ML19220B861
| ML19220B861 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/01/1977 |
| From: | Arnold R Metropolitan Edison Co |
| To: | Regan W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904270506 | |
| Download: ML19220B861 (22) | |
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x.m METHOPOLil AN EDISON COMPANY PCST OFFICE SCX 512 RE ACING. Pc'.NSYLVA'.O 19603 TELEPwCNe 215 - 9.'94601
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scouring. In addition intake channel surveys are =isplaced in the I"S.
"hese surveys shculd be included in the safety technical specifications in tnat these surveys are required for safety reascns rather than environmental Icnitcring. We vill provide a proposed benthic =cnitoring specificaticn.
Sactions L.h and h.5 " Iresien Control Inspectien" and "Eerbicile c.
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Section 5.6.2 requires a report to be filed for events that
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Director of :Iuclear Reacter Rer21aticn Attn-Mr.
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H. Pegan, ief April 1, 377
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" ste per=its appended to the March 9, 1977 versien of ES do not reflect certain recent revisiens. We have attached cne copy of each of the 7 < a 1.
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o In general we believe that the direction the :EC staff appears to te headed with the = cst recent versicns of rs is =cs: appropriate. Tne unnecessary duplicaticn of EPA and State requirements in the r5 has been appropriately eliminated.
levertheless we are concerned that the rS have act been finalized at this late d. ate in spite of our early
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.u May so that we nay begin procedure preparation in time to support the scheduled license date.
Please note that we have not ccmpleted cur reviev cf the March 9 rs and that we anticipate we vill have additional ec=ents.
'~nese cc=ents vill be forwarded to you no later than April 30, 1977 Q 4.
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2.a ECA: C'40 : rk Attachments:
(1) Revisions to T4P's ^270204 and 22722C2 (cne copy)
(2) Revised ES (LC copies) b ~ IbE3
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COpfch"qyggALTH or PEN Ns e
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DEPARTME:NT OF ENVIPCNMENTAL RESCURCES Ecos 1002 Health & Welfare Ecilding Earrisburg, Paylvania 17120 Dece=ber 10, 1975 v
Industrial waste Per=it Hes. 2272202 5 2270204 i..
Metropolita Edison Cc=pany Three 2M1o Island Ncclear Statica Lendenderry Tcucchip Dauphis Ccunty Matropolitan Ediscu Cc=pany P.O. Ec= 542 Reading, Pe=nsylvania 19603 Ar.tr.
R. C. Ar=old, Vice Presidest antic =an:
This is in response to your ecueers that the discharge linitaticus
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in the subject per=its are being applied en a gross rather than net basts.
We have evaluated the i= pact of def* d g the effluent 21:ltatiens as net rather than g css, and have found that in this case there wS?
be no significant i= pact en vatar quality. We therefore agree witi=. _
your request, cud hereby revise the above per=its for Thres lille Islace!
to reflect net li=itaticus. Obviously, this does not apply to the 11=i-taticus en pH and Te=perature.
Wa hope that this vill be sufficient to ell =inate any proble=s s-ith per=it cc=pliance due to intake water quality.
Should you have any questions, do not has teate to call.
Siacerely, W,"
A.iav Terry R[:abian Regi nal Water Quality Manage:
Harrisburg Regional Office TRE:TFJ.:kew f
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.9evi s ice 3 January 21, 1976
-..., u a wy yEALTH or PENNsyg 'NA go kh
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DEPARTMENT OF ENVIRONMENTAL RESOURCES
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2002 Health & Welfare Building Earrisburg, P 7 vania 17120 1
J.m ury 21, 1976 Industrial Wastes Metropolitan v44-en'Cc=pa=y Three Ella Isla=d Lcade=darry Tevnship Daup%d Ccunty s
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R. C. Arncid, Vice-Presf r'an
- Eetropolit:n Edisen Ccupany P. O. Bez 542 Fa'Ad 2,P q lvz=ia 19603
Dear Hr. Arnold:
This is in respc sa to ycur letter of January 5,1976, relative to the Industrial 7astes Per=its for your Three Mile Island Ucclear Station
{k-in Lende=de _f Tcveship, Dauphin County.. Tcu requested clarificatica en the effect of a=hient pH and te=perature in tha river en ycur discharge requirc=ents.
