ML17331B272
| ML17331B272 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/25/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | Siewert S AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 9403040217 | |
| Download: ML17331B272 (39) | |
Text
Docket No. 50-315 South Haven Tribune ATTN:
Hs.
Sue Siewert 950 Bailey Avenue South
- Haven, MI 49090 February 25, 1994 After publication, please send a copy of the proof of run to my attention.
Please note that the enclosed Public Notice and Advertising Order were faxed to you on Friday, February 25,
- 1994, and these hard copies are for confirmation only. If you have any questions, please call me at (301) 504-1991.
Sincerely, Original signed by:
Ledyard B. Harsh, Director Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Public Notice 2.
Advertising Order DISTRIBUTION w/o encl.
2 Docket File NRC 8 Local PDRs PD3-1 Rdg LNarsh JHickman CJamerson OGC
'4003040217 OPA PDR ADOCK IDENTICAL LETTER SENT TO:
Herald-Palladium (Dated 2/28/94) 3450 Hollywood Road P. 0.
Box 128 St. Joseph, HI 49085 ATTN: Hs., Valerie Bunnell 940225 050003i5 P
PDR ~
- Previously concurred on Public Notice
Dear Hs. Siewert:
Enclosed is a Public Notice for the D. C.
Cook Nuclear Plant, Unit 1, that we would like published on Tuesday, March 1, 1994, in the South Haven Tribune.
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PUBLIC NOTICE NRC STAFF CONSIDERING LICENSE AMENDMENT RE(UESTS FOR D.
C.
COOK UNIT 1
The U.S.
Nuclear Regulatory Commission (NRC) has received two applications dated February 15,
- 1994, from Indiana Michigan Power Company'the licensee) for exigent amendments to Facility Operating License No.
DPR-58 for the Donald C.
Cook Nuclear Plant, Unit No.
1, located in Berrien County, Michigan.
If approved, the amendments would implement interim steam generator (SG) tube plugging criteria for the tube support plate elevation outer diameter stress corrosion cracking for Cycle 14 (AEP:NRC: 1166L) and would incorporate an acceptance criterion for SG tube degradation in the tubesheet region known as F*, taking into account the reinforcing effect of the tube sheet on the external surface of the tube in the roll expansion region (AEP:NRC: 1166K).
Amendment request AEP:NRC: 1166L also supplements a previous amendment request dated December 15, 1993, which was noticed in the Federal Re ister on January 5,
1994 (59 FR 621).
The February 15,
- 1994, submittal revises the acceptance criteria from 1.0 volt to 2.0 volt.
Other changes to the proposed amendment are made consistent with the voltage change in acceptance criteria.
The NRC has determined that the licensee used its best efforts to make timely applications for the proposed changes and that exigent circumstances do exist and were not the result of any fault of the licensee.
The exigent circumstances result from a recent change in NRC staff acceptance of higher interim voltage limits (i.e., 2.0 volts).
This change was made known to the licensee during a meeting on February 9, 1994.
As a result of this meeting, the licensee has requested to incorporate the 2.0 volt criterion into the Unit 1
SG inservice inspection and repair program during the current Unit 1
refueling outage.
The repairs are currently scheduled to begin March 6, 1994.
The required technical analyses for the F* amendment were pursued by the licensee when it became aware that F* could be coupled with a
tube rolling technique, making F* applicable to the licensee's SG design.
When the analyses were completed the request was promptly proposed to the NRC and submitted.
The licensee has evaluated the requested amendments against the standards in 10 CFR 50.92 and the NRC staff has made a proposed (preliminary) determination that the requested amendments involve no significant hazards considerations.
Under NRC regulations, this means that operation of the facility in accordance with the proposed amendments would not (1) involve a
significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated,,
or (3) involve a
significant reduction in a margin of safety.
The licensee*s analyses are summarized below:
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Incor orate 2.0 Volt Criterion AEP:NRC: 1166L (1)
Based on the existing data
- base, the Regulatory Guide
- 1. 121 criterion requiring maintenance of a
safety factor of 1.43 times the steamline break pressure differential on tube burst is satisfied by 7/8 inch diameter tubing with bobbin coil indications with signal amplitudes less than 9.6 volts, regardless of the indicated depth measurement.
A 2.0 volt plugging criteria compares favorably with the 9.6 volt structural limit considering the previously calculated growth rates for outer diameter stress corrosion cracking (ODSCC) within the Cook Nuclear Plant Unit 1
SGs.
