 5.13E-05 5.30E-05 4.39E-05 Unit 1 ADVs to CR Center 1.39E-02 7.45E-03 2.39E-03 2.59E-03 2.15E-03 Unit 2 ADVs to Unit 1 CR Normal Intake 3.88E-03 2.43E-03 9.94E-04 8.19E-04 6.10E-04 Unit 2 ADVs to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 ADVs to Unit 1 CR Emergency Intake 2.87E-04 1.92E-04 7.48E-05 6.61E-05 5.07E-05 Unit 2 ADVs to CR Center 1.22E-02 8.16E-03 3.28E-03 2.78E-03 2.09E-03 Unit 1 MSLB to Unit 1 CR Normal Intake NIA NIA NIA NIA N/A Unit 1 MSLB to Unit 2 CR Normal Intake 4.23E-03 2.90E-03 1.13E-03 1.11 E-03 1.02E-03 Unit 1 MSLB to Unit 2 CR Emergency Intake 3.06E-04 1.54E-04 5.19E-05 5.32E-05 4.38E-05 Unit 1 MSLB to CR Center 1.24E-02 7.10E-03 2.24E-03 2.43E-03 2.07E-03 Unit 2 MSLB to Unit 1 CR Normal Intake 3.81E-03 2.40E-03 1.01E-03 8.09E-04 5.88E-04 Unit 2 MSLB to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 MSLB to Unit 1 CR Emergency Intake 2.75E-04 1.91E-04 7.45E-05 6.53E-05 4.86E-05 Unit 2 MSLB to Control Room Center 1.09E-02 7.35E-03 3.01 E-03 2.48E-03 1.86E-03 Unit 1 MSSVs to Unit 1 CR Emergency Intake 4.66E-04 2.92E-04 1.16E-04 1.04E-04 8.08E-05 Unit 2 MSSVs to Unit 2 CR Emergency Intake 4.90E-04 2.29E-04 8.24E-05 8.07E-05 6.49E-05 Unit 1 ADVs to Unit 1 CR Emergency Intake 4.66E-04 2.92E-04 1.16E-04 1.04E-04 8.07E-05 Unit 2 ADVs to Unit 2 CR Emergency Intake 4.90E-04 2.29E-04 8.24E-05 8.08E-05 6.48E-05 Unit 1 MSLB to Unit 1 CR Emergency Intake 4.35E-04 2.94E-04 1.15E-04 1.01 E-04 7.76E-05 5
File Name dcmssv30 Notes: File names N/A CR MSSVs AD Vs MSLB TABLE 3 -Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Radiological Releases from MSSVs/ADVs/MSLB Description of Release-Receptor Cases X/Q (sec/m3) 0 -2 hours 2 -8 hours 8 -24 hours 1 -4 days Unit 2 MSLB to Unit 2 CR Emergency Intake 4.76E-04 2.24E-04 8.14E-05 7.94E-05
=Input (.rsf), Output (.log) = Not applicable due to the source-receptor distance being much less than 10 meters, outside of the applicability of ARCON96.
= Control Room = Main Steam Safety Valves = Atmospheric Dump Valves = Main Steam Line Break 6 4-30 days 6.40E-05 File Name dctsc01 dctsc02 dctsc03 dctsc04 dctsc05 dctsc06 dctsc07 dctsc08 dctsc09 dctsc10 dctsc11 dctsc12 dctsc13 dctsc14 dctsc15 dctsc16 dctsc17 dctsc18 dctsc19 dctsc20 Notes: File names CB PV RWST PL TABLE 4 -Input I Output File Names Atmosoheric Disoersion Factors (X/Qs) atTSC Receptors for LOCA Radioloaical Releases Release-Receptor Case Description Unit 1 CB Edge to TSC Normal Intake Unit 1 CB Edge to TSC Center Unit 1 PV (ECCS Leakage) to TSC Normal Intake Unit 1 PV(ECCS Leakage) to TSC Center Unit 1 RWST Vent to TSC Normal Intake Unit 1 RWST Vent to TSC Center Unit 1 140'. Elevation Area Leakage to TSC Normal Intake Unit 1 140' Elevation Area Leakage to TSC Center Unit 1 PL to TSC Normal Intake Unit 1 PL to TSC Center Unit 2 CB Edge to TSC Normal Intake Unit 2 CB Edge to TSC Center Unit 2 PV (ECCS Leakage) to TSC Normal Intake Unit 2 PV (ECCS Leakage) to TSC Center Unit 2 RWST Vent to TSC Normal Intake Unit 2 RWST Vent to TSC Center Unit 2 140' Elevation Area Leakage to TSC Normal Intake Unit 2 140' Elevation Area Leakage to TSC Center Unit 2 PL to TSC Normal Intake Unit 2 PL to TSC Center =Input (.rsf), Output = Containment Building
=Plant Vent = Refueling Water Storage Tanks = Penetration Leakage 7 X/Q (seclm3) 0 -2 hours 2 8 hours 8 -24 hours 2.57E-04 1.18E-04 4.27E-05 2.90E-04 1.33E-04 4.98E-05 3.12E-04 1.77E-04 6.91E-05 3.54E-04 1.95E-04 7.71 E-05 2.72E-04 1.27E-04 4.80E'::05 2.94E-04 1.38E-04 5.40E-05 3.64E-04 1.74E-04 6.55E-05 4.27E-04 1.91E-04 7.45E-05 4.BOE-04 2.51 E-04 8.31 E-05 5.98E-04 3.03E-04 1.04E-04 5.48E-04 2.00E-04 8.52E-05 5.57E-04 2.01E-04 8.81E-05 5.52E-04 2.35E-04 1.06E-04 5.43E-04 2.16E-04 9.97E-05 3.63E-04 1.68E-04 6.47E-05 3.72E-04 1.68E-04 6.64E-05 5.47E-04 2.41E-04 9.36E-05 5.72E-04 2.43E-04 9.75E-05 1.80E-03 7.72E-04 3.07E-04 1.83E-03 7.49E-04 3.16E-04 Enclosure Attachment 2 PG&E Letter DCL-15-130 1 -4 days 4-30 days 4.24E-05 3.50E-05 4.83E-05 4.02E-05 6.29E-05 5.21 E-05 6.70E-05 5.67E-05 4.49E-05 3.71E-05 4.89E-05 3.97E-05 6.14E-05 5.00E-05 6.84E-05 5.62E-05 8.64E-05 6.95E-05 1.03E-04 8.46E-05 8.37E-05 6.84E-05 8.89E-05 6.92E-05 8.71 E-05 6.95E-05 8.11 E-05 6.58E-05 6.04E-05 4.91 E-05 6.17E-05 5.10E-05 8.83E-05 7.02E-05 9.12E-05 7.52E-05 2.87E-04 2.33E-04 2.92E-04 2.41E-04 Data Disc 1 Enclosure Attachment 3 PG&E Letter DCL-15-130 Security-Related Information
-Withhold Under 10 CFR 2.390 / Data Disc 2 (10 CFR 2.390) 1 Enclosure Attachment 4 PG&E Letter DCL-15-130 Security-Related Information
-Withhold Under 10 CFR 2.390 The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Pacific Gas and Electric Company Barry S. Allen Canyon Power Plant Vice President, Nuclear Services Mail Code 104/6 P. 0. Box 56 November 2, 2015 PG&E Letter DCL-15-130 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03. "Application of Alternative Source Term" Avila Beach, CA 93424 805. 545. 4888 Internal:
691.4888
 
==References:==
: 1. PG&E Letter DCL-15-069, License Amendment Request 15-03, "Application of Alternative Source Term," dated June 17, 2015 (ADAMS Accessi.on No. ML 15176A539)
: 2. PG&E Letter DCL-15-105, Supplement to License Amendment Request 15-03, "Application of Alternative Source Term," dated August 31, 2015 (ADAMS Accession No. ML 15243A363)
: 3. Email from NRC Project Manager Siva P. Lingam, "Diablo Canyon 1 and 2 -Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term per 1ffCFR 50.67 (TAC Nos. MF6399 and MF6400),"
dated October 1, 2015 Dear Commissioners and Staff: Pacific Gas and Electric (PG&E) Letter DCL-15-069, "License Amendment Request 15-03, 'Application of Alternative Source Term,"' dated June 17, 2015, and supplemented by PG&E Letter DCL-15-105, "Supplement to License Amendment Request 15-03, 'Application of Alternative Source Term,'" dated August 31, 2015, submitted License Amendment Request (LAR) 15-03, "Application of Alternative Source Term." On October 1, 2015, the NRC Radiation Protection and Consequence Branch (ARCB) requested (Reference
: 3) additional information required to complete the review of LAR 15-03. PG&E's responses to the ARCB staff's questions are provided in the Enclosure.
A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance CaUaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
The Enclosure, Attachments 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Document Control Desk November 2, 2015 Page2 PG&E Letter DCL-15-130 Attachment 1 provides Input Data for the EN-113 Dispersion Model, the description of input contained in the EN-113 User's Manual, the input files for the Unit 1 Exclusion Area Boundary (EAB), Unit 2 EAB, and the Units 1 and 2 Low Population Zone dispersion model runs. Attachment 2 summarizes the description of the Release-Receptor cases and the associated input/output file names. Attachment 3 provides various data files in response to the NRC requests for information.
Attachment 4 provides various plant drawings.
Because the information contained in the drawings may be useful to adversaries, PG&E requests that Attachment 4 be withheld from public disclosure under 1 O CFR 2.390. This information does not affect the results of the technical evaluation or the no significant hazards consideration determination previously transmitted in PG&E Letters DCL-15-069 and DCL-15-105.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter. This letter includes no revisions to existing regulatory commitments.
If you have any questions, or require additional information, please contact Mr. Hossein Hamzehee at (805) 545-4720.
I state under penalty of perjury that the foregoing is true and correct.
