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| | issue date = 02/28/1997 | | | issue date = 02/28/1997 |
| | title = Forwards DC Cook Nuclear Plant Units 1 & 2 1996 Annual Operating Rept. | | | title = Forwards DC Cook Nuclear Plant Units 1 & 2 1996 Annual Operating Rept. |
| | author name = FITZPATRICK E | | | author name = Fitzpatrick E |
| | author affiliation = AMERICAN ELECTRIC POWER CO., INC. | | | author affiliation = AMERICAN ELECTRIC POWER CO., INC. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY j REGULRTOINFORMATION DISTRIBUTION TEM (RIDE)(ACCESSION NBR:9703100078 DOC.DATE: 97/02/28 NOTARIZED: | | {{#Wiki_filter:CATEGORY j REGULRTOINFORMATION DISTRIBUTION TEM (RIDE) |
| NO DOCKET¹FQCIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C..Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E. | | ( |
| .American Electric Power Co., Inc., RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | ACCESSION NBR:9703100078 DOC.DATE: 97/02/28 NOTARIZED: NO DOCKET ¹ FQCIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C..Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. . American Electric Power Co., Inc., |
| | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards"DC Cook Nuclear Plant Units 1 a 2 1996 Annual Operating Rept." DISTRIBUTION CODE: IE47D COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.59 Annual Report of Changes, Tests or Experiments Made W NOTES: 2 A out Approv>RECIPIENT ID CODE/NAME PD3-INTERNAL FILE CENTE EXTERNAL: NOAC , COPIES LTTR ENCL 1 0 1 1 1 1 RECIPIENT ID CODE/NAME HICKMANFJ RGN3 FILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 D M E NOTE TO ALL"RIDS" RECIPIENTS: | | Forwards "DC Cook Nuclear Plant Units 1 a 2 1996 Annual Operating Rept." |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL.NUMBER OF COPIES REQUIRED: LTTR 6 ENCL, 5 | | SIZE: 2 A DISTRIBUTION CODE: IE47D COPIES RECEIVED:LTR ENCL TITLE: 50.59 Annual Report of Changes, Tests or Experiments Made W out Approv > |
| | NOTES: |
| | RECIPIENT , COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3- 1 0 HICKMANFJ 1 1 INTERNAL FILE CENTE 1 1 RGN3 FILE 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| | M E |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL .NUMBER OF COPIES REQUIRED: LTTR 6 ENCL, 5 |
|
| |
|
| Indiana Michigan Power Cr.apany 500 Circle Drive Buchanan, Ml 491071395 February 28, 1997 Z INDIANA NICHIGAN PQMfER AEP:NRC:1147G Docket Nos.50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 February 28, 1997 Gentlemen: | | Indiana Michigan Power Cr.apany 500 Circle Drive Buchanan, Ml 491071395 Z |
| Donald C.Cook Nuclear Plant Units 1 and 2 1996 ANNUAL OPERATING REPORT Paragraph 6.9.1.5 of the Donald C.Cook Nuclear Plant Technical Specifications requires that an annual report be submitted to address personnel exposure, steam generator in-service inspection | | INDIANA NICHIGAN PQMfER February 28, 1997 AEP:NRC:1147G Docket Nos. 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 February 28, 1997 Gentlemen: |
| 'results, challenges to power-operated relief and safety valves, and information regarding I-131 reactor coolant activity.In addition, 10 CFR 50.59(b)(2) requires submittal of an annual report describing changes, tests, and experiments made in the preceding year.Consistent with these requirements, a copy of the Cook Nuclear Plant 1996 Annual Operating, Report is contained in attachment 1.Sincerely, EF E.E.Fi zp trick Vice President jen Attachment cc: A.A.Blind A.B.Beach MDEQ DW 6 RPD NRC Resident Inspector J.R.Padgett I-~(//'9703100078 970228 POR ADQCK 050003i5, R PDR 07008< | | Donald C. Cook Nuclear Plant Units 1 and 2 1996 ANNUAL OPERATING REPORT Paragraph 6.9.1.5 of the Donald C. Cook Nuclear Plant Technical Specifications requires that an annual report be submitted to address personnel exposure, steam generator in-service inspection |
| TABLE OF CONTENTS TZTL~G QQ~B 9.1.6 Install a 10'28'odular Building (Haz-Stor Building)9.1.7 CO, Fire Suppression System in Turbine Lube Oil Rooms 15 15 9.1.8 Replace Existing Controllers and Associated I/P Transducers 16 9.2 9.2.1 Minor Modifications (Mms)Addition of a Vent Line to the Safety Injection (SZ)Pump Suction Header'7 17 9.3 Plant Modifications (Pms)17 9.3.1 Circulating Water Pumps (CWPs)Motor Replacement 9.3.2 Disable Main Turbine Exhaust Hood Temperatu: | | 'results, challenges to power-operated relief and safety valves, and information regarding I-131 reactor coolant activity. In addition, 10 CFR 50.59(b)(2) requires submittal of an annual report describing changes, tests, and experiments made in the preceding year. Consistent with these requirements, a copy of the Cook Nuclear Plant 1996 Annual Operating, Report is contained in attachment 1. |
| Trip 18 9.3.3 Installation of Safety Valve Test Stand 9.3.4 Refurbishing of the Hot Chemistry Laboratory 18 19 Temporary Modif ications (Tms)19 9.4.1 Install Ground on 1-RU Instrument Housing 19 9.4.2 Install Temporary Covers over By-Pass Dampers (I-HV-AES-2) | | Sincerely, EF E. E. Fi zp trick Vice President jen Attachment cc: A. A. Blind A. B. Beach MDEQ DW 6 RPD NRC Resident Inspector J. R. Padgett I |
