ML17326B385
| ML17326B385 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/16/1988 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | John Miller AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 8805250170 | |
| Download: ML17326B385 (10) | |
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0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION wAsHINGToN, D. c. 20555 8EI05Q50 f70 8805/6 May 16 1988 -,
PDR ADOCH; 05000315 f
PDR Dr. Joseph Miller Associate Professor Department of Justice Education Saint Mary's College Notre Dame, Indiana 46556-5001
Dear Dr. Miller:
Your May 4, 1988,.letter requested information about the approval by the Nuclear Regulatory Comission (NRC) staff of the repair of the Unit 2 steam generators at the Donald C.
Cook Nuclear Plant.
In addition, your request for information related to whether the NRC could approve this repair, which requires an amendment to the operating license without providing any opportunity for citizen input or without requiring the utility to submit an environmental impact statement; whether the bottom sections of old steam generators are classified as high or low level radioactive waste; and any overall economic and safety records for the D. C.
Cook and Palisades Nuclear Plants.
Enclosure 1 is a copy of Amendment 100 to Facility Operating License No.
DPR-77 for the Donald C.
Cook Nuclear Plant, Unit 2.
The amendment approved the steam generator repair program as proposed by Indiana Michiga'n Power Company (IMPC) and provides a license condition related to the repair program.
Prior to issuing the amendment, the NRC published in the Federal Register a "Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Prior Hearing".
This notice alerted the public of the.NRC's intent to issue the amendment and gave the public an opportunity to petition the NRC for a hearing.
Enclosure 2 is a
copy'f the notice published in the Federal Register.
No petitions for hearirg on the amendment were received.
During the preparation of this proposed amendment, the NRC reviewed the environmental impact of the steam generator repair in accordance with the requirements set forth in 10 CFR Part 51 of the NRC regulations.
The NRC staff findings were published in the Federal Register.
Enclosure 3 is a
copy of the Federal Register Notice.
The NRC staff concluded that there were no significant radiological or nonradiological impacts associated with the repair of the steam generator and that the repair would not have a significant impact on the quality of the human environment; therefore, a full environmental impact statement was not necessary.
The contamination levels in the steam generator lower assemblies are such that, if prepared for burial, the resultant waste packages would be classified as Class A low-level disposal category.
This classification is determined by the waste classification requirements of 10 CFR Part 61.
In reference to your request for economic records, the NRC does not collect economic records on a plant-specific basis;.however, Enclosures 4 and 5 are annual reports for Indiana Michigan Power Company (D. C. Cook) and Consumers
'r. Miller "2-Power Company (Palisades).
These reports contain some economic data concerning the utilities which may be of interest to you.
In reference to your request for safety records, enclosures 6 and 7 are
. Systematic Assessment of Licensee Performance (SALP) reports f'r the D.
C.
Cook and Palisades Nuclear Plants.
The SALP process is an integrated method to collect and evaluate data on the performance of a specific nuclear power plant in a structured manner in order to assess and better understand the reasons for a licensee'-s performance.
The SALP process is intended to be sufficiently diagnostic to provide a rationale for allocating NRC resources and to provide meaningful feedback to a licensee's management.
If you need further detailed information regarding the licensing records of the Palisades and D.
C.
Cook Nuclear Plants, you may wish to visit the local Public Document Rooms.
The local public'document room for the D.
C.
Cook Nuclear Plant is located at the Ma'ude Preston Palenske Memorial Library, 500 Market Street, St.
- Joseph, Michigan 49085.'he local public document room for the Palisades Nuclear Plant is located at the Van Zoeren Library, Hope College, Holland, Michigan 49201.
, Thank you for your interest in our process of ensuring the continued safe operation of nuclear power plants.
Sincerely,
Enclosures:
As stated Denn>s M.
rutch ield, irector Division of Reactor P
jects - III, IV, V 8 Special Projects Office of Nuclear Reactor Regulation cc:
Chairman Department of Justice Education
Or. Miller liay 16, 1988 Power Company (Palisades).
These reports contain some economic data concerning the utilities which may be of interest to you.
In reference to your request for safety records, enclosures 6 and 7 are Systematic Assessment of Licensee Performance (SALP) reports for the D.
C.