Executed on November 2, 2015. Sincerely,
!37 . s: AtL---Barry S. Allen Vice President, Nuclear Services A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance Callaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
The Enclosure, Attachments 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 Document Control Desk November 2, 2015 Page3 mjrm/4557150307101 Enclosure*
cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Administrator PG&E Letter DCL-15-130 Thomas R. Hipschman, NRC Senior Resident Inspector Siva P. Lingam, NRR Project Manager Gonzalo L. Perez, Branch Chief, California Dept of Public Health A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance Callaway
* Diablo Canyon
* Palo Verde*
* Wolf Creek The Enclosure, Attachment 4 Contains Security-Related Information
-Withhold Under 10 CFR 2.390 When separated from Attachment 4, this document is decontrolled.
ENCLOSURE ARCB Response 1 Enclosure PG&E Letter DCL-15-130 Enclosure PG&E Letter DCL-15-130 PG&E Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, "Application of Alternative Source Term" NRC Request for Additional Information General 1. The licensee used the NRG-accepted ARCON96 dispersion model (based on NUREGICR-6331, Rev. 1 as implemented by Regulatory Guide (RG) 1.194) to estimate onsite impacts to the Unit 1/Unit 2 Control Rooms (CRs) as well as the . Technical Support Center (TSC). The licensee included the TSC pursuant to Supplement 1 to NUREG-0737 (Clarification of TM/ Action Plan Requirements
-dated January 1983) and RG 1. 183. There are 58 source-receptor pairs evaluated for each unit.
* PG&E Response This request for additional information (RAI) is a statement of fact. No response is necessary.
NRC RA/ General 2. The licensee used a (presumably) proprietary dispersion model referred to as EN-113 (Atmospheric Dispersion Factors),
which is said to implement provisions in* RG 1. 145 for accident releases and from RG 1. 111 for routine releases, to estimate short-term relative concentrations (X/Qs) and long-term (annual average)
X/Qs at the Exclusion Area Boundary (EAB) and the outer boundary of the Low Population Zone (LPZ) similar to the NRC-accepted PAVAN andXOQDOQ dispersion models, respectively.
Unlike PAVAN andXOQDOQ,
: however, the EN-113 code runs on hourly meteorological data and has, among other things, the ability to directly calculate XIQ values for the intermediate, short-term averaging intervals (i.e., 2-8 hours, 8-24 hours, 1-4 days, and 4-30 days). Because of conflicting discussions within the application package.
it is not clear at this stage of the review how these provisions were implemented for this LAR. The licensee also cites other facilities where this code has been used and approved by the NRG staff. The licensee will need to provide justification for the use of the EN-113 code at the DCPP. PG&E Response The following clarifies the discussion in Section 5.1 of Attachment 4 of License Amendment Request (LAR) 15-03:
* Regulatory Guide (RG) 1.145 provides the methodology to establish the 0-2 hour (hr) X/Q, as well as the intermediate, short-term averaging time period X/Qs, (i.e., 2-8 hrs, 8-24 hrs, 1-4 days, 4-30 days) -RG 1.145 calls out use of RG 1.111 methodology (which focusses on developing "long term, annual average" X/Qs). 2 Enclosure PG&E Letter DCL-15-130
* Short term (accident) ground level release X/Qs were developed for DCPP using RG 1.145, Revision 1 methodology, using CB&I computer code EN-113 utilizing 2007 through 2011 hourly average meteorological data.
* Intermediate averaging time X/Qs were developed for DCPP using RG 1.111, Revision 1 methodology, using CB&I computer code EN-113, utilizing logarithmic interpolation between the 0-2-hr and the annual average X/Q values. The "sliding average" methodology was not used for DCPP (see Section 5.1 of LAR 15-03), although the capability was discussed in Section 3.0, Attachment 4 of LAR 15-03.
* EN-113 calculates all of the X/Qs (0-2 hr, 2-8 hrs, 8-24 hrs, 1-4 days, 4-30 days) using hourly average meteorological data.
* EN-113 follows RG 1.145 methodology which intrinsically means that the intermediate, short-term averaging time period X/Qs are* developed using RG 1.111 methodology
* EN-113 has the capability to calculate the intermediate, short-term averaging time period X/Qs using a) sliding average methodology OR b) logarithmic interpolation between the 0-2 hr and the annual average X/Q values.
* For DCPP, the EN-113 logarithmic interpolation methodology option was chosen to establish the intermediate, short-term averaging time period X/Qs
* PG&E is asking for NRC approval for use of EN-113 for development of accident X/Qs. The LAR does not address normal operation routine releases.
As justification for the usage of EN-113, Section 5.1 of Attachment 4 of LAR 15-03 provides
'a summary of how RG 1.145 methodology was implemented by EN-113 including the applicable equations used and the key assumptions made to ensure conservative results.
Also included is a discussion of the selection process of the appropriate X/Q values for the 0-2 hour averaging time and intermediate period averaging times. As noted in Section 3.0 of Attachment 4 of LAR 15-03, EN-113 has been used in prior alternative source term (AST) licensing applications (e.g., Fort Calhoun Power Station [ML013030027]),
and its results accepted by the NRC. As depicted in Attachment 8 of LAR 15'."03, the proposed update of Section 2.3.2 oft.he Updated Final Safety Analysis
'Report (UFSAR) reflects the use of the EN-113 computer code to provide short-term (i.e., accident) dispersion estimates.
It includes the same level of detail as is provided in Attachment 4 of LAR 15-03. NRC RA/ General 3. The licensee has updated the meteorological data set used to make its related XIQ estimates (i.e., a more recent 5-year period of record (POR) consisting of data for calendar years 2007 through 2011 ). Data and summaries through Rev. 20 (November 2011) of the Updated Final Safety Analysis Report (UFSAR) -latest available on NRR's V:\ drive -are based on various 2-or 3-year PORs, which
* appear to be associated with the initial submittal for this facility.
The purpose 3 Enclosure PG&E Letter DCL-15-130 of some of those summaries appears to be related to the complicated meteorological conditions that characterize this coastal site, which includes complex terrain.
It is riot clear at this stage of the review how (or iO these previous studies.
and the issues previously considered to be important as addressed by those studies.
relate to the dispersion modeling analyses performed for this LAR. PG&E Response The referenced meteorological studies in the UFSAR with respect to X/Qs were provided by PG&E within the original license application since it pre-dated the availability of the NRC guidance documents.
The previous meteorological studies conducted at DCPP in the 1970s are not related to the X/Q dispersion modeling/analyses in support of LAR 15-03. The X/Q analyses supporting LAR 15-03 followed the current NRC guidance available in RG 1.145, Revision 1, and uses the updated meteorological data set (i.e., a more recent 5-year period of record (POR) consisting of data for calendar years 2007 through 2011 ). NRC RA/ Meteorological (Met} Data -Offsite Impacts 1. Need Met data for calendar years 2007 thru 2011 a. Sequential hourly file(s) formatted in accordance with Appendix A to Revision 1 of RG 1.23 or equivalent with proper explanation;
: b. Explanation of any data formatting differences between RG 1.23 (Appendix A) and as input to EN-113 dispersion model; \ c. Whether Met data is input to the EN-113 dispersion model as a concatenated 5-year data set or run as individual years and if the latter how the modeling results are interpreted.
PG&E Response
: a. The 2007 through 2011 sequential hourly file(s),
formatted in accordance with RG 1.23, Revision 1, Appendix A are provided in the following five Excel files in the enclosed Attachment 3 data disc:
* NRC07
* NRC08
* NRC09
* NRC10
* NRC11 b. The RG 1.23, Revision 1, Appendix A format is different than that used in EN-113. 4 ----------------
Enclosure PG&E Letter DCL-15-130 The RG 1.23, Revision 1, Appendix A format is focused on an h_ourly presentation, i.e., it provides all parameter values on an hourly basis on one line. Thus each line presents the wind speeds, wind directions, temperatures, etc. for the upper level, intermediate, and lower level tower measurements followed by other parameters such as temperature difference and solar radiation for that
* hour. _This is repeated for each hour in the day and each day of the year. The EN-113 format is focused on a daily presentation, i.e., 24 hourly values for each parameter of interest is presented on a line. Each parameter has a code associated with it such as "111" for 10-meter wind speed and "112" for 10-meter Wind_ direction.
Thus, hourly values for each parameter are provided on a daily basis and repeated for each day of the year. Both formats record the days on a Julian day basis (i.e., Days 1 -365). c. The 2007 through 2011 onsite meteorological data are utilized by the EN-113 dispersion model as concatenated 5-year data set. NRC RA/ Meteorological (Met} Data -Offsite Impacts 2. Joint frequency distributions (JFDs) of wind speed and wind direction by atmospheric stability class for indicated 5-year POR or, if EN-113 was run for individual years, JFDs for each year and for the composite 5-year POR; PG&E Response As noted in PG&E response to NRC Radiation Protection and Consequence Branch . (ARCB) RAl-2 (General) above, PG&E used hourly average meteorological data to develop the offsite atmospheric dispersion factors.
JFDs of wind speed and wind direction by atmospheric stability class for the indicated 5-year POR have not been submitted to NRC since JFDs were not used to support LAR 15-03. NRC RA/ Meteorological (Met} Data -Offsite Impacts . 3. Bases for determining hourly stability class and if different methods were used 1 ' throughout the data set(s) (e.g., depending on wind speed as suggested by UFSAR Table 2.3-41) an accounting of such hours when implemented and an explanation for having done so; PG&E Response The hourly stability classes were based on the vertical temperature difference methodology (i.e., delta T) identified in RG 1.23, Revision
: 1. Temperatures were measured at an upper level of 76 meters and a lower level of 10 meters on the tower. 5 Enclosure PG&E Letter DCL-15-130 The delta T method was used to type stability class throughout the entire concatenated 5-year data base. NRC RA., Meteorological (Met) Data -Offsite Impacts 4. Summary of data recoveries by year and for the 5-year POR for individual Met parameters and as composite recovery of concurrent wind speed, wind direction, and atmospheric stability class for the same periods; PG&E Response As depicted in Attachment 8 of LAR 15-03, the proposed update of Section 2.3.2 of the UFSAR reflects the use of the 2007 through 2011 onsite meteorological data for the calculation of accident diffusion estimates.