| .20 9.4.3 9.4.4 Isolation of Leaking 2-URV-130 Steam Dump Valve...,...20 Install Temporary Covers Over By-Pass Dampers (2-HV-AES-2) | | -~(/ / |
| .21 9.4.5 Install Temporary Spent Fuel Pit (SFP)Demineralizer 21 9.4.6 Alternate Miscellaneous Sealing and Cooling Water (MSCW)Supply 22 9.4.7 Temporary Sodium Hypochlorite System in Screen House 22 Page 1 1.0 INTRODUCTIOh The Donald C.Cook Nuclear Plant is owned by Indiana Michigan Power Company and is located north of Bridgman, Michigan.The plant consists of two nuclear power units, each employing a Westinghouse pressurized water reactor nuclear steam supply system.Each reactor unit employs'n ice condenser reactor containment system.The American Electric Power Service Corporation was the architect-engineer and constructor. | | '9703100078 970228 POR ADQCK 050003i5, R PDR 07008< |
| Units 1 and 2 reactor.licensed power levels are 3250 Mwt and 3411 Mwt, respectively. | | |
| The main condenser cooling method is open cycle usir.Lake Michigan water as the cooling source for each unit.2.0 PERSONNEL RADIATION EXPOSURE | | TABLE OF CONTENTS |
| | ~G TZTL QQ~B 9.1.6 Install a 10' 28'odular Building (Haz-Stor Building) 15 |
| | : 9. 1.7 CO, Fire Suppression System in Turbine Lube Oil Rooms 15 9.1.8 Replace Existing Controllers and Associated I/P Transducers 16 9.2 9.2.1 9.3 Addition of Pump Suction Header'7 Minor Modifications a Vent Plant Modifications (Mms) |
| | Line to the Safety Injection (Pms) |
| | (SZ) 17 17 9.3. 1 Circulating Water Pumps (CWPs) Motor Replacement 9.3.2 Disable Main Turbine Exhaust Hood Temperatu: Trip 18 9.3.3 Installation of Safety Valve Test Stand 18 9.3.4 Refurbishing of the Hot Chemistry Laboratory 19 Temporary Modifications (Tms) 19 9.4.1 Install Ground on 1-RU Instrument Housing 19 9.4.2 Install Temporary Covers over By-Pass Dampers (I-HV-AES-2) . 20 9.4.3 Isolation of Leaking 2-URV-130 Steam Dump Valve ...,... 20 9.4.4 Install Temporary Covers Over By-Pass Dampers (2-HV-AES-2) . 21 9.4.5 Install Temporary Spent Fuel Pit (SFP) Demineralizer 21 9.4.6 Alternate Miscellaneous Sealing and Cooling Water (MSCW) |
| | Supply 22 9.4.7 Temporary Sodium Hypochlorite System in Screen House 22 |
| | |
| | Page 1 1.0 INTRODUCTIOh The Donald C. Cook Nuclear Plant is owned by Indiana Michigan Power Company and is located north of Bridgman, Michigan. The plant consists of two nuclear power units, each employing a Westinghouse pressurized water reactor nuclear steam supply system. Each reactor unit employs ice condenser reactor containment system. The American Electric |
| | 'n Power Service Corporation was the architect-engineer and constructor. |
| | Units 1 and 2 reactor. licensed power levels are 3250 Mwt and 3411 Mwt, respectively. The main condenser cooling method is open cycle usir. |
| | Lake Michigan water as the cooling source for each unit. |
| | 2.0 PERSONNEL RADIATION EXPOSURE |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| Table 1 provides a summary of the number, of station, utility, and contractor/other personnel receiving exposures greater than 100 millirem in 1996.The total record dose for all personnel was 216.325 rem as measur=d by thermoluminescent dosimetry (TLD)and reported in accordance with Regulatory Guide 1.16.The values shown in the individual categories (routine maintenance, etc.)represent only the count of the num',ier of people that received 100 millirem in that particular category.The grand total figure represents the total number of people that received 100 millirem, whether in one of the categories or multiple categories. | | |
| A specific person could receive 100 millirem in two or more categories and still would be counted in the grand total.Therefore, the summation of the totals in the individual categories would.not necessarily equal the grand total.}} | | Table 1 provides a summary of the number, of station, utility, and contractor/other personnel receiving exposures greater than 100 millirem in 1996. The total record dose for all personnel was 216.325 rem as measur=d by thermoluminescent dosimetry (TLD) and reported in accordance with Regulatory Guide 1.16. |
| | The values shown in the individual categories (routine maintenance, etc.) represent only the count of the num',ier of people that received 100 millirem in that particular category. The grand total figure represents the total number of people that received 100 millirem, whether in one of the categories or multiple categories. A specific person could receive 100 millirem in two or more categories and still would be counted in the grand total. Therefore, the summation of the totals in the individual categories would .not necessarily equal the grand total.}} |
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Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view] |
Text
CATEGORY j REGULRTOINFORMATION DISTRIBUTION TEM (RIDE)
(
ACCESSION NBR:9703100078 DOC.DATE: 97/02/28 NOTARIZED: NO DOCKET ¹ FQCIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C..Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. . American Electric Power Co., Inc.,
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards "DC Cook Nuclear Plant Units 1 a 2 1996 Annual Operating Rept."
