ML20039B111
| ML20039B111 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/09/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039B112 | List: |
| References | |
| NUDOCS 8112220302 | |
| Download: ML20039B111 (25) | |
Text
.
- ' 4%g'o UNITED STATES
- 5y q (',i NUCLEAR REGULATORY COMMISSION g.5' p'. '~
f.n E
WASHINGTON, D. C. 20555 a,
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CAROLINA POWER & LIGHT COMPANY DOCXET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. CPR-71 1.
The Nuclear Regulatary Commission (the Commission) has found that:
A. The application for amendment by Carolina Fower & Light Company dated November 25, 1981, as supplemented October 30, 1981, complies with the standards and requirercents of the Atomic Energy Act of 1954, as amended (the Act), and the Ccanission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations o'f 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense ard 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in tne attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Apcendices A and B, as revised thrcugh Amendment No. 43, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
9112220302 811209' PDR ADOCK 05000324 p
2 13.
This license amendment is effective as of the date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION Lg j l-Thomas A Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 9,1981 i.
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ATTACHMENT TO LICENSE AMENDMENT N0. 43 FACILITY OPERATING LICENSE N0. DPR-71 DOCKET NO. 50-325 Revise the Appendix B Technical Specifications as follows:
J Remove Insert 11 11 2-10 2-10 2-11 2-11 2-12 2-12 2-12a 2-13 2-13 2-19 2-19 2-20 2-20 2-21 2-21 1
2-30 2-30 l
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I l-
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i LIST OF TA3tES D
PACI NO.
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TA3LE _
2-24 to 2-25 Padioactive Liquid Sa:pling and Analysis 3.5-1 2-26to2-2h 2adioactive Caseous Waste Saepling and Analysis 3.5-2 2-28 Liquid vaste System:
3.5-3 Location of Prc:ess and Iffluent Monitors and Sa=plers Required By Technical Specifications 2-29 Caseous vaste water Systed:
3.5-4 14 cation of Process and Iffluent Mrnitors and Samplars laquired by Technical Specifications 2-30 3.5-5 Dose Factors 2-31 Assu=ptions for Limiting Equation for Iodine and 3.5-6 Radioactive Particles 4-11. to 4-13 Z=vironmental Radiological Monitoring Program -
~4.2-1 3runswick Stass Ilectric Plant 4-16 to 4-19 4.2-2 1.nalysis of Sa=ples l
4-20 to 4-22 Environ = ental Radiological Monitoring Program 4.2-3 Su==ary - Brunswick Steam Ilsetric Plant 4-23
(
Typical Mini =un Detectable Concentrations -
4.2-44 Ce-Li Ca==a Spectronetry 4-24 4.2-4b Mini =u: Detectable Concentrations 4-25 Control Stations for 3 SIP Inviron= ental 4.2-5 Radiological Monitoring Program
(
11 Amendhent No. Jg 43 9
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BSEP-1 & 2 20 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.1 Liquid Was te Effluents (cont'd) 3.5.1 Liquid Waste Effluents (cont'd) g.
The maximum radioactivity to be con-e.
The flow rate of liquid radioactive tained in any liquid radwaste tank waste shall be continually measured and that can be discharged directly to recorded during release.
the environs shall not exceed 10 C1, f.
All liquid effluent radiation ronitors i
excluding tritium and dissolved and shall be calibrated at least quarterly antrained fission and activation by means of a known radioettive source L
gases.
which has been calibrated to a National l
h.
If the cumulative release of Bureau of Standards source.
Each radioactive materials in liquid monitor shall also have a functional affluents excluding tritium and test monthly and an instrument check dissolved and entrained fission and prior to making a release.
ectivation gases, exceeds 2.5 Ci per reactor in a calendar quarter, the.
1 licensee shall make an investigation to identify the ca2ses of such releases, def'ne and initiate a program of action to reduce such 3.5.2 Specifications for Gaseous Was ce releases to the design objective Sampling and Monitoring i
levels listed in Section 2.5, and report these actions to the a.
Plant records shall be maintained and Commission within 30 days from the records of the sampling and analysis and of the quarter during which the results shall be submitted in accordance release occurred.
with Section 5.4 of these Specifications.
Estimates of the 2.5.2 Specifications for caseous Waste sampling and analytical error associated
' Discharges with each reported value should be included.
s.
(1)
The release rate limit of noble b.