If the pH er te=perature of the intala vater are in excess of the per=it 14 dtatien, your discharge ca==ct exceed these values.
If you havei a.~.f further questicus please feel free to contr.t =e.
very truly ycurs, s,
A Terry E.
abian Regional Water Quality Manager Harrisburg Regie al Office TFJ:jl b3 ar
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?.evis ic.m 1 January 21, 1976
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c NWEALTH or PEN Nsg.
OF.1 ; W gyA CO
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p DEPARTMENT OF ENVIRONMENTAL RESCURCES Ecc= 1002 Eealth & Welfare Building Earrisburg, Pec=sylvania 17120 Dece=ber 10, 1975
.~u Industrial Waste Pernit Nos. 2272202 & 2270204
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Metropolit=n Edison Cc=pany
.-J Three Mile Island Nuclear Station Lecdonderry Township
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Dauphin Cou=ty
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,.011111 P""cu Co=pany P.O. Eox 542 Rand
- 3, Pennsylvania 19603 l
A en:
R. C. Arnold, Vice President Centle=en:
This is in response to your concern that the discharge li=itaticus
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in the subject per=its are being applied on a gross rather than net basis.
We have evaluated the i= pact of defiring the effluent li=itations as net rather than gross, and have fcu=d that in this case there vould be no sig=ificant i= pact on water quality. We therefore agree with ycur request, and hereby revise the above permits for Three Mile Island to reflect net 14-* tations. Obviously, this does not apply to the 14 3-tatices on pH and Te=perature.
We hope that this vill be sufficient to el*-inate any p:eble=s with per=it ecepliance due to intake water quality.
Should you have any questions, do not hesitate to call.
Sincerely, w-
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Terr / R :abian Regiona Water quality Manager Harrisburg Regional Office I?S:TFJ.:kew OC.',l
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Revisica 2 Janu?.ry 21, 197o
ve ms a z un gt pyEALTH or pet 4Nsyt.g-4 ^
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DEPARTMENT OF ENVIRONMENTAL RESOURCES
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1002 Health. & Welfare Buildi=g Harrisburg, Pe=nsylva=la 17120 Ja m ry 11, 1976 Industrd-1 Wastas Metropolita: Edison Cc=pany c
Three Eila Isind Lendc=darry Tcw. ship Dauphin Ccunty
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't. C. Arnold, Vict-President s
Matropolits: Edisen Cc=pany
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P. O. Ecz 542
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Reading, Pe==sylva=in 19603
Dear Mr. Arscid:
This is in respcuse to your letter of January 5,1976, relative to the Industrial Wastes Pemits for ycur Three Mile Island Nuclear Statien
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in Leedcederry Tew= ship, Dauphin County.. Teu requested clarificatien cn the effect of a=hient pH and tc=perature in the river en ycur discharge requirc=ents.
If the pH or te=perature of the int:1e water are in excess of the pe = it li=itatics, your discharge ca==ct exceed those values.
If ycu have any further questions.please feel free to contact me.
Very truly ycurs, TerryK.pe A
W Fabian Regicnal k'ater Quality Manager Harrisburg Regiceal Office TFJ:fl 83 2C0 1
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s{t 6 E e'.~i S i O T 2 Jar.n q 21, 1976
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y/EALTH or PEN Ns
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Cccie,h DEPARTMENT OF ENVIRCNMENTAL RESOURCES
~cC '3 - 4 3 Roos 1002 Health & Welf are Ecilding
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Harrisburg, Pennsylvania l'120 C#
gC (717) 787-9665 rf
' %o January 6,1977 g"
~ /x Industrial Waste Per=it No. 2270204 Three Mile Island Nuclear Station Londonderry Toveship
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Dauphin County h
'b 'f Mr. L. L. Lawyer, Manager
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Operational Quality Assurance e
K Metropolitan Edison Conpany 4
P.O. Fox 542 g
Reading, Pennsylvania 19603
Dear Mr. Lawyer:
In reply to your letter of Dece=ber 22, 1976 concerning the a=endment of the above centioned permit, please be advised that these changr.s are hereby being approved by this office; and all =aterial subritted in this matter shall be incorporated as a part of the said 'per=1t.
