ML20245J684
| ML20245J684 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/26/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245J690 | List: |
| References | |
| NUDOCS 8907030124 | |
| Download: ML20245J684 (18) | |
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UNITED STATED NUCLEAR REGULATORY. COMMISSION
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_ CAROLINA' POWER & LIGHT COMPANY, et al.
_00_CKET NO. 50-325
.i BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO TACILITY OPERATING LICENSE l
Amendment No. 1 34
]
License No. D.0R-71 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated June 23, 1987, as revised March 29, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this atendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
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(2).'TechnicalSpecifications The Technical Specifications contained.in Appendices A and B, as revised through _ Amendment No.134, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility.
-in accordance with the Technical Specifications.
~3.
This' license amendment is effective as of. the date of its issuance and shall be implemented within 60-days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original. Signed By:
Elinor G. Adensam, Director Project Directorate II-1 Division of. Reactor Projects *I/II Office of Nuclear. Reactor Regulation 4
Attachment:
Changes,to_the. Technical
. Specifications L
Date of Issuance: - June 26, 1989 1'
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1 f-ATTACHMENT TO LICENSE AMENDMENT N0. 134
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i FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 i
Replace the following pages of the Appendix A Technical Specifications with' the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages-Insert Pages 3/4 11-12 3/4 11-12 3/4 11-14a 3/4 11-16 3/4 11-16 8 3/4 11-3 8 3/4 11-3 8 3/4 11-5 B 11-5 6-24 6-24 l
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-Y TABLE 4.11.2-1.(Continued)
RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM.
TABLE-NOTATION (i) Releases from incinerated oil may be discharged via. points other than the main vent'(e.g.,. incinerator). ' Release shall be accounted for based on pre-release grab sample data.
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Samples of waste oil'to be incinerated shall be collected from and-representative of oil in~1iquid form.
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BRUNSWICK - UNIT 1 3/4 11-14a Amendment No. 134 1
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RADIOACTIVE EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES Id PARTICULATE FORM l
l.
LIMITING CONDITION FOR OPERATION l
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l 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, I
tritium, and.all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond I
the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:
f I
a.
During any calendar quarter:
Less than or equal to 15 mrems to any organ; and b.
During any calendar year: Less than or equal to 30 mrems to any organ.
c.
Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of l
burning contaminated oil.
APPLICABILITY: At all times.
I I
ACTION:
a.
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare acd submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
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 for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.
NOTE: See Bases 3/4.11.2.3 BRUNSWICK - UNIT 1 3/4 11-16 Amendment No. $7,134
s RADIOACTIVE EFFLUENTS BASES 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor tanks that are not surrour.ded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system with the exception of the auxiliary surge tank. The auxiliary surge tank is excluded from this specification because the tank and its associated piping are all Seismic Class I.
Since the condensate storage tanks have continuous influent and effluent, stratification should not occur.
Samples taken from the operating condensate transfer pump (s) vent or drain shall be deemed representative of this system.
"Without delay" implies that the operator, upon determining the limiting condition for operation is being exceeded, takes the next appropriate action to comply with the specification.
3/4.11.2 CASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose rate limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentration of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II, of 10 CFR Part 20
[10 CFR Part 20.106 (b)).
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.
This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of waste oil.
l i
l With regard to footnotes (c) and (g) of Table 4.11.2-1, (1) to determine d
l whether the DOSE EQUIVALENT I-131 concentration in the primary coolant has 1
increased by more than a factor of 3, the iodine-131 analysis performed after l
the transient will be compared to the most recent routine analysis for DOSE l
EQUIVALENT I-131 concentration performed before the transient; and (2) to 1
determine whether the main condenser air ejector noble gas monitor has l
increased by more than a factor of 3, the activity indiciated on the monitors' j
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BRUNSWICK - UNIT 1 B 3/4 11-3 Amendment No. $7, 134
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RADIOACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the requirements of Section II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED ARE/ S will be kept "as low as is reasonably achievable." The ODCH calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evalu-sting Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi-tions. The release rate specification for iodine-131, iodine-133, tr' fum, and radioactive material in particulate form with half-lives gerater than 8 days are dependent on the existing radionuclides pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are:
(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.