Gaseous releases to the environment from -
gases from this site shall be:
the two reactor building vents, the two n
4 turbine building vents, and the off gas
{ (DETB (8.0 x 10 )0,g+ DTB (1.3 x 10 )0yg)<1 vent (stack), except as noted in g
g 1-1 Specification 3.5.2.c below, shall be where O - release rate from main stack continuously monitored for gross s
in Ci/sec (elevated release) ra'dioactivity and the flow measured and recorded. Whenever these monitors are Q = release rate from vents in Ci/sec inoperable, grab samples shall be taken y
(ground re' ease) and analyzed daily for gross gaseous th radioactivity.
If these monitors are i = the i individual nuclide.
inoperable for more than seven days, n = total number of nuclides.
these releases shall be terminated or the plant shall be shut down.
Total-body elevated release dose DETB c.
An isotopic analysis shall be made of a g
factor from Table 3.5-5 in representative sample of gaseous mrem /Ci activity, excluding tritium, at the Total-body dose factor from discharge of the steam jet air ejectors DTB t
3 Table 3.5-5 in mrem-m /pCi-yr and' at a point prior to dilution and discharge.
(1) at leas t monthly.
BRUNSWICK - UNIT 1 2-10 Amendment No. J9 43
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l BSEP-1 & 2 y
P 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUITJfENTS 2 5.2 caseous Waste Effluents (cont'd) 3.5.2 Caseous Waste Effluents (cont'd)
(2) The release rate limit of I-131 and (2) within 1 month, following each radioactive materials in particulate refueling outage.
f om with half-lives greater than eight (3) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if the gaseous days, released to the environs as part waste monitors indicate an increase of the gaseous wastes from the site of greater than 50% in the steady shall be:
state fission gas release af ter 6
factoring out increases due to power
[3.7 x 10')0, + [5.8 x 10 ]Oy< 1 changes.
where 0, = release rate from the main d.
All waste gas effluent monitors shall be stack in Ci/sec (as elevat-calibrated at least quarterly by seans ed release) of a known radioactive source which has been calibrated to a National Bureau of O = release rate from the vents Standards source.
Each monitor shall y
in C1/sec (ground release) have a functional test at least monthly and an instrument check at least daily b.
Should any of the conditions of excluding days of no " discharge.
Specifications 2.5.2.b(1) or 2.5.2.b(2) listed below be exceeded, the licensee e.
Sampling and analysis of radioactive shall make an investigation to identify material in gaseous waste, particulate the causes of the release rates, define form, and radiciodine shall be perforned and initiate a program of action to in accordance with Table 3.5-2.
reduce the release rates to design objective levels listed in Sections 2.5.a and 2.5.b for gaseous wastes and report these actions to the Commission within 30 days from the end of the calendar quarter during which the releases occurred.
(1) the calculational method for determin-ing the average release rate of noble gase9 from the site during any 12 consecutive months shall be:
n
[ DAB ((4.0 x 10.2)0,1 + (1.6 x 10 )0d1 5
i+1 and n
5 5
[(DETA(1.9x10)0gDAG(3.2x10)0yg]f1 g
i+1 whare 0,g = release rate of radioisotope i frem the main stack in C1/sec.
0..,
= release rate of radioisotope i from the vents of each reactor in C1/sec.
3RUNSWICK - UNIT 1
,2-11 Amendment No. 29 43
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BSEP-1 li 2
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2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.1 Gaseous Effluents (cont'd)
DAB
= The beta air dose factgr from g
Table 3.5-5 in mrad-e / pct-yr DETAg = Camma air elevated release dose factor from Table 3.5-5 in mrad /Ci DAG
= The gamma air dose facgor from g
Table 3.5-5 in arad-m /pci-yr (2) The calculational method for determin-f.
Calculations for meeting the ing the average release rate from the site of I-131 and radioactive materials in par-requirements of Specifications ticulate form with half-lives greater than 2.5.2.b(1) and (2) shall be performed at eight days during any 12 consecutive months least once every 31 days.
shall be:
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6 7
(6.56 x 10 0 ) + (7.46 x 10 0 ) 11 3
9 (If no teen, child or infant milk consumption)
The ' consumption of milk.must be demon-strated by the Radiological Environ-mental Monitoring Program 4.2.7.
If the Radiological Environmental Monitoring Program determines the consumption of milk by teen, child, or infant the above equation shall be modified by the appropriate coefficient (Dose Factors) of Regulatory Guide 1.109.
c.
Should any of :he conditions of Specifications 2.5.2.c(1) or 2.5.2.c(2) listed below be exceeded, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Sections 2.5.a and 2.5.b for gaseous wastes and report these actions to the Commission within 30 days from the end of the calendar quarter during which the
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releases occurred.