Cook and Palisades Nuclear Plants.
The SALP process is an integrated method to collect and evaluate data on the performance of a specific nuclear power plant in a structured manner in order to assess and better understand the reasons for a licensee's performance.
The SALP process is intended to be sufficiently diagnostic to provide a rationale for allocating NRC resources and to provide meaningful feedback to a licensee's management.
If you need further detailed information regarding the licensing records of the Palisades and D.
C.
Cook Nuclear Plants, you may wish to visit the local Public Document Rooms.
The local public document room for the O.
C.
Cook Nuclear Plant is located at the Maude Preston Palenske Memorial Library, 500 Mar ket Street, St.
- Joseph, Michigan 49085.
The local public document room for the Palisades Nuclear Plant is located at the Van Zoeren Library, Hope College, Holland, Michigan 49201.
Thank you for your interest in our process of ensuring the continued safe operation of nuclear power plants.
Sincerely, original signed by
Enclosures:
As stated Dennis M. Crutchfield, Director Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation 88 OFFICE:
Tech Ed.
SURNAME:
A.
Ka to ski DATE:
05/13/88 cc:
Chairman Department of Justic Education OFFICE:
RSP 8
P D:
SURNAME:
RIn am JSP&ng/
1 Dhfdl ler GHol an DCrutchfiel d DATE:
05'/88 05/jg/88 05/y$ /88 05/I(/88
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DISTRIBUTION
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SECY (3)
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STELLO D.
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W/INCOMING P.
SHEA J.
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- y Federal Regbter. / Vo). 52. ND. 53 / Thursday, March 19; 19IP:/"Notices 'nC1OSure sy construction permit ofany utQity that.-. <;
.does not meet the proposed ><~:y;~: <9'.
requ(rements that emerge &om (3). 'lie " ~
UCS'equests concern Arkansas '.".".,
Nuclear One, Unit No. 1, Crystal River:
Unit 3'Nuclear Generating Plant, Davls-Besse Nuclear Power Station, Unit No. 2 Ocoiiee Nuclear Statloni Units Nos. 1, 2.
'nd
- 3. Rancho Seco Nuclear Generating Station, Three Mile Island Nudear Station, Unit No. 1, and Bellefonte Nuclear Plant. Units Nos. 1 and 2.
The UCS'etition alleges a variety of design deficiencies in nuclear power plants designed by B&W.Those alleged
~ design deficiencies form the bases for UCS'equests.
The NRC willtreat the petition pursuant to 10 CFR 2.206 (1986) of the Commission's regulations and, accordingly, edu take appropriate acUon.
on its requests within a reasonable time.
Acopy of the petiUon is available for lnspecUon in the Commission's Public Document Room, 1727 H Street NW.,
Washington, DC. 20555, and in the followingLocal Public Document Rooms:
Tainlinson Ubrary. Arkansas Tech
'University. Russettvillc. Arkansas 72801.
~
Crystal River Public Ubraiy, 688 N.W.
First'venue, Crystal River, Florida 32629.
~
Sacramento City~unty Library; 828 I Street. Sacramento. California 95813.
Government Publications Section, State Ubraiy of Pennsyh anta. Education Building.
Commonwealth and Walnut Streets,.
Harrisburg. Pennsylvania 1712th University ofToledo Ubea~, Documents DepazunenL 2801 Bancroft Avenue. Toledo.
Ohio 4360L Ocanec County Library. 501 West Southbroad Street. Wahaga, South Carolina 29691.
'1, IDockat.ttos 50-.31$ at aQ c'4'-'s', 6-'. I
" Reccel pt of PetIUoti tor Director'a Decision; Arkansas Power & I.ight Co
- Arkansas Nuclear One Unit No.1 etaL Docket No. SM13-Arkc'ngas Power
&'ght Company, Arkansas Nudesr Onc, Units.
Dackcl Na SM48-Toledo Edison Companyi ct al Davis-Besse Nudear Station, Unit No. 1.
Docket Na. 50-322-Sacramenta Municipal UtilityDistrict. Rancho Scca Nuclear Generating Station.
Dackeis Nas. $0-438 end $0-439-Tennessee Valley Authority, Bellefontc Nudear Plant. Units Nas.1 and 2.