The summary of data recoveries for this period, in percent, is provided in the table below: Meteorological Parameter 2007 2008 2009 2010 2011 2007-2011 1 O m wind direction 99.2 96.9 91.0 91.3 95.2 94.7 1 O m wind speed 99.2 96.9 91.0 91.3 93.8 94.4 Stability Class 99.2 '96.9 91.0 91.3 95.2 94.7 76 m wind direction 99.1 96.8 90.8 90.9 95.2 94.6 76 m wind speed 99.1 96.8 90.8 91.3 92.4 94.1 Composite 99.1 96.8 90.8 90.9 92.4 94.0 The data recovery for each year of the 2007 through 2011 period and the entire 2007 to 2011 period meet or exceed the "greater than 90 percent data recovery" guidance identified in RG 1.23, Revision 1 . . NRC RA/ Meteorological (Met) Data -Offsite Impacts 5. (Part 1) Whether any data substitution was implemented to supplement data 'recovery over the indicated 5-year POR and, if so, an accounting of hours and parameters substituted, 6
PG&E Response Enclosure PG&E Letter DCL-15-130 The following table summarizes the data substitutions for the DCPP Primary Tower for the period 2007 through 2011. Substitution Summary 2007 2008 2009 2010 2011 Totals Day/Time Day/Time Day/Time Day/Time Day/Time Substituted Hrs Substituted Hrs Substituted Hrs Substituted Hrs Substituted Hrs 100/1230-98/1545-29/1945-123/1100-5/1015-113/1245 312 111/1700 313 30/0030 5 133/1345 242 11/1345 148 276/1245-143/1230-121/0000-305/0000-83/1400-299/1030 550 153/1530 243 135/1645 353 313/0200 194 90/1115 166 154/1115-314/1330-95/1145-157-0145 63 315/0930 20 106/1315 266 157/1445-145/1415-158/2230 32 145/1800 4 159/1230-216/1145-228/0700 1651 221/0815 117 229/1330-262/1000-229/2330 10 282/0030 471 230/0730-287/0945-All Parameters Substituted 239/0700 216 291/1345 100 Total 862 Total 2528 Total 358 Total 456 Total 1272 Total Hrs Substituted 5476 J Hrs in year 8760 Hrs in year 8784 Hrs in year 8760 Hrs in year 8760 Hrs in year 8760 Total Hrs 5 year period 43824 Percent Percent Percent Percent Percent Total Percent Substituted 9.84%_ Substituted 28.78% Substituted 4.09% Substituted 5.21% Substituted 14.52% Substituted 12.50% 7 NRC RA/ Meteorological (Met) Data -Offsite Impacts Enclosure PG&E Letter DCL-15-130
: 5. (Part 2) an explanation of why any substitutions were necessary, and the source of such data; and PG&E Response The DCPP Primary Tower is taken out of service for calibration approximately every six months per Equipment Control Guideline (ECG) surveillance requirement (SR) 40.1.2. Each calibration period lasts from two to three weeks in duration.
These calibration periods represent the majority of the time that data substitution was necessary.
Additionally, in 2008 the DCPP Primary Tower was taken out of service for replacement due to damage inflicted by a boom truck. During 2011, in addition to calibrations, some instruments on the Primary Met Tower needed replaced, resulting in increased unavailability.
Primary Met Tower Backup Met Tower (parameter substituted) 10M Temperature 10M Temperature 76-1 OM Delta T 60-1 OM Delta T 46-10M Delta T None 1 OM Wind Speed 1 OM Wind Speed 76M Wind Speed 60M Wind Speed 1 OM Wind Dfrection 1 OM Wind Direction 76M Wind Direction 60M Wind Direction Data substitution techniques were employed using back-up tower data when primary tower data were missing during calibrations and unscheduled meteorological monitoring outages.
Stability class from the back-up tower was calculated from temperature difference measurements at the 60-meter and 10-meter levels. NRC RA/ Meteorological (Met} Data -Offsite Impacts 6. Comparisons between the indicated 5-year POR and the PORs reflected in the current (or previous)
UFSAR to establish the long-term representativeness of the 2007 through 2011 POR from an atmospheric dispersion standpoint.
PG&E Response Regulatory Position C.3.1 of RG 1.194 states that "the size of the data set used in the X/Q assessments should be sufficiently large such that it is representative of long-term meteorological trends at the site. The NRC staff considers 5 years of hourly observations to be representative of long-term trends at most sites." Therefore, the 8 Enclosure PG&E Letter DCL-15-130 2007 through 2011 onsite meteorological data base is sufficient in length to establish long-term representativeness from an atmospheric dispersion standpoint.
NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 1. Need Met data for calendar years 2007 thru 2011 a. Sequential hourly file(s) formatted in accordance with NUREGICR-6331 (PNNL-10521) (Rev. 1). b. Note that the cover sheet for Appendix A to Attachment 4 of the LAR submittal package (see Part 2 of 8. ML 15176A528) states that "ftlhe on-site meteorological data input to ARCON96 (January 1, 2007 through December
: 31. 2011 ), in the ARCON96 input data format. is embedded below)",
followed by a list of the five individual calendar years. The phrase "is embedded below" suggests that this Met data may have already been provided with the LAR submittal package.
If already in hand, copies of those files should be provided to my attention at NROIDSEAIRHMB1/RMOT.
and a separate request for that data is not necessary.
PG&E Response
: a. The 2007 through 2011 sequential hourly file(s),
formatted in essentially the same format (with some differences in spacing) as NUREG/CR-6331 Revision 1, are provided in the following five Excel files in the enclosed Attachment 3 data disc:
* DCPP _Primary_2007 (DIT 50503441-02-00).xls
* DCPP _Primary_2008 (DIT 50503441-02-00).xls
* DCPP _Primary_2009 (DIT 50503441-02-00).xls
* DCPP _Primary_2010 (DIT 50503441-02-00).xls
* DCPP _Primary_2011 (DIT 50503441-02-00).xls I Note: Unavailable data for the given hour period is indicated by a "999." b. It appears that due to the scanning approach used to package LAR 15-03 prior to submittal to the NRC, the meteorological data in ARCON96 format that were embedded in Appendix A of Attachment 4, were inadvertently omitted.
NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 2. If different from the sequential hourly Met data sets input to the EN-113 dispersion model, bases for determining hourly stability class and if different methods were 9 Enclosure PG&E Letter DCL-15-130 used throughout the data set(s) (e.g., depending on wind speed as suggested by UFSAR Table 2.3-41) an accounting of such hours when implemented and an explanation for having done so; PG&E Response The sequential hourly meteorological data input into ARCON96 to determine the onsite atmospheric dispersion factors are the same as the sequential hourly meteorological data input into the EN-113 dispersion model; the only difference being the format of the data that is input into the respective computer codes. NRC RA/ Met Data -Onsite Impacts (Control Room and Technical Support Center) 3. Atmospheric stability class appears to have been based, at least in part, on the temperature difference between the 76-and 10-m measurement levels on the primary Met tower. Except for the Unit 1 and Unit 2 Plant Vent release scenarios (Release Height= 74.1 m), all other source release heights for estimating CR and TSC impacts are no greater than 32.0 m (and most are less than that height).
Explain the basis for not having defined atmospheric stability based on the temperature difference between the 46-and 10-m measurement levels on the primary Met tower for those release scenarios with source-receptor pairs within that 46-to 10-m surface boundary layer. This comment also applies to the Met data input to the EN-113 dispersion modeling analyses to estimate impacts at the EAB and LPZ. *
* PG&E Response The DCPP licensing basis for stability class has always been based on the temperature difference (delta-T) of the 10-meter and 76-meter measurements.
The 91 JFD tables currently presented in UFSAR Section 2.3 provide stability classes from delta-T data based on the 76-meter to 10-meter difference, and there is no reference made to the 46 meter to 10 meter delta-T.
Stability class based on the 46-meter to 10-meter delta-T values has never been a part of the DCPP licensing basis. At the time of the original license when Safety Guide 23 was in force, PG&E as well as NRC, may have likely focused on the parenthetical statement "plant vent height" when locating meteorological instrumentation to determine stability
'classes for atmospheric dispersion factors.
At that time, Regulatory Position C.(2) of Safety Guide 23 stated that " ... the upper set should sense wind speed and direction and temperature at the height of release of radioactive material (plant vent height) but should be positioned not less than 30 meters above the lower sensor height."
In accordance with the current plant licensing basis and design, the primary meteorological tower is instrumented to provide temperature difference between the 10 Enclosure PG&E Letter DCL-15-130 76-meter and 10-meter elevations and the 46-meter and 10-meter elevations, and the backup meteorological tower is instrumented to provide temperature difference between the 60-meter and 10-meter elevations.
Additionally, Section 5.6.1 of DOE-HDBK-1216-2015, "DOE Handbook Environmental Radiological Effluent Monitoring and Environmental Surveillance,"
states that "If a vertical temperature difference (i.e., /1T//1z) is used along with solar radiation to determine atmospheric stability, the temperature difference should be determined over an interval of sufficient thickness to avoid undue influence of the ground (typically at least 50 meters).
The temperature monitoring levels should be selected and spaced such that the profile is representative and characterizes the magnitude of atmospheric turbulence at the potential release height(s)."
Thus, the 46-meter to 10-meter levels is deemed insufficiently distant from each other to provide a vertical temperature difference that would support a valid stability class methodology.