Very truly yours, NiYd' d/
7
' James V. Donato, P.E.
Chief. Facilities Section Harrisburg Regional Of fice JVD:kew OI$.0?((
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.m O DEPARTMENT OF ENVIRONMENTAL RESOURCES uv Room 1002 Health & ',Telf are Building Ih Harrisb:rg, 'iennsyi,vania 17120 (717) 787-9665 January 11, 1977 i
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',d ' m -, e r b Industrial Waste Permit No. 2270204
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Three Mile Island Nuclear Station I
Londonderry To mship
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Dauphin County j
'* I2 1977 I GENERATjON Mr. L. L. Lawyer, Manager Operational Quality Assurance
/
Metropolitan Edison Conpany g
P.O. Box 542 g
Reading, PA 19603 F.
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Dear Mr. Lawyer:
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In response to a call from Courtney S=yth on my letter of January 6, li 1977, the proposed change in filters is approved and has been made a part of the records under Pe=it No. 2270204. The specific documents incor-2 porated in the permit are Mr. Lawyer's letter of December 22, 1976, i
Module 26-G-1 with attachments dated Decenber 9,1976.
Very truly yours, D.
/ Lt1 Ja=es V. Donato, P.E.
Chief, Facilities Section Harrisburg Regional Office JVD:j m E3 ?G
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Industrial Wastes October 24, 1975 Page ;
Fer=it No.
2270204
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This supercedes the Special Condition I in your permit dated August 17, 1971.
I.
The following li=its and conditions shall apply for the centrolled release of radioactive =aterials in liquid effluents to the environs:
1.
The calculated annual dose above background to an individual in an unrestricted area should not ;xceed 3 n:a= to the whole body or 10 = rem to any organ.
2.
The concentration of radioactive =aterials released in liquid wastes from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Colu=n 2, for unrestricted areas.
3.
The talease rate of radioactive materials in liquid wastes, excluding critium and dissolved gases, shall not exceed i
10 Ci/ reactor / calendar quarter.
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4.
During the release of radioactive wastes, the effluent control l
=enitor shall be set to alars and to initiate the automatic
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closure of the waste discharge valve prior to exceeding the limits specified in 2 above.
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I 5.
The operability of the autoctatic isolation valves in the liquid f
discharge lines shall be de=enstraced annually.
6.
When the release rate of radioactive materials in liquid wastes, excluding critius and dissolved gases, exceeds 2.5 C1/ calendar I
quarter / reactor, the per=ittee shall make an im estigation to identify the causes for such release rates, define and initiate a program of action to reduce such release rates to the design i
objective levels, and report these actions to the Fa. DER within 1
30 days from the end of the quarter during which the release I
occu n ed.
l 7.
The =axi=t:::2 a=ount of tritium released per reactor pei calendar.
year shall not exceed 1,000 curies.
83 03
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Both progra s described in (a) and (b) vill be continued fer two yet.rs.
Reportin: Fecuirements
'"he results of this prcgra: vill be included in the as ual Invirc = ental Mccitering Reper as defined in Sectic 5.6.13.
Bases Measurement of species cc=pesitice, relative abundance, and relative desinance vin deter =ine chssges in the natu al vegetative cc== unity that may be due to statics cperatics. Increases er decreases in certain species shculd beccue evident if they do in fact occur.
Exa=1-natice of vegetatice for physical discrders vill indicate if salt da= age is cecurring with respect to actual injury er death of plants.
3.2 IIVIRCNMrt"AL RADICLCGIC E MCNITCREiG Cbfeetive An envircemen* al radic1cgical =ccitoring progrs= shan be cceducted to verify that radioactive releases are within allevable li=its and that statics cperatices have no detrimental effect en the envircement.
Specificatices A.
