ML20072H741
| ML20072H741 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/11/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20072H745 | List: |
| References | |
| DPR-62-A-079, DPR-71-A-054 NUDOCS 8303290558 | |
| Download: ML20072H741 (30) | |
Text
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g NUCLEAR REGULATORY COMMISSION
%*..},j WASHINGTON. D. C. 20585 g
CAROLINA POWER & LIG11T CONDANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPE dTING LICENSE Amendment No. 54 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Carolina Power & Light Company (the licensee) dated April 21, 1981 and February 19, 1982 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and re-gulations set forth in 10 CFR4hapter I; B.
The facility will operate in confamity 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8303290558 830311 PDRADOCK05000g
I a
2y 2.
Accordingly, the license is amended by deleting paragraphs 2.E.a and,'
2.E.b and by changes to the Technical Specifications as indicated in -
the attachment to this license amendment. Paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
2, Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificaticas.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~~
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 11, 1983 O
e 4
l f
s n
i ATTACHMENT TO LICEWS AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the followkng pages of the Appendix B Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Insert Rem ve o
i 1
111 111 2-1 2-1 2-2 2-3 2-4 2-5 2-6 2-6 2-15 2-15 2-15a 2-16 2-16 4-1 4-1 4-2 4-3 4-4 4-5 4-Sa 5-4 5-4 5-5 5-5 5-Sa 5-5b 5-6 5-6 5-7 5-7 6-1 6-1 6-2 6-3 6-4 6-5 6-6 6-7 l'
Figure 3.3-1
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3EmiSECT. 5"'Tui ELI C ?! AIC, CC*S 1 f 2 w :.
EN73CIFTX" IC22CCAL 5?It :.C.1'" C iS
- A3LI 0F C::!CI2C5 sze-CN
?ACI NO.
1.0 Defd d=1==s
'l-1 to 1-3 2.0 E=71
s' ? ::ee:1:n C==di-h 2-1 2.1 ner-21-Dele ted 2-1 2.2 Cs d -e1 -Dele ted 2-1 2.3 Hydre"'*-
2-6 2.4 Ife:a==:10g7 2-7 2.5 Zad1:ac:ive Discharges 2-8 to 2-14a 3.0 Sc=ve " s--a Requirs=es:s 2-1 d
3.1 "he==21 - Deleted 2-1 3.2 Cha d al-Deleted 2-1 3.3 Eydra"'d-2-6 3.4 Ife:ac: elegy 2-7 3.5 Radica :1ve Discha.ges 2-8to2-14al 3ases 2-15.c 2-23 4.0 Z vi.e._.es:2.1 Sc v=d " '- e 4.1 Nonradiological Monitoring 4-1 4.2 Radiologd- ' I=vt.
en 21 M:=.d:::1=3 ?:cg z=
4-6 to 4-10 5.0 u-d derra.d_ve C:====1s 5-1 to 5-8 6.0 Special Sc v=d s ce and S=.'.d7 Ac 1vi:1es-Deleted 6-1 6.1 id.arsh P:cdue:ivity-Deleted 6.2 Deleted 6.3 Dele:ed 6.4 Sal: Depes1 1== Meul.cring-Deleted figures
.b Amendment ~No.
54 1
1
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{Q*
LIST.OF TIGURES
- FIGURE NO.
TITLZ
[*]
/
4.2-1A I4 cation of Radiological Environmental Monitoring Staticus Location of Radiological E=vironmental Moni:oring Stations 4.2-13 5.1-1 Management Organization Chart
,(
Amendme'nt No.
54 111
i BSEP-1 & 2 2.0 ENVIRONMENTAL PROTICTION CONDITICNS 3.0 SURVEILLAMCI REQUIREMENTS General: During a national power emergency, regional emergency, reactor emergency, when the health, safety, or welfare of the public may be endangered by the inability of Carolina Power &
Light Company to supply electricity, the protection 14 dts provided in these en-vironmental technical specifications shall be inapplicable. During such emergencies however, the protection limits shall not be exceeded except as is necessitated by the emergency.
Certain Environmental Protection Conditions and Surveillance Require-ments are specified in the effective National Pollutant Discharge Elimina-tion System (NPDES) p.ermit issued by the State of North Carolina, Department of Natural Resources and Community Development, Division of Environmental Management. This agency is responsible for regulation of matters involving thermal discharges, chlorine, normal-izer tank pH, and piezometric head.