Docket Na. SM02-Flartde Power Coeporation, ct clcrystal River Unit 3 Nudear Generating Plant.
Dackcta Naa. 50-289, 50-270 cnd 50-287 Duke Power Company, Ocanec Nudear Station, Units Noa 1. 2 and 3.
Docket Na. 50-289-GPU Nuclear
~
Corporation. ct ct. Three Mile Island Nudear Station. Unit Na.1.
The Nuclear Regulatory Commission (NRC) hereby gives notice that. by petition dated February 20. 2987, the Union of Concerned Scientists (UCS)'equested the NRC (1) to suspend Inmediately the operating licenses and
'onstruction permits ofall utilities
- 'utilities) operating or building nuclear power reactors designedby the Babcock
~
& Wilcox Company (B&W):(2) to require the utilities to modify their B&W.
designed nuclear generating facilities in
'rder to correct certain alleged safety defidenctes; (3) to hold pubic hearings on the sufficiency ofmodifications required in (2) to correct the alleged deficiencies at each plant involved: and, (4) to revoke the nperating license or
~
Scottsbora Public Ubrary, 1002 South petition iu the Nuclear Regulslory Commission
~
Bmad Street. Scatts xiza. Atnbcina 3576L lnduding. as well as the union of Concerned Dated at Bethesda, Maiyiand, this 13th day Sdenusis Thc heksnsss Alliance. Ciuzens forLand of March 2987.
'I a Water Usc. Inc Concerned Citizens uihshtabula Cuunty. Concerned Ceuzcns ot Cesuga County.
For the Nudcar Regulatory Comntssian.
Concerned Citizens ofLake County. Cuyahoga Ftank J. Mtragtta, ActingDircatan Officeaf¹clcar Reaclar Deaiun, Sian Diosiss Enrironmenial Congress of itcgula(iarI Arkansas. Faycticvillc Peace a iustice Ccniee.
Nancy Haiien hLD Newton County Health OfAccr.
(FR Dac. %-$98". Filed 3-18-87: 8:4$ cm)
~
Norman P. Henick Vice-Chairman. Dauphin County Board of Commissioness. Kiski Valley Coslilion ta Save Our Chiusen. Masylsnd Nudesr Ssjcty Coalilion. Nalive Amencsns for ~ Ciean Enrieonment. Noeihem Chio Cliizcns Against persy IDOcket t4O 70-364; Uccnsc NO. SNht 414 S Davis.Bassa. People's Action for ~ Safe EnrironmenI People Agsinsi Nudear Energy. Louis D. Putney. Sacrsmcnisns roe Safe Enesgy, Save Oue Babcock & Wlcox; Issuance Ot, slate Feum Radloacuve waste. s squehanna valley Directors Decision Alliance. Laszio Teazkovich. Shelley Teazkuvich,
'hc Wesiem Rescsvc hiHance. the Custtucn for ~
NoUce is hereby given that the NudcaeyeceCecaiLskes Senate'u" 'mey Ed Director. Office of Nuclear Material Creen, Tlmoihy F. Hagsm Commissionen County nr Cuyshugs. Laesy I. Hochendonen Commissionen 'afety and Safeguards. has taken action
..- Dauphin Cuunty Board of Commissioners. These
=
with regard to Petitioners for ection 649ats)snd hlcsI Tctcdn Cusliucn for Safe Enesgy, under 10 CFR 2 206 received from Ms.
Frances Munko and Mrs. Mildred
~ ': Houccsble Pates C. Wamhach. les n Whne. Cheek
'" OsssL 4gsan Csey nr Cievetsnd.'Aw peuuoness will-., Chelko. dated July 31. 1986, and August gneugecovstg>> thc 1'-,.;.; ~
1, 1986, respectively, with respect to the i
IDockct No. 50-3161 tndiana and Michigan Etectric Co.;
~
Consideration of issuance ot Amendment to Facility Operating ucense and Opportunity tor Prior Hearing; Indiana and Michigan Electric Company The United States Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operation License No. DPR-74 issued to the Indiana and Michigan Electric Company (the licensee), for operation of the Donald C. Cook Nuclear Plant. Unit No. 2 located in Berrien County. Michigan.
