ML20099L700
| ML20099L700 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/16/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17195A674 | List: |
| References | |
| NUDOCS 8412030058 | |
| Download: ML20099L700 (6) | |
Text
f 4
UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 3
p WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTINGAFEt[DMENTNO.83TOPROVISIONALOPERATINGLICENSENO.DPR-19 AND AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO. DPR-25 DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-237/249
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Commonwealth Edison Company has filed with the Commission plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal operations, including expected operational occurrences, as low as is reasonably achievable. Commonwealth Edison originally filed this information with the Commission by letter dated -
February 16, 1979 and then supplemented that filing with a letter dated May 3, 1984, which requested changes to the technical specifications appended to Provisional Operating License No. DPR-19 and Facility Operating License No. OPR-25 for Dresden Unit Nos. 2 and 3, respectively. The proposed technical specifications update those portions of the technical specifications addressing radioactive waste management and make them consistent with the current staff positions as expressed in NUREG-0473.
These revised technical specifications would reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR 50.36a, as supplemented by Appendix I to 10 CFR Part 50, with 10 CFR 20.105(c),106(g),.
and 405(c); with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64; and with 10 CFR Part 50, Appendix B.
A Notice of Consideration of Issuance of Amendments to Licenses and Proposed l
No Significant Hazards Consideration Determination and Opportunity for s
Hearing related to the requested action was published in the Federal Register on July 24, 1984 (49 FR 29905). No requests for hearing or publ'ic comments were received.
2.0 BACKGROUND
AND DISCUSSION 2.1 Peculations b
10 CFR Part 50, "Dcmestic Licensing of Production ard Ut'ilization Facilities," Section 50.3Ea, " Technical Specifications on Effluents from Nuclear Power Reactors," provides that each license authorizing cperttien of a nuclear power reactor will include technical specifications that (1) require compliance with applicable provisions of Part 20.106, " Radioactivity in Effluents to Unrestricted Areas;"
%12030058 841116 oPR ADOCK 05000237 PDR p
(2) require that operating procedures developed for the control of effluents be established and followed; (3) require that equipment
-installed in the radioactive waste system be maintained and used; and l-(4) require the periodic submission of reports to the NRC specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents, any quantities of radioactive materials released that are significantly above design objectives, and such other information as may be required by the Commission to estimate maximum potential radiation dose to the public resulting from the effluent releases.
-10 CFR Part 20, " Standards for Protection Against Radiation,"
paragraphs 20.105(c), 20.106(g), and 20.405(c), require that nuclear power plant and other licensees comply with 40 CFR Part 190,
" Environmental Radiation Protection Standards for Nuclear Power Operations" and submit reports to the NRC when the 40 CFR Part 190 limits have been or may be exceeded.
10 CFR Part 50, Appendix A - General Design Criteria for Nuclear Power Plants, contain Criterion 60, Control of releases for radioactive materials to the environment; Criterion 63, Monitoring fuel and waste st.orage; and Criterion 64, Monitoring radioactivity releases.
Criterion 60 requires that the nuclear power unit design include means to control suitably the release of radioactive materials in gaseous and liquid effluents and to handle radioactive' solid wastes produced during normal reactor operation, including anticipated operational occurrences.
Criterion 63 requires that appropriate systems be provided in radio-active waste system and associated handli.ng areas to detect conditions that may result in excessive radiation levels and to initiate appropriate safety actions. Criterion 64 requires that means be provided for monitoring effluent discharge paths and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences and postulated accidents.'
10 CFR Part 50, Appendix B, establishes quality assurance requirements for nuclear power plants.
10 CFR Part 50, Appendix I, Section IV, provides guides on technical specifications for limiting conditions for operation for light-water-cooled nuclear power reactors licensed under 10 CFR Part 50, 2.2 Standard Radioloaical Effluent Technical Specifications tiUREG-0473 provides radiological effluent technical specifications for boiling water reactors which the staff finds to be an acceptable standard for licensing actions.