2.1 THERML 3.1 THERMAL Deleted Deleted 2.1.1 Maximum Temperature Rise Deleted 3.1.1 Maximum Temp'erature Rise Deleted 2.1.2 Rate of Change of Discharge Temperature 3.1.2 Rate of Change of Discharge Deleted Temperature Deleted 2.1.3 Heat Treatment of Circulating Water System 3.1.3, Heat Treatment of Circulating Deleted Water System Deleted 2.2 CHEMICAL l
Deleted 3.2 CHEMICAL Deleted 2.2.1 Chlorine' Deleted 3.2.1 Chlorine Deleted 2.2.2 Other Chemicals
~
Deleted 3.2.2 Other Chemicals Deleted 2.2.3 Hydrogen Ion Deleted 3.2.3 Hydrogen Ion Deleted Amendment No. 54 NOTE: Pages 2-2 through 2-5 have been deleted.
2-1 w-'
=
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~;
j BSEP-1 & 2
~
7 I)g.
2.0 ENVIR0!OIENTAL P20*ECTION CONDITICNS 3.0 SURVEILLANCE REQUIRC.'ENTS 2.3 _HT_DRAULIC 3.3 HYDRAULIC 2.3.1 Water Level in the Discharte Canal 3.3.1 Water Level in the Discharte Canal Obiective: To minimize impact Specification: Water level of the discharge canal on the local in the discharge canal near the groundwater supply.
plant shall be monitored daily.
Specification: Water level in the discharge canal shall nor= ally be maintained between +3.5 feet msl
/
and +5.5 feet msl at the discharge voir. These limits may be exceeded as required either for plant maintenance or as a result of natural conditions such as heavy rainfall which is beyond the control of plant personnel..
. 3.2 Pferecee-4e vend 3.3.2 Pier ~ nee-da u-ad 1
Deleted Deleted l
/
i h
l Amendment No.
54 24
BASES:
a 2-15 NOTE: Page 2-15a has been deleted.
Amendment No. 54 l
1 g
.g Specifica:icus 2.3.I and 3.3.1 =ain=ain :Se discharge canal va:e level within a range cha: vill =ininize che po:encial for upuelling and downvelling effec:s on :he aquifer.
Specifica:1on 2.4 provides :he me:aorological parace:ars which ara =easured a:
he plan: vill p cvide che i$fer=a:1on necessary :o es i=a:e po:en:ial radia:1:n
- doses :o the public f cm rou:ine or acciden:al releases of radioactive sa erials I
- s de a:=csphere and nee: :he require =en:s of subparagraph 50.36a (a) (2) of 10Cn Par: 50 and Appendices D and ? to 10Cn 50.
RADICAC-"TI DISCF.A?.CIS IICUID *.7AS I I??tt*ITJS - The release of radi:ac:ive =acerial in liquid ef'luen:s :o unres::ic:ed areas shall no: exceed :he concen: 2:ica id-d:s specified in 10 Cn ?ar:
20 and shculd be as lov as prac:1 cable in aces: dance vi:h :he require =en:s of 10 Cn Par: 50.36a. These specifica:icns provide reasonable assuranca cha: de resul:1ng
. annual dose to :he o a1 body or any cegan of an individual in an us:ss::1cted area vd no: exceed 5 sre=.
A: the same ti=e, these specifica:1:ns per=1: the flaxibili:y of opera:1cn, cc=pa:1ble vi:h censideraticus of heal d and safscy, :s assure :ha: :he public is p cvided a dependable source of power under unusual opera:1:3 condi:1cus 5 eases higher :han :he design objective' levels but which =ay e porarily :esul-d-
-=
sed vi:hi: de c=ncen::a:1:n
'd d:s specified in 10 C a Par: 20.
I: is expec:ed
- hat by using this opera:icnal flexibili:y under unusual opera ing condizions, and exerting every effer: :o keep levels of radicac:ive naterial is liquid was:es as low as prac:icable, che annual releases vill sec exceed a s=all. frac:ica of :he cencen::a-
- 1cn 1d 4:s specified in 10 C n Par: 20.
The desig. cbjec:1ves have been developed based 'on eperacing experience, :aking s
D) in:o accoun: a c:=hination of variables including defective fuel, primary sys:em leakage, and de perf:r=ance of :he vari =us vas:e :: eat =en: systens, and are consisten: vi d Appendix I :o 10 C a Par: 30.
