ML19347B239
| ML19347B239 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/20/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347B240 | List: |
| References | |
| NUDOCS 8010140101 | |
| Download: ML19347B239 (15) | |
Text
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nuro g'o, UNITED STATES
+
8 NUCLEAR REGULATORY COMMISSION g.
.E WASHINGTON. D. C. 20555 o
8
%-*..../
JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 49 License No. OPR-16 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Jersey Central Power & Light Company (the licensee) dated February 15, 1980, 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 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; I
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 Comission's regulations and all applicable requirements have been satisfied.
i l
8 010140lol
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Provisional Operating License No. OPR-16 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, are hereby incor-porated 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 HE NUCLEAR REGULATORY COMMISSION M
Dennis M. Crutchfiel, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 49 PROVISIONAL OPERATING LICENSE NO. OPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are 'ientifiad by the captioned amendment number and contain vortical lines indi ating the area of change.
REMOVE INSERT 3.6-1 3.6-1*
3.6-la*
3.6-2 3.6-2 3.6-2a 3.6-2b 3.6-Sa 3.6-7 3.6-7 3.6-8 (Table 3.6-1) 3.6-9 (Table 3.6-2) 3.6-10 (Table 3.6-2) 3.6-11 (Table 3.6-2) 4.6-lc 4.6-Ic**
There are no changes to the provisions contained on these pages; they are included for editorial purposes only.
Procosed by the licensee as page 4.6-3.
3.6-1 3.6 Radioactive Effluents Acolicability: Applies to the radioactive effluents of the facility.
Objective:
To assure that radioactive material is not released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released is kept to a practical minimum and in any event, within the limits of 10 CFR 20.
Soeci fication:
A.
Plant Stack Effluents (1) The maximum release rate of gross activity, except iodines and particu-lates with half lives longer than eight days, shall be limited in accordance with the following equation:
Q = 0.21 Ci/sec.
whereQibthestackreleaserate (Ci/sec) of gross activity and E is the average gama energy per disintegration (MeV/ dis).
(2) The maximum release rate of iodines and particulates with half lives longer than eight days shall not exceed 4 uCi/sec.
1 (3) Radiogases released from the stack shall be continuously monitored except for the short time. during monitor filter changes.
If this specification cannot be met, the reactor shall be placed in the isolated condition.
B.
Discharce Canal Effluents (1) The release of radioactive liquid effluents shall be limited such that the concentration of radionuclides in the discharge canal at the site boundary shall not at any time exceed the concentrations given in Apoendix B, Table II, Column 2, of 10 CFR 20 and notes 1 through 5 thereto.
(2) Radioactive liquid effluent being released into the discharge canal shall be continu-ously monitored, or, if the monitor is inoperative, two independent samples of any tank to be discharged shall be taken, one prior to discharge and one near the completion of discharge, and two station personnel shall independently check valving prior to discharge radioactive liquid effluents _.
Change No. -7' Amendment No. 49
s I
3.6-la l
l C.
Radioactive Liquid Storage The maximum amount of radioactivity, excluding tritium, nobel gases, and those isotopes with half lives shorter than three days, contained in the radwaste storage tanks outside the rad-waste buf1 ding shall not exceed 10.0 curies.
If this activity exceeds 5.0 curies, then the stored liquid will be recycled to tanks within the radwaste facility until the level is reduced below 5.0 curies.
I l
Change No.
10G Amendment No. 49
3.6-2 C.
Reactor Ccclant Radicactivity The concentration of tne totrl diine in the reacter coolant shall not exceed 8.0 uCi/g:n. If this specification cannot be met, the reactor snall be placed in tne cold snutdown ccrdition.
E.
Licuid Radicactive Waste Control Equipment installed for the treatment of liquid wastes shall ::e used if release of an untreated caten would result in concentrations in excess of 20% of the li. tits given in Secticn 3.6.3.(1).
F.
Annual Casecus Release Li. tits 1.