BRUNSWICK - UNIT 1 12 Amendment No. 22 43
BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Geseous Was te Effluents (cont'd) 3.5.2 Caseous Waste Effluents (cont'd)
(1) The calculational method for determinina
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the average release rate of noble gases dur-ing any calendar quarter from the site shall -
be:
n 2
[ DAB [(2.0 x 10 )0s1 + (8.0 x 10')Q ] f1 g
i+1 a
1 [DETA (9.3x10')0,1+DAc (1.6x10 )n )i1 5
1 1
i+1 (2) The calculational method for determining g.
Calculations for meeting the the average release rate of I-131 and radio-requirements of $pecifications active materials in particulate form with 2.5.2.c(1) and (2) shall be performed at half-lives greater than eight days during least once every 31 days.
anycalendarquarterfromthesiteshallbe:l 0
7
[3.26x10 0,]+[3.74x10 g] 11 (if no teen, child or infant milk consumption)
The consumption of milk.must be demonstrated by the Radiological Environmental Monitoring Program 4.2.7.
If the Radiological Environmental Moni-toring Program determines the consumption of milk by teen, child, or infant, the above equation shall be modified by the appropriate coefficients (Dose Factors) of Regulatory Guide 1.109.
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BRUNSWICK - UNIT 1 2-12a Amendment No. 43
BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILI).NCE REQUIREMENTS 2.5.2 Caseous Was te Effluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd) d.
Whenever the augmented off gas (A0G) h.
The operability of each automatic system is out of service, at least one isolation valve in the gaseous radwaste' of the condenser / air ejector off gas discharge line shall be demonstrated monitors listed in Table 3.5-4 shall be quarterly.
operating and set to alarm and capable to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.5.2.a above.
o.
If both condenser / air ejector off gas monitors are incapable of initiating automatic closure of tbc waste gas discharge valves, a shutdown shall be initiated so tha t the reactor will be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The augmented off gas (A0G) process monitor shall be operable whenever a release is being made from the A0G system storage tanks.
If the augmented off gas system is out of service and the air ejector off gas monitors are inoperative, a reactor shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
f.
If the release rate from the site of noble gases in not:
DAB ((2.0 x 10 )0,1 + (8.0 x 10')0 g) 11 2
y 1+1 n
((DETA1(9.3 x 10 )O,g+DAG (1.6 x 10 )0d]II g
i+1 BRUNSWICK - UNIT 1
'2-13 Amendment No.19 43
CASEOUS WASTE EFFLUENTS
'Ih2 'relsc03 ef r:diccctive mataricls in g sscus waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20, and should be as low as reasonably achievable in accordance with the requirements of 10 CFR Part 50.36.
These specifications provide reasonable assurance that the resulting annual air dose from this sita due to gamma radiation will not exceed 20 mrad, and an annual air dose due to beta radiation will not exceed 40 mrad from noble gases, and that the annual dose to any organ of an individual from I-131 and particulates with half lives greater than 8 days will not exceed 30 mrea.
Table 3.5-5 provides dose factors for DTB, DAB and DAG from Table B-1 in Regulatory Guide 1.109.
Values for DETB and DETA in Table 3.5-5 are based L
on the NRC meandering plume model as described in Appendix F of Regulatory Guide 1.109.
A continuous release rate of gross radioactivity in the amount specified in 2.5.2.a(1) will not result in offsite annual doses above background in excess of the limits specified in 10 CFR Part 20.
The specified release rate limits restrict, at all times,.the corresponding gamma and beta dose rates above background to an individual at or-beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or
~e equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an 1
BRUNSMICK - UNIT 1 2-19' Amendment No.19 43
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infant via the cow-mLik-inf ant pathway. to less than or equal to 1500 mrem /
year for the nearest cow to the plant.
For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors and critical pathways for I-131 and radioactive material in particulate form with half-lives greater than eight days. The calculations consider site meteorology for these releases.
Specification 2.5.2.b establishes upper site levels for the releases of noble gases, iodines and particulates with half lives greater than eight days, and iodine-131 at the design objective annual quantity during any period of 12 consecu-tive months. Since BSEP does not have an A0G that has been demonstrated to be con-I tinuously operable, the content of these limiting conditions for operation assumes that the design objectives of 2.5a and b for gaseous wastes can be met.
This specification does not limit the instantaneous gaseous radioactive release rate, but permits the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which =ay temporarily result in higher releases than the objectives and yet remain below annual design objective releases.
The equation limiting radioactivity releases was established based on on-site meteorological data
^
and methodology of Regulatory Guides 1.109 and -1.111, and methods provided in Meteorology and Atomic Energy (1968).