Accordingly, it is PG&E's position that the delta-T used to determine stability class at DCPP to all short-term (accident) atmospheric dispersion factors is in accordance with its current licensing basis, as well as current regulatory
: guidance, with respect to recommended locations for temperature instrumentation to determine stability class. ' NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 1. Need input files for EN-113 model runs along with a key explaining file format and identification of model input parameters so that equivalent input data files can be developed for NRG staff confirmatory modeling runs using NRG-accepted PA VAN dispersion model. PG&E Response Attachment 1 provides the description of input contained in the EN-113 User's Manual and the input files for the Unit 1 EAB, Unit 2 EAB and the Units 1 and 2 LPZ dispersion model runs. NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 2. Since this appears to be the first use of the EN-113 dispersion model at the DGPP and the licensee indicates that the code's provisions implement certain guidance from RG 1. 145 and RG 1. 111, provide documentation that demonstrates the equivalency of EN-113 results to the output from the NRG-accepted PAVAN and XOQDOQ dispersion models, which implement the guidance in RGs 1. 145 and 1.111, respectively, with the understanding that EN-113 operates on sequential
, 11 ------
Enclosure Letter DCL-15-130 hourly Met data whereas the PA VAN and XOQDOQ dispersion models operate on JFDs of wind speed and wind direction by atmospheric stability class. PG&E Response As noted in PG&E response to RAI 2 in the General section, Section 5.1 of Attachment 4 of LAR 15-03 which provide the technical assessment supporting the application, and Attachment 8 of LAR 15-03 which provides the proposed update of Section 2.3.2 of the U FSAR, both reflect the use of the EN-113 computer code to provide short-term (accident) dispersion estimates.
The referenced sections of LAR 15-03 describe how EN-113 follows the methodology of RG 1.145, Revision 1, induding the equations used and the selection of the appropriate XIQ values for the 0-2 hour averaging time and intermediate averaging times. EN-113
* uses the RG 1.111 Revision 1 methodology guidance to calculate the annual average XIQ used for the intermediate averaging times calculation.
Thus, the methodology used by PG&E to determine the short-term (accident) dispersion estimates are equivalent to that used by NRG-accepted PAVAN and XOQDOQ dispersion models, which also implement the guidance in RGs 1.145 and 1.111, respectiyely.
* NRC RA/ EN-113 (Atmospheric Dispersion Factors)
Model Input Information
: 3. Confirm whether the XIQ values for the 0-to 2-hour averaging time and the other intermediate averaging intervals (i.e., 2-8 hours, 8-24 hours, 1-4 days, and 4-30 days) and annual average are determined as sliding averages or interpolated between the 0-to 2-hour and annual average X!Qs. The text in different parts of the application package appears to be inconsistent such that it is not clear which *approach has been used and Which discussions may only be intended to describe the capabilities of the EN-113 dispersion model. PG&E Response The 0-2 hr X/Q calculation followed the methodology in RG 1.145, Revision 1, and the annual average X/Q calcylation followed the methodology in RG 1.111, Revision
: 1. The XIQ values for the 0-2-hr averaging time and the other intermediate averaging intervals (i.e., 2-8 hrs, 8-24 hrs, 1-4 days, and 4-30 days) were determined by logarithmic*
interpolation between the 0-2-hr and annual average X/Qs. Only hourly average meteorological data is used as input in EN-113. For additional detail see* PG&E response to RAI 2 in the 'General' section.
12 ----------
NRC RAJ ARCON96 Dispersion Model Input I Output Files 1. Need input and output files for all ARCON96 model runs. PG&E Response Enclosure PG&E Letter DCL-15-130 The ARCON96 input/output files are provided in in the enclosed Attachment 3 data disc. Attachment 2 summarizes the description of the Release-Receptor cases and the associated input/output file names. NRC*RAI ARCON96 Dispersion Model Input I Output Files 2. In addition to Figure A-1 in Appendix A to Attachment 4 of the LAR submittal
: package, need legible drawings of all structures used to determine building related parameters as input to the ARCON96 model runs, as well as drawings that illustrate release and receptor heights.
This comment also applies to the EN-113 dispersion modeling analvses if building wake has been accounted for as part of those analyses.
PG&E Response The following drawings are provided in in the enclosed Attachment 4 data disc: Drawinq No Sheet Rev. Title Filename 57727<2> Equipment Location; Plan at Elevation
: 1. 41. 140'-0";
Aux., Containment and Fuel DWG 57727-1 (r41}.pdf Handlinq Bldqs. 57729<2> 1 12 Equipment Location; Section A-A Auxiliary DWG 57728-1 (r12}.pdf Building 57732<1>'2> Mechanical; Equipment Location; Section 1 17 'E-E' -Auxiliary, Turbine & Fuel Handling DWG 57732-1 (r17}.pdf Buildings l 59353(2) 1 10 Mechanical; Air Conditioning Area "K" DWG 59353-1 (r10}.pdf Elev. 154'-6" Auxiliary Building 101942'1><2> [Local Instrument Panel Index; Coordinate-3 35 Column Line Cross Reference sheet] DWG 101942-3 (r35}.pdf (note that the drawinq has no title block) 438040\"'I 1 43 Civil; Finished Grading Plan; Plant Area DWG 438040-1 (r43).pdf 438042\<!)
1 27 Civil; Finish Gradinq Plan; Plant Area DWG 438042-1 (r27).pdf 443115<2> 1 10 Architectural; Ladder Details; Exhaust Vent DWG 443115-1 (r10}.pdf Containment Structure 471124\<!)
1 11 Civil; Plot Plan DWG471124-1 (r11).pdf 500059<2> 1 15 Piping & Mechanical; Area G, GW and GE; DWG 500059-1 (r15}.pdf Plan at Elevation 140'-0" 501551<2> 1 9 Piping & Mechanical; Areas GE & GW; DWG 501551-1 (r9}.pdf Plan Above El. 140'-0" 508911<2> 1 9 Mechanical; Outdoor Storage Tanks; DWG 508917-1 (r9}.pdf Pipinq Modification; Sections 13 Drawing No Sheet Rev. 511155<2> 1 16 512905<2> 1 22 663071<2> 129 6 lJFSAR Figure 2.1-2 11 UFSAR Figure 2.1-15 22 Title Mechanical; Plans & Sections; Air Conditioning Control Room Pressurization Fan Arrangements; Area "A" Elevation 140'-0" Mechanical; Plans, Sections, and Schedule; Onsite Technical Support Center and Laboratory Refueling Water Storage Tank; Elevation and Orientation Details Site Plan and Gaseous/Liquid Effluent Release Points Low Population Zone (Historical)
Enclosure PG&E Letter DCL-15-130 Filename DWG 511155-1 (r16).pdf DWG 512905-1 (r22).pdf DWG 663071-129 (r6).pdf UFSAR Figure 2.1-2.pdf UFSAR Figure 2.1-15.pdf (1): Drawings 101942 and 57732 were used to develop cross-sectional building areas to account for building wake effect in ARCON96 and EN-113. (2): Note: These drawings are considered Security Sensitive and should be withheld under 10 CFR 2.390. 14 Input Data for EN-113 Dispersion Model EN-113 Input Description 1 Enclosure Attachment 1 PG&E Letter DCL-15-130 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGR.t\H OOCUt.tENTAUON s*roNE & WBBSTBR SECTION:
V OPR&\TING INSTRUCTIONS REVISED DATE: I). Selection of Type of Calculation and Output Format READl !nput Data Card l (UA4,3A4}
CLIENT -Client's name (left-justified).
JOBNO -Job Number (left-justified).
Card 2 (11A4,SA4)
SITE -Site Name (left-justifiud).
-Ca 1.culal:ion nu111ber.
Gat"d 3 (4I5,F5.0,I5)
ISTART -Start date (on) (year ancl Julian date) if othet' than start of data. ISTOP -Stop date (after) (year and Julian date) if other than end of NDYSDT -Numbet' of days input data. HETSTB -Method of determining stability d.ass: 1 -Radiation index (WBAN tape)
(llM) (3A4) 2 -Split sigma {3 and 4 or 5 below) 3 -Delta temperatur0 (must have DllT) 4 -Wind direet!on t:'ange 5 -Wind direc:tlon standard deviation.
DRT -Height: difference for delta t:cmpera t:m:e: If temperature is in deg F then DHT must be ln feet U:
is in <leg C t:ben DIIT must bo in l'.leters.
IREDIS -Rcdist-e:l'oution of CALMS switch: 0 -:Preyfous good wind di tection 1 -Cal111 speed -1. 5 mph speed class sector frequency distri button 2 -Calm speed -t. 5 mps (3 *. 3557 mph) speed class sector frequency distribution 1118.ke Device tl available.
Card 4 (9(2X,A3),2I5)
ID -Met data three.-character ID: ID(l) -Wind speed ID(2) -Wind direction.
!D(3) -Temperature
!0(4) -Wind direction range ID(S) -Wlnd dir:ect:ion standard deviation tD(6) -Delta temperature t0(7) -Wind speed (upper levd) !0(8) -Wind direction (upper level) ID(9) -Temperature (upper 2
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM OOCUMSN!Ar!ON sroNE & wessrER EN-113 SECrtoN:
v OPERArtNG INSrRUCUONS REV!SEI>
DArE: PAGE 5 ISPUNr -Wind speed units indicator:
tf input data is ill mph, ISPUNI' is 0 If input: data ls in
!SPUNr is l If input data is i.n rnps, ISPUNr is 2. IfPtnir -temperature units indicator:
If input data is .in F, IrPUNr is 0 If input data is in Deg c, I!PUNr is 1. PARMUL -Parameter Mulcipliet:
PARMUL(l)
-Wind speed Uefault t.O ?ARMUL(2)
-Wind direction Default 1.0* PARMUI.(3)
-!elllperatute Default 1.0 PARMUL( 4) -Wind direction range Oefault 1.0 PARMUL(S)
-Wind direction standard deviation Normally 0.1 PARMUL(6)
-Delta tempeJ;ature Default 1.0 PARi.'1.UL(7)
-Wind speed (upper level) Default 1.0 PARMUI.(8)
-Wind direction (upper level) 'Dafault t.O PARMUJ.{9)
-!emperature (upper level) Default 1.0. rPGRAD -Specified tempei:atur:e gradients (6) for specific toimr height differentials to be used to determine stability classes (hourly data LE apecified.gt'ad:tent seta stability class). Specified gradient should include parameter multiplier.