Tne cverage release rate of ncble gases fran ne site during any calendar year shall ::e limited by tne following equaticas:
for beta r.ir dese:
(3.17 EG4) x (3.6 E-08) x I
Qi Ni < = 20 i
for ga.ma air dose:
1 E
Ci Mi <= 10 1
~ tere:
n E denotes su= ration ever all isoccces detected i
3.17 E04 cenversien factor pCi - yr/Ci-sec
=
3.6 E-08 X/Q at site ocundary 569 M SE.
=
l Ci Average release rate of isotcpe 1, in Ci/yr
=
Ni dose conversien facter for te:a air dese,
=
mrad - m(3)/ pCi-yr. frcm Table 3.6-1 Mi dose conversien factor for ga:=a. air dese,
=
mrad /Ci frcm Table 3.6-1 1
Change No. 7
Amendment No. 49
)
a
3.6-2a 2.
Se average release rates of radicicdines and radicactive materials in l
particulate form released in gasecus effluents from tne site during any calendar j
year shall be limited by :ne following equation:
(3.17 E-02)C [Rii (4.8 E-08 :: Qis + 2.3 E-05 x Qiv) +
(Fqi + Rvi) (5.5 E-09 x Qis + 1.0E-07 x Qiv)] < = 15 vinere:
J I
denotes su:n.atica cver all isc:cpes detected i
3.17 E-02
= conversion facter, uCi-yr/Ci-sec R:.i
= dose factor for innala:icn, mrem-m(3)/uCi-yr, Table 3.6-2 Egi
= dese facter for greurd plane exposure, m(2) -mrem-sec/
uC:.-yr, Ta:le 3.6-2 i
Rvi
= dose facter fer vegetatien censu=ptien m(2) mrem-sec/
uCi-yr. Tacle 3.6-2 4.8 E-08
= X/O at 390 m SE for stacx releases (Ref. 13) 2.3 f.-05
= X/Q : 890m SE for vent releases (Ref. 13) 5.5 E-09
= D/0 at 390m SE for stsex releases (Ref. 16)
I
' 0 E-07
= D/Q a 890m SE for vent releases (Ref. 16) l Qis = :verage release ra e of isc cpo :. frcm :ne stack in Ci/yr Qiv = average release rate of isctcpe i frcm :ne vent in Ci/yr I;cte:
The Rvi for tricit.m snculd be multipl:.ed by X/G ratner : nan by D/G as is cene for all etner nuclides.
1 i
4 L
(
Amendment No. 49
o 3.6-2b Bases: Some radic crive material is released from :ne plan under centrolled concicions as part of :ne nor=al operatica cf tne facility. Ctner radicactive material not rcr ally inter 4ed for release could te inadvertently released in ene event of certain accident conditions winnin tne facility. terefere, limits have been placed en tne accve types of radioactive materials to assure not exceeding tne limits of 10 CFR 20 for the femer type and tne guideline limits of 10 CFR 100 for tne latter type.
Radioactive gases frcra the reactor pass through the steam lines to tne turbine and then to the main condenser where eney are extracted by tne air ejector, passed entcugn 30-minute noldup pipig and released via tne plant sack.
Se limits of release and radicactive material frca che plan stack nave been calculated using me:eorological data frca an instr =ented 4C0 f: cwer at =e plant site. te analys.s of tnis onsite metecrological da:a snows :na: tne expected ccmposition cf radiegases af ter 30 minutes ccidup in tne of f-gas system, a continuous release of 0.3 CL/sec would not result in a wncle body radiaticn dcse exceediq tne 10 CFR 20 value of 0.5 rem per year. The Eclland plume rise scdel witn no correcticn fac ct was used in tne calculation of :ne effect of =ccentus and bucyancy of a continucusly emitted p1=e.
Irdeperdent dose c lcula:icns for several locacicas offsite nave been made by
- ne AiC staff. Se me:ncd utilized cnsite meteorological data develcped by tne licensee anc util::ed diffusion assu=ptiens apprcpriate to tne site. S e metnod
- .s described in Section 7-5.2.5 of Meterclogy and Accmic Energy - 1958" j
ecuation 7.63 teing used. te results of :nese calculatiens wer i eculvalent to
- ncse generated by cne licensee provided me avercge ga==a energy per alsintegration for tne assumed rcole gas mixture wi:n a 30 minute hold up is 0.7 dieV per disintegra:lon.
Based on tnese calculaticns, a maximen release rate I
limit of gross activity, except for iccines and particMates witn nalf lives longer enan eigne days, in ene amount of 0.21 ? curies per secord will not result in offsite annual doses in excess of :ne limits s ecified in 10 CFR 20.
he c determina:ica need consider only tne average gamma energy per disintegraticn since :ne centro 11ing wr. ole body cose is due to me ciced passage over tne receptor ari not cicud sucmersien :.n.hien ene beta dcse could be i
add itive.
