ML13312A735
| ML13312A735 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/05/1993 |
| From: | Anderson C SOUTHERN CALIFORNIA EDISON CO. |
| To: | Good G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 9312290304 | |
| Download: ML13312A735 (8) | |
Text
Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92674-0128 November 5, 1993 NRC Region V 1450 Maria Lane, Suite 210 Walnut Creek, Ca 94596-5368 Attention:
Ms. Gail Good 5 m
Dear Ms. Good:
0
Subject:
Radiation Monitor Emergency Action Levels in S023-VIII-1, Recognition and Classification of Emergencies, Revisions 9 and 10
Reference:
"SO 1 (23)-VIII-1, Recognition and Classification of Emergencies, Revision 10", letter from C. K. Anderson to G. Good, dated September 10, 1993 The enclosed documents provide values used in determining radiation monitor Emergency Action Levels in revisions 9 and 10 of Emergency Plan Implementing Procedure S023-VIII-1, Recognition and Classification of Emergencies. This information is provided in response to your questions regarding the referenced letter.
Please contact me if you need further information.
C,
K. Anderson Supervisor, Emergency Planning RAG:NRC931 Enclosures cc:
W. C. Marsh K. C. Yhip W. G. Zintl R. A. Garcia G. T. Gibson EP File CDM File Attachme
, Page 1
MEMORANDUM FOR FILE November 5, 1993
SUBJECT:
Reference Values Used in Tab A of S023-VIII-1 "Recognition and Classification of Emergencies," Revisions 9 and 10
REFERENCES:
- 1.
S023-VIII-1 "Recognition and Classification of Emergencies," Revisions 9 and 10
- 2.
"Additional Information on Recommended Changes to 2/3 EPIPs Dated 1/17/92" K Yhip, 10/12/93.
- 3.
"Adverse X/Q Values" M. Goeders to E.S. Medling, 10/15/91
- 4.
Units 2/3 Offsite Dose Calculation Manual, Revisions 18, 19, and 25
- 5.
"Numerical Bases for Classification of EAL for Uncontrolled Release of Radioactivity for Units 2/3" Angeline Ong to Wayne Otto, 7/21/83 This memorandum lists the input parameters used to calculate radiation monitor Emergency Action Levels in Emergency Plan Implementing Procedure (EPIP) S023-VIII-1, "Recognition and Classification of Emergencies." The values listed are for Emergency Action Levels (EALs) which changed between Revisions 9 and 10. These values, obtained from the listed references were calculated in accordance with reference 4.
EAL changes for Revision 10 were the result of routine changes to calibration constants (Reference 2),
new adverse atmospheric dispersion factors (Reference 3) and revised flows for effluent release points (Reference 4). Original documentation for Revision 9 was not readily available but revisions of licensing documents containing values pertinent to that period were used as references.
The information is presented in the order that the radiation monitors are listed in the EPIP. Radiation monitor EALs for various combinations of effluent flows, pump rates and release times are not provided where the values are proportional to, and easily obtained from, those listed. Alert EALs are not provided because they are exactly 10 times the Unusual Event EALs and are proportional for the various release times.
Richard A. Garcia Emergency Planning Engineer RAG/mtfepip Attachment cc:
C. K. Anderson P. K. Chang D. Dick E. M. Goldin K. C. Yhip EP files, Page 2
Attachment Parameters and Values Used for Revisions 9 and 10 of S023-VIII-1 Unusual Event - Tab Al-1
- 1.
Containment Purge Monitor, 2(3) RE-7828 Values below apply to full purge conditions lasting one hour.
Revision 9 Revision 10 Radiation Monitor Indication (pCi/cc) 6.57 E-2 4.38 E-2 Dose Rate (mR/hr) 2.00 E-1 2.00 E-1 X/Q (sec/m3) 4.80 E-6 4.80 E-6 Effluent Flow (cfm) 4.00 E+4 6.00 E+4 Values below apply to mini purge conditions lasting 15 minutes.
Revision 9 Revision 10 Radiation Monitor Indication (pCi/cc) 5.25 E+0 3.50 E+0 Dose Rate (mR/hr) 2.00 E-1 2.00 E-1 X/Q (sec/m 3) 4.80 E-6 4.80 E-6 Effluent Flow (cfm) 2.00 E+3 3.00 E+3 The mini purge values are outside the range of the monitor and are identified in the EPIP as offscale high. The values are included here for information only.
- 2.
Plant Vent Stack Monitor, 2/3 RE-7808C Values below apply to one exhaust fan releasing for one hour.
Revision 9*
Revision 10 Radiation Monitor Indication (cpm) 5.60 E+5 6.94 E+5 Dose Rate (mR/hr) 2.00 E-1 2.00 E-1 X/Q (sec/m 3) 4.80 E-6 4.80 E-6 Effluent Flow (cfm) 9.15 E+4 8.20 E+4 Ki (Dose Conversion Factor mR/yr per pCilm) 2.94 E+2 2.94 E+2 Calibration Constant (cpm per pCi/cc) 5.13 E-8 4.62 E-8 Values taken from revisions of documents pertinent to that timeframe. Radiation monitor indication for Revision 9 is more conservative than the value above.