The amendment would add a license condition relating to the repair and replacement of the four steam generators in accordance with:he licensee's application fo: amendment dated March 12, 1987 as supplemented by earlier letter dated November 7, 198L Prior to issuance of the proposed license amendment, the Commission willhave made findings required by the
~ v
. i L
r" Babcock & WilcoxParks Township
facility.The PeUUoners request that a
'proceeding be Instituted to revoke the
~.,
'icense for the'fadlity and to require that the site be cleaned up. In addition.':
Ms. Chelko requests that action be" -'.
taken to require that any other site that
.'ontains material or waste from its'.
previous activities and licenses be
'leaned up.
The Director ofthe OHice ofNuclear Material Safety and Safeguards has determined to deny the Petitions. The reasons for this denial are explained in the "Director's Decision under 20 CFR 2.206." (DD-67-05) which is available for
'ublic inspection in the Commission'8 Public Document Room, 1717 H Street, NW,. Washington. DC 20555. A copy of this decision willbe filed with the Secrethry for the Commission'8 review in accordance with 10 CFR 2~[c) of the Commission's regulations. As
'rovided by this regulation, the decision willconstitute the final action of the Commission 25 days after the date of issuance of the decision unless the Commisison on its own motion insUtutes a review of the decision withinthat, time.
Deted ci Siliver Spring. Maryland. this 12th day of March 1987.
For the Nuclear Regulatory Cominislin.
Hugh I Thompson. Jr Director. Ogiccof¹clcar Moterial Safet and Sofegaard>>.
(FR Doc. 87-5988 Filed 3-18-87: 8:45 am]
slLINo coos z6sea i&
Ai Federal Register./ Vol. 52, No. 53 / Thursday. March 19, 1987 / Notices 8681
~!
- -.htomfc Energy Act of1954, as amended the amendment under consideration. A Memorial Library, 5M Market Street, St.
"'lhe Act) and the Commission's petitfoner who fails to fi!e such a., "..
Joseph, Michigan 49085.
- = regufatfans. -,
supplement which satisfies these pated at Beihesds, Msiyfaiid, tbfs 13th day
-':; By April'20,1987, the licensee may fife requirements. with.respect to at least one ofMsicb 1M7. -"
"~ request for a hearing with respect to;
. contention willnot be permitted to
'or the Nuclear Retpifatoiy Commission.'
- lssuance of the'amendment to the participate as a party ""'"'."'
J, Yaungblood,
~ subject facilityoperating license and:....
=
Those permitted to intervene become:
. >';~<~>><p~~'ocr girectorareki; pivisiori any person whose interest may be
~ parties to the proceeding, subject to any
+ypgj~<<~Qg
- effected by this proceeding and who '.".'imitations in the order granting leave to p
87~989 FjJ d 3 1~7 845 sm)
'wishes to participate'as a party in the ',
intervene, and have the opportunity to proceeding must file a writtenpetition participate fullyin the conduct of the -':
for leave to fntervene. Request for a...
hearing, fnc]udfng the opportunity to '-.
~ ':
'-". hearlng and petition for leave to '" =present evidence and crosswxamfne:
IQyggjg tto
~34/]'-
intervene shall be filed in acc'ordance witnesses.
with the Commission's ".Rules of.;
request for a hearing or a petition '
Minerals Expforatfon Co. Pfnaf Finding
'" Practice for Domestfc Licensing, for leave to intervene shall be filed with of No Significant Impact Regardfnf]
<. Proceedings" in 10 CFR Part 2. Ifa the Secretary of the Commission, United Termfnatfon of Source Material
, request for hear]ng or petition for leave States Nuclear Regulatory Commission
. Ucense'SUA-1223 for the Minerals to intervene is filed by the above date, '! Washington, DC 20555, Attention:
" "'xploration Company R80 in Situ
~
the Commission or an Atomic Safety
., Docketing and Service Branch. or may 'each facility,Located in Sweetwater
-r. and Licensing Board, and designated by be delivered to the Commission's Public
. County ~
the Commission or by the Chairman of
~
Document Room. 1717 H Street NW
'he Atomic Safetymd Licensing Board Wash>>8ton, Dcby the above date. "
A0EN~U.S.NuclearRegufatory
..'" Panel, willrule on the request and/or Where petitions are filed during the last petition and the Secretary or the ten (10) days of the notice period. itfs...
porto~: Notice of<<ndfn8 af na -".!
designated Atomic Safety and Licensing requested that the petitioner or ~,;
~
signi<<<<n'pact.