Envirce= ental sa=ples shall be ecliected and analyced acccrding to Table 3.2-1 at the locaticas presented in Figures 3.2-1, 3.2-2, 3.2-3, 3.2-h, and 3.2-5.
3.
Reports shall be sut=itted in.teccrdance with the require =ents of Sectic: 5.6 (Statics Repert'.*g Require =ents).
C.
During the seascer that animals producing sin fer human ecusu=ptics are ce pasture, sw ples of fresh =12 vin be obtained =cuthly frc=
these ani=als at locatices presented in Table 3.2-1 and analyced for their radioicdine ccetent, calculated as icdine-131. Suitable ana-lytical procedures vill be used to deter =ine the radiciodine cct-centratic to a sensitivity of 0 5 picccurie per liter, the ecunting errer (cce sissa eccfidence level) cf the analysis vill be withi : 251.
Results vill be repcrted with associated esiculated errer, as picccuries of I-131 per liter cf =in at the time cf sa=pling.
Special attentic vill be pali to these locatices where sin is pre-duced fcr direct ecusu=ptice by hu=ans, e.g., the fe=ily far..
D.
A census vin be cceducted annually (during the =idpcist of the gracing seasen) to determine the locatice of mill-producing an'-='s in j
cetentially affected areas.
N,.".M
- ik -
Rev.1 (3/30/77)
l E.
'4eekly samples =ay be missed in the event of adverse cendti:ns, such as veather, equi;=ent failure, etc.
- 4eekly sanples that are =issed vill not ie rescheduled and the next semple vill te taken :n the next scheduled sa=ple date, after the adverse :enditica nc icnger exists l
Or the equipment failure is rectified. M0nthly sed lenger period semples, if =issed due to these ccnditiens, vill be taken within a rassenable time l
after the adverse cendition no lenger exists. All deviatiens frc= the sampling schedule s hall be described in the annual repcrt.
Bases The number and distributien of semp2ing locatiens and the vericus types of reasurements described in Table 3.2-1 tcgether with the preeperati:nal backgrcund data, vill provide verification cf the effe:Greness of staticn effluent centrol and indication of measurable changes in the activity Of the environ =ent.
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TABLE 3.2-1 RADIOLOGICAL ENVIRONMENTAL SAMPLING No. of Sample Stations Collect ion /Analys is Siuupl e Indicator linck g round
'lype of Analysis (LLD)
Frequency Coll *ction Site Aquatic Vegetation (l) 2 1
GS (2)
Semi-Annually,J uly See Fig. 3.2-1 i
and October (if available)
Soil 8
3 GS (2) 1/3 years 40 Strontium 150 pCi/Kg(dry) 1/3 years Beer 1
1 GS (2)
Annually (1) Composite of all samples for the month or quarter in two groups - Background Samples and Indicator Samples.
(2)LLD's are based on Met-Ed data, vendors data, and EPA Surveillance Guide ORP/SID 72-2.
(3) Shelly & Kohr Island TLD's (3) vill be changed semi-annually.
(1 )In the event of icing or dangerous conditions on the Susquehanna River, the sampling frequency may be 4
extended unt.il river conditions permit sampling.
(5) River unter samples will be ecllected weekly and composited for monthly and quarterly analyseu.
A SH-89 analysis will be performed on each sample analyzed for SH-90 if the SH-90 value exceeds the 10 pC1/L.
NOTE: GB = Gross Beta GS = Gamma Scan
'y Rev. 1 ( 3/ 30/77) c?.
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Cc pcrate respcnsibility for implementation of the Eviren= ental Technical Specifications, and for assuring that station cperations are centrelled to previde prctectica for the enviren=ent and for coordination of hvironmental Technical Specifications with Safety Technical Specificatiens has been assigned by the President of Metrepelitan Edisen Cc=pany to the Vice President k Manager - Generation Division.
Management responsibilities at the plant level, for cc=pliance with the Enviren= ental Technical Specifications, rest with the Statien Superintendent /
Senior Unit Superintendent thrcugh the Unit Superintendents, and the Superviser of Radiation Protectica and Chemistry. Management respensibilities for the Enviren= ental Menitoring Program required by the Envirec= ental Technical Specificatiens rest with the Manager - Generation hgineering, and are carried cut by the Superviser - Radiation Safety and hviren= ental Engineering.