- 3.
Condenser Air Ejector WRGM, 2(3)RE-7870 and Plant Vent Stack WRGM, 2(3)RE-7865 Values did not change from Revision 9 to Revision 10 1, Page 3
Attachment Unusual Event - Tab Al-2
- 1.
Liquid Radwaste Monitor, 2(3) RI-7813 Values below apply for a one hour release diluted by one circulation pump:
Revision 9 Revision 10 Radiation Monitor Indication (cpm) 2.76 E+5 7.62 E+4 MPC Effective 1.00 E-6 3.00 E-7 Effluent Flow (gpm) 1.85 E+5 1.85 E+5 Waste Flow (gpm) 1.40 E+2 1.40 E+2 Calibration Constant (cpm per pCi/cc) 4.79 E-9 5.20 E-9
- 2.
Steam Generator Neutralization Sump, 2(3) RI-7817 Values below apply for a one hour release diluted by one circulation pump.
Revision 9 Revision 10 Radiation Monitor Indication (cpm) 4.88 E+4 1.96 E+4 MPC Effective 1.00 E-6 3.00 E-7 Effluent Flow (gpm) 1.85 E+5 1.85 E+5 Waste Flow (gpm) 8.00 E+2 6.00 E+2 Calibration Constant (cpm per pCi/cc) 4.74 E-9 4.73 E-9
- 3.
Turbine Building Sump, 2(3) RI-7821 Values below apply for a one hour release diluted by one circulation pump.
Revision 9 Revision 10 Radiation Monitor Indication (cpm) 3.64 E+5*
1.07 E+5 MPC Effective 1.00 E-6 3.00 E-7 Effluent Flow (gpm) 1.85 E+5 1.85 E+5 Waste Flow (gpm) 1.06 E+2 1.00 E+2 Calibration Constant (cpm per pCi/cc) 4.80 E-9 5.21 E-9 Value taken from revisions of documents pertinent to that timeframe. Radiation monitor indication is within 10% of the value listed in Revision 9.
- 4.
Steam Generator Bypass, 2(3) RI-6753 or RI-6759 Values below apply for a one hour release diluted by one circulation pump.
Revision 9 Revision 10 Radiation Monitor Indication (cpm) 4.73 E+4*
4.86 E+4 MPC Effective 1.00 E-6 1.00 E-6 Effluent Flow (gpm) 1.85 E+5 1.85 E+5 Waste Flow (gpm) 2.00 E+2 2.00 E+2 Calibration Constant (cpm per pCi/cc) 1.95 E-8 1.91 E-8 Values taken from revisions of documents pertinent to that timeframe. Radiation monitor indication for Revision 9 is more conservative than the value above.
2, Page 4
Attachment Site Area Emergency - Tab A3-1
- 1.
Plant Vent Stack Monitor, 2/3 RE-7808C Values below apply to one exhaust fan releasing for 15 minutes.
Revision 9 Revision 10 Radiation Monitor Indication (cpm) 9.88 E+6 2.44 E+5 Dose Rate (mR in x mins) 50/15 50/30 Adverse X/Q (sec/m) 2.72 E-4 1.60 E-4 Effluent Flow (cfm) 9.15 E+4 8.20 E+4 Xe-133 Dose Equivalent 1.00 E+0 4.26 E+1 Calibration Constant (cpm per pCi/cc) 5.13 E-8 4.62 E-8 Ki (Dose Conversion Factor mR/yr per pCi/rn 3) 2.94 E+2 2.94 E+2 Values taken from revisions of documents pertinent to that timeframe. Radiation monitor indication for Revision 9 is more conservative than the value above.
- 2.
Air Ejector WRGM, 2(3)RE-7870 Values below apply to a' 15 minute release.
Revision 9 Revision 10 Radiation Monitor Indication (pCi/sec) 2.23 2+7 4.36 E+5 Dose Rate (mR in x mins) 50/15 50/30 Adverse X/Q (sec/
- 3) pM2.72 E-4 1.60 E-4 K, (Dose Conversion Factor mR/yr per pCilm3 2.94 E+2 2.94 E+2 Xe-133 Dose Equivalent 1.00 E+o 4.26 E+1
- 3.
Plant Vent Stack WRGM, 2(3)RE-7865 Values below apply to a 15 minute release.
Revision 9 Revision 10 Radiation Monitor Indication (pCi/sec) 2.23 E+7 4.36 E+5 Dose Rate (mRhr) 5.00 E+1 5.00 E+1 Adverse X/Q (sec/m) 2.72 E-4 1.60 E-4 K, (Dose Conversion Factor mR/yr per pCi/m) 2.94 E+2 2.94 E+2 Xe-133 Dose Equivalent 1.00 E+0 4.26 E+1 3
Attach.ent 1, Page 5
October 12, 1993 ADDITIONAL INFORMATION ON RECOMMENDED CHANGES TO 2/3 EPIPs DATED 1/17/92
REFERENCES:
(1)
Units 2/3 Offsite Dose Calculation Manual, Revisions 18, 19, and 25 (2)
S023-VIII-1 "Recognition and Classification of Emergencies",
Revisions 9 and 10 (3)
"Numerical Bases for Classification of EAL for Uncontrolled Release of Radioactivity for Units 2/3", Angeline Ong to Wayne Otto, 7/21/83 (4)
"Adverse X/Q Values", M. Goeders to E.S. Medling,10/15/91 This memorandum addresses the bases for changes in radiation monitor setpoints to the Units 2/3 EPIP, S023-VIII-23, as recommended on 1/17/92 by Effluent Engineering.