Board willissue a notice of hearing or representative of the petitioner promptly an appropriate order. ',
~,
so inform the Commission by a toff-free (1) Proposed Ac"on,
~
- !.'s required by 10 CFR?.714, a telephone call to Western Union at (800)
The U.S. Nuclear Regu]atory
.'. petition for leave to intervene shall set 32~ (in Missouri (800) 34~700),,
Commission (the Commission) is forth with particularity the interest of The Western Union operator should be proposing to terminate Source Material the petitioner fn the proceeding, and given Datagram Identificatfon Number 'cense SUA-1223 for the hfinerals how'that interest may be affected by the 3737 and the followingmessage Exploration Company's AARkD in situ results of the proceeding. The petition addressed to B. J. Youngblood:.; '"'
leach facilitylocated in Sweetwater should specifically explain the reasons (petitioner's name and telephone County, Wyoming.
why intervention should be permitted number); (date petition was mailed);
with particular reference to the (plant name); and (publication date and
)
a th F>>ding following factors: (1) The nature of the page number of this Federal Registe~',
S 8 <<~
petitioner's right under the Act to be
~
notice). A copy of the petition should
=.
The Commission's Uranium Recovery made a party to the proceeding; (2) the -'lso be sent to the Of<<ce, of General Field Office has reviewed the Minerals nature and extent of the petitioner's Cousel-Bethesda.U.S.
Nuclear ',
exploration Company's final c]osure property, financial, or other interest in 'egulatory Commission, Washington,'lan and decommissioning activities the proceeding; and (3) the possible DC20555. and to Gerald CharnoK
.. which were performed in accordance effect of any order which may be Esquire, Shaw, Pittman, Potts and with the requirements ofSource entered in the proceeding on the Trowbridge, 1800 M Street, NW.,
Material License SUA-1223. Based on a petitioner's interest. The petition should Washington, DC 20036, attorney for the review of the decommissioning also idenity the speci<<c aspect(s) of the licensee.',
activities, the Cornmissfon has,.
subject matter of the praceeding as to Nontimely filings ofpetitions for leave determined that no signiTicant which petitioner wishes to intervene.
- to intervene. amended petitions, '
environmental impact has resulted.
Anyperson who has filed a petition for supplemental petitions and/or requests The followingstatements support the
~
leave to intervene or who has been
" for hearing willnot be entertained
<<nding ofno sign)i<<icant impact and admitted as a party may emend the absent a determination by the
~
~
summarize the decommissioning petition without requesting leave of the Commission. the presiding officer or the activities:
Board up to fifteen (15) days prior to the presiding Atomic Safety and Licensing (a) Two test patterns were utilized in first prehearing conference scheduled fn Board that the petition and(or request, the A-3 R5D in situ leach project. Test the proceeding. but such an amended should be granted based upon a..:;
pattern A was operated for eight days petition must satisfy the spectificity.
~ balancing of the factors specified in 10
~
bl;ginning on August 2, 1976 using an requirements described above..
~
. CFR?.714(a)(1)(i) through (v) an4
~
ammonium bicarbonate lixivfant.After Not later than<<ifteen(15) days prior to 2.714(d). '""-. ',
~.,;.,:", "
a ten daypump out, aqueous carbonfc the first prehearing conference':.~...,
. Far further details with respect to this acid was used with hydrogen peroxide
-'cheduled in the proceedfng, a petitioner 'ction. see the application for <...." -,
or oxygen as the oxidant. Injection/; ':"
. shall file a supplement to the petition to amendment dated March 12, 1987 as,'. ".: production terminated on March 23, ~:: "!