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For iodine-131 and radioactive material in particulate form with half-lives greater than eight days, the critical location for ground releases is the SSE sector distance of 1464 meters where X/O is 6.5 x 10-6 sec/m for the dose due 3
to inhalation.
The critical location for elevated releases is the SSE sector at a distance of 1464 meters where the X/O is 3.45 x 10-8 sec/m for the dose,
3 due to inhalation. The assumptions for the grass-cow-milk-thyroid chain are i
lis ted in Table 3.5-6.
The grass-cow-milk-thyroid chain is controlling.
1 BRUNSWICK - UNIT 1 2-20 Amendment No. Ig 43 x
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The repsreing requirteents'ef 2.5.2.b and 2.5.2.c dalin ato that the causa be identified whenever the release of gaseous effluents exceeis the annual objective during any 12 consecutive months or one-half the annual objective quantity during any calendar quarter, and describe the proposed program of action to reduce such release rates to the design objectives.
Specifications 2.5.2.d and 2.5.2.e assure compliance with NRC general design criterion 64.
The 24-hour period will allow an investigation of several hours to determine the cause,of the monitor inoperability and possible repair prior to initiating the hot-shutdown.
Specification 2.5.2.f is to monitor the performance of the core. A sudden increase in the activity levels of gaseous releases may be the result of defective fuel. Since core performance is of utmost importance in the resulting doses, a report must be filed -within 10 days following the specified i
increase in gaseous radioactive releases.
Specification 2.5.2.g requires that the primary containment atmosphere receive creatment for the removal of gaseous iodine and particulates prior to its release.
Specification 2.5.2.h requires that hydrogen concentration in the system shall be monitored at all times during A0G operation to prevent buildup of combustible concentrations.
The sampling and monitoring requirements given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64.
These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive wastes released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of Section 5.4 of these Technical Specifications and in conformance with Regulatory Guide 1.21.
On the basis of such reports and any additional information the Commission. may obtain from the licensee or others, the Commission may from time to time require the licensee to take such' action as the Commission deems appropriate.
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BRUNSWICK - UNIT 2 1 2-21 Amendment No. U 43
' Tabla 3.5-5.
DOSE FACTORS ISOTOPE DETB DTB DAB DETA DAG 3
mrem /Ci mrem-m mrad-m3 mrad /Ci mrad-m3 pCi-yr pC1-yr pCi-yr Kr-83m 1.0 x 10-9 7.6 x 10-8 2.9 x 10-4 6.0 x 10-3 1.9 x 10-5 Kr-85 6.0 x 10-7 1.6 x 10 3 2.0 x 10-3 7.5 x 10-7, 5
5 Kr-85m 4.5 x 10 4 1.2 x 10-2.0 x 10-3 4.5 x 10-5 1.7 x 10 3 5
1.2 x 10-2.0 x 10 4 5.9 x 10-3 1.0 x 10-2 2.0 x 10-4 6.2 x 10-3 Kr-87 Kr-88 6.0 x 10-1.5 x 10-2 2.9 x 10-3 6.0 x 10-4 1.5 x 10-2 Kr-89 2.7 x 10-4 1.7 x 10-2 1.1 x 10-2 2.7 x 10-4 2
Xe-131m 1.1 x 10-5 9.1 x 10-5 7.8 x 10 3 2.7 x 10-4 1.7 x 10 2 Kr-90 2.7 x 10-4 1.6 x 10-2 3
1.6 x 10-Xe-133 9.0 x 10 2.9 x 10-4 1.1 x 10 3 1.2 x 10 1.6 x 10-4 1.0 x 10-5 3.5 x 10-4 Xe-133m 8.2 x 10-6 2.5 x 10-4 1.0 x 10 3 9.5 x 10-6 3.3 x 10-4 1.5 x 10-Xe-135 7.0 x 10-5 1.8 x 10-3 2.5 x 10-3 8.0 x 10 4 1.9 x 10-3 5
Xe-135m
'1.1 x 10-4 3.1 x 10-3 7.4 x 10-4 1.3 x 10-3.4 x 10-3 5
5 Xe-137 3.5 x 10 4 g,4 x 13-3 1.3 x 10-2 3 5 x'10 4 1.5 x 10-3 Xe-138 3.0 x 10 4 8.8 x 10-3 4.8 x 10-3 3.3 x 10 4 9.2 x 10-3 Ar-41 3.7 x 10-8.8 x 10-3 3.3 x 10-3 4.0 x 10-9.3 x 10-3 t
BRUNSWIQs - UNIT 2 1 2-30 Amendment No. 43
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UNITED STATES
[ j ~, ",( [~,j NUCLEAR REGULATORY COMMISSION
/.. E WASHINGTON, D. C. 20555
- '\\
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CAROLINA POWER & LIGHT COMPANY DOCXET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company dated November 25, 1981, as supplemented October 30, 1981, 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 (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 Commission's regulations; D.