Amendment No. 54 p--
,3 e,--
-n m
o 4.0 Environmental Monitoring 4.1 Nonradiological Monitoring The nonradiological biological monitoring requirements are specified in the effective National Pollutant Discharge Elimination System (NPDES) permit issued by the State of North Carolina, Department of Natural Resources and Community Development, Division of Environmental Manage-ment.
This agency is responsible for regulation of matters involving water quality and aquatic biota.
i l
NOTE: Pages 4-2 through 4-Sa have been deleted.
4-1 Amendment No. 54
Escoria of changes as describcd in See:1on 5.4.2.cCLL
' =, '
c.
and (2).
5.4.1.2 A separata annual envir=== ental radiological report covering the previous 12 : months of opera:Lon shall be subt:ittad within 90 days af ter January 1 of each De first such report shall be submitted for year.
the 12-month calendar period during which. initial cri:1cali:7 is achieved. Data not available for inclusion in the report will be submi::ad as soon as Amendment No.
54 3-4
e possible in a supplementary report. The report shall g}
include the following:
a.
Summary records of monitoring requirements surveys and samples.
b.
Analysis of environmental data.
r 5.4.2 Non-Routine Resorts Radiological Reports as Violations of an Environmental Technical Specification, including unplanned release of radioactive materials of significant quantities from the site shall be reported to the Director of the appropriate regional office (copy to the Director of Nuclear Reactor Regulation) within 14 days of an environmental event. The written report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact; (b) de-scribe the cause of the event; and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the event and to prevent similar events involving similar components or systems. The environmental protection conditions for radiological discharges are described in Section 2.5.
1N i
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5-5 i
Amendment No.
54
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Tha radiological environments 1 monitoring is dnacribsd in Srction 4.2.
Analyses of environmental samples which exceed the larger of either the control station value (Table 4.2-5)
~
or the minimum detection
'd
't by a f actor of 10 or more for that same sample type and time period vill be iden-tified and if determined to be attributable to the opera-tion of the Brunswick Plant, a written report shall be sub-mitted to Director of the appropriate regional office (copy to the Director of Nuclear Reactor Regulation) within 30 days af ter confirmation.* The test for exceeding the guide value vill be a T test at 99.5% confidence. The test vill be considered positive when:
I - (I 10) > T99.5. /c 2+g 2 (100) i e
i e
where:
~
- 1
- ** * (
- 1 T99.5%
...i.
G I = value obtained at station i X = either value obtained at control station or
~4n4== detection
'd** t (mdl), whichever is larger.
i o = standard deviation of station i value g
.., = sta.d.rd d.,iacon.f cont =a -aco.
l
- A confirmatory reanalysis of the original, a duplicate or a new sample may be desirable, as appropriate. The results of the confir=atory analysis shall-be jj~E ce=aleted at the earliest time concistent with the analysis, but in any case vithin 30 days. If the high value is real, the report to the NRC shall be sub-r mitted.
5-6 Amendment No.
54
?
o
,. ~
A If silk samplas collacced over a calendar quarter show
.4.+
average I-131 concentrations of 4.8 picoeuries per liter
.=.
or greater and the increase is determined to be attribu-table to the operation of the Brunswick Plant, a written report shall be submitted to the Director of the appro-priate regional office (copy to the Director of Nuclear j
Reactor Regulation) within 30 days, and should include an evaluation of a=y release conditions, environmental factors, or other aspects necessary to explain the anoma-lous results.
c.
Miscellaneous Reoorts (1) When a change to the plant design, to the plant operation, or to the procedures described in Section 5.3 is planned which would have a signi-ficant adverse radiological effect on the environ-l ment as determined by the Plant Manager or which
]
involves a significant radiological environmental l matter or question not previously reviewed and evaluat,ed by the NRC, a report on the change shall be submitted to the NRC for information prior to implementation.
The report shall include descrip-tion and evaluation of the impact of the change.
(2) Raquest for changes in Environmental Teeh4e=1 Specifications shall be submitted to the Director of Nuclear Reactor Regulation, NRC, for prior review and authorization. The request shall in-clude an evaluation of the impact of the change.
=.
25 5
.=?
5-7 Amendment No.
'54
_ =
6.0 (Deleted) b' 6.1 (Deleted) 6.2 (Deleted) i 6.3 (Deleted) r 6.4 (Deleted) 1 4
i 1
I 1
2 4
i Amendment tio~., 54 6-1 s
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[9, UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
8 WASHINGTON, D. C. 20585
\\...../
~
CAROLINA POWER & LIGHT COMPANY DOCKET M0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMEND *ENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-62 1.
