ML19206B399
| ML19206B399 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/15/1976 |
| From: | Arnold R Jersey Central Power & Light Co, Metropolitan Edison Co, Pennsylvania Electric Co |
| To: | |
| Shared Package | |
| ML19206B396 | List: |
| References | |
| NUDOCS 7905090442 | |
| Download: ML19206B399 (9) | |
Text
{{#Wiki_filter:METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLMID NUCLEAR STATION UNIT 2 Application For Class 104 b Utilization Facility Operating License DOCKET No. 50 320 Applicant herewith submits forty (40) copies of responses to co=ments made by Iocal, State, and Federal agenc'.es in connection with che Commission's Draf t Supplement to the Final Environ = ental Statement for Three Mile Island Nuclear Station Unit 2. METROPOLITRI EDISON COMPMiY ATIEST: f M h By: /' L /- assistant Secretary Vice Presideit' k Sworn to and subscribed before me this day of M 1976. Notary Pul[l tic ~ qi 1 - ryfz-- gu-N,, L. J '7 90 l2 0 9 0 WZ
APPLICANT'S RESPONSE TO THE U.S. ENVIRORIENTAL PROTECTION AGENCIES' CCMMENTS on the NUCLEAR REGULATORY COMMISSION'S Draft Supplement to the Final Environmental Statement RELATED TO THE OPERATION OF THREE MILE ISLA..J NUCLEAR STATION, UNIT 2 DOCKET No. 50-320 NOVEMBER, 1976 G '! n ') L*
CCM2.TT A ".4.e radicac:ive ef.";uen:s used in the doce ecmputaricna care thcec catimated by :he a:aff to recscnch y characterize che w.aa: release cf radicac: ire materia:. :: ccuid have been helpful :c ccmpare these uith ac:uci release data frcm the ccrianien ;
- ant, DiI- :. "
RESPONSE
c e c. en.4.,g ": y-{4 -so' + Effluent release data for CC-1 was included in.a.. j g, 5 f0T -?' an \\. Radioactive Iffluen s" in 'he DC-1 Semi-Annual Eep0T*3 cc=raris n. enclosei are Tables 2 L and 3-3 taken frc= the AppenJX * "na s m. ZG' 1 filed with the Cc: =ission on June k,1976. The infor=ation contained in the M-1 Semi-Annual Reports shows the actual release data through 1975. The inf or=ation taken f rom the Appendix ! Analysis indicates annual average release infor=ation as predicted by that analysis. It must be pointed out that the actual radioactive effluents released will fluctuate as a functica of Radwaste System operatien. ~herefore, any co=parisons should be perforced over a period of several years to obtain more meaningful data. CCSCG.V: 9 "'ha staff reaches the ccne:ucien that therc vill be no measurable impcot cn mn frce rcutine cperaticn of :MI-2. Ecdioicgical envircnnental mcnitoring reports fecm Unit 1 have shcun a very amati, but meccurable iqcat. It aculd be helpful in the final state-ent if a:t infor-aticn bearing upcn the radicicgical impact is s:.rrarized. " RESPOiSE The operational Radiological Environ = ental Mcnitoring Progra= conducted by Met -Ed and its consultant, Radiation Management Corporation, has been collecting data since June 5,1974. To date, the Radiological Environ = ental Monitoring Reports, which have been submitted to the N~AC, indicate that *MI-l has had very little af fect on the surrounding environ =ent. Although the Radiological Environmental Menitoring Progra=s considered =any other possible dose pathways to man in the environs of the IMI site, Tritium, CC-60, I-131, and Co-58 were the only radionuclides of ni!NS crigin detected above background levels with only CO-58 and CO-60 potentially contributing to dese. The radiation dose to people from ambient Ga==a radiaticn, as =casured by ther=clu=inescent dosimeters, averaged 5.3 =re=/=onth to date and showed no evidence of a TMINS centributien since the unit began operation. ~he radiatien dose to people in the DiINS environs reported to date is as fcilews: Source of Excesure Annual Dose in =ren Tritium in Vater 0.002 q 'I } CO-60 in Water <0.1 y CO-58 in Sediment <0.1 'l'N L' L. The TMI-l dose centribution to population exposure is very s=all (approxi=ately O.1% of that frc= other sources). Therefore, it can be concluded that cper-
- t. tion of TMI-l did not significantly alter the radiological characteristics of the 211NS environs. The radionuclides and radiation levels observed were principally due tc natural radioactivity and global fallout.
CCM:,': C ":he stare ther ci erandard is inadcq:ctely defined in the repcrt. It dces not specify hcv c: where this standard vill be applied pursuan: to Secticn 37.82 c. ar.d b. of the PennsyEvania Stare Water icus.