Desired gradient of -3.0 and parameter multiplier of 0.1. should. give rPGRAD of -30. tf all are set to ioro default classes of -1,9, -t.7, -1.5, -0.), l.5 and 4.0 deg C/100 will be used. REJ.D2 Int>ut Data Ca.rd 5 lREi'lP RE LS ID Cat'd 6 !SrIY'P WPLUB S!KHr srKDIA (15, 11A4) Release {X/Q) (D/Q) -Release point and calculation type switch: (1) gl:'ound (2) efo*mted (3) ground (4) Qlavated
?oi.nt ID ( lef t-jus tHied) (IS,FtO.O,SFS.0,2FlO.O,Il 1I4IS,2F5.0)
-Station t:ype l -nuclear, 2 -fossil (llA4) fossil -No more than t:i;.-o do1mwJ.nd distances when calculating hourly and .11.nnual averages together.
ran downwind distances calculating annual averages only. -Stack gaa flow. -
holght. -Scack exit: diame.ter.
(lb/hr) (f C:) (ft:)
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRA.o\I' DOCUC18Nl'ArION srom:: & W&BSrBR 1m-113 SECUON: ,, Ol'ERArING rnsra.ucrIONS REVISED DAI'E: GAS VE!. rs HLID WFUE:L H.VAT .. UE !S!RLN !CALM ucu ucs Card 7 ISECVG MESHr IAECSG IBWEFP PAGE 6 -Stack exit velocity
-Stack exit temperature
(&deg;F). -
mixing L!O height (Geters).
-Fuel f1ow (Lucas and Moore Plume Rise) (lb/hr).
-Heat value of fuel (Lucas and Moore) (Btu/hr).
-Calculilta hourly averages from straight line Oil log-log paper: (0) -no ealculation
( positive number) -Limiting index of l.)0 loop, . Wtll calcul.ate averages with straight lines scarting at. land going to the limit (!SrRLN),
Must make the 1-hour average calculation and the annual calculation at the same t1111e. If the 1-hour, 50 percent x/Q 11alues is t:o be used, 6et the left-inost digit to 1.
the 50 percent equal risk value is used. (lEQSO) -Switch to allow wind speed or height corrected lrlnd speed to be reset to calm speed if wind apeed falls below calm speed: Default (0) -W/S reset: (1) -W/S not: reset. -Unstable and neutral W/S height correction factor (Stabilities A -D) Default UCU Q 1.0. -Stable W/S height correction factor (Stabilities E -G) Default UCS 1.0. (7IS,2(3X,7tl),3IS,2F5,0)
-Sector average:
0 -with 1 -
cotrection.
-Height of wind speed meaaurement (ft).
= O, Speed modification with height not made (ASHE). -Dispersion coefficient:
0 -AEC (POLYN) Gtfford1s l -S&W {SIGY, SIGZ) rurner' g 2 -AEC (POL'!ND)
Dasert. -Building effect (short-term):
0 -Not used (if not o. t:'ead Cards 9 and 10) l -Meandering plume GJethod.
If stability E, F or G and wind speed LE 2.5 mph, 2*Pt*S!GY*SIGZ is increased four times. 2 -AEC method (Sagendorf) yjQ = l/(U*(PI*S!GY*SIGZ+c*A))
3 -Sigma Squared method :(/Q = l/(PI*U*SlGY*S!GZ)
SIGY (SIGY**2+C*A/PI)**0.5 S!GZ = (SIGZ**2+c*A/?.I)**0.5 4
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM OOCUMENrArION sroNE & 1masr1m BN-113 sncrroN:
v oPERAl'ING REVISED DAl'E: IrOPO . lXERIN IS!GMA ISrABY !SrABZ NHR624 PAGE 7 4 -A.bbey Plume Meander method, CPRlM must be specified.
If CPRIM = O.O, there is no building wake effect 5 -Rancho Seco ( '77) building wake l.'llennder.
Number of directions
"'11th inputted topographic dat;a . (l-16): 0 -
topography Terrain adjustment factor selection switch (annual).
If input data cards are needed, they will be read in by Subroucine
!8RAIN after all other READ2 Cards. (0) -No adjustment
( l) Plain '(2) -Desert ( 3) -Plain (4) -Desert (S) -Valley (input data (6) -Coast (7) -
valley (point) (point) (curve) (curve) required see Card 30 below) (B) -Raad in data for (5, 6, and 7) (9) -Read only sil:e-specific ground release factors (10) -Re*ld only site-specific eleN<ltcd release factors (11) -Read both site-specific ground and elevated release factors.
(Input of this dat:a is i.n the same format as topographic
.input, 16 directions and up . to. 12 doi;,-nwind dis ta.nee a. Reading sequence f.3 the same as Cards 30 -32; ground first and elevated second.)
(12) -Use site specific ground-level release recirculation factors in calculation.
(13) -Use site elevated release recirculation f'actol:'s
.1.n calcul.ation.
-*sigma printout print control:
0 -no printout 1 -printout.
-Horizontal di.spersion coefficient:
.selo?ctio11 array. rhe seven locations of this array represent stability claesoe A -G. By inserting a nurnber l -7 in a 1ocatton the sigma curve ( l
* 7) will be used tor that particular stability clasi;. If the array is left blaok, the normal sigma cur'1os f.i"ill be used for ehe stability classes.
Set to (1). Vertical ciispersio11 coefficient selection
:a.rray.
Other .. cooments are the surne as ISfABY above. Number of hours to be slid for 72-hour sliding average, NumbQr of houra to be slid for 624-hour sliding average.
NRR72 and NRR624 default to 1 if not values used must di11ide 72 or 624 without remainder.
5 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENrArION sroNE & WEBSrER EN-113 sgcn:ON:
v OPERA.UNG REVISED DArE: PAGE 8 L!HXQR x/Q l!lnit write switch: 0 -no pt:intout t -printout.
(Supply XQLIM values Card 8A.) PRGHRS -Number of hours intermittent (purga) release.
(must not be set to 0.0)
-Wind speed below whlch recirculation fraction
-will be applied Nora:
and R?CWSP used only for intermittent release calculation which mui;t he.ve special GNCHIQ and ourCHQ subroutines.
Card 8 JHRARY (7IS,5F5.0,15X,15) rime period control:
1 a 16 72 24 (6I5) 624 1000 1000 0 Fossil 1 3 8 Blank or zero -no calculation 1000 -Annual Average (one level of winds), 2000 -Annual Average (use upper level winds if to elevated shift ts to be made) JHRARY(l)
If used, can only be for JHRARY(2-5)
Nuclear JHRAR'l(6)
Nuclear JHRARY(2-4)
Fossil JHRARY(S)
Fossil NOrESt l hout. 1001 or*2001 ground to elevated shift (Regulat-0ry Guide l.111 pt'1Jporations) using l or 2 levels of wlnds. 3001 or 400t same as above plus aeronynamic downwash.
If used can range tt'orn 2 to 624 hrs If used can only be 1000, 1001, 2000 or 2001 If used can range from 2 to 624 hrs If used can only be 1000 or 2000 l. Any a*Terage of S hours or less ...,ill uae term equat:!ons.
: 2. ro obtain only undecayed annual x/Q printout use 1001 or 2001 as a control.
-Plume Use Equation: 1 -Bolland Equation Eq 4.1, Briggs 1969) 2 -Lucas and Hoore (HVALUE) 3 -Optimized 6
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENTATION STONE & WEBSTER EN-113 SECTION:
,, OPERATING rnSTRUCTIONS REV!SED DATE: 4 -Opt11nized Csanady 5 -Clarke 6 -'Sriggs 7 -2/3 Law 8 -Zero ?tume Rise 9 -Spadfied Plume Rise (PLUMRS) 10 -Rriggs (Revised 1970) 11 -Rolland (C:q 4.1, Turner's Wot'kbook) 12 -Briggs (Revised 1972) PAGE 9 1.3 -Briggs ('Rr:l.ggs
-Sagendorf, Non-Buoyant Plume) 14 -Briggs (Revised 1975). The fol lowing parar:netet"s (X) are needed for the equat.ton number at the top: N l 2 3 4 5 6 7 8 9 10 11 WFUEL -x -------W.FLIJF:
-x x,-x x -x x GASl/EL
* x x x -x TSS x x x x x x x --x x STKllT -x --x x -x ---STl<DIA x x x -x 'l'A x x x x x x x --x x WNDSPD x x x x x x x --x x RVALUE -x -------where \.IFIJeL
"' Fue.l Flow WFT,tre = Flue Gas Flow GASVEL
* Stack Gas Exit Velocity TSS = Stack Gas Eidt Teoperature STKHT "' Stack Height STKDIA = Stack Exit Diameter TA = knblent Air Temperature H11DSPD = \Hnd Speed HVALUE = Heat Value of :'uel. Specified Plu:ne Rise (ft). 12 -x -x --x x x --x x x 14 x -x --x :< -WFUEL WFLUR GASVEL TSS STKHT STKDIA TA WNDSPD HVA1UE PLTP.iRS CAL::t.\C
-fiT!nd speed (::iph) assigned to calm observ<ltion for accident x/Q calculation.
Stop 6, i.f needed and not given. CALMAN -Wind speed (mph) assigned to calm observation for annual yJQ calculation.
Stop 6, if needed and not given. -Building height wake effecc. (long-turm)
(Annual).
If zero defaults to l.ong-tem ground release (11eter:s).
(NOTE: BRT must be eero when SPDBWE is -3
* 0. ) 7 Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENt'ArION srmra & WEBSL'ER SECl'!ON:
v Ol;>ERArING lNS!R.UCrrocrn RK'JISE:D OAl'E: PAGE 10 Sl?DBWE Ground to ele*1ated release shift: attd stack downwnsh switch (annual).
Zero (0) -??o shift or downwash.
-.Pos!.t:lva
-SPDBt.JB is wind speed (mph) below which shift from ground to release will be made. (Staclt 'height (SrKHr) must: be specified.)
-Negative
(-1.0) t:o elevated proportional shift (Regulatory Guide 1.111 2B) is made. (Stack gas exit (GASV8L) and (Sl'KH!)
must be specified.)
-Negative
(-3.0) -Aerodynamic downwash Guide 1.111, F..q (5) 1s used). (Stack diameter (S l'KDIA),
(SrlCIIr) and (GASVEL) must: be apecified.)