The issuance of thi 3 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 Commission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-i ifications 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:
l l
(2) Technical Scacifications The Technical Scecifications contained in Appendices A and B, as revised through Amendment No. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
A
_2-1 J
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 9, 1981 4
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l ATTACHMENT TO LICENSE AMENDMENT N0. 66 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix B Technical Specifications as follows:
Remove Insert 11 ii 2-10 2-10 2-11 11 2-12 2-12:
2-12a 2-13 2-13
- j 2 2-19 2-20 2-20 2-21 2-21 2-30 2-30 i
I.
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LIST OT TA3 TIS 9
PACE NO.
?)
TA3LI_
f,...
c,7 2-24 to 2-25 3.5-1 Radioactive Liquid Sa=pling and Analysis 2-26 to 2-27 3.5-2 Radioactive Caseous Waste Sa=pling and Analysis 2-28 3.5-3 Liquid Waste Systes:
Incation of Process And I.ffluent Monitors and Samplars Raquired By TecW N 1 Specifications 2-29 3.5-4
. Caseous vasta vatar Syster":
Iocation of Process and Effluent Monitors and Samplars Required by Te.hnical Specifications 2-30 3.5-5 Dose Factors 2-31 3.5-6 Assumptions for Limiting Equation for Iodine and Radioactive Particien 4-11 to 4-15 4.2-1 Enviroc= ental Radiological Monitoring P togram -
3runswick Staa= Ilectric Plant 4-16'to 4-19 i
4.2-2 Analysis of Sa=ples 4 20 to 4-22 l,_
4.2-3 Z:viron= ental Radiological Monitoring Progra=
Su=ary - 3:u:urvick Steam Electric Plant l'
4-23 4.2-4a Typical Mini =:: Detectable concentrations -
i.
Ge-Li Ca==a Spectr netry 4u24 i !
4.2-4b Mini =u= Detectable Concentrations 4-25 4.2-5 Cc trol Stations for BSIP I:viren= ental Radiological Monitori=g Progra=
I s
11' Amendment N6.,43 66
+
BSEP-1 & 2 q
2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS i
I i
2.5.1 Liquid Waste Effluents (cont'd) 3.5.1 Liquid Was te Effluents (cont'd) i i
-g.
The maximum radioactivity to be con-e.
The flow rate of liquid radioactive tained in any liquid radwaste tank
~ waste shall be continually measured and 4
that can be discharged directly to recorded during release.
the enviroas shall not exceed 10 C1, f.
All liquid effluent radiation monitors 3
excluding tritium and dissolved and shall be calibrated at least quarterly i
. entrained fission and activation by means of a known radioactive source gases.-
which has been calibrated to a National h.
If the cumulative release of Bureau of Standards source. Each radioactive materials in liquid monitor shall also have a functional l
effluents excluding tritium and test monthly and an instrument check i
dissolved and entrained fission and prior to making a release.
l activation gases, exceeds 2.5 Ci per reactor in a calendar quarter, the i
licensee shall make an investigation to identify the causes of such j
releases, define and initiate a i
program of action to reduce such 3.5.2 Specifications for caseous Waste releases to the design objective Sampling and Monitoring j
levels listed in section 2.5, and l
reporr these actions to the a.
Plant records shall be maintained and i
Commission within 30 days from the records of the sampling and analysis end of the quarter during which the results shall be submitted in accordance release occurred.
with Section 5.4 of these Specifications.
Estimates of the 2.5.2 Specifications for Gaseous Waste sampling and analytical error associated Discharges with each reported value should be included.
4 l
a.
(1) The release rate limit of noble b.
Gaseous releases to the environment from gases from this site shall be:
the two reactor building vents, the two n
3 4
turbine building vents, and the off gas
[ [DETB (8.0 x 10 )Q,g+ m (1.3 x 10 )0yg)f,1 vent (stack), except as noted in g
g l
i+1 Specification 3.5.2.c below, shall be i
whers 0, = release rate from main stack continuously monitored for gross in C1/sec (elevated release) radioactivity and the flow measured and i
recorded. Whenever these monitors are 0, - release rate from vents in C1/see inoperable, grab samples shall be taken j
(ground release) and analyzed daily for gross gaseous i
radioactivity.