The f uclear Regulatory Cornission (the Commission) has found that:
A.
The applications for amendment by Carolina Power & Light Company (the licensee) dated April 21, 1981 and February 19, 1982 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and re-gulations set forth in 10 CFR Chapter I; s
B.
Tne facility will operate in confomity with the application, the previsions of the Act, and the rules and regulations of the Cornission; C.
There is reasonable assurance (1) that the activities' authorized by this anendment can be conducted without endapgering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
Tlie 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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l l'
9
t2-l 2.
Accordingly, the license is amended by deleting paragraphs 2.D.a. b, and c and by changes to the Technical Specifications as indicated in the attachment to this license amendment. Paragraph 2.C.(2) of Facility I
Operating License No. DPR-62 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 11, 1983 O
m a
ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix B Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert i
i iii 111 2-1 2-1 2-2 2-3 2-4 2-5 2-6 2-6 2-15 2-15 2-15a 2-16 2-16 4-1 4-1 4-2 4-3 4-4 4-5 4-5a 5-4 5-4 5-5 5-5 5-Sa 5-5b 5-6 5-6 5-7 5-7 l
6-1 6-1 6-2 6-3 l,
6-4 6-5 6-6 6-7 Figure 3.3-1 ao r
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4 e
(.,,.
D.g.--
3E NS CI SZuf I*I CC ?! A2C, C. & 2
%:J7 ZN72.".LCIDfE1 CAL '"bCZ1C"AL S?Eu _C1~~CNS
".A3LI 0F C C CS SIC-*0N
?A 2 NS.
1.0 Defd-d:icus 1-1 to 1-3 2.0 !=vi =-- -s i ? c:ee:1cn C==di. dons 2-1 2.1 he==al-Dele ted 2-1 2.2 Ch-d -s!-Deleted 2-1 2.3 Eye. aull:
2-6 2.4
.!'.a:ac :1cgy 2-7 2.5 Radicactiva Discharges 2-8 to 2-14a 3.0 Su_ r" a--a Requirs=a=:s 2-1 3.1 Se: a1 - Deleted 2-1 3.2 Ch* d-s9-Deleted 2-1 2-6 E7 ra"'d-d 3.3 2-7
- 3. /. Sfe:ac::1=gy 2-8to2-14al 3.3 Radica::17e Discharges
'2-1.3.m 2-23 A"
3ases 2 v1 an=21 Su:v d' *- a 4.0 4.1 Nonradiological Monitoring 4-1 4.2 Radialegd ='
-vi :c=e= 11 Mani:::t=g 2:=gra=
4-6 to 4-10 3.0
- d d==ra:1ve C:====1s 5-1 to 5-8 6.0 Special Su=vad" mee a d S=ady Ac:1vi:ies-Deleted 6-1 6.1
.'d.z sh Produe:1vity-De1eted 6.2 Deleted 6.3 Deleted 6.4 Sai: Depos1_1== ifeni_criss-Deleted h.=u l
i l
Amendment No.
79 1
.o (h..
LIST.OF TICmtIS
- FICmt! NO.
E i
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/
4.2-1A Iacation of Radiological Environmental !!anitoring Stations I4 cation of #mA4 alogical Environmental lionitoring Stations 4.2-13 5.1-1 Ifanagement organizacion Chart e
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Amendment No.
79 es ew,
s:
BSEP-1 & 2 2.0 ENVIRONMENTAL PROTICTION CONDITIONS 3.0 SURVIILLAMCI RIQUIREMENTS i
Genersl: During a national power emergency, regional emergency, reactor emergency, when the health, safety, or welfare of the public any be endangered by the inability of Carolina Power &
Light Company to supply electricity, the protection limits provided in these en-vironmental technical specifications shall be inapplicable. During such emergencies, however, the protection limits shall not be exceeded except as is necessitated by the emergency.
~
Certa'in Environmental Protection Conditions and Surveillance Require-t ments are specified in the effective National Pollutant Discharge Elimina-tion System (NPDES) permit issued by the State of North Carolina, Department of Natural Resources and Community Development, Division of Environmental Management. This agency is responsible for regulation of matters involving thermal discharges, chlorine, normal-izer tank pH, and piezometric head.