-Negative
(-2.0) -will apply aerodyrui!ll!.c downwaah
(-3.0) to elevated portion of ground to ele*1ated release (-1.0). lAJDIR -Adjacent doW"tlwlnd disl:ilnce switch (short-term only); (0) -Card St\ XQLnt Card 9 not used, {GT.O) -used. (2El0.0)
(Card not needed if Array containing lower and upper x/Q *1alues for and ootwecn which, the d1tte, time and meteorology (speed, direction and vertical stability class) are printed out. READ2 will limit release potnts to the first zero time period and the LPZ distances.
tf all r:aeteotology is desired, set the. lower limit = O.O and uppeT limit 1.0 or greater.
(3F5.0) (Card not needed if WSP&#xa3;ED -Wind speed above which building effect w!ll be considared (mph). C -Constant (0.5 CPRIM -Const:ant used in Abbey ?lume Meander method, CPRIH .. O.O removes bu1ld1ng waka effect, Card 10 (16F5.0)
(Card not needed U IBWEFF .. O.) A -Building wake effect area by df.rection:
l -wind fro1n the nol.*t:h
-ai*ea on the south side of building.
Card 11 (16"F5.0)
D!SrrE -Sita boundary distance by direction (metet's): 1 -wind north.-distance south of release point. 8 ---------------
Enclosure Attachment 1 PG&E Letter DCL-15-130 PROGRAM DOCUMENTATION STONE & WEBSTER EN-113 SECTION:
V OPERATWG INSTRUCTIONS REVISED DATE: PAGE 11 Card 12 -(16FS.O)
DISLPZ -Low population zone boundary distance by direction (meters): l -wind from north -distance south of. release point. NOTE: For Cards 10, 11 and 12, if the values eor all directions are the: same, punch the value in location (l) and 99999 in location (2). Card 13 (I5110F5.0) IDSLP -Number oE downwind distances other than site boundary or low population zone bou1\dary.
DISTAN -Downw1ud distances (1-10) {meters)
Cards 14 -29 (I5,12PS.O)
(Cards not needed 1f ITOPO=O)
IDR -Wind direction index* -
blo"1ing from (l-16). TOPORT Ground elevation obo*1e stack basa downwind Erorn the point (feet). (If IDR "" l (1101.'th),
elevation should be those south o.f the refousc point.) Cards 30 -32 (12,6(!2,2F5.Q)/2X,6(I2,2F5.0)/2X,4(I2,2F5.0))
* These data cat'ds will be read in by Subroutine TERAUl when the ITER!N Em! t:c.h is set to 3, 4 or ;. INUM IDRA UISTHX XQMlIT.T
-
of conrUtion groups
-Winrl direction identification (l -wind from north). (Direction not given means no adju5traent.)
-Downwind distance (mJ.les) bi!yond i*hich no adjustments are made. For up-valley sot distance to 1000.0. x/Q adjustment value.
* Typic.al values are --Down-Valley XQ!1ULT "" 5 XQMUtT == 1.5 XQMULT = l DISTM.'{
* 20 Hiles DISTHX = 1000 DISTitX = 1000 -
-Cross-Valley 9
Unit 1 EAB EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE Pacific Gas & Electric Company GROUND LEVEL (X/Q) CALCULATION NUMBER 14078104-C-M-00002 Diablo Canyon Nuclear Power Plant Unit 1 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 1 I START I STOP NDYSDT METS TB DHT IREDIS 87001 91365 1826 3 100.0 2 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL(9) 0.10 1.00 1.00 1.00 1.00 0.10 **********
READ2 (6.8) INPUT DATA**********
IRETYP RELSID(ll) 1 GROUND LEVEL (X/Q) ISTTYP 1 WFLUE 0. STKHT 0.00 ISECVG MESHT IAECSG IBWEFF 1 0 0 5 JHRARY(6) 1 0 0 0 WSPEED C CPRIM 0.00 0.50 0.00 A(l6) STKDIA 0.00 ITO PO 0 0 GASVEL 0.00 ITERIN 1 1001 JOBN0(3) 14078101 CALCNU(5) 14078104-C-M-00002 ELEVATED CONDITIONS SPEED 0 1. 00 TS 0. I SIGMA 0 IPLM!1Q 8 DIR 0 1. 00 HLID 0. PLUMRS 0.0 TEMP ISPUNT ITPUNT 0 0 1 1. 00 0.00 0.00 WFUEL 0. ISTABY ISTABZ 0000000 0000000 CAL MAC CAL MAN BHT 0.5 0.3 66.5 2 14078104 TPGRAD(6) 0.00 0.00 HVALUE ISTRLN 0. 0 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 0.00 0.00 I CALM ucu ucs 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE (16) 830.0 830.0 780.0 780.0 750.0 750.0 750.0 750.0 730.0 730.0 740.0 740.0 890.0 890.0 920.0 830.0 DISLPZ (16) 0.0 o.o 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 IDSLP DISTAN(lO) 0 0.0 0.0 0.0 0.0 0.0 0.0 o.o 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 4.000 2 4.000 10 3 4 5 6 7 8 9 10 11 12 13 14 15 16 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 ---
11 Enclosure Attachment 1 PG&E Letter DCL-15-130 Unit 2 EAB EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE CALCULATION NUMBER 14078101-ME-003 Pacific Gas & Electric Company GROUND LEVEL (X/Q) Diablo Canyon Nuclear Power Plant Unit 2 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 2 ISTART ISTOP NDYSDT METSTB DHT IREDIS 87001 91365 1826 3 100.0 2 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL (9) 0.10 1. 00 1. 00 1. 00 1. 00 0.10 **********
READ2 (6. 8) INPUT DATA **********
IRETYP RELSID (11) 1 GROUND LEVEL (X/Q) ISTTYP WFLUE STKHT STKDIA GASVEL 1 0. 0.00 0.00 0.00 ISECVG MES HT IAECSG IBWEFF ITO PO ITERIN 1 0 0 5 0 1 JHRARY (6) 1 0 0 0 0 1001 WSPEED c CPR IM 0.00 0.50 0.00 A(16) 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE (16) 730.0 730.0 740.0 780.0 780.0 780.0 DISLPZ (16) 0.0 0.0 0.0 0.0 0.0 0.0 IDS LP DISTAN (10) 0 0.0 0.0 0.0 0.0 0.0 JOBN0(3) 14078101 CALCNU(5) 14078101-ME-003 ELEVATED CONDITIONS SPEED DIR TEMP I SPUNT IT PUNT 0 0 0 0 1 1. 00 1. 00 1. 00 0.00 0.00 TS HLID WFUEL 0. 0. 0. I SIGMA ISTABY ISTABZ 0 0000000 0000000 IPLMEQ PLUMRS CALMAC CAL MAN BHT 8 0.0 0.5 0.3 66.5 2745.0 2745.0 2745.0 2745.0 2745.0 830.0 830.0 830.0 830.0 820.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 4.000 2 4.000 12 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 14078101 TPGRAD (6) 0.00 0.00 0.00 0.00 HVALUE ISTRLN I CALM ucu ucs 0. 0 2 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 820.0 870.0 870.0 850.0 730.0 0.0 o.o 0.0 0.0 0.0 3 4 5 6 7 8 9 10 11 12 13 14 15 16 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4.000 4. 000 4.000 4.000 4.000 4.000 4. 000 13 Enclosure Attachment 1 PG&E Letter DCL-15-130 I
Unit 1/2 LPZ EN-113 Run lCHI/Q -D/Q PROGRAM EN-113 VERSION 6 LEVEL 8 DATE 20121102 PAGE CALCULATION NUMBER 14078101-ME-003 Pacific Gas & Electric Company GROUND LEVEL (X/Q) Diablo Canyon Nuclear Power Plant Unit 1 **********
READl (6.8) INPUT DATA **********
CLIENT (11) Pacific Gas & Electric Company SITE (11) Diablo Canyon Nuclear Power Plant Unit 1 ISTART ISTOP NDYSDT METSTB DHT IREDIS 87001 91365 1826 3 100. 0 1 SPEED DIR TEMP RANGE STD DEV DELTA T 131 132 0 0 0 136 PARMUL(9) 0.10 1. 00 1. 00 1. 00 1. 00 0.10 **********
READ2 (6. 8) INPUT DATA **********
IRETYP RELSID(ll) 1 GROUND LEVEL-(X/Q) ISTTYP WFLUE STKHT STKDIA GASVEL 1 0. 0.00 0.00 0.00 ISECVG MES HT IAECSG IBWEFF ITO PO IT ERIN 1 0 0 5 0 1 JHRARY(6) 1 0 0 0 0 1001 WSPEED c CPR IM 0.00 0.50 0.00 A(16) 2745.0 2745.0 2745.0 2745.0 2745.0 2745.0 DISITE(16) 9650.0 9650.0 9650.0 9650.0 9650. 0 9650.0 DISLPZ (16) 0.0 0.0 o.o 0.0 0.0 0.0 IDS LP DISTAN(lO) 0 0.0 0.0 0.0 0.0 0.0 JOBN0(3) 14078101 CALCNU (5) 14078101-ME-003 ELEVATED CONDITIONS SPEED DIR TEMP I SPUNT IT PUNT 0 0 0 0 1 1. 00 1. 00 1. 00 0.00 0.00 TS HLID WFUEL 0. 0. 0. ISIGMA ISTABY ISTABZ 0 0000000 0000000 IPLMEQ PLUMRS CALMAC CAL MAN BHT 8 0.0 0.5 0.3 66.5 2745.0 2745.0 2745.0 2745.0 2745.0 9650. 0 9650.0 9650.0 9650.0 9650.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 **********