If these monitors are
)
i = the i individual nuclide.
inoperable for more than seven days, th i
n - total number of nuclides.
these releases shall be terminated or the plant shall be shut down.
Total-body elevated release dose c.
An isotopic analysis shall be made of a DETB g = f ac tor f rom Table 3. 5-5 in representative sample of gaseous mrem /Ci activity, excluding tritium, at the DTB
= Total-body dose factor from discharge of the steam jet air ejectors g
3 Table 3.5-5 in mrem-m /pci-yr and at a point prior to dilution and discharge.
t (1) at least monthly.
BRUNSWICK - UNIT 2
,2-10 Amendment No. g3 66
)
BSEP-1 & 2
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l 2.0 ENVIRONMENTALPROTECTIONCONDITIbNS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Casaous Waste Efiluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd)
(2) The release rate limit of I-131 and (2) within 1 month, following each radioactive materials in particulate refueling outage.
form with half-lives greater than eight (3) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if the gaseous days, released to the environs as part waste monitors indicate an increase of the gaseous wastes from the site of greater than 50% in the steady shall be:
state fission gas release af ter 4
6 factoring out increases due to power
[3.7 x 10 ]Q, + [5.8 x 10 ]O, i 1 changes.
where Q, = release rate from the main d.
All waste gas effluent monitors shall be stack in Ci/sec (as elevat-calibrated at least quarterly by means ed release) of a known radioactive source which has been calibrated to a National Bureau of Q = release rate from the vents Standards ' source. Each monitor shall y
in C1/sec (ground releasc) have a functional test at least monthly and an instrument check at least daily b.
Should any of the conditions of excluding days of no discharge.
Specifications 2.5.2.b(1) or 2.5.2.b(2) listed below be exceeded, the licensee e.
Sampling and analysis of radioactive shall make an investigatien to identify material in gaseous waste, particulate the causes of the release: tates, define form, and radioiodine shall be perfor.ned and initiate a progra= of action to in accordance with Table 3.5-2.
reduce the release rates to design objective levels listed in Sections 2.5.a and 2.5.b for gaseous wastes and report these actions to the Commission within 30 days from the end of the calendar quarter during which the releases occurred.
(1) The calculational method for detemin-l ing the average release rate of noble gases from the site during any 12 consecutive months shall be:
2 5
DAB ((4.0 x 10 )0,1 + (16 x 10 )0yg]Il g
i+1 and
[DETA(1.9x10h,g6 (3.2 x 10 b oyg]il g
1 i+1 whare 0,1 = release rate of radioisotope i from the eain stack in Ci/sec.
Qyg = release rate of radioisotope i from the vents of each reactor in Ci/sec.
BRUNSWICK - UNIT 2 2-11 A=endment No. 43 66
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BSEP-1 & 2 u
- I 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous Waste Efiluents (cont'd) 3.5.2 Gaseous Effluents (cont'd)
= The beta air dose factgr from DAB g
Table 3.5-5 in mead a /pci-yr DETAg,= Gamma air elevated release dose factor from Table 3.5-5 in 3 rad /Ci DAG
= Ihe gamma air dose facgor 'from g
Table 3.5-5 in mrad-a-/pc' -
(2) The calculational method
.2cer-l f.
Calculations for " meeting the mining the average release rate from the requirements of Specifications site of I-131 and radioactive materials 2.5.2.b(1) and (2) shall be performed at in particulate form with half-lives least once every 31 days.
greater than eight days during any 12 consecutive months shall be:
6 7
(6.56 x 10 0s) + (7.46 x 10 0 ) f,1 9
(If no teen, child or infant milk consumption)
The consumption of milk must be demon-strated by the Radiological Environ-mental Monitoring Program 4.2.7.
If the Radiological Environmental Monitoring Program determines the consumption of milk by teen, child, or infant the above equation shall be modified by the appropriate coefficient (Dose Factors) cf Regulatory Guide 1 109.
c.
Should any of the conditions of Specifications 2.5.2.c(1) or 2.5 2.c(2) listed below be exceeded, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Sections -
2.5.a and 2.5.b for gaseous vastes and report these actions to the Commission within 30 days from the end of the calendar quarter during which the releases occurred..
l BRUNSWICK - UNIT 2 2-12 Amendment No. 46 66
BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIFJtMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.2 Caseous Waste Effluents (cont'd)
(1) The calculational method for determin-l ing the average release rate of noble gases during any calendar quarter from the site shall be:
n 2
[ DAB ((2.0 x 10 )0,g + (8.0 x 10 )Qg) f1 g
i+1 n
[(DETA(9.3x10)Q,g+DAG(1.6x10)Qg]il g
g 1+1 (2) The calculational method f :r determin-g.