Independent audit and review functicns may te provided for all =atters by the Quality Assurance / Quality Centrol Section, under the directicn of the Manager - Generation Quality Assurance. Additionally, these sections of the Inviron= ental Technical Specificatiens which are not i=ple=ented by the Manager - Generatica Z:gineering through the Radiatien Safety and Enviren ental Engineering (RS&EE) Section =ay be audited and reviewed by the RS&EI Section.
.5.2 CRGAN:'AT!c3 The organicatica for perfer=ing, reviewing, auditing, envirennental nenitoring, or surveillance activities is shcvn in F1 ure 5 2-1 6
I l
5.3 REVIEW AND AUDIT e
i Independent reviev and audit for enviren= ental =atters vill be perferred under the direction cf the Ma. nager - Generation Quality Assurance. Se j
review or audit vill be cenducted by the Quality Assurance / Quality Centrol Section reperting to the Manager - Generatien Quality Assurance.
- dependent reviev fer =atters net i=plemented by the RS&EE section reper-ing to the Manager - Generatien Engineering =ay be performed either by the above =entioned Quality Assurance / Quality Centrol Section er by the RS&EE Section.
"he abcve mentiened independent audit and reviev shall enec pass:
A)
Ccordination of hviren= ental Technical Specificaticns development with the Safety Technical Specificatiens to avoid ecnflicts and maintain consistency.
83.?10 Rev. 1 (3/3C/77)
3/
Proposed changes to the Enviren= ental Technical Specifications and evaluated i= pact of the change.
C)
Propcsed written precedures, as descrihed in Sectica 5 5, and prepcsed changes thereto, which affect the environmental i= pact of the station.
D)
Frcposed changes er =cdificaticns to station er unit equipment, or syste=s which =ight have an enviren= ental i= pact to deter =ine the enviren= ental i= pact of the cha=ge.
E)
Results of the Enviren= ental Monitoring Progra=s prior to their suhmittal in each Enviren= ental Menitoring F.epert (descrihed in 5.6.1).
F)
Investigaticas of all reported instances of viciation of Envirc = ental Technical Specifications, associated corrective acticn, and =easures taken to prevent recurrence.
Auditing of enviren= ental activities which are ec= ducted under the direction and centrol of the Manager - Generation Quality Assurance, will 'ce ccnducted in accordance with the Operational Quality Asst snee Plan.
b5?$
.'? *.1 Pev. 1 (3/30/77)
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ss
B.
Enviren= ental Menitoring (1) A report on enviren= ental surveillance progra=s for the previous twelve =enths operations will be sub=1tted in writing to the Director of Licensing, U.S. Neclear Regulatory Coenissien, Wash 1=gton, D.C. as part of the Annual Operating Report within 90 days after January 1 of each year. The report will su==arize the results of the enviren= ental activities for the twelve-nonth period and the observed i= pacts of the station operation on the enviro n=en t.
(2) In the event that some results or evaluations are not available within the 90-day period, the report shall be submitted noting and explaining the reasons for the
=issing information. This =1ssing infor=atien shall be m2b=1tted as soon as possible in a supple =entary report.
5.6.2 Non-Routina Recorts A.
Radioactive Discharee The non-routine reporting require =ents for radioactive dis-charges are specified in Suction 2.4 of these Envf ron= ental Technical Specifications.
B.
Radiological Enviren= ental Menitoring (1) Anenalous Measure =ents (a)
If, during any twelve-=cnth report period, a =easured level of radioactivity in any environ = ental =edium other than those associated with gasecus rr.dioicdine releases exceeds ten times the mean of the acolicable orecoerationa/coerational control statien data, or lackicz this value, ten ti=es the applicable centrol station data, a written notification vill be submit;ed within 30 days, advising the NRC of this cenditient.
l This notification should include an evaluation of any release conditions, enviren= ental factors, or ether aspects necessary to explain the anc=alous result.
lIn case of a tentatively anc=alous value for radiostrentiu=, a ccafir=atory reanalysis of the original, a duplicate, or a new sample =ay be desirable.