2.1 THERMAL 3.1 THERMAL Deleted U*A*E*d 2.1.1 Maximum Temperature Rise 3.1.1 Maximum Temperature Rise Deleted Deleted 2.1.2 Rate of Change of Discharge 3.1.2 Rate of Change of Discharge Temperature Deleted Temperature Deleted 2.1.3.Hp t Treatment of Circulating Water Sy: stem 3.1.3 Heat Treatment of Circulating Deleted Water System Deleted 2.2 CHEMICAL Deleted 3.2 CHEMICAL
. Deleted 2.2.1 Chlorine Deleted 3.2.1 Chlorine Deleted 2.2.2 Other Chemicals Deleted 3.2.2 Other Chemicals Deleted 2.2.3 Odrogen Ion Deleted 3.2.3 Hydrogen Ion Deleted NOTE: Pages 2-2 through 2-5 hava been deleted.
Amendment No. 79 2-1 e
m.--
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BSEP-1 & 2 r
n_;.
~q )
2.0 EN7IRChEE:!TAL PROTECTICt! CC:IDITIONS 3.0 SURVEILI.ANCE REQUIRC.'CITS 2.3 HTURAULIC 3.3 HYDRAULIC 2.3.1 Water Level in the Discharte canal 3.3.1 Water tevel in the Discharme Canal Obiective: To minimiae impact Specification: Water level of th7 discharge canal on the local in the discharge canal near the plant shall be mnicored daily.
groundwater supply.
Specification: Water level in the discharge canal shall normally be maintained between +3.5 feet asi and +5.5 feet asi at the discharge weir. These limits may be exceeded as required either for plant maintenance or as a result of i
natural conditions such as heavy
~
rainfall which is beyond the control of planc personnel.
2.3.2 Pterecer-te Wend 3.3.2 Piermsee-*
- Wead I
Deleted Deleted Amendment No. 79 2-6 e
.-m c
+ -
v--
.m
-m
4 8
0 BASES:
A s
1 4
/
f r
2-15 e_.
NOTE: Page 2-15a has been deleted.
Amendment No.
79
~ ~
G
,_g
Specifica: ions 2.3.1 an'd 3.3.1 =ain: sin the discharge canal va:e level vi:hin a range cha: vill -" '-* the potential 'for upuelling and dcunwelling effee:s en the aquifer.
Specifica:10
- 2. '. p;cvides the neceorolegical pars =ecers which are =easured a:
the plan: vill p;cvide :he infe =acien necessary :o es:i=a:e potencial radia:ica
- deses to the public fres rou:ine or acciden:al releases of radioactive sacerials to :he a::: sphere and zee: the require:en:s of subparagraph 50.36a (a) (2) of 10Cn Par: 50 and appendices D and ? :o 10CFR 50.
EADICACT!*F. DISCO.ACIS
~
'w MOUI3 *.TAS I L c'.~E'IT5 - The release of radi=ac:ive =s:erial is liquid effluen:s to e
unrescri::ed areas shall not exceed :he cencen: 2:1:n li=1:s specified i= 10 C n Par:
20 and shculd be as lov as prac:1:able in ac::: ance vi:h :he require =e :s of 10 Cn
?ar: 50.36a. These specifica:1:ns provide reascnable assurance tha: :he resul:i:3 annual dose d :he :ccal body or any organ of an individual i= an unrest:1 :ed area vill not exceed 3 =rs=.
A: the sa=a ti=e,.hese specifica:1:ns per:1: :he flexib111:7 of opera:icn,~ ce=pacible vi:h c: sideraci cs of heal:h and saf t:y, :o assure :ha: :he publia is provided a dependabla source of pcuer under unusual cpera:1:g condi: ices which =ay ce=porarily resul- *-
-*1 eases higher :han :he design objec:1ve levels but se' vir.hi: :he c:ccan::a:1:= d:s specified in 10 C a Par: 20..I: is expec:ed f
- ('
tha: by,using this opera:icnsi flexib111:7 under u= usual opera:ing :=cdi:icas, and exer isg every effor: :o keep levels of radicac:1ve =a:arial 1: liquid vastes as 1:v s
as prac:icable, :he a :usi releases vill =ce exceed a s all frac:i:n of the c =cen::a-
' :1:n id-4:s specified 1: 10 CII Far: 20.