TERRAIN ADJUSTMENT FACTORS USED **********
IDR FACTORS ( 1) 1 1.250 2 1.250 14 2 Enclosure Attachment 1 PG&E Letter DCL-15-130 14078101 TPGRAD(6) 0.00 0.00 0.00 0.00 HVALUE ISTRLN I CALM ucu ucs 0. 0 2 0 0.00 0.00 NHR72 NHR624 LIMXQR PRGHRS RFCWSP 0 0 0 0.0 0.0 SPDBWE _ IAJDIR 0.0 0 2745.0 2745.0 2745.0 2745.0 2745.0 9650.0 9650.0 9650.0 9650.0 9650.0 0.0 0.0 0.0 0.0 0.0 3 4 5 6 7 8 9 10 11 12 13 14 15 16 1.250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1. 250 1.250 1. 250 1. 250 15 Enclosure Attachment 1 PG&E Letter DCL-15-130 Release-Receptor Cases 1 Enclosure Attachment 2 PG&E Letter DCL-15-130 File Name dccase01 dccase02 dccase03 dccase04 dccase05 dccase06 dccase07 dccase08
 
dccase09 dccase10 dccase11
 
dccase12 dccase13 dccase14 dccase15 dccase16 dccase17 dccase18 dccase19 dccase20
 
dccase21 dccase22 dccase23 dccase24 dccase25 dccase26 dccase27 dccase28
* dccase29 TABLE 1: Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Post-Accident LOCA Radioloaical Releases Description of Release-Receptor Cases. XIQ (sec/m3) 0-2 hours 2 -8 hours 8 -24 hours 1 -4 davs 4-30 davs Unit 1 CB Edge to Unit 1 CR Normal Intake 1.28E-03 7.12E-04 2.87E-04 2.90E-04 2.84E-04 Unit 1 CB Edge to Unit 1 CR Emergency Intake 4.11 E-04 2.30E-04 9.62E-05 8.69E-05 7.03E-05 Unit 1 CB Edge to Unit 2 CR Emergency Intake 1.67E-04 7.95E-05 2.63E-05 2.81 E-05 2.34E-05 Unit 1 CB Edge to CR Center 8.85E-04 4.43E-04 1.75E-04 1.77E-04 1.65E-04 Unit 1 PV to Unit 1 CR Emergency Intake 5.59E-04 3.38E-04 1.32E-04 1.12E-04 8.38E-05 Unit 1 PV to Unit 2 CR Emergency Intake 2.26E-04 1.48E-04 5.40E-05 5.47E-05 4.45E-05 Unit 1 PV to CR Center 1.26E-03 8.96E-04 3.44E-04 3.44E-04 2.99E-04 Unit 1 RWST Vent to Unit 1 CR Emergency Intake 3.27E-04 1.90E-04 7.13E-05 6.99E-05 5.76E-05 Unit 1 RWST Vent to Unit 2 CR Emergency Intake 2.10E-04 9.83E-05 3.73E-05 3.53E-05 2.86E-05 Unit 1 RWST Vent to CR Center 1.07E-03 4.86E-04 1.99E-04 1.75E-04 1.43E-04 Unit 2 CB Edge to Unit 2 CR Normal Intake 1.96E-03 9.42E-04 4.48E-04 3.98E-04 3.18E-04 Unit 2 CB Edge to Unit 1 CR Emergency Intake 1.70E-04 1.06E-04 4.23E-05 3.81E-05 2.95E-05 Unit 2 CB Edge to Unit 2 CR Emergency Intake 3.85E-04 1.47E-04 5.94E-05 5.84E-05 4.84E-05 Unit 2 CB Edge to CR Center 1.08E-03 5.46E-04 2.47E-04 2.12E-04 1.68E-04 Unit 2 PV to Unit 1 CR Emergency Intake 2.03E-04 1.29E-04 5.13E-05 4.32E-05 3.19E-05 Unit 2 PV to Unit 2 CR Emergency Intake 5.71 E-04 2.96E-04 1.20E-04 1.04E-04 8.19E-05 Unit 2 PV to CR Center 1.13E-03 7.08E-04 2.85E-04 2.39E-04 1.70E-04 Unit 2 RWST Vent to Unit 1 CR Emergency Intake 1.91E-04 1.21E-04 4.58E-05 4.39E-05 3.53E-05 Unit 2 RWST Vent to Unit 2 CR Emergency Intake 3.29E-04 1.61E-04 6.10E-05 5.53E-05 4.45E-05 Unit 2 RWST Vent to CR Center 1.07E-03 5.80E-04 2.18E-04 2.19E-04 1.79E-04 Unit 1 140' Leakage to Unit 1 CR Normal Intake 6.84E-03 3.08E-03 1.21E-03 1.12E-03 8.75E-04 Unit 1 140' Leakage to Unit 1 CR Emergency Intake 3.75E-04 2.33E-04 9.12E-05 8.45E-05 6.62E-05 Unit 1 140' Leakage to Unit 2 CR Emergency Intake 2.55E-04 1.25E-04 4.42E-05 4.38E-05 3.55E-05 Unit 1 140' Leakage to CR Center 3.22E-03 1.42E-03 5.54E-04 5.20E-04 4.21E-04 Unit 1 PL to Unit 1 CR Normal Intake 4.90E-03 3.45E-03 1.37E-03 1.37E-03 1.28E-03 Unit 1 PL to Unit 1 CR Emergency Intake 8.20E-04 5.40E-04 2.15E-04 1.87E-04 1.43E-04 Unit 1 PL to Unit 2 CR Emergency Intake 2.58E-04 1.54E-04 4.95E-05 5.26E-05 4.48E-05 Unit 1 PL to CR Center 2.59E-03 1.81 E-03 7.29E-04 7.15E-04 6.64E-04 Unit 2 140' Leakage to Unit 2 CR Normal Intake 6.71 E-03 3.12E-03 1.21E-03 1.22E-03 1.02E-03 2
File Name dccase30 dccase31 dccase32
 
dccase33 dccase34 dccase35 dccase36 dccase37
* dccase38 dccase39 dccase40 dccase41 dccase42 dccase43 dccase44 dccase45 dccase46 Notes: File names CR CB PV 140' Leakage RWST PL TABLE 1 : Input I Output File Names. Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Post:. Accident LOCARadiological Releases Description of Release-Receptor Cases Unit 2 140' Leakage to Unit 1 CR Emergency Intake Unit 2 140' Leakage to Unit 2 CR Emergency Intake Unit 2 140' Leakage to CR Center Unit 2 PL to Unit 2 CR Normal Intake Unit 2 PL to Unit 1 CR Emergency Intake Unit 2 PL to Unit 2 CR Emergency Intake Unit 2 PL to CR Center Unit 1 PV to Unit 1 CR Normal Intake Unit 2 PV to Unit 2 CR Normal Intake Unit 1 CB Edge to Unit 2 CR Normal Intake Unit 2 CB Edge to Unit 1 CR Normal Intake Unit 1 PV to Unit 2 CR Normal Intake Unit 2 PV to Unit 1 CR Normal Intake Unit 1 140' Leakage to Unit 2 CR Normal Intake Unit 1 PL to Unit 2 CR Normal Intake Unit 2 140' Leakage to Unit 1 CR Normal Intake Unit 2 PL to Unit 1 CR Normal Intake = Input (.rsf), Output (.log) = Control Room = Containment Building
=Plant Vent = Containment Penetration (GE Area) = Refueling Water Storage Tanks =Containment Penetration (GW/FW Area) Or 2 hours 2.28E-04 3.97E-04 3.16E-03
 
3.55E-03 2.28E-04 8.64E-04 2.21 E-03 1.67E-03 1.51E-03 6.52E-04 6.93E-04 9.10E-04 7.88E-04 2.24E-03 1.38E-03 2.14E-03 1.22E-03 3 XIQ (sec/m3) 2 -8 hours 8 -24 hours 1 -4 days 4-30 days 1.60E-04 6.25E-05 5.52E-05 4.21E-05 1.76E-04 6.93E-05 6.44E-05 5.27E-05 1.85E-03 7.17E.:.04 6.84E-04 5.43E-04 1.19E-03 4.82E-04 4.56E-04 3.03E-04 1.62E-04 6.58E-05 5.43E-05 3.99E-05 4.23E-04 1.50E-04 1.48E-04 1.20E-04 1.17E-03 4.?0E-04 3.90E-04 2.61E-04 1.22E-03 4.90E-04 4.90E-04 4.44E-04 9.41E-04 3.86E-04 3.23E-04 2.23E-04 3.51E-04 1.51E-04 1.49E-04 1.37E-04 3.84E-04 1.67E-04 1.42E-04 1.0SE-04 6.57E-04 2.68E-04 2.62E-04 2.45E-04 4.86E-04 2.01 E-04 1.69E-04 1.17E-04 1.15E-03 3.98E-04 3.89E-04 3.20E-04 9.83E-04 3.92E-04 3.88E-04 3.65E-04 1.39E-03 5.72E-04 4.83E-04 3.62E-04 6.26E-04 2.53E-04 2.12E-04 1.41 E-04 TABLE 2 -Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for FHA File Name dcfhc1 dcfhc2 dcfhc3 dcfhc4 dcfhcS dcfhc6 dcfhc7 dcfhc8 dcfhc9 dcfhc10 dcfhc11 dcfhc12 dcfhc13 dcfhc14 dcfhc15 dcfhc16 dcfhc17 . dcfhc18 dcfhc19 dcfhc20 Notes: File names CR FHB EH Radiological Releases Description of Release-Receptor Case Unit 1 FHB to Unit 1 CR Normal Intake Unit 1 FHB to Unit 2 CR Normal Intake Unit 1 FHB to Unit 2 CR Emergency Intake Unit 1 FHB to CR Center Unit 1 EH to Unit 1 CR Normal Intake Unit 1 EH to Unit 2 CR Normal Intake Unit 1 EH to Unit 2 CR Emergency Intake Unit 1 EH to CR Center Unit 2 FHB to Unit 1 CR Normal Intake Unit 2 FHB to Unit 2 CR Normal Intake Unit 2 FHB to Unit 1 CR Emergency Intake Unit 2 FHB to CR Center Unit 2 EH to Unit 1 CR Normal Intake Unit 2 EH to Unit 2 CR Normal Intake Unit 2 EH to Unit 1 CR Emergency Intake Unit 2 EH to CR Center Unit 1 FHB to Unit 1 CR Emergency Intake Unit 2 FHB to Unit 2 CR Emergency Intake Unit 1 EH to Unit 1 CR Emergency Intake Unit 2 EH to Unit 2 CR Emergency Intake =Input (.rsf), Output (.log) = Control Room = Fuel Handling Building