- he."P:ES pc&t issued by EFA to.3!DS, effective December 30, 1976 irrcsed an effluent liritation of 87'? for the prctecticn of the aqua:ic ccer:w:ity.
PennsyEvanic later c; proved Metropolitan Edison's request to discharge at the ambient receiving strec~t tempem:ure uhen the tmpemture is abcve 87*F. De ccmx:ny is trying to nego:iate a ucrkable applicchicn of the 5*? rise ti.dtaticn with the Stare. Be final supplement shculd report hcu this prcycsed variance vill affect the cpplicaticn of thermal standa:ds a .3'Z: 5. "
RESPONSE
The Pennsylvania Department of Environ:cental Resources (DER) pro =ulgated Industrial k'aste Regulations pursuant to its authority u. der the Clean Streams Law. Section 97.82 (a) and (b) of the Industrial Waste Regulaticns limit thermal discharges to the following: 197.82 Allowable Discharges (a) The heat centent of discharges shall be limited to an amount which could not raise the temperature of the entire strea: at the point of discharge 5*F above a=bient te=perature or a =aximum of 87'F, whichever is less, nor change the te=perature by = ore than 2*F during any one-hour period, assuming co=plete mixing, but the beat content of discharges may be increased or further li=1ted where location conditicus would be benefited thereby. (b) If downstrea= circumstances earrant, the specific area in which the te=perature may be artificially raised above 87'? or greater than 5'? above a=bient temperature or by = ore than 2*F during any one-hour period shall be prescribed. Section 97.82 (a) of the regulaticus limits the discharge from raising or changing the temperature of the entire strea at the point of discharge by said a=ounts. All data collected by the Applicant's consultant to date, support the centention that the TMI-l discharge will not exceed these limits, nor is it expected that the addit:.onal discharge volume that will result from the operation of TMI-2 will cxceed these li=itations. The require =ents for.cc=pliance with these limitations assu=e =easurc=ent af ter co=clete =ixing. The ter= cc=plete mixing is not defined in the regulation. As a result, it is not clear hcw or where the discharge limitaticns should be 3FP ied. l r)} L. t_
Since the f 7 f./" e.d the 2 F/hcur change li='ta* 4 -- ~~~+Se met censistenti/ 0 at the peint of dir:harge,.Me:-Ed is planning to negctiate with the DIF. in Order to define a thermal 21.cing :One, at the edge c f which these ' '" * "' ~ s vculd e.pply. 3-/ =cnitoring at the peint cf discharge and meeting the applicable limits within a few degrees at the discharge, :: pliance with the limits at the edge Of the mixing :One vill be assured. C:MC i 3 "In light of the Neen: Nicicgical data collected at the site, the final supplerent shculi shcu the tccation of the in:cke structurs' in reta:icn to k7:cun sic:,;1:ing crecs in the vicinity of the pcuer plant. "
RESPONSE
Presently, there are no specific data a milable to identify major spawning iccati:ns within Lake Frederic. Field observations cade in the i==ediate vicinity of the intake structures and results of ichthyoplankton entrainment studies as carried out as part of the TMI-l Environ = ental Technical Specifications by the Applicant's consultant, Ichthyolegical Associates, Inc., indicate that there are nc =ajor spawning areas in the inz:lediate vicinity of the intake structures. CCM"iT E "It is enccuraging to see a discussicn of the possible tecith haza:rls due to induced elsetric field effects and to read that the appl 1 cant is corr ~:tted to ta:dertake a seriee of safety steps in this crec. EPA is ccncerned, hcuever, vith the 500 XV trans~issicn line that crosses Fennsylvanic ? cute
- C0 ecs: of Sechteisville, and uculd like to have this transmission line included in ali safetg impic enta:icn plans regarding induced field effects. "
RESPONSE