Considering a voltage growth component of 0.8 volt (40% voltage growth based on 2.0 volts beginning of cycle
,(BOC))
and an NDE
[nondestructive examination] uncertainty of 0.40 volt *(20% voltage uncertainty based on 2.0 volts BOC),
when added to the BOC interim plugging criteria of 2.0 volts results in a bounding end of cycle (EOC) voltage of approximately 3.2 volts for Cycle 14 operation.
A 6.4 volt safety margin exists'(9.6 structural limit 3.2 volt EOC
= 6.4 volt margin).
Conserva'tively, an upper limit of 3.6 volts will be used 'to assess tube integrity for those bobbin indications which are above 2.0 volts but do not have confirming rotating pancake coil (PRC) ca'lls.
Relative to the expected'leakage during accident condition loadings, it has been previously established that a
postulated main steamline break outside of containment but upstream of the 'ain steam isolation valve represents the most limiting radiological condition relative to the IPC.
In support of implementation, of the interim plugging criteria, it will be determined whether the distribution of crack indications at, the tube support plate intersections at the end of Cycle 14 are projected 'to be such that primary to secondary leakage would result in; site boundary doses within a
small fraction of the 10 CFR 100 guidelines.'
separate calculation has determined this allowable steamline break leakage limit to be 12.6 gpm.
Tube pull results from Cook Nuclear, Plant Unit 1 indicate that tube wall degradation of greater than 40% 'throughwall was detectable either by the bobbin or RPC probe.
The tube with maximum throughwall penetration of 56%
(43% average) had a voltage of 2.02 volts.
This indication also was the largest recorded bobbin voltage from the EOC 12 leakage of 2.81 volts, inclusion of all IPC intersections in the leakage model is quite conservative.
(2)
Implementation of the proposed SG tube interim plugging criteria does not introduce any significant changes to the plant design basis:
Use of the criteria does not provide a mechanism which could result in an accident outside of the region of the tube support plate elevations; no ODSCC is occurring outside the thickness of the tube support plates.
Neither a single or multiple tube rupture event would be expected in a
SG in which the plugging criteria has been applied (during all plant conditions).
Specifically, the licensee will continue to implement a maximum leakage rate limit of 150 gpd (0. 1 gpm) per SG to help preclude the potential for excessive leakage during all plant conditions.
The RG 1. 121 criterion for establishing operational leakage rate limits that require plant shutdown are
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based upon leak-before-break considerations to detect,.a free span crack before potential tube rupture during faulted plant conditions.
The 150 gpd limit should provide for leakage detection and plant shutdown in the event of the occurrence of an unexpected single crack resulting in leakage that is associated with the longest permissible crack length.
(3)
The use of the voltage based bobbin probe interim tube support plate elevation plugging criteria at Cook Nuclear Plant Unit 1
is demonstrated to maintain SG tube integrity commensurate with the criteria of RG 1. 121.
This is accomplished by determining the limiting conditions of degradation of SG tubing, as established by inservice inspection, for which tubes with unacceptable cracking should be removed from service.
Upon implementation of the criteria, even under the worst case conditions, the occurrence of ODSCC at the tube support plate elevations is not expected to lead to a
SG tube rupture event during normal or faulted plant conditions.
As noted previously, implementation of the tube support plate elevation plugging criteria will decrease the number of tubes which must be repaired.
The installation of SG tube plugs reduces the reactor coolant system (RCS) flow margin.
- Thus, implementation, of the interim plugging criteria will maintain the margin of flow that would otherwise be reduced in the event of increased tube plugging.
'ncor orate F* SG Tube Plu in 'Criterion AEP:NRC: 1166K (1)
The supporting technical and safety evaluations ofthe subject criterion demonstrate that the presence', of the tubesheet will enhance the tube integrity in the region of the hardroll by pr'ecluding tube deformation beyond its initial expanded outside diameter.
The resistance to both tube rupture and tube collapse is strengthened by the presence of the t'ubesheet in that region.
The F* length of roll expansion is'suffi'cient to preclude tube pullout from tube degradation located below the F* distance, regardless of the extent of the tube degradation.
Any leakage out of the tube from within the tubesheet at any elevation in the tubesheet is fully bounded by the existing SG tube rupture analysis included in the, Cook Nuclear Plant FSAR [Final Safety Analysis Report].
(2)
Implementation of the proposed F* criterion does not introduce any significant changes to the plant design basis.
Use of the criterion does not provide a mechanism to initiate an accident outside of the region of the expanded portion of the tube.