- .Intervenewhichmustincludealistof supplementedbyearlierletterdated
-..',r.>> 1978.RestorationofTestPatternAwas
..the contentions which are sought.to be.November 7, 1988, both ofwhich are < 'ompleted in September 1978 using a" iitigated in the matter, and the bases for - available forpublic inspection at the
~:;..": ground-water sweep. Post restoration"'ach contention set forth with -<< "'
" Commission's Public Document Room,:..'stability monitoring continued through reaso'nable speci<<city. Contentions'shall, 1717 H Street NWWashington! DC and; '1984. The Commfssfon accepted the::::
be limited to matteis within the scope'of ~at the Maud e Preston Palenske s!.~q.air~; I: restoration on April28. 1986.;%~>i "if.:"'s
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t Enclosure 3.
P jthmi)'ejfsfer f Vo) 52', N0.'2%'
&cdnesdarj", Decimber Wi9Pf:/VSdtts NUCLEAR AEGULATORY COMMISSION fDocket No. 50-21$ I Connecticut Yankee Atomic Power Co.; Haddam Neck Plant; issuance of Knvironmentaf'Assessment and Finding of No Significant impact The U.S. Nucleur Regulatory Cununission (tbe Cummission) ia considering the issuance of u proposed amendment to Facility Operating Lic<.nse No. DPR-61, issued to Connecticut Yankee Atomic Power Company (the licensee), which would change the expiration date for the Haddam Neck Plant Operating License.
DPR-61 from hiay 26. 2004. to Junc 29.
2007.
'Identification of Proposed Action Tbu currently licensed term for the I lead<I <m Neck Neck Plant is 40 years c<immrncing with issuance of th>>
<xinalrurlion permit (hfuy 26, 1964).
Accounting for the time that was required fur plunt construction. this represents an effective operating license term of 36 years. 10 months and 26 days.
Tbe licensee'8 ~pplication dated November 24. 1986 requests a 40-year operating license term for the Haddam Neck Plant.
Summary of Environmental Assessment Tb<. NRC at'iffhas reviewed the pot<:n'.ial unviionmental impact of the prapuaud chungc in the expiration date of the Oper itmg License for the ifaddam Neck Plant. This evaluation considered the previous environmental studies, including the "Final Environmental Statement Related to the Haddam Neck (Connecticut Yankee)
Nuc!ear Power Plant." (October 1973),
and more recent NRC policy.
Radiological Impacts Although the population in the vicinity of tbe Iladdam Neck Plant has incre ised. the site requirements of 10 CFR I'art 100 are still met with regard to Exclusion Ares Boundary. Low Population Zone. and nearest population center distances. In addition. the proposed additional years of ceactar operation do not increase the annual public risk from reactor operatiqn.
With regard to normal plant operation. the licensee compiles with NRC guidance and requirements for keeping radiation exposures "as low as is reasonable achievable" (AIJtRA) for occupational exposures and for radioactivitv ib efflugnts. The licensee would continue to comply with these requirements during <tny'additional..
y'ears of facilityoperation and also '
apply advanced technology when available and appropri<ite.
Non-Radiological Impacts Tb<<XRC review idcntilied'no addition~i degradation of the habitat a<irr<iunding the Haddam Neck Plant with regard to indigenous plant and animal species. including those that are commercially valuable. for'he additional years of facility operation. In addition. the National Pollutant Discharge Elimination System permit provides additional environmental protection.
Finding ofNo Significant Impact The staff bas reviewed tbe proposed chang<: ': the expiration date of the I iaddam Neck Plant Facility Operating License relative to the requirements aet forth in 10CFR Part 51. Baaed upon thu environment<<l assessment.
the st<<ff concluded that there are no significant radiological nor non radiological impacts associated with the proposed action and that the proposed license amendment willnot have a significant effect on the quality of the human environment. Therefore. the Commission has det<irmined. pursuant to 10 CFR 51.31. nut to prepare an environmental impact statement for the proposed amendments.
For further details with reaper t to this ection. see (1) the application for amendment d<<ted November 24. 1986.
(2) the Final Environmental Statement Related to the Haddam Neck (Connecticut Yankee) Nuclear Power Plant, issued October 1973, and (3) the Environmental Assessment dated November 23. 1987. These documents are available forpublic Inspection at the Commission's Public Document Room, 1717 H Street NW.. Washington. DC 20555 and at the Russell Library. 1&
Broad Street. Middietown. Connecticut 06457.
De<cd at Bethesda. Maryland. tbis 23rd day of November 198..