Doses due to the incineration of waste oil will be determined in accordance with the ODCM.
3/4.11.2.4 CASEOUS RADWASTE TREATMENT SYSTEM This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The CASEOUS RADWASTE TREATMENT SYSTEM refers to the 30-minute offgas holdup line, stack filter house filtration, and the Augmented Off-Cas-Treatment System.
BRUNSWICK - UNIT 1 B 3/4 11-5 Amendment No. $7,134
4 '.
e ADMINISTRATIVE CONTROLS
- SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) 1 6.
Solidification agent or absorbent (e.g., cement, urea formaldehyde).
1 c.
A list of description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
d.
Any changes made during the reporting period to the PROCESS' CONTROL PROGRAM (PCP) or the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
e.
A summary of radioactivity released from the site by incineration of radioactive waste oil.
l 6.9.1.10 The portion of the Semiannual Radioactive Effluent Release Report to be submitted within 90 days after January 1 of each year shall include the following:
a.
An annual summary of hourly meteorological data collected over the previous calendar year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form'of joint frequency distri direction,andatmosphericstability.gutionsofwindspeed, wind
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b.
An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the station during the previous calendar year.
MONTHLY OPERATING REPORTS 6.9.1.11 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to main steam system safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.
6/ In lieu of submission with the Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data in a file that shall be provided to the NRC upon request.
BRUNSWICK - UNIT 1 6-24 Amendment No. /0,134
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NUCLEAR REGULATORY COMMISSION t
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_ CAROLINA POWER 8 LIGHT COMPANY, et al.
DOCKET NO. 50-324
. BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No.164 License No. DPR-62
'I.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company-(thelicensee),datedJune 23, 1987, as revised March 29, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) 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 Connission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
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(2). Technical Specif1 cations The! echnical Specifications contained in Appendices.A and B, as T
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' revised through Amendment No.:164.- are hereby incorporated in the' U
license. Carolina Power &' Light' Company shall operate the facility g
in accordance with the Technical Specifications
- 3.. ' This license amendment 'is' effective as of the date of its issuance and shall.be implemented'within 60 days of issur.nce.
FOR THE NUCLEAR REGULATORY COMMISSION
. r Original Signed By:
Elinor.G. Adensam, Director Project Directorate II-l' Division of Reactor Projects I/II' 0ffice of Nuclear Reactor Regulation
Attachment:
, Changes to the. Technical Specifications t
. Date of_1ssuance:
June 26,1989 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 164 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-32_4 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
R_emove Pages Insert Pages 3/4 11-12 3/4 11-12 3/4 11-14a 3/4 11-16 3/4 11-16 B 3/4 11-3 8 3/4 11-3 B 3/4 11-5 8 3/4 11-5
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TABLE 4.11.2-1'(Continued)
RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROCRAM TABLE NOTATION (i) Releases from incinerated' oil'may'be discharged.via points other than the main vent (e.g., incinerator).. Release shall.be accounted for based on pre-release grab sample data.
(j)' Samples of waste oil to be incinerated shall be collected from and representative of oil'in liquid form.
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BRUNSWICK - UNIT 2 3/4 11-14a Amendment No.164
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.D RADIOACTIVE EFFLUENTS l.
DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITINC CONDITION FOR OPERATION 3.11.2.3.The dose to a MEMBER OF THE PUBLIC.from. iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to' areas at and beyond
'the SITE BOUNDARY:(see Figure 5.1.3-1) shall be limited to the followings a.
-During any' calendar quarter: Less than or' equal to 15'mrems.to any-
. organ; and b.'.
During any calendar year: Less than or equal to 30 mrems to any organ.