Any hypothetical accident as a result of any tube degradation in the expanded portion of the tube would be bounded by the existing tube rupture accident analysis.
(3)
The use of the F* criterion has been demonstrated to maintain the integrity of the tube bundle commensurate with the requirements of RG 1. 121 (intended for indications in the free span of tubes) and the primary to secondary pressure boundary under normal and postulated accident conditions.
Acceptable tube degradation" for the F* criterion is any degradation indication in the tubesheet
- region, more than the F* distance below the
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.4-bottom of the transition between the roll expansion 'arid the unexpanded tube; The safety factors used in the verification of the strength of the degraded tube are consistent with the safety factors in the ASHE Boil,er,and Pressure Vessel Code used in SG design.
The F* distance,.has been'erified by testing to be greater than the length of roll expansion 'required to,preclude both tube pullout and significant leakage during normal and postulated accident conditions.
Implementation of the tubesheet plugging criterion will decrease the number of tubes which must be taken out of service with, tube plugs or repaired with sleeves.
Both plugs and sleeves reduce the RCS flow margin;
- thus, implementation of the F* criterion will maintain the margin of flow that would otherwise be reduced in the event of increased plugging or sleeving.
If the proposed determinations that the requested license amendments involve no significant hazards considerations become final, the NRC will issue the amendments without first offering an opportunity for a public hearing.
An opportunity for a hearing will be published in the Federal
~Re ister at a later date and any hearing request will nnt delay the effective date of the amendments.
If the NRC staff decides in its final determinations that the amendments do involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Re ister and, if a hearing is granted, it will be held before the amendment is issued.
Comments on the proposed determinations of no significant hazards considerations may be telephoned to Ledyard (Tad) Harsh, Director, Project Directorate III-1, by collect call to 1-(301)-504-1991.
or submitted in writing to the Rules and Directives Review Branch, Division of Freedom of Information and Publication Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
All comments received by close of business on March 7,
- 1994, will be considered in reaching a final determination.
Copies of the applications may be examined at the NRC's Local Public Document Room located 'at the Maud Preston Palenske Memorial Library, 500 Market Street, St.
- Joseph, Michigan
- 49085, and at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC 20555.
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September 17, 1993 DOCKET NO(S).
50-315 DISTRIBUTION Docket File CJamerson BMetzel Reading File
SUBJECT:
INDIANAHICHIGAN PRIER CQIPANY DONALD C-COOK NUCLEAR PLANT The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant impact Notice of Issuance of Environmental Assessment Notice of Consideration of issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nifIcant Hazards Conditions See Page(s)
Exemption DATED Construction Permit No. CPPR-Facility Operating License No.
Order
, Amendment No.
,Amendment No.
Monthly Operating Report for Jul 1993 for DC Coolc Annual/Semi. Annual Report:
Other transmitted by Letter Os/O5/93 transmitted by Letter Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc:. See next page OFFICE~ LA:PDXX suRNplME~ CJamerso DAlE 09/ I I/93 NRC FORM 318 (10/80) NRCM 0240 OFFICIAL RECORD COPY
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Regional Radiation Representative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street
- Chicago, IL 60604 Chief Division of Habitat Conservation U. S. Fish 5 Wildlife Conservation U. S. Department of the Interior Washington, DC 20204 Dr. William Cunningham FDA Research Chemist National Institute of Standards 5 Technology Reactor Building 235, Room B-108 Gaithersburg, MD 20899
DOCKET NO(S).
50-315 July 22, 1993
/ DISTRIBUTION w/o enclosures:
Docket File CJamerson BWetzel PD 3-1 Reading File
SUBJECT:
INDXANAMICHIGAN POttER COHPANY DONALD C.
COOK, UNIT 1 The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nificant Hazards Conditions See Page(s)
DATED Exemption Construction Permit No. CPPR-Facility Operating License No.
Order
, Amendment No.
Amendment No.
X Monthly Operating Report for C
ok Unit 1 for June 1993 Annual/Semi. Annual Report:
Other transmitted by Letter July 6t transmitted by Letter Office of Nuclear Reactor Regulation
Enclosures:
As Stated See next page OFFICP SURNAME>
OATEt.
LA:PDI 1
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NRC FORM 3ta tto/80) NRCM 0240 OFFICIAL RECORD. COPY
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July 21, 1993 DOCKET NO(S).
50-315 Distribution w/o endlosures:
lc-Docket File CJamerson BMetzel Reading File PD3-1 MN 8 C.