For ibc Nuclear Regulatory Commission.
Michael L Bayle.
Act<ngO<rearar. lnraflraradSaja+
Asaassmenr Aajaas OLraatara<a. D<visian of Reactor Pmgea<s ill.lV,-Vand Speaal prajec<s.
IFR Doc. 87-27888 FUed 1Z t-ar: 8;4$ am) a<LL<<<a coos ~MI IDockatffo.hfdf
Indiana and kfchioan Power Co Donald C. CookJt~Phnt, VoltNo.
2; iasuanc<t of Environmental Assessment and Flndino of No Significant Impact The U.S. Nuclear Regulatory Commission INRC) is considering issuance of a license amendment to Facility Operating License No. DPR-74 issued to Indiana and Mtchig<<n Power Company (the licensee) for operation of the Donald C Cook Nuclear Plant, Unit No. 2. located in Semen County, hiichigan.
Identification of Proposed Action The license amendment would permit the licensee to replace major components of the four steam generators in Cook Unit 2 in order to restore the plant to its original operating condition.
The amendment would revise the Technical Specifications in response to
!he lie<<nsee's application dated March
- 12. 1987. as supported by the Steam Generator Repair Report submitted November 7. 1986 and revised Marrh 30 and July 24. 1987. as may be further revised based on the NRC staA's continuing, review.
The NRC staff has prepared an environmental assessment ofthe proposed action. "Environmental Assessment by the Office of Nuclear Reactor Regulation Related to the Repair of Steam Crenerators. Indiana and hfichigan Electric Company. Donald C. Cook Nuclear Plant. Unit No. 2.
Docket No. 50-316." dated November 23.
1987.
Summary of Environmental Assessment The steam generators (SG) at Cook Unit 2 have experienced corrosion-related phenomena which have required periodic examination and plugging of SG tubes to ensure continued plant operation. The licensee has limited plant operation to 80% power to retard the rate of SG tube degradation. However, the need to plug tubes willcontinue and willeventually result in further power reductions and operating dINculties.
There are no practical repair techniques:
thus. the licensee proposed to replace SG lower assemblies. This replacement would repair the SG's and ailow the unit to operate at its design capacity.
The proposed license amendment would not degrade the level of safety attained by the original licensing of the plant. The repaired steam generators would be constructed of tube materials less prone to corrosion than the original tube materials. There would be a diminished chance of accident doses to
5
.... Federal Register. /"Vol; $2 "No. 231 /..Wednesday, December 2;.$ 987<< / 'Notices,:;;.,::.'45891~":..
t the environment since the probability:of an SG tube rupture, the accident of concern, would have a lower probability of occurrence than in the originally licensed plant.
The NRC staff has reviewed the potential environmental impact of the proposed action that would permit the licensee to replace major components of the four steam generators. This evaluation consideri.d the previous environmental studies. including the "Final Environinental Statement Relating to Operation of Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2," dated August 1973.
Radiological Impacts The licensee has taken appropriate steps to ensure occupational doses to the work force and population willbe within the limits of 10 CFR Part 20 and are below the annual dose design objectives of 10 CFR Part 50. Appendix I.
Therefore, the radiological impact of the repair project to the public and the work force willnot significantly affect the human environment.
Nonradiological Impacts With regard to potential nonradiological impacts, the proposed license amendment involves features located entirely within the restricted area as defined in 10 CFR Part 20. It does not affect nonradiological plant effluents. Any such efiluents willbe controlled by the licensee under existing plans to prevent or mitigate the impact of such efflucnts. The licensee will control noisy operations of construction machinery and willrestore any area inadvertently disturbed. Therefore. the Commission concludes that there are no significant nonradiological environment impacts associated with the proposed license amendment.
Hndlng ofNo Significant Impact The staff ha reviewed the proposed steam generator repair program and the proposed amendment relative to the requirements set forth in 10 CFR Part 51.
Based upon the environmental assessment.
the staff concluded that there are no significant radiological or nonradiological impacts associated with the proposed action and that the proposed action willnot have a significant effect on the quality of the human environment. Therefore, the Commission has determined. Purpuant to 10 CFR 51.31. not to prepare an environmental impact statement for the proposed amendment.