3 3
Amendment No. 49 J
3.6-5c t
2e noble cas releases are centrolled so ::a ne beta air dose is less enan or 4
equal to 20 mrad /yr ard tne gama air dcce is less enan or equal to 10 mead /yr (in accrdance with 10 CFR 50 Appendix !) at tne site bcundary in the direction with the highest X/Q. A X/Q of 3.6 E-08 at 569 m in the SE direction was
. chosen on the basis of the NRC Apoendix I Analysis.
The X/Q used is
+
that for releases from the stack, since almost all noble gas releases are from that source.
Equations B-1 and B-4 from Regulatory Guide 1.109,
~
Rev.1 (October 1977) Appendix B, are used to calculate the gama and beta air doses, respectively.
The site specific dose factors, Ni, for l
gama air dose were obtained from the NRC RABFIN code and are based on the finite plume dose calculational mode.
- ne releases of radiciodines and radicactive materials in particulate form are controlled so that tne enyrcid dcse to any real persen is less enan or egal to 15 = rem /yr, in accordance with the design Objectives of 10 CFR 50 Appendix I.
One X/Q and D/0 values used are for a distance of 890 m in tne SE directicn wnich is the locacica of the highest pctential nyroid dose based en the Oyster Cree.< Appendix I Analysis (Ref.12) Se patnways censidered at tnis loc tion are stcred and fresa fruits and vegetacles, innalation and ground plane descsition.
- 4c milk patnway exists at tnis 1ccation.
Ine seat patnway is insignificant and 3
is not censidered (Ref.12).
Equations from NUREG-0133 (Ref.14) are used to calculate tne dose facters, along witn dese conversion facters frc:a Fagulatory Guide 1.109 (Ref.15). nnere no data wts previded in Fagulatory Guide 1.109 for nyroid dose convernien facects for certain nuclides, the total body dose conversion facters were used. All calcula:icns are dene for a enild since enis j
produces the highest dese.
(Fef.12).
i a
i
=
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Amendment ?!o. 49 au dA*
3.6-7
References:
(1)
FDSAR, Volume I, Section IX-3.3.
(2) Licensing Application, Amerriment 13, Meteorological Radiological Evaluation for the Oyster Creek Nuclear Power Station Site.
(3) Deleted.
(4-FDSAR, Vol me I, Section VII-6.2.3.
(5) Deleted.
(6)
FDSAR, Volume I, Section IX-3.1.1 (7)
FDSAR, Volume I, Section II-4.3 (8) Licensing Application, Amendment 11, Question 1-4.
(9) Licensing Application, Amendment 11, Cuestion 1-5.
(10) Deleted (11) Licensing Application, Amendment 11, Cuestion IV-8.
(12) Evaluation cf the Oyster Creek Nuclear Station to demonstrate conformance to the Design Cbjectives of 10 CFR 50 Appendix I, May 1976, Table 3-10 page 2 of 2.
(13) Meteorological Information and Diffusion Estimates to conform with Apper: dix I Requirements: Cyster Creek, July 1976, Table 1.3-11 B.
(14) NUREG-0133, Preparatien of Radiological Effluent Technical Specifications for Nuclear Power Plants, Draft of August,1978, Pages 30-33 ard 36-37.
(15) Regulatory Guide 1.109, Calculation of Annual Doses to Pm frcm Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Psrt 50, Appendix I, Tables E-6, E-9, E-13.
(16) Ref. 13, Table 1.3-133.
l Amendment No. 49 D""AD "D ~9' 1 N}f[
e
=
3.6 8 Tacle 3.6-1 DCSE FAC"CM FCR EXPCSURE TO A SEMI-INFINI*"E CICCD CF ICi!LE GMES Nuclide Ni*
Mi+
pCi-yr u
Kr-83m 2.88E-04 3.18E-03
_ 4.28E-06 Kr-852 1.97E-03 Kr-85 1.95E-03 7.13E-03 Kr-67 1.03E-02 2.30E-05 Kr-s8 2.93E-03 5.83E-05 Kr-59 1.06E-02 4.68E-05 Kr-90 7.83E-03 4.41 E-05 Xe-131m 1.11E-03 1.09E-06 Xe-1332 1.48E-03 8.98E-07 Xe-133 1.05E-03 8.26E-07 Xe-135m 7.39E-04 1.25E-05 Xe-135 2.46E-03 7.18E-06 Xe-137 1.27E-02 4.03E-06 Xe-138 4.75E-03 3.65E-05 Ar-41 3.28E-03 4.40E-05
- Scurce: Regulatcry Guide 1.109, Revisien 1, Cet:ber 1977, Tacle 5-1.