Generally speaking, the input values used to derive recommended setpoints for Revision 10 of the EPIP, release or dilution rates and calibration constants, are those listed in Revision 25 of the Units 2/3 Offsite Dose Calculation Manual (ODCM). In some instances, the documentation of previous values (Revision 9 EPIP) used for Revision 9 is not readily available. Typically they were based on data from Revision 19 of the ODCM.
The discussion is broken down by mode of release and event class.
NOBLE GAS - UNUSUAL EVENT & ALERT
- 1.
Containment Purge, 2(3) RE-7828 Release flowrates recorded on strip charts occasionally showed previous values used were not conservative for all scenarios. In particular, venting a pressurized containment can result in a fleeting rush of air with an immediate return to lower flowrates. To ensure that dose rates do not exceed the specified limits of 2000 cfm and 40000 cfm for mini and main purge respectively, default flowrates used in calculating Unusual Event (UE) and Alert setpoints for containment purge were conservatively increased to 3000 cfm and 60000 cfm., Page 6
.2.
Plant Vent Stack, 2/3 RE-7808C Revision 9 EPIP setpoints were provided in a 12/9/87 transmittal from K. Helm to D. H. Peacor and used the calibration constant of 5.13E-8,uCi/cc per cpm listed in Revision 19 of the Units 2/3 ODCM. The values recommended for Revision 10 use the more recent (1989) calibration constant of 4.62E-8 jCi/cc per cpm.
The other change in input parameters was for discharge rates. Based on actual flow measurements for various fan 'and damper configurations in the radwaste building, the discharge rate for one plant vent stack fan has been decreased from 91500 to 82000 cfm.
LIQUIDS - UNUSUAL EVENT & ALERT
- 1.
Liquid radwaste, 2(3) RI-7813 Revision 9 setpoints were based on a calibration constant of 4.79E-9 compared to 5.20E-9 pCi/ml per cpm. A more conservative MPCef was used, that for 1311 (3E-7 uCi/ml) compared to one based on the RCS of 1 E-6 uCi/ml. The release rate of 140 gpm was used for both calculations.
- 2.
Steam Generator Neutralization Sump, 2(3) RI-7817 Revision 9 setpoints were based on a calibration constant of 4.74E-9 compared to 4.73E-9 uCi/ml per cpm. A more conservative MPCen was used, that for 1311 (3E-7 pCi/ml) compared to one based on the RCS of 1 E-6 uCi/ml. The release rate of 800 gpm was decreased to 600 gpm to reflect measured rates of discharge versus design values.
- 3.
Turbine Building Sump, 2(3) RI-7821 Revision 9 setpoints were based on a calibration constant of 4.80E-9 compared to 5.21 E-9 FCi/ml per cpm. A more conservative MPCen was used, that for 1311 (3E-7 uCi/mi) compared to one based on the RCS of 1 E-6 pCi/mI. The release rate of 106 gpm was also changed (to 100 gpm) to reflect ODCM data.
- 4.
Steam Generator Bypass, 2(3) RI-6753 or RI-6759 The calibration constant was changed from 1.95E-8 to 1.93E-8 pCi/mI per cpm.
Neither the release rate nor MPCen were changed. Using values that would have been typical for that timeframe, the exact numbers in Revision 9 cannot be reproduced. It is important to note, however, that the actual numbers used were more conservative than the calculated values, 3.4E4 for 1 circ pump at the UE level versus 4.7E4 cpm., Page 7
NOBLE GASES - SITE AREA EMERGENCY In addition to calibration constant updates for 7808C and flowrates, the adverse X/Q five-percentile value provided by Corporate Health Physics and Environmental for use in the calculations was based on the 1979-1983 data set (Reference 4). A value of 1.602E-4 sec/m3 was selected as the highest value for a landward sector, to the WNW; the maximum value of 2.34E-4 sec/m 3 is in a seaward direction and therefore less likely to result in dose to a member of the public. The FSAR lists a maximum adverse five-percentile dispersion coefficient of 2.7E-4 sec/m 3 based on the 1973-1976 pre-operational meteorological data set. Given that the ODCM annual average historical value listed is based on a more recent data set, it is appropriate to also use this information rather than the value listed in the FSAR.
Finally, noble gases released during any accident involving the core would be a mixture rather than pure xenon-133. As outlined in the memo from Angeline Ong to Wayne Otto (Reference 3), data from the FSAR was used to' derive iodine and xenon equivalent factors.
Kathleen Yhip Corporate HP&E Engineer cc:
Cyrus Anderson Po Chang Daryl Dick Eric Goldin HP&E files, Page 8