SIZE: 2 A DISTRIBUTION CODE: IE47D COPIES RECEIVED:LTR ENCL TITLE: 50.59 Annual Report of Changes, Tests or Experiments Made W out Approv >
NOTES:
RECIPIENT , COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3- 1 0 HICKMANFJ 1 1 INTERNAL FILE CENTE 1 1 RGN3 FILE 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
M E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL .NUMBER OF COPIES REQUIRED: LTTR 6 ENCL, 5
Indiana Michigan Power Cr.apany 500 Circle Drive Buchanan, Ml 491071395 Z
INDIANA NICHIGAN PQMfER February 28, 1997 AEP:NRC:1147G Docket Nos. 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 February 28, 1997 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 1996 ANNUAL OPERATING REPORT Paragraph 6.9.1.5 of the Donald C. Cook Nuclear Plant Technical Specifications requires that an annual report be submitted to address personnel exposure, steam generator in-service inspection
'results, challenges to power-operated relief and safety valves, and information regarding I-131 reactor coolant activity. In addition, 10 CFR 50.59(b)(2) requires submittal of an annual report describing changes, tests, and experiments made in the preceding year. Consistent with these requirements, a copy of the Cook Nuclear Plant 1996 Annual Operating, Report is contained in attachment 1.
Sincerely, EF E. E. Fi zp trick Vice President jen Attachment cc: A. A. Blind A. B. Beach MDEQ DW 6 RPD NRC Resident Inspector J. R. Padgett I
-~(/ /
'9703100078 970228 POR ADQCK 050003i5, R PDR 07008<
TABLE OF CONTENTS
~G TZTL QQ~B 9.1.6 Install a 10' 28'odular Building (Haz-Stor Building) 15
- 9. 1.7 CO, Fire Suppression System in Turbine Lube Oil Rooms 15 9.1.8 Replace Existing Controllers and Associated I/P Transducers 16 9.2 9.2.1 9.3 Addition of Pump Suction Header'7 Minor Modifications a Vent Plant Modifications (Mms)
Line to the Safety Injection (Pms)
(SZ) 17 17 9.3. 1 Circulating Water Pumps (CWPs) Motor Replacement 9.3.2 Disable Main Turbine Exhaust Hood Temperatu: Trip 18 9.3.3 Installation of Safety Valve Test Stand 18 9.3.4 Refurbishing of the Hot Chemistry Laboratory 19 Temporary Modifications (Tms) 19 9.4.1 Install Ground on 1-RU Instrument Housing 19 9.4.2 Install Temporary Covers over By-Pass Dampers (I-HV-AES-2) . 20 9.4.3 Isolation of Leaking 2-URV-130 Steam Dump Valve ...,... 20 9.4.4 Install Temporary Covers Over By-Pass Dampers (2-HV-AES-2) . 21 9.4.5 Install Temporary Spent Fuel Pit (SFP) Demineralizer 21 9.4.6 Alternate Miscellaneous Sealing and Cooling Water (MSCW)
Supply 22 9.4.7 Temporary Sodium Hypochlorite System in Screen House 22
Page 1 1.0 INTRODUCTIOh The Donald C. Cook Nuclear Plant is owned by Indiana Michigan Power Company and is located north of Bridgman, Michigan. The plant consists of two nuclear power units, each employing a Westinghouse pressurized water reactor nuclear steam supply system. Each reactor unit employs ice condenser reactor containment system. The American Electric
'n Power Service Corporation was the architect-engineer and constructor.
Units 1 and 2 reactor. licensed power levels are 3250 Mwt and 3411 Mwt, respectively. The main condenser cooling method is open cycle usir.
Lake Michigan water as the cooling source for each unit.
2.0 PERSONNEL RADIATION EXPOSURE
SUMMARY
Table 1 provides a summary of the number, of station, utility, and contractor/other personnel receiving exposures greater than 100 millirem in 1996. The total record dose for all personnel was 216.325 rem as measur=d by thermoluminescent dosimetry (TLD) and reported in accordance with Regulatory Guide 1.16.
The values shown in the individual categories (routine maintenance, etc.) represent only the count of the num',ier of people that received 100 millirem in that particular category. The grand total figure represents the total number of people that received 100 millirem, whether in one of the categories or multiple categories. A specific person could receive 100 millirem in two or more categories and still would be counted in the grand total. Therefore, the summation of the totals in the individual categories would .not necessarily equal the grand total.