The desig cbjec:ives have been developed based en opera:ing experience, :aking s
D.J !=:s ace:u== a cc bina:ica of variables includi=g def ective fuel, pri=ary syste=
['
leakage, a=f. :he perf::=sace of the vari:us vaste ::ea:=en: systa=s, and are censistan: vi:h Appendix I :o 10 CIR Par: 30.
7g
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Amendment'No. 79 2-15
~
1
c o A
4.0 Environmental Monitoring N
4.1 Nonradiological Monitoring The nonradiological biological monitoring requirements are specified in the effective National Pollutant Discharge Elimination System (NPDES) permit issued by the State of North Carolina, Department of Natural Resources and Community Development, Division of Environmental Manage-ment.
This agency is responsible for regulation of matters involving water quality and aquatic biota.
1 NOTE: Pages 4-2 through 4-Sa have been deleted.
4-1 Amendment No. 79
Recnzd'3 of changes cc dese:1htd in S criou 5.4.2.cGL c.
and (2).
5.4.1.2 A separate an=ual env1:::= ental radiological report c=vering the previous 12 =enchs of operati=u shall be subt:itted vi:hi: 90 days after January 1 of each De first such report shall be submit:ad fc year.
the 12-centh calendar period during which ini:121 criticality is achieved. Data co: available for inclusien in the :nport will be submi::ad as soon as 5-4 Amendment No. 79
possible in a supplementary report. The report shall
{g include the followinr:
a.
Summary records of monitoring requirements surveys and samples, b.
Analysis of environmental data.
3.4.2 Non-Routine Recorrs a.
Radiological Reports Violations of an Environmental Technical Specification, including unplanned release of radioactive materials of significant quantities from the site shall be reported to the Director of the appropriate regional office (copy to the Director of Nuclear Reactor Regulation) within 14 days of an environmenta?. event. The written report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact; (b) de-scribe the cause of the event, and (c) indicate the corrective actioh (including any significant changes
, made in procedures) taken to preclude repetition of the event and to prevent similar events involving similar
[
components or systems.
The environmental protection i
conditions for radiological discharges are described in Section 2.5.
s Amendment No.
79
l a
es,
e, The radiological environm.ntal monitoring is dzscribsd in Section 4.2.
~
Analyses of environmental samples which exceed the
~
1arger of either the control station value (Table 4.2-5) or the m4n4== detection
'4
't by a f actor of 10 or more for that same sample type and time period vill be iden-tified and if determined to be attributable to the opera-tion of the Brunswick Plant, a written report shall be sub-nitted to Director of the appropriate regional office (copy to the Director of Nuclear Reactor Regulation) within 30 days after confir= anion.* The test for exceeding the guide value will be a T test at 99.5 confidence. The test vill be considered positive when:
I - (I 10) > T99.5. /c 2+g 2 (loo) i e
i c
where:
- ** * ( *
}
99.51
.51&
I = value obtained at station i g
I = either value obtained at control station or e
=4n4== detection id dt (mdl), whichever is
- larger, o = standard deviation of station i value g
e = standard deviation of control station c
- A confir=atory reanalysis of the original, a duplicate or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be f fE coupleted at the earliest eine consistent with the analysis, but in any case V
vithin 30 dayt. If the high value is real, the report to the NRC shall be sub-r.itted.
5-6 Amendment No. 79
.a
-h If -Ek sat:ples coll'acced over a calendar quarter show average I-131 concentrations of 4.8 picoeuries per liter or greater and the increase is determined to be attribu-
~"
table to the operation of the 3runswick Plant, a written report shall be submitted to the Director of the appro-priate regional office (copy to the Director of Nuclear Reactor Regulation) within 30 days, and should include an evaluation of a=y release conditions, environmental factors, or other aspects necessary to explain the anoma-lous results.
c.
Miscellaneous Reoorts (1) When a change to the plant design, to the plant operation, or to the procedures described in Section 5.3 is planned which would have a signi-ficant adverse radiological effect on the environ-l ment as determined by the Plant Manager or which involves a significant radiological environmental l matter or question not previously reviewed and evaluated by the NRC, a report on the change shall be submitted to the NRC fo'r information prior to implementation. The report shall include descrip-tion and evaluation of the impact of the change.
(2) Request for changes in Rnvironmental Technical Specifications shall be submitted to the Director of Nuclear Reactor Regulation, NRC, for prior j
review and authorization. The request shall in-clude an evaluation of the impact of the change.
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79 Amendment No.
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