Further clarification of these accept-able methods is provided in NUREG-0133, " Preparation of Radiological Effluer.t Techrical Specificaticns for Nuclear Power Plcnt." NUREG-0133 describes methods found acceptable to the staff of the NRC for the calculation of certain key values required in the preparation of
_m T
1
- proposed radiological effluent technical specifications for light-water-cooled nuclear power plants. NUREG-0133 also provides guidance to licensees in preparing requests for changes to existing radiological effluent technical specifications for operating reactors.
It also
. describes current staff positions on the methodology for estimating j
radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems.
The ab'ove NUREG documents address all of the radiological effluent technical specifications needed to assure compliance with the guidance
- and requirements provided by the. regulations previously cited.
However,' alternative approaches to the preparation of radiological effluent technical specifications and alternative radiological effluent technical specifications may be acceptable if the staff determines that the alternatives are in compliance with the regulations and with the intent of the regulatory guidance.
The standard radiological effluent technical specifications can be grouped under the following categories; -
t (1
Instrumentation Radioactive effluents Radiological environmental monitoring Design features Administrative controls.
Each of the specifications under the first three categories is comprised of two parts: the limiting condition for operation and the surveillance requirements. The limiting condition for operation provides a statement of the limiting condition, the times when it is applicable, and the actions to be taken in the event that the limiting condition is not met.
In general, the specifications established to assure compliance with 10 CFR Part 20 standards provide, in the event the limiting conditions for operation are exceeded, that, without delay, conditions are restored to within the limiting conditions. Otherwise, the facility is required to effect approved shutdown procedures.
In general, the specifications established to assure compliance with 10 CFR Part 50 provide, in the event the limiting conditions for operation.are exceeded, that within specified times corrective actions are to be taken, alternative means of oceration are to be employed, and certain reports are to be subritted to
~
the faC describing these conditiens and actions.
j i
The specifications concerning design features and administrative controls contain no limiting cerditions for operation or surveillance i
recuirements.
.w-
~
^
n a
Table 1 indicates the standard radiological effluent technical specifications that are needed to assure compliance with the particular provisions of the regulations described in Section 1.0.
3.0 EiALUA[ ION The attached report (EGG-PBS-6633) was prepared for the staff by EG&G, Idaho, Inc., as part of a technical assistance contract program. The
~
report provides a technical evaluation of the compliance of the licensee's submittal with NRC orovided criteria. The staff has reviewed this TER and agrees with the evaluation.
3.1 Summary
- I The proposed changes to the radiological effluent technical specifications for Dresden Station, Units 2 and 3, have been reviewed, evaluated, and found to be in compliance with the requirements of the NRC regulations and with the intent of NUREG-0133 and NUREG-0473 (Dresden Station, Units 2 and 3, are boiling water reactors) and thereby fulfill all the require-t ments of the regulations related to radiological effluent te.chnical specifications.
Theproposedchangeswillnotrenoveorje'laxanyexisting requirement related to the probability or consequences-of accidents previously considered.
The proposed changes will not remove or relax'any existing requirement needed to provide reasonable assurance that the health and safety of the public will not be endangered by coeration in the proposed manner. Tha staff, therefore, finds the proposed changes acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
1 These anendments involve a change in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. The staff has determined
.that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents thay may be released offsite and that there is no significant increase in individual or curulative occupational radiation exposure. The Commission has previously Swad a proposed findino that this amendnant involves no significant nacards consideration and there has been no public concent on such finding.
Accnrdingly, this arendront meets the eligibility criteria for catecerical exclusion set forth in 10 CFR 51.??('c)(9). Pursuant to 10 CFR 51.2?(b) no environmental inpact statement or environrental assessment rcd be prepared in connection with the issuance of this amendrent.