= Equipment Hatch 4 XIQ (sec/m3) 0 -2 hours 6.98E-03 2.93E-03 2.56E-04 3.78E-03 2.61E-02
 
2.88E-03 2.64E-04 5.51E-03 2.72E-03 6.98E-03 2.49E-04 3.7.1 E-03 2.49E-03 2.51E-02 2.49E-04 5.19E-03 3.31 E-04 3.50E-04 4.36E-04 4.68E-04 File Name dcmssv02 dcmssv03 dcmssv04 dcmssv05 dcmssv07 dcmssvOB dcmssv10 dcmssv11 dcmssv12 dcmssv13 dcmssv15 dcmssv16 dcmssv18 dcmssv19 dcmssv20 dcmssv21 dcmssv23 dcmssv24 dcmssv25 dcmssv26 dcmssv27 dcmssv28 dcmssv29 TABLE 3 Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Radiological Releases from MSSVs/ADVs/MSLB Description of Release-Receptor Cases X/Q (sec/m3) 0 -2 hours 2 -8 hours 8 -24 hours 1 -4 days 4-30 days Unit 1 MSSVs to Unit 1 CR Normal Intake NIA NIA NIA NIA NIA Unit 1 MSSVs to Unit 2 CR Normal Intake 4.29E-03 2.76E-03 1.04E-03 1.06E-03 9.46E-04 Unit 1 MSSVs to Unit 2 CR Emergency Intake 3.14E-04 1.53E-04 5.12E-05 5.29E-05 4.38E-05 Unit 1 MSSVs to CR Center 1.39E-02 7.40E-03 2.38E-03 2.56E-03 2.15E-03 Unit 2 MSSVs to Unit 1 CR Normal Intake 3.87E-03 2.42E-03 9.89E-04 8.17E-04 6.09E-04 Unit 2 MSSVs to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 MSSVs to Unit 1 CR Emergency Intake 2.89E-04 1.91E-04 7.45E-05 6.62E-05 5.08E-05 Unit 2 MSSVs to CR Center 1.22E-02 8.10E-03 3.27E-03 2.76E-03 2.08E-03 Unit 1 ADVs to Unit 1 CR Normal Intake NIA NIA N/A NIA NIA Unit 1 ADVs to Unit 2 CR Normal Intake 4.30E-03 2.79E-03 1.05E-03 1.06E-03 9.49E-04 Unit 1 ADVs to Unit 2 CR Emergency Intake 3.13E-04 1.54E-04 5.13E-05 5.30E-05 4.39E-05 Unit 1 ADVs to CR Center 1.39E-02 7.45E-03 2.39E-03 2.59E-03 2.15E-03 Unit 2 ADVs to Unit 1 CR Normal Intake 3.88E-03 2.43E-03 9.94E-04 8.19E-04 6.10E-04 Unit 2 ADVs to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 ADVs to Unit 1 CR Emergency Intake 2.87E-04 1.92E-04 7.48E-05 6.61E-05 5.07E-05 Unit 2 ADVs to CR Center 1.22E-02 8.16E-03 3.28E-03 2.78E-03 2.09E-03 Unit 1 MSLB to Unit 1 CR Normal Intake NIA NIA NIA NIA N/A Unit 1 MSLB to Unit 2 CR Normal Intake 4.23E-03 2.90E-03 1.13E-03 1.11 E-03 1.02E-03 Unit 1 MSLB to Unit 2 CR Emergency Intake 3.06E-04 1.54E-04 5.19E-05 5.32E-05 4.38E-05 Unit 1 MSLB to CR Center 1.24E-02 7.10E-03 2.24E-03 2.43E-03 2.07E-03 Unit 2 MSLB to Unit 1 CR Normal Intake 3.81E-03 2.40E-03 1.01E-03 8.09E-04 5.88E-04 Unit 2 MSLB to Unit 2 CR Normal Intake NIA NIA NIA NIA NIA Unit 2 MSLB to Unit 1 CR Emergency Intake 2.75E-04 1.91E-04 7.45E-05 6.53E-05 4.86E-05 Unit 2 MSLB to Control Room Center 1.09E-02 7.35E-03 3.01 E-03 2.48E-03 1.86E-03 Unit 1 MSSVs to Unit 1 CR Emergency Intake 4.66E-04 2.92E-04 1.16E-04 1.04E-04 8.08E-05 Unit 2 MSSVs to Unit 2 CR Emergency Intake 4.90E-04 2.29E-04 8.24E-05 8.07E-05 6.49E-05 Unit 1 ADVs to Unit 1 CR Emergency Intake 4.66E-04 2.92E-04 1.16E-04 1.04E-04 8.07E-05 Unit 2 ADVs to Unit 2 CR Emergency Intake 4.90E-04 2.29E-04 8.24E-05 8.08E-05 6.48E-05 Unit 1 MSLB to Unit 1 CR Emergency Intake 4.35E-04 2.94E-04 1.15E-04 1.01 E-04 7.76E-05 5
File Name dcmssv30 Notes: File names N/A CR MSSVs AD Vs MSLB TABLE 3 -Input I Output File Names Enclosure Attachment 2 PG&E Letter DCL-15-130 Atmospheric Dispersion Factors (X/Qs) at Control Room Receptors for Radiological Releases from MSSVs/ADVs/MSLB Description of Release-Receptor Cases X/Q (sec/m3) 0 -2 hours 2 -8 hours 8 -24 hours 1 -4 days Unit 2 MSLB to Unit 2 CR Emergency Intake 4.76E-04 2.24E-04 8.14E-05 7.94E-05
=Input (.rsf), Output (.log) = Not applicable due to the source-receptor distance being much less than 10 meters, outside of the applicability of ARCON96.
= Control Room = Main Steam Safety Valves = Atmospheric Dump Valves = Main Steam Line Break 6 4-30 days 6.40E-05 File Name dctsc01 dctsc02 dctsc03 dctsc04 dctsc05 dctsc06 dctsc07 dctsc08 dctsc09 dctsc10 dctsc11 dctsc12 dctsc13 dctsc14 dctsc15 dctsc16 dctsc17 dctsc18 dctsc19 dctsc20 Notes: File names CB PV RWST PL TABLE 4 -Input I Output File Names Atmosoheric Disoersion Factors (X/Qs) atTSC Receptors for LOCA Radioloaical Releases Release-Receptor Case Description Unit 1 CB Edge to TSC Normal Intake Unit 1 CB Edge to TSC Center Unit 1 PV (ECCS Leakage) to TSC Normal Intake Unit 1 PV(ECCS Leakage) to TSC Center Unit 1 RWST Vent to TSC Normal Intake Unit 1 RWST Vent to TSC Center Unit 1 140'. Elevation Area Leakage to TSC Normal Intake Unit 1 140' Elevation Area Leakage to TSC Center Unit 1 PL to TSC Normal Intake Unit 1 PL to TSC Center Unit 2 CB Edge to TSC Normal Intake Unit 2 CB Edge to TSC Center Unit 2 PV (ECCS Leakage) to TSC Normal Intake Unit 2 PV (ECCS Leakage) to TSC Center Unit 2 RWST Vent to TSC Normal Intake Unit 2 RWST Vent to TSC Center Unit 2 140' Elevation Area Leakage to TSC Normal Intake Unit 2 140' Elevation Area Leakage to TSC Center Unit 2 PL to TSC Normal Intake Unit 2 PL to TSC Center =Input (.rsf), Output = Containment Building
=Plant Vent = Refueling Water Storage Tanks = Penetration Leakage 7 X/Q (seclm3) 0 -2 hours 2 8 hours 8 -24 hours 2.57E-04 1.18E-04 4.27E-05 2.90E-04 1.33E-04 4.98E-05 3.12E-04 1.77E-04 6.91E-05 3.54E-04 1.95E-04 7.71 E-05 2.72E-04 1.27E-04 4.80E'::05 2.94E-04 1.38E-04 5.40E-05 3.64E-04 1.74E-04 6.55E-05 4.27E-04 1.91E-04 7.45E-05 4.BOE-04 2.51 E-04 8.31 E-05 5.98E-04 3.03E-04 1.04E-04 5.48E-04 2.00E-04 8.52E-05 5.57E-04 2.01E-04 8.81E-05 5.52E-04 2.35E-04 1.06E-04 5.43E-04 2.16E-04 9.97E-05 3.63E-04 1.68E-04 6.47E-05 3.72E-04 1.68E-04 6.64E-05 5.47E-04 2.41E-04 9.36E-05 5.72E-04 2.43E-04 9.75E-05 1.80E-03 7.72E-04 3.07E-04 1.83E-03 7.49E-04 3.16E-04 Enclosure Attachment 2 PG&E Letter DCL-15-130 1 -4 days 4-30 days 4.24E-05 3.50E-05 4.83E-05 4.02E-05 6.29E-05 5.21 E-05 6.70E-05 5.67E-05 4.49E-05 3.71E-05 4.89E-05 3.97E-05 6.14E-05 5.00E-05 6.84E-05 5.62E-05 8.64E-05 6.95E-05 1.03E-04 8.46E-05 8.37E-05 6.84E-05 8.89E-05 6.92E-05 8.71 E-05 6.95E-05 8.11 E-05 6.58E-05 6.04E-05 4.91 E-05 6.17E-05 5.10E-05 8.83E-05 7.02E-05 9.12E-05 7.52E-05 2.87E-04 2.33E-04 2.92E-04 2.41E-04 Data Disc 1 Enclosure Attachment 3 PG&E Letter DCL-15-130 Security-Related Information
-Withhold Under 10 CFR 2.390 / Data Disc 2 (10 CFR 2.390) 1 Enclosure Attachment 4 PG&E Letter DCL-15-130 Security-Related Information
-Withhold Under 10 CFR 2.390}}

Revision as of 20:44, 8 July 2018

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML15321A235&oldid=854425"