In this instance, the results of the confir=atory analysis shall be completed at the earliest ti=e censistent with the analysis, and if the high value is real, the report to the NRC shall be sub=itted within ten days following this analysis report.
[L"] # $3 (b)
If, during any twelve-=cnth repcrt period, a =easured level of radioactivity in any enviren= ental mediu= other than those associated with gasecus radioicdine releases excee's the Investigatien level (Section 2 below), the d
f711cving action vill be taken:
1.
Confir= Cata By:
~.
Verificatien of sa=ple integrity, i
11.
Ccnfirming calculatiens, iii. Confirming ner=al instru=ent operation.
2.
Investicate Cause 1.
An investigation of levels of radiation er cencentra* ions of radicactive material which exceed investigation levels but are less than reporting levels vill be docu=ented.
ii. Docu=entation vill include discussion of probable cause and corrective action if required.
(2) Investi:ation Level (Criteria for when a centrol station value is exceeded.)
(a) This value has not been exceeded if there is a 99.9%
probability of it belonging to the background er control statien data population distribution.
This means that 0.1% of the time this value vill be said to be different frc= the background, when in fact, it is not different.
(b) The li-4ts for this criteria are expressed as:
( l a of I x 3.1) + 5; where X is the =ean and c = cne standard deviation - if the data point is greater than (background + 3.lc of background), then the investigatien level has been reached.
i (3)
Mi"< "'**vay Measure =ents If = ilk sa=ples collected ever a calendar quarter shev average concentratiens of 10 ricccuries ter liter or greater, a pian shall be submitted within 30 days advising the NRC of the propcsed action to ensure the statien-related annual deses vill be vithin the design cbjective of 15 =re=/ year to the thyroid of any individual.
i 3e -
'3 $ j((3
(k) If levels of radiation er radicactive material can be reascnably shewn to result frc= sources other than the licensed statien the reporting actions in 5.6.2 Non-Rcutine Reperts need not be taken. Justification for assigning high levels of radicactivity to sources other than the plant shall te prcvided in the annual report.
5.6.3 chanzes A.
When a change to the staticn design, to the statien operaticn, er to the procedures described in Section 5 5 is planned which veuld have a significant adverse effect en the enviren=ent er which involves an environmental =atter er questien net previcusly reviewed and evaluated by the NEC, a repcrt en the change vill be =ade to the KRC prior to i=ple=entation. The report vill include a description and evaluation of the change including a supporting benefit-cost analysis.
3.
Changes or additions to per=its and certificates required by federal, state, local, and regional authorities for the protecticn of the environ =ent will be reported. When the required changes are submitted to the concerned agency for approval, they vill also be submitted to the Deputy Directer for Reacter Projects, Directorate of Licensing, U. S. NEC, for infor=ation. The sub=ittal vill include an evaluation of the enviren= ental impact of the change.
C.
Requests for changes in Enviren= ental Technical Specifications vill be sub=itted to the Deputy Director for Reactor Projects, Directorate of Licensing, U. S. NRC, for prier review and authorisation. The request vill include an evaluatien of the i= pact of the change, including a supporting benefit-cost analysis.
5.6.h other If har=ful effects er evidence of irreversible da-a;e are detected by the =cnitoring pregrams, the Licensee vill provide an analysis of the problem and vill develop a course of action to be taken to alleviate the probler. If the ecclegy of the river significantly changes at a future date as, for exa=ple, by =ajor changes in water chemistry er reintroduction of shad, the Licensee vill provide an analysis of expected i= pacts and a course of acticn to =inimize the impacts.
a,;.
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A.
Records and legs relative to the fc11cving areas vill be retained for life of the station.
(1) Records a.d drawing changes reflecting statien and unit design changes nade to syste=s and equip =ent as described in Section 5.6.3.
k$,3' ~ '57 ? M (2) Records of enviren= ental su m e111ance data.
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