For further details with respect to this action, see (1) the Environmental Assessment dated November 23. 1987; and (2) the application for amendment dated March 12, 1987 as supported by an earlier transmittal dated November 7, 1986 with the Steam Generator Repair Report that was later revised on March 30 and July 24. 1987. These documents are available for public inspection at the Commission's Public Document Room.
1717 H Street, NW., Washington. DC, and at the Maude Preston Palenske Memorial Library. 500 Market Street, St.
Joseph; Michigan 49085.
Dated at Bethesda. Maryland. this 23rd day ofNovember 1987.
For the Nuclear Regulatory Commission.
David LWiggiatoa, ActingDirector. Project Directorate IIIN.
DivisionofReaalar Prajects.
(FR Doc. 87-27889 Filed 12-1-87; 8:45 am) iuLUNo coos 75944 w4 IDocket No. 50-298)
Nebraska Public Power District; Environmental Assessment and Finding of No Significant impact The U.S. Nuclear Regulatory Commission (NRC/the Commission) is considering issuance of an exemption from the requirements of 10 CFR 50.54(w)(1) to the Nebraska Public Power District (the licensee) for the Cooper Nuclear Station located in Nemaha County. Nebraska.
Environmental Assessment Identification ofProposed Actiam The licensee would be exempted from the requirement of Paragraph 54(w)(1) of 10 CFR Part 50 from December 5. 1987 through December 4, 1988. 10 CFR 50.54(w)(1) requires that licensees have.
within 60 days of the effective date of the Rule. property damage insurance in the amount of at least $1.06 billion to provide financial security for stabilizing and decontaminating their licensed reactors in the event ofan accident.
The Need forthe Proposed Action:
The licensee is a political subdivision of the State of Nebraska and. as such. is prohibited by State Iaw from becoming a subscriber to the stock or any portion of interest ofany corporation or association. The licensee is therefore prohibited from becoming a member of Nuclear Electric Insurer's Limited (NEIL).As a result, the licensee is unable to obtain the $1.06 billion. of property insurance as required by the Rule. The District is seeking a declaratory judgement from United States District Court which willenable it to become a NEILmember. Until such time, the maximum amount of property insurance available. to the licensee is the
$585 millionavailable from the American Nuclear Insurers and the Mutual Reinsdrance Pool. The requested exemption'will grant the licensee
~ additional time to obtain the necessary ruling.
Environmental Impacts ofthe Proposed Actiam The proposed action affects only insurance requirements and willhave no effect on nuclear safety or on plant effluents. Therefore. the Commission has determined that there is no environmental impact associated with the proposed action.
Alternative Use ofResources: This action involves no use of resources.
Agencies Persons Consulted: The NRC staff did not consult other agencies or persons.
Finding ofNo Significant Impact The Commission has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to this action. see the licensee's application dated October 5. 1987. which is available for public inspection at the Commission's. Public Document Room, 1717 IiStreet. NW.. Washington. DC.
and at the local Public Document Room in the Auburn Public Library. 11815th Street. Auburn. Nebraska 88305.
Dated at Ikthesda. Maryland this 27th day ofNovember, 1987.
For the Nuclear Regulatory Commission.
Walter h. Pautson, ActingDiractar. Projis.l DirectorateIV, Di<<isian ofRcaalor Prateats III.IV. V. and Sprciat Project+ Officeaf¹el<<ar R<<ucrur Ikgulalion.
lFR Doc. 87-27691 Fitnt 12-1-8.: a:45 am)
BILUNOCoos 75~1M IDocket No. 50-285i Omaha Public Power District; Environmental Assessment and Finding of No Significant Impact The U.S. Yuc)ear Regulatory Commission (the Commission) is considering issuance of an exemption from the schedular requirement of 10 CFR 50.54(w)(1) to the Omaha Public Power District (licensee) for the Fort Calhoun Station. Unit 1. located at the licensee's site in Washington County, Nebraska.
Environmental Assessment Identification ofthe Proposed Action:
The proposed action would grant an exemption to the licensee from ti 50.54(w)(1) of 10 CFR Part 50 which was recently amended to require that the licensees of nuclear power reactors maintain a minimum insurance coverage in the sum of $1.06 billion to provide financial security for stabilizing and
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