~.v.--
...._....__ _._ i a
' 4 5.0 GENERAL CONCLUSION The staff has concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner; and'(2) public (1) there is reastnable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical-to the common defense and security or the health and safety of the public.
6.0 ACKNOWLEDGEMENT
.The following staff mambers have contributed to this evaluation:
C. Miller C. Willis W. Meinke F. Congel
Attachment:
Technical Evaluation Report by EG&G Idaho, Inc.
f Dated: November 16, 1984 6
4 9
= [c.
q,-
w.
-e
.'.e'l s
e,
-i 0
e' v-
,a
,. n r, n
n, iv
-
v, O H o."L C w
- J e
.e
-9 9
9 e-N.* M em 4 ** '">
Q O
-=
) () 7 4 e======, e =
l9-O O. I l "J
==-"5
-3 l34C C"h
- N=== 3 c.
- =0g==**
c' ee n.at (,s e 3C 3=== as em L.a n,. -
9 O "3
-. 3.. e**t e
== 3 ee
- ~
ww
< c-C c. 3 a sg a c4 e
- - e= e O
e G.
Cl3 lg 1 e
9
[('"t C e* *; as C -m 3 s'
C e c r=
!===<=.
= = '
3== 1==
O
,,,g n
9 q *4 0"
e ** 3 CT n
"%.3 Oe -
7.2 J O O O==
OO 739
+3 3 3 e 4 3
- e
,c.,
l t.
- 1
-1 o 7 C.
C O ee 3 D
i3 n a rt 3 c= 3" -= =*
er*
,, c O s't te G a s.
7 t-a 3 3 3
3U
== =#O ce de e9
- 3m O
3 c"i O O
at JJ r3 C, te (3 a
e* C7 V e*
3 -- 3 em -=
c 3
3 C's @
CFt C"6 3 De O 3
as 2C n O
3 3 en t'3 O e-O C se e*
3 c3 9 O 8 3 - -- ** C -*
C C.
Es t a
==
QC=- Q
- 1 4
3 ** n 7 C. e*
e*
4.= 3
-3 On7 n f% c= -en wt -=- e* Ce 3 r3
=
C. g ese C
4 -
H
* O '3 CD 0""
c*
O ** "'==
O - < es a
m a e e
e a
=ai =*
n g
O==. en
=
O 3 -== O -- J IS O m in O 3 3
e
- #3
==
C-77
- 1 m>
a-4 m
-1 en e'
w.
3 eO en 3 e Ch em 9
=V O-
,, V, v3
==
" e* 3 3
-'t #
f*
== =e oO9 C 3o CM ee
== =3
.=
y.
-= CD
==6 OQ 3.g g
-. 3.i-C. = e* c' O m ee C O
==
e e
3"1 C
-= 1 3
es OpC wt g,
g wm a's as T e
e.n e"1 3
s*
==
C e* ce==
ft
"'1 en
=
CL E en K U
- -=
5 3.,
eE
. e e* O s
3===
C%
mm w
a
-=
r3 et O
to n O
o O e
- 1. O. o
- E3 C.
e,,,
nO n "1 ne C
O 1 en c* -
3 es O
O O 9 n e*
C Oe en m 7.= r3 ee 7
c n,,,,
CO
- c. CL a --nO es - r3 3
en
- 1
- ==
n
==
0 ar*
9 C=
E 3
,,E,,,s,e e'
3 as M
=B
- e= 3 ne r3 3 3 c*
1 -* O l N
3 n
O
t
=
0 D
CL c= #9 C e.