+ Source:
Site scecific finite plume gani:a air dose factors from NRC RABFIN comouter code.
Amendment No. 49 l
, 4 3.6-9 TABLE 3.6-2
'IEYROID DOSE FACTCRS FCR INEALATICN (Rii), GRCOND PIANE EXPCSURE (Egi), AND VEGETATION CCNSI.NFIION (Rvi) j NUCLIDE Rii*
IkJi**
Rvi**
H-3 1.1E03 0
4.0 E03 C-14 6.7E03 0
1.8 E08 Na-24 1.6E04 1.9E07 3.7 EOS P-32 9.9E04 0
1.3 E08 Cr-51 8.5E01 4.7E06 6.5 E04 Mn-54 9.5E03 1.3E09 1.8 E08 Hu-56 3.lE-01 9.0E05 4.2 Fe-55 7.8E03 0
1.3 EOS Fe-59 1.7E04 2.8E08 3.3 E08 Co-58 3.2E03 3.8E08 2.0 E08 Co-60 2.3E04 2.lE10 1.1 E09 Ni-63 2.8E04 0
1.3 E09 Ni-65 1.6E-Cl 3.0E05 6.6 l
Cu-64 1.1 6.1E05 6.8 E03 Zn-65 7.0E04 7.5E08 1.3 E09 Zn-69 8.9E-03 0
3.2 E02 Br-83 4.7E02 4.9 E03 5.7 Br-84 5.5E02 2.0 EOS 3.8 E-ll Br-85 2.5E01 0
2.6 E-13 Rb-86 1.lE05 3.4 E02 0
Bb-88 3.7E02 3.3 E04 3.1 E-22 Pb-89 2.9E02 1.2 EOS 3.5 E-26 Sr-89 1.7E04 2.3 E04 1.1 E09 i
l Amendment i:o. 43 l
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TABLE 3.6-2
. ___ (contid).
3.6-10 s
Sr-90 6.4E06 0
3.2 Ell Sr-91 4.6 2.2 E06 2.1 E04 Sr-92 5.3E-01 7.8 E05 2.9 E01 Y-90 1.1 E02 4.5 E03 6.2 E02 Y-91m 1.8E-02 1.0 EOS 4.2 E-10 Y-91 2.4 E04 1.1 Ebh 5.0 E05 Y-92 5.8 E-01 1.8 EOS 4.5 E-2 Y-93 5.1 1.9 EOS 8.5 Zr-95 3.7E04 2.5 E08 7.7 E05 Zr-97 1.6E01 3.0 E06 4.9 E01 tb-95 6.5E03 1.4 EOS 1.1 EOS Mo-99 4.3 E01 4.0 E06 1.9 E06 Tc-99m 5.8 E-02 1.8 E05 1.6,E02 I
Tc-101 1.1 E-03 2.0 E04 6.9 E-30 l
Ru-103 1.1 E03 1.1 EOS 5.9 E06 Ru-105 5.6E-01 6.4 E05 3.3 E01 l
l Ru-106 1.7 E04 4.2 EOS 9.3 E07 l
Ag-110m 9.1 E03 3.5 E09 1.7 E07 Te-125m 1.9 E03 1.6 E06 9.8 E07 l
Te-127m 6.1 E03 9.2 E04 3.2 E08 l
Te-127 2.0 E02 3.0 E03 6.9 E03 Te-129m 6.3 E03 2.0 E07 2.8 E08 Te-129 7.1 E-02 2.6 E04 7.7 E-04 Te-131m 9.8 E01 8.0 E06 1.1 E06
~
Te-131 1.7E-02 2.9 E04 1.4 E-15 Te-132 3.2E02 1.0 EC8 2.5 E08.