COOK NUCLEAR POUR PLANT UNIT 1 - INDIAN I'IICHIGAHPO~ COI~ANy The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application Draft/Final Environmental Statement DESCRIPTION OF DOCUMENT DATED Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nifleant Hazards Conditions See Page(s)
Exemption Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for D-C- Coo~ <or ~
Annual/Semi Annual Report:
Other
, Amendment No.
,Amendment No.
transmitted by Letter transmitted by Letter Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc-'ee next page OFFICE>
SURNAMEt.
DATE~
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DOCKET NO(S). 50-315 and 50-316 5ay 7, 1993 DISTRIBUTION:
Q)ocket File l/'Shuttleworth WDean Reading File
SUBJECT:
Xndiana Hichigan Comyyny Donald C.cCoolc Nuclear Power Plant C
f' The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nif/cant Hazards Conditions See Page(s)
DATED Exemption Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for
, Amendment No.
,Amendment No.
transmitted by Letter Annual/Sggj@r)tr)II Report:
k lear Plant Units 1 and 2 Annual EnvtttronmenMl Opexating Report 920101-1231 w 930821 etter.
transmitted by Letter Other gil 21'ffice of Nuclear Reactor Regulation
Enclosures:
As Stated See next page DFacE>> Eh:PDIII-1 f'%uttleworth DATE>> 05/ -
/93 NRC FORM 318 l10/col NRCM 0240 OFFICIAL RECORD COPY
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Regional Radiation Representative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street
- Chicago, IL 60604 Chief Division of Habitat Conservation U.S. Fish
& Mildlife Conservation U.S. Department of the Interior Washington, DC 20204 Dr. Milliam Cunningham FDA Research Chemist National Institute of Standards
& Technology Reactor Building 235, Room B-10S Gaithersburg, ND 20899
March ll, 9993 DOCKET NO(S).50-315
~
Hnd 50-316 Bee next yoge DISTRIBUTION:
Docket File MShuttleworth MDean Reading File
SUBJECT:
Indian Ihchigan Power Company Donald C. Cook Nuclear Paver Plant, The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses.
Involvin No Si nificant'Hazards Conditions See Page(s)
Exemption DATED Construction Permit No. CPPR-
., Facility Operating License No.
Order Monthly Operating Report. for
, Amendment No.
,Amendment No.
transmitted by Letter x
Mnual/Semi-Annual Report:,
ook Semiannual Radioactive Effluent Release Repor transmitted by Letter Other For July o Dec 1992 Office of Nuclear Reactor Regulation
Enclosures:
= As Stated cc:See next page LA:PDIII-1 suRNAMf (Shutt 1ewor NRC FORM 318 110/ao) NRCM 0240 OFFICIAL RECORD COPY
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CC:
Regional Radiation Representative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street
- Chicago, IL 60604 Chief Division of Habitat Conservation U.S. Fish
& Wildlife Conservation U.S. Department of the Interior Washington, DC 20204 Dr. William Cunningham FDA Research Chemist National Institute of Standards 5 Technology Reactor Building 235, Room B-108 Gaithersburg, HD 20899
DOCKET. NO(S). ".50-315 58 "316 I
C September 18, 1992 DISTRIBUTION Docket:.File PDIII-1 r/f PDIII-l p/f JStang PShuttleworth
SUBJECT:
Donald C. Cook Nuclear Power Plant, Units 1 and 2 The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment
,Notice of Consideration of Issuance of Facility Operating License or Amendment-to Facility Operating License.
DATED'iweekly Notice;,Applications and Amendments to Operating Licenses Involvin No Si nificant Hazards Conditions Exemption See Page(s)
Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for Amendment. No;
,Amendment No.
transmitted by Letter.,
. Annual/Semi. Annual Report:
dioactive Effluent Release Re ort X
..Other transmitted by Letter 8/26/92 Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc:
See next page OFFICE>
SURNAME>
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.. 9/.18/92.....
h;m NRC FORM ala (to/ao) NRCM 0240 OFFICIAL RECORD COPY
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Regional Radiation Representative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street
- Chicago, IL 60604 Chief Division of Ecological Services Bureau of Sport Fisheries 5 Wildlife U. S. Department of the Interior Washington, DC 20240 Dr. William Cunningham FDA Research Chemist National Institute of Standards
& Technology Reactor Building 235, Room B-108 Gaithersburg, MD 20899
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DOCKET NO(S).