O ee **-QD - en ne =es ne C
C e*
n me' N==
h g
3 3 CL *)
b'
. C ce O at C CM 89 C Q e* **
O 0
O,
,3,
-1 m w* e*
3 3ll *C es
-* m er se
- 1
- O==
m 3
f3===
CLf3.s<
r3 CLfD te *
.ie e
.= e - -eac O wn
-= -
3s e
3 T
fD *'" "m 3 1 O p y O,.i. n CL 7'* fD se-n C.
es w* O e 3n 3
O O = ce en e
en se ee CT en f3 l=*
O 3 f3 C
e O
m w= c w
ee ci e
m 7
ct -
r i-ee
-3 g
> r3 g
O a
em em n
-= O n ce c, n3 3 3-m3 0
e*
e'*
CL
,,,,g, O
O 3 c=
f3 e* ** 3--
3 C 3
e* Q. c= es r3 we e
e*
ft O
O (D
g,,,
ee"7
-1 te
- 1 33 ' n O 7 3
1 sg 7
C" f3 te f"4 3" r r, T
9 r3 te f5 ne e
.C c, C.,.h. 4 Og.1.,
,3,e.5 G G f.3 m #.1 > f3 f3 M
3a O
g l
Sc O
fD g rg gy
- 5 n 3
==
M f3 3a es f5 9
e= es
' t"4 ce wt
- 1 e=
ef*
3
==*
,,, g
- h e'1 3 O *1 fB 0 -.CT r" 9 Q c*
est es r3 t'* "'t 3==
e*
-a f3
,,,,3 to ar"
.= 0 4
C 3 es *i es FD CL 3mf3.C f3 C
V
==
7 3
3 O
C c
,, a 9aa.
M ee
- 1 m et 4
- 1 r3 n
it 4
s n
==*
f3 C
g fg M
e r* > te ". 3 en te f3 ft ee es
==
7 a O e=
3 a= > 9
==e*
3 3O 4
3
,C,L 23 3a em
-=< f4 O a e* en ce es 3 te
- U,
- 3
-'t f3 r-c.
ne s n
ee a
0-o
-o O
n O
- 3. -
- v. e, e*=
C
,===
se n
3
- Q wt
.f3 c 3
7
.c.
r, n
3 a
f e
.a 3
e e
O 3 --
O
- l# S S S S-Rad. Liquid Effl. Monitoring ee
-a3
=
O 3 ee se 3 e* e*
G
[c S S
.9 8
Rad. Gas. Effl. Monitoring p
g en
.a S,
9e Effluent Concentration t-E' E
O 99 e
S S S gage
~
- a.
- O
' e G
G G G Li4uid Radwaste Treatment x
. U.
a S
S SS Liquid Holdup Tanks a
a.
e-3 S
S'S Dose Rate p
g
... ![
O,,, O G
'e g~ ef G G Dose I-131. Trit. and Part. *
- 7. C g ~.
. rg
, ;e n -
S.G 9 Dose Noble Gases..
,E OSS e
2% g g G
G S
Explosive Gas Mixture n
O SS S
S..S. S....
Gaseous Radwaste Treatment.
e@
r G
S st ~~ '
Gas Sto-age Tanks
..3
~-
C m
e.
O G
S S S Gaseous Radwaste Treatment 5 g n
O O' S S
S S 99 Ventilation Exhaust Treatment E
". g 5
S S
^ G Main Condenser g
7 S
SS Mark I. or II Containment -
m.
c n
S S
S Solid Radioactive Waste ne f.
S S Total Dose i's
~
2%
am e-4 O es
==i ft G
S Rad. Env. Monitoring Program 3 c-n C.
r 3
S S
Land Use Census O,c' 3
3 n,
e
,8 9
Interlab. Comparison Progr.am. c, a
=-
rs 4/5 7
u 3
r3 n
e n
,3. f3 a
ne Site Boundaries
- g *.
,e w
e, f3 3 u
c.e vt f3
=
E e9 Review and Audits n
~
lo.
.t=
ne O
'a G
S Precedures y
C F-
..r.=','**
O S
Reports
- r
- 1 c
-5 Record Retention g
.e.
e g
e,
.z O
O e
S S
S S S S#
Offsite Cose Calc.. Manual i
O b
S,'
. Major Changes to Rad. Syste.s y
k O
"1 ere 9-
.