I-130 1.8 E06 5.5 E06 7.0 E07 1
1 amandment.'lo. 49 T
-F
TABLE 3.6-2
~
3.6-11 (cont'd)
I-131 1.6 E07 1.7E 07 2.4 E10 I-132 1.9 EOS 1.2 E06 3,4 E03 I-133 3.8 E06 2.4 E06 3.9 EOS I-134 5.1 E04 4.4 EOS 2.7 E-03 I-135 7.9 EOS 2.6 E06 5.0 E06 C3-134 2.2 E05 6.8 E09 5.5 E09 Cs-136 1.2 EOS 1.6 E02 1.6 E08 Cs-137 1.3 E05 1.0 E10 3.4 E09 Cs-138 5.6 E02 3.6 EOS 5.8 E-ll Ba-139 5.4 E-02 1.1 E05 1.4 E-03 Ba-140 4.3 E03 2.1 E07 1.6 E07 Ba-141 6.4 E-03 4.1 E04 2.9 E-23 a -142 2.8 E-03 4.6 E04 0
a La-140 7.5 E01 1.9 E07 3.8 E02 La-142 1.3 E-01 7.4 E 05 2.4 E-05 Ce-141 2.9 E03 1.4 E07 4.9 E04 Ce-143 2.9 E01 2.3 E06 1.3 E02 Ce-144 3.6 EOS 6.9 E07 6.8 E06 Pr-143 9.1 E02 0
7.3 E03 Pr-144 3.0 E-03 1.8 E03 2.6 E-27 Nd-147 6.8 E02 8.5 E06 4.5 E03 W-187 4.3 2.4 E06 1.7 E04 Np-239 2.3 E01 1.7 E 06 1.3 E02
- mr o-m(3)/uci-yr.
- m(2)-n. rem sec/uCi-yr.
14CTE: Knere no data was available for the thyroid dose factor in in R.G.1.109, Rev.1, Tables E-9 cr E-13, the total bcdy dose factor was used to calculate Rii or Rvi, as applicable.
Kvi factors for iodines were reduced by half based en the assumption that cne-half the iodine released is non-elemental.
(Per R.G. 1.109, Rev. 1, Page 26) kendment No. 49
4.6-1c C.
A sample of reactor coolant shall be analy ed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to determine total radioactive iodine contant.
D.
Liquids contained in the waste sample tar.ks, floor drain sample tanks, and the waste surge shall be samnled and analyzed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to determine the. total activity in curies unless a tank has been valved out of service after determining ils radioactive content.
E.
The operability of all equipment installed for the treat-ment of liquid wastes shall be verified at least once per quarter.
F.
The calculations specified in section 3.6.F shall be performed at least once per month.
Basis:
The check, test, and calibration requirements are specified to detect possible equipment failure and to show that maxirpyrp permissible release rates are not exceeded.
The monitors \\ /
operate continuously and by virtue of normal plant ooeration, the operators daily observe that the instruments are per-forming.
Failure of an instrument is evident, because of upscale, downscale, or loss of voltage alarms.
The monitor trip points may be readily checked by a built-in pushbutton operated circuit. A portable test source may be affixed to the detector to re-establish calibration.
Experience with instrument drift and failure modes indicates that the speci#ied test frequency is adequate and consistent with other instrumentation.
Continuous monitoring of the gaseous and collection of the particulate stack effluents provides the means fd determining that the limits of Specification 3.6. A are not exceeded and for recording the actual levels of radioactivity that are being released from the stack.
The frequencies of filter and cartridge analyses and isotopic analyses are specified to assure proper identification of the isotooes being released.
The sampling and analysis of each batch of the radioactive liquid effluent provide the means for detemining the release rate to the discharge canal to assure the limits of Soecifica-tion 3.6.B are not exceeded.
The isotopic analyses of the weekly and monthly proportional composites of licaid waste j
samples provide the data for recording and report 11g the i
average concentrations of radioactivity and total radioactivity released # am the discharge canal.
These isotocic analyses shall also provide the normal means for calibrat:ng gross aloha, beta and gama analyses that are used to uetermine the concentration of batch for discharge on an unidentified basis.
More frequent isotopic analyses shall be required in confor-mance with 4.6.B.2.(e) & (f) to assure that the calif ation of gross counts has not been altered by a cnange in :he mixture of radioisotoces.
Char.ge No. #
Ammdment No.