'50-315 50-316 See next page May 27, 1992 DISHGHUIXQl:
Jhcket:FLLe~
Mhuttlemrth,
~
JStang Reading Pile
SUBJECT:
indiana Hichigan Power Comyany '-.',Donald C. Cook Nuclear Power Plant The following documents concerning our review of the subject facility,are transmitted for your information; I
DESCRIPTION OF DOCUMENT'.
Notice of Receipt of Application Draft/Final Environmental Statement
. Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant impact Notice of, Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility-Operating License Biweekly Notice; Applications and Amendments to Operating Licenses S
p Involvin No Si nifleant Hazards Conditions
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DATED
'xemption Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for
, Amendment No.
Amendment No.
transmitted by Letter xx Annual/Semi-Annual Report Annual Environ 0 eratin Re t 1991 Other transmitted by Letter 1991 0//2//92 Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc:
See next paae OFFICE>
SURNAME>
OATEN LA:PD1Il-1 Khuttletmr
~92 NRC FORM 3ta (tolaOI NRCM 0240 OFFICIAL RECORD COPY
CC:
Regional Radiation Representative U. S. Environmental Protection Agency Region Y Office 230 South Dearborn Street
- Chicago, IL 60604 Chief Division of Ecological Services Bureau of Sport Fisheries 5 Wildlife U. S. Department of the Interior Washington, DC 20240 Dr. William Cunningham FDA Research Chemist National Institute of Standards
& Technology Reactor Building 235, Room B-108 Gaithersburg, MD 20899
Apr)l 24, 1992 DISTRIBUTION Docket-F1'-1'e.
PDIII-1 JStang PShuttleworth DOCKET NO(S). 50-316 DONALD C.
COOK NUCLEAR POWER PLANT, UNIT 2, INDIANA MICHIGAN POWER CO.
The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nihcant Hazards Conditions See Page(s)
Exemption DATED Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for Amendment No.
Amendment No.
transmitted by Letter Annual/Semi.AnnualReport:
Radloactlve Effluent Release Re t. Jul-Dec 1991 S
transmitted by Letter Other Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc: See next page OFFICE&
SURNAME>
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Regional Radiation Repr esentative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street Chicago, IL 60604 Chief Division of Ecological Services Bureau of Sport Fisheries 5 Mildlife U. S. Department of the Interior ltashington, DC 20240 Dr. william Cunningham FDA Research Chemist National Institute of Standards 5 Technology Reactor Building 235, Room B-l08 Gaithersburg, MD 20899
April 24, 1992 D>STRIBUTION Docket F11+=~
PDIII-) r/f PShuttleworth JStang DOCKET NO(S).
50-315
SUBJECT:
DONALD C ~
COOK NUCLEAR PONER PLANT, UNIT 1, INDIANAMICHIGAN POl'IER CO.
The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nihcant Hazards Conditions See Page(s)
DATED Exemption Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for Annual/Semi. Annual Report:
Other
, Amendment No.
Amendment No.
transmitted by Letter 4/10/92 transmitted by Letter Office of Nuclear Reactor Regulation
Enclosures:
As Stated
": See next page OFFICE>
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Division of Ecological Services Bureau of Sport Fisheries fi Mildlife U. S. Department of the Interior Mashington, DC 20240 Dr. Milliam Cunningham FDA Research Chemist National Institute of Standards I Technology Reactor Building 235, Room B-108 Gaithersburg, HD 20899
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DOCKET NO(SI 50-315/316 Aprjl 24, 1992 DISTRIBUTION pocket:Fi.1~e PDIII-1 r/f JStang PShuttleworth DONALD C.
COOK NUCLEAR PONER PLANT, UNITS 1 AND 2, INDIANA MICHIGAN POWER CO.
The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availabilityof Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendmen'ts to Operating Licenses Involvin No Si nificant Hazards Conditions See Page(s)
Exemption DATED Construction Permit No. CPPR-Facility Operating License No.
Order Monthly Operating Report for Annual/Semi-Annual Report:
Other December 1991
, Amendment No.
,Amendment No.
transmitted by Letter 1/8/92 transmitted by Letter Office of Nuclear Reactor Regulation
Enclosures:
As Stated See next page OFFICE>
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DATE%
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Regional Radiation Representative U. S. Environmental Protection Agency Region V Office 230 South Dearborn Street Chicago, IL 60604 Chief Division of Ecological Services Bureau of Sport Fisheries 5 Mfldlffe V. S. Department of the Interfor Mashfngton, DC 20240 Dr. Mfllfam Cunningham FOA Research Chemist National Institute of Standards 5 Technology Reactor Building 235, Room B-108 Gaithersburg, ND 20899