ML20209E608
| ML20209E608 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/20/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209E612 | List: |
| References | |
| TAC-54862, TAC-54863, NUDOCS 8609110260 | |
| Download: ML20209E608 (18) | |
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+i UNITED STATES
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WASHINGTON, D. C. 20555 5
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated April 27 and August 29, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8609110260 860020 PDR ADOCK 05000361 P
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No, hPF-15 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 52, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULAT0FY C0fEISSION I
r T
b Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1986 l
l l
August 20, 1986
- ATTACHMENT TO LICENSE AMENDMENT N0. 52 FACILITY OPERATING LICENSE N0. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 l
l l
TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Minimum Detection Sampling Analysis Type of (LLD)
Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml),
P P
9 A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters -
1x10 4 Tank Grab Sample 9
1x10 4 B.
Containment Purge P
P Principal Gamma Emitters b
b 42 inch Each Purge,c Each Purge b
9 1x10 4 8 inch M
M Principal Gamma Emmitters Grab Sample H-3 1x10 6 D
D 9
C.
- 1. Condenser M
M Principal Gamma Emitters 1x10 4 l
Evacuation Grab System Sample H-3 1x10 6
- 2. Plant Vent b
b W,e y
Stack D.
All Release Types Continuous #
W I-131 1x10 12 d
as listed in B and Sampler Charcoal C above.
Sample I-133 1x10 10 Continuous #
W Principal Gamma Emitters d
9 1x10 11 j
Sampler Particulate (I-131, Others)
Sample Continuous #
M Gross Alpha 1x10 11 Sampler Composite Particulate Sample l
Continuous #
Q Sr-89, Sr-90 1x10 11 Sampler Composite Particulate Sample Continuous #
Noble Gas Noble Gases lx10 8 Monitor Monitor Gross Beta or Gamma h
I i
9 5x10 7 E.
Incinerated Oil Each batch Each batch Principal Gamma Emitters Grab Sample SAN ONOFRE-UNIT 2 3/4 11-9 AMENDMENT NO. 52
TABLE 4.11-2 (Continued)
TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s b
LLD =
E V
2.22 x 106 Y
exp (-Mt)
Where:
LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
is the standard deviation of the background counting rate or of sh tne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass o.r volume),
is the. number of tran'sformations per minute per microcurie, 2.22 x 106 Y is the fractional radiochemical yield (when applicable),
I A is the radioactive decay constant for the particular radionuclide, ard at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of h
1 the background counting rate or of the count,ing rate of the blank.
samples (as appropriate) rather than on an unverified theoretically predicted variance.
~
In calculating the LLD for a radionuclide determine by' gamma ray spectrometry, the background should include the typical co.ntributions of other radio-nuclides normally present in the samples.
Typical values of E, V, Y and at should be used in the calculation.
I It should be recognized that the LLD_is defined as an a' priori (before the fact) limit representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
"For a more complete discussion of the LLD, and other detection limits, see
)
the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).
(
(3) Hartwell, J.
K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
SAN ONOFRE-UNIT 2 3/4 11-10 t
TABLE 4.11-2 (Continued)
TABLE NOTATION b.
Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when c.
the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
Tritium grab samples shall be taken at least once per 7 days from e.
the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
g.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported.
i I
h.
Incinerated oil may be discharged at points other than the plant vent stack.
Release shall be accounted for based on pre-release grab sample data.
I 1.
Samples for incinerated oil releases shall be collected from repre-sentative samples of filtered oil in liquid form.
I i
SAN ONOFRE-UNIT 2 3/4 11-11 AMENDMENT NO. 52
{
1 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES
/
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LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year:
Less than or_ equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLI'CABILITY: At all times.
ACTION a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specificati,on 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed f
\\
corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.2.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be deterniined in accordance with the 00CM at least once per 31 days.
l l
SAN ONOFRE-UNIT 2 3/4 11-12
RADI0 ACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result c.
i of burning contaminated oil.
APPLICABILITY:
At all times.
ACTION:
With the calculated dose from the release of tritium, radioiodines, a.
and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above y
limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.3.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.
~
SAN ONOFRE-UNIT 2 3/4 11-13 AMENDMENT NO. 52
RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT
(
LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the GASE0US RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ.*-
APPLICABILITY: At all times.
ACTION:
a.
With the GASE0US RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the
(
following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.*4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.'