8 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:
a.
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days,'in gaseous. effluents exceeding any of the above
' limits, in' lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defi'es the corrective actions that have been taken to reduce the relecses and the proposed corrective actions to.be taken to assure that subsequent releases will be in compliance with the above limits.
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 for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.
NOTE: See Bases 3/4.11.2.3 BRUNSWICK - UNIT 2 3/4 11-16 Amendment No. $$,164
J e.
s RADIOACTIVE EFFLUENTS BASES 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system with the exception of the auxiliary surge tank. The aux'.liary surge tank is excluded from this specification because the tank and its associated piping are all Seismic Class I.
Since the condensate storage tanks have continuous influent and effluent, stratification should not occur. Samples taken from the operating condensate transfer pump (s) vent or drain shall be deemed representative of this system.
l "Without delay" implies that the operator, upon determining the limiting condition for operation is being exceeded, takes the next appropriate action to comply with the specification.
3/4.11.2 CASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose rate limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B. Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II, of 10 CFR Part 20 (10 CFR Part 20.106 (b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above j
background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.
This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of waste oil.
With regard to footnotes (c) and (g) of Table 4.1I.2-1, (1) to determine whether the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased by more than a factor of 3, the iodine-131 analysis performed after the transient will be compared to the most recent routine analysis for DOSE EQUIVALENT I-131 concentration performed before ;he transient; and (2) to determine whether the main condenser air ejector noble gas monitor has increased by more than a factor of 3, the activity indicated on the monitor's BRUNSWICK - UNIT 2 B 3/4 11-3 Amendment No. $$, 164
r RADIOACTIVE EFFLUENTS BASES-3/4.11.2.3 DOSE - IODINE-131. IODINE-133, TRITIUM, AND RADIONUCLIDES IN j
PARTICULATE FORM
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This specification is provided to implement the requirements of Section II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix _I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release j
rates of the subject materials are required to be consist-a* with the methodology provided in Regulatory cuide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evalu-ating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi-tions. The release rate specification for iodine-131, iodine-133, tritium, and radioactive material in particulate form with half-lives greater than 8 days are dependent on the existing radionuclides pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are:
(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.
Doses due to the incineration of waste oil will be determined in accordance with the ODCM.
3/4.11.2.4 CASE 00S RADWASTE TREATMENT SYSTEM This requirement provides reasonable assurance that the releases of
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radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements-of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR,Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
Until such time as the Augmented Off-Cas Treatment System becomes operational at the Brunswick Steam Electric Plant, the CASEOUS RADWASTE TREATMENT SYSTEM shall refer to the 30-minute offgas holdup line and stack filter house BRUNSWICK - UNIT 2 B 3/4 11-5 Amendment No. $$,164 l
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-e ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued).
'6.
-Solidification agent or absorbent (e.g., cement, urea formaldehyde).
l A list of description of unplanned releases'from the site to c.
UNRESTRICTED AREAS of radioactive materials'in gaseous and liquid
. effluents made during the reporting period.
d.
Any changes made _'during the reporting period to the PROCESS CONTROL' PROGRAM (PCP) or the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2; A summary of radioactivity released from the site by incineration of e.
radioactive waste oil.
6.9.1.10 The portion of the Semiannual Radioactive Effluent Release. Report to be submitted within 90 days after January 1 of each year shall include the-following:
a.
An annual summary of hourly meteorological data collected over'the previous calendar year. This annual summary may be either in the forn of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the-form of joint frequency distri direction,andatmosphericstability.gutionsofwind~ speed, wind
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b.
An assessment of the radiation doses due to'the radioactive liquid and gaseous effluents released from the station during the previous calendar year.
MONTHLY OPERATINC REPORTS 6.9.1.11 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to main steam system safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.
l 6/ In lieu of submission with the Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data in a file that shall be provided to the NRC upon request.
BRUNSWICK - UNIT 2 6-24 Amendment No. $$,164
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