Calculations for meeting the ing the average release rate of I-131 and requirements of Specifications radioactive materials in particulate form 2.5.2.c(1) and (2) shall be performed at with half-lives greater than eight days least once every 31 days.
during any calendar quarter from the site shall be:
[
6 (3.26x10 0,)+(3.74x10 O ) 11 y
(if no teen, child or infant milk consumption)
The' consumption of milk must be demonstrated by the Radiological Environmental Monitoring Program 4.2.7.
If the Radiological Environmental Moni-toring Program determines the consumption of milk by teen, child, or infant, the above equation shall be modified by the ' appropriate coefficients (Dose Factors) of Fagulatory Guide 1.109.
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j BRUNSWICK - UNIT 2 2-12a
/.mendment No. 66
BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Caseous Waste Effluents (cont'd) 3.5.2 caseous Waste Effluents (cont'd) d.
Whenever the augmented off gas (A0G) h.
The operability of each autamatic system is out of service, at least one isolation valve in the gaseous radwaste of the condenser / air ejector.off gas discharge line shall be demonstrated monitors licted in Table 3.5-4 shall be quarterly, operating and set to alarm and capable to initiate tha automatic closure of the waste gas discharge talve prior to exceeding the limits specified in l
2.5.2.a above.
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o.
If both condenser / air ejector off gas monitors are incapable of initiating automatic closure of the vaste gas discharge valves, a shutdown shall be initiated so that the reacter will be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The augmented off gas (A0G) process monitor shall be operable whenever a release is being made from the A0G system storage tanks.
If the augmented off gas system is out of service and the air ejector off gas monitors are inoperative, a reactor shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 24 tours.
f.
If the release rate from the site of noble gases is not:
fDAB[(2.0x10)Q,1+(8.0x10')0yg)11 2
g
.1+ 1 or i+1[DETA (9.3 x 10')0,1+DAG (1.6 x 10 )0yg]Il 5
g l
DRUNSWICK - UNIT 2 2-13 Amendment No. 43 66 l
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, CASEOUS WASTE EFFLUENTS - The rela:sa cf rcdiozetiva matsricis in g:secus waste effluents to unrestricted areas shall not exceed the concentration
'l limits specified in 10 CFR Part 20, and should be as low as reasonably achievable in accordance with the requirements of 10 CMt Part 50.36. These specificatiens provide reasonable assurance that the resulting annual air dose from this site due to gamma radiation will not exceed 20 mrad, and an annual air dose due to beta radiation will not exceed 40 mrad from noble gases, and that the annual dose to any organ of an individual from I-131 and particulates with half-lives greater than 8 days will not exceed 30 exes.
Table 3.5-5 provides dose factors for DTB, DAB and DAG from Table B-1 in Regulatory Guide 1.109.
Values for DETB and DETA in Table 3.5-5 are based on the NRC meandering plume model as described in Appendix F of Regulatory lu
. Guide 1.109.
A continuous release rate of gross radioactivity in the amount specified in 2.5.2.a(1) will not result in offsite annual doses above background in excess of the limits specified in 'O CFR Part 20.
The specified release rate limits restrict, at all times, the corresponding gasna and beta
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dose rates above background to an individual at or beyond the site boundary.tg less than or equal to 500 :nrem/ year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate linits also restrict, at all times, the corresponding thyroid dose rate acove background to an BRUNSWICK - UNIT 2 2-19 Amendnent No. 43 66
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infant via the cow-silk-infant pathway to less than or equal to 1500 mres/
year for the nearest cow to the plant.
For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors and critical pathways for I-131 and radioactive material in particulate form with half-lives greater than eight days. The calculations consider site meteorology for these releases.
Specification 2.5.2.b establishes upper site levels for the releases of noble -
,l gases, iodines and particulates with half lives greater than eight days, and iodine-131 at the design objective annual quantity during any period 12 con-f i
secutive months.
Since BSEP does not have an A0G that has been demonstrated to be continuously operable, the content of these limiting conditions for operation assumes that the design objectives of 2.5a and be for gasecus wastes can be met.
This specification does not limit the instantaneous gaseous radioactive release rate, but permits the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in higher releases than the objectives and yet remain below annual design objective releases.
The equation limiting radioactivity releases was established based on on-site meteorological data and methodology of Regulatory Guides 1.109 and 1.111, and cethods provided in Meteorology and Atomic Energy (1968).