As the EPA suggests, the Applicant will include that section of the 500 KV transmission line which crosses Pennsylvania Route 100 east ef Sechtelsville in its safety i=plementation plans. These plans include inferming property evners of possible electrestatic effects and precautions that can be taken to mini _1ze such effects prior to line operation. The Applicant will also ~ take field =easure=ents at the crossing of Route 100 once this line beccces energized to identify the potential for such occurrences. The Applicant wishes to point cut that these actions are consistent with the Appliennt's nor=al practices. ,. f (J L'. t n, r3 COMM ONWEALTH O F' PENNSYLVANIA (g g ,g$[4~,4 9j PENNSYLVANIA HISTORICAL AND MUSEUM COMMISSION
- t-witui.-.c ~ ~ - c-e.iic -u.cu -.~ o a c ~ive su itoi n a ECM 1024
-.R Ni S A u R G. Mc N N S YLV.N I A 17120 October 27, 1976 Mr. D. Callahan Envircraental Engineer GPI' Service Corporation 26C Cherty Hill Road Par::1ppany, New Jerrey 070f+
Dear Mr. Callahan:
As far as we can tell the continued operation of the Three Mile Island Nuclear Generating Station will not affect any historic or archaeological site. Sincer 7 yours . C' Vance P. Packard Office of Historic Preservation I o 'I ', qf 61 ad
PlSULTS OF FURTHER ITIESTICATION I'iTO THE UN!TED STATES DEPAR'"ME'iT OF TEE I'L"ERICR' S CCMMENT CN " FISH RR LS" Further investigation by the Applicant as to the source of the U. S. Department of the Interior's co==ent pertaining to " fish kills", revealed that the local Pennsylvania Fish Ccemission's waterway patrolman observed a number of dead fish along the western shore of Three Mile Island (TMI) downstream f rem the station during the spring of 1974 and 1975. A telephone conversation between the Applicant and the waterway patrelenn who observed these occurrences identified the following: (1) the dead fish were observed between April and Y2y of 1974 and 1975, I2) the number of dead fish observed during these occurrences was roughly 200 in 1974 and 300 in 1975, and (3) the dead fish, although observed downstream from the station discharge, could not be attributed to station operation since the fish observed were dead for several days, which suggests they died at a core distant upstrzam location and were washed ashore at IMI. Although the Applicant cannot deter =ine the exact cause of these occur-rences, we do wish to point out that fish die regularly throughout the year in large rivers like the Susquehanna due to natural causes, such as old age, parasites, disease, etc. Dead fish are observed more of ten in the spring of the year. The deaths of =any of these fish can be attributed to bac te-ial diseases, such as Aerocones. The Applicant wishes to emphasize thu fact that " fish kills" did not occur during the spring of 1974 and 1975, or at any other time which could be attributable to thermal or chemical discharges from Three ! Ele Island Nuclear Station as suggested by the U. S. Department of the Interior. 'il] 9) b' t.,
05/31/76 TAALE 2-4 c ' ) R LEASES -- 8ASE CASE C LICUIO (CURIES / YEAR) ISOTCPE RELEAFE H----3 5 00E+02 CR--51 1 70E-04 i' MN--54 4 10E-05 .2 FE--55 1 80E-04 FE--59
- 9. ROE-05 Idy CO--98 1 60E-03 CO--60 2 105-04 d
d 9R--83 3 00E-05 4 0.0--86 3 10E-05 ,j SR--89 3.90E-05 Q SR--91 1 705-05 Y--91M 1 10E-05 q M0'-99 4.90E-02 g 1 TC-99M 3.00E-02 TE127M 2 40E-05 j TE-127 3 70E-05 TE129M 1 30E-04 TF-129 8.50E-05 TE131M 4 90E-05 T5-132 1 30E-03 I--130 6.70E-05 I--131 3.4 0 E-0 2 q I--132 s.708-03 I--133 1 60E-02 I--134 1.40E-05 I--135 4.108-03 CS-134 1.90E-02 CS-136 3.70E-03 CS-137 1 40E-02 9A137H 1.30E-02 GA-140 1.60E-05 LA-140 1 10E-05 NP-239 7.00E-05 OTHERS 6 10E-05 I t, -) o ',3 c u
/ - l I 06/01/76 Ta9LE 3-1 CA3 ECUS ' E4 5 asis -- 9 ASE CASE (CU4IE!/vE41 i C.EL E A S E FCOM ~ I ILOTCPE rLANT VENT TU44INc VENT TOTAL H----3 3.40E+02 1 70E+02 5 10E+02 C---14 4 00E+00 0. S.00E+C0
- R--41 2 50:+01 0.
2.50E+31 PN--54 2 2SE-04 J. 2.25E-34 CE--59 7.59E-05 3. 7.5AE-05 CO--58 7 59E-04 0. 7.59E-04 Co--60 3 44c-04 3. 3.44E-04 KR-59M 2.CO E +0 0 - 0.
- 2. JOE +00
<R--85 1 95E+02 0. 1.95E+02 KR--86 3 00E+C3 1 00E*00 4.00E+00 54--89 1.F55-05 0. 1.65E-35 53--90 3 04E-Ou 0. 3.04E-06 XE131M 1 70E+01 3. 1.70E+31 XE133M 2 20E+01 1 00E+00 2,30E+01 XE-133 2 31E+G3 6 10E+01 P.37E+0? i XE-135 1 20E+01 ?.00E+00 1.40E601 I--in 5 29E-G3 3 29E-02 3.32E-02 I--133 5 51s-03 3.4 0 E-0 2 3.95E-02 CS-134 2 2SE-04 3. 2.285-04 CS-137 3 79E-04 0. 3.79E-J4 cf ' r o3 L}}