4.11.2.4.2 The GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASE0US RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
"These doses are per reactor unit.
SAN ONOFRE-UNIT 2 3/4 11-14
.g.,,,.
[f UNITED STATES
,' p, NUCLEAR REGULATORY COMMISSION 5
S j WASHINGTON. D. C. 20SS5
- /
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-15 1.
The huclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated April 27 and August 29, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be ccnducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I Os -
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 41, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective cate of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r/$
Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1986 l
l l
l
August 20, 1986 ATTACHMENT TO LICENSE AMENDMENT N0. 41 FACILITY OPERATING LICENSE N0. NPF-15 i
DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 i
l i
i f
i l
I i
_ _ _ _ _ _ _ - _ _ _ _,..., _ _. _ _ ~..... _.
TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (gLD)
Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)
A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emittersg 1x10 4 Tank Grab Sample B.
Containment Purge P
P Principal Gamma Emitters 9 1x10 4 b
b 42 inch Each Purge,c Each Purge H-3 1x10 6 4
b D
8 inch M
M Principal Gamma Emmitters9 1x10 4 Grab Sample g-3 1x10 6 b
b C.
- 1. Condenser M
g
-Principal Gamma Emitters 9 1x10 4 Evacuation Grab System Sample H-3 1x10 u
- 2. Plant Vent b
b W,e y
Stack 0.
All Release Types Continuous #
W I-131 1x10 12 d
as listed in B and Sampler Charcoal C above.
Sample I-133 1x10 10 f
d Continuous W
Principal Gamma Emitters 9 1x10 11 Sampler Particulate (I-131,Others)
Sample Continuous #
M Gross Alpha 1x10 11 Sampler Composite Particulate Sample f
Continuous Q
Sr-89, Sr-90 1x10 11 Sampler Composite Particulate Sample Continuous Noble Gas Noble Gases 1x10 6 f
l Monitor Monitor Gross Beta or Gamma h
i i
E.
Incinerated Oil Each batch Each batch Principal Gamna Emitters 9 5x10 7 i
SAN ON0FRE - UNIT 3 3/4 11-9 AMENDMENT NO. 41
l TABLE 4.11-2 (Continued)
TABLE NOTATION i
The LLD is the smallest concentration of radioactive material in a sample a.
that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
i 4.66 s 0*
E V
2.22 x 106 Y
exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above (as 1
microcurie per unit mass or volume),
s is the standard deviation of t'he background counting rate or of b
tne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
I V is the sample size (in units of mass or volume),
2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLD for a particular g
measurement sy5 tem shall be based on the actual observed variancelof the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background should include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing.the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968)
(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972).
SAN ON0FRE-UNIT 3 3/4 11-10 h
TABLE 4.11-2 (Continued)
TABLE NOTATION b.
Analyses shall also be performed following shutdown, startup, or a THERMAL F0WER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
c.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
Tritium grab samples shall be taken at least once per 7 days from e.
the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
g.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported.
h.
Incinerated oil may be discharged at points other than the plant vent stack.
Release shall be accounted for based on pre-release grab sample data, t
i.
Samples for incinerated oil releases shall be collected from repre-r sentative samples of filtered oil in liquid form.
SAN ONOFRE - UNIT 3 3/4 11-11 AMENDMENT NO. 4l
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equa.1 to 20 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification,6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed
(
corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.2.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.
'I SAN ON0FRE-UNIT 3 3/4 11-12 l
RADI0 ACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calerdar quarter:
Less than or equal t'o 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
c.
Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of burning contaminated oil.
APPLICABILITY:
At all times.
ACTION:
t a.
With the calculated dose from the release of tritium, radioiodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.3.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l
4.11.2.3 Dose Calculations Cumulative dose contributions for the current l
calendar quarter and current calendar year shall be determined in accordance l
with the ODCM at least once per 31 days.
SAN ONOFRE-UNIT 3 3/4 11-13 AMENDMENT NO. 41
RADIOACTIVE EFFLUENTS
(
GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gasecus effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gasaous effluent releases from the site (see Fjgure 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ.*
APPLICABILITY: At all times.
ACTION:
a.
With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days,
{
pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taker. to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS i
l 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCH.
4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREANENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
AThese doses are per reactor unit.
SAN ONOFRE-UNIT 3 3/4 11-14
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