For iodine-131 and radioactive material in particulate forns with half-lives greater than eight days, the critical location for ground releases is the SSE X/O is 6.5 x 10-6,,cy,3 for the dose due sector distance of 1464 meters where to inhalation.
The critical loca. tion for elevated releases is the SSE sector 3
X/O is 3.45 x 10~8 sec/m for the dose, at a distance of 1464 meters where the due to inhalation. The assumptions for the grass-cow-milk-thyroid chain are listed in Table 3.5-6.
The grass-cow-milk-thyroid chain is controlling.
l BRUNSWICK - UNIT 2 2-20 Amendment No. 43 66
- The r: porting requirements cf 2.5.2.b and 2.5.2.c delinasta. that the cauto be identified whenever the release of gaseous effluents exceeds the annual objective during any 12 consecutive months or on-half the annual objective quantity during any calendar quarter, and describe the proposed program of action to reduce such release rates to the design objectives.
Specifications 2.5.2.d and 2.5.2.e assure compliance with NRC generr.1 design criterion 64.
The 24-hour period will allow an investigation of -several hours to determine the cause of the monitor inoperability and possible repair prior to initiating the hot-shutdown.
Specificat' ion 2.5 2.f is to monitor the performance of the core. A sudden increase in the activity levels of gaseous releases may be the result of defective fuel.
Since core performance is of utmost importance in the resulting doses, a report must le filed within 10 days following the specified increase in gaseous radioactive releases.
Specification 2.5.2.g requires that the p$1 mary containrent atmosohere receive treatment for the removal of gaseous iodine and particulates prior to its release.
Specification 2.5.2.h requires that hydrogen concentration in the system shall be monitored at all times during A0G operation to prevent buildup of combustible concentrations.
The sampling and monitoring requirements given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes are properly controlled and monitored in conformance with the requireunts of Design Criteria 60 and 64.
These requirements provide the date for the licensee and the Commission to evaluate the plant's performance relative to raf.ioactive wastes released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of Section 5.4 of these Technical Specifications and in conformance with Regulatory Guide 1.'21.
On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to. time require the lic'ensee to take such'~
action as the Commission deems appropriate.
l BRUNSWICK - UNIT 2 2-21 Amendment No. U 66 e
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T:blo 3.5-5 DOSE FACTORS i
ISOTOPE DETB DTB DAB DETA DAG 3
3 mres/Ci mrem-3 mrad-m mrad /Ci stad-33 pCi-yr pCi-yr pCi-yr Kr-83m 1.0 x 10-9 7.6 x 10-8 2.9 x 10-4 6.0 x 10-8 1.9 x 10-5 Kr-85 6.0 x 10-7 1.6 x 10-5 2.0 x 10-3 7.5 x 10-7 1.7 x 10-5 Kr-85m 4.5 x 10-5 1.2 x 10-3 2.0 x 10 2 4.5 x 10 '5 1.2 x 10-3 3
Kr-87 2.0 x 10-4 5.9 x 10-3 1.0 x 10 3 2.0 x 10 4 6.2 x 10-3 Kr-88 6.0 x 10-4 1.5 x 10-2 2.9 x 10 2 2.7 x 10-'
I.7 x 10 2 6.0 x 10-1.5 x 10-2 Kr-89 2.7 x 10-4 1.7 x 10-2 y,g x to-2 Kr-90 2.7 x 10-4 1.6 x 10-2 7.8 x 10-3 2.7 x 10 5 1.6 x g Xe-131m 1.1 x 10-5 9,t x 19-5 1.1 x 10 3 1.2 x 10 5 1.6 x 10-'
1.0 x 10 3 9.5 x 10-6 3.3 x 10 3 6
3.5 x 10-
1.0 x 10-Xe-133m 8.2 x 10 2.5 x 10'3 1 5 x 10-5 Xe-135 7.0 x 10 4 1.8 x 10-2.5 x 10-3 8.0 x 10 '5 1.5 x 10-Xe-135m 1.1 x 10-3.1 x 10-3 7.4 x 10-'2 1.3 x 10-3.4 x 10-3 Xe-137 3.5 x 10-5 1,,, x 19-3 3,3 x 19-3.5 x 10-5 1.5 x 10-3 Xe-138 3.0 x 10-4 8.8 x 10-3 4.8 x 10-3 3.3 x 10-
9.2 x 10-3 Ar-41 3.7 x 10-4 8.8 x 10-3 3.3'x 10-3 4.0 x 10-9.3 x 10-3
)
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BRUNSWICK - UNIT 2 2-30 Amen'd:nent No. 66 r
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