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Category:ANNUAL OPERATING REPORT
MONTHYEARML17326A0621999-01-22022 January 1999
DC Cook Nuclear Plant Rept of Changes,Tests & Experiments Pursuant to 10CFR50.59(b)(2).
ML17334B7841997-12-31031 December 1997
DC Cook Nuclear Plant Units 1 & 2 1997 Annual Operation Rept,Main Rept.
ML17333A3391995-12-31031 December 1995
DC Cook Nuclear Plant 1995 Annual Operating Rept.
ML17332A5911994-12-31031 December 1994
DC Cook Nuclear Plant 1994 Annual Operating Rept.
ML17331B2821993-12-31031 December 1993
DC Cook Nuclear Plant 1993 Annual Operating Rept.
ML17331A0671992-12-31031 December 1992
1992 Annual Operating Rept.
ML17329A3991991-12-31031 December 1991
DC Cook Nuclear Plant 1991 Annual Operating Rept. W/920226 Ltr
ML17328A9731990-12-31031 December 1990
Corrected Annual Operating Rept for DC Cook for 1990.
ML17328A9521990-12-31031 December 1990
DC Cook Nuclear Plant 1990 Annual Operating Rept, Including Steam Generator Inservice Insp results.W/910228 Ltr
ML17334B3471989-12-31031 December 1989
Annual Operating Rept for DC Cook Nuclear Plant for 1989. W/900228 Ltr
ML17326B5481988-12-31031 December 1988
Annual Operating Rept,1988. W/890228 Ltr
ML20196E6601987-12-31031 December 1987
DC Cook Nuclear Plant Annual Operating Rept,1987
ML20211A2271985-12-31031 December 1985
Annual Operating Rept 1985. W/
ML20087D0031983-12-31031 December 1983
Annual Operating Rept,1983
ML20041E1701982-02-26026 February 1982
Annual Operating Rept,1981.
ML17319A7331981-02-27027 February 1981
Annual Operating Rept,1980.
ML17326A5751980-03-0303 March 1980
Annual Operating Rept 1979.
ML17318A7481980-02-12012 February 1980
Annual Operating Rept,1979
ML19270F6801978-12-31031 December 1978
1978 Annual Operating Rept.
1999-01-22
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Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
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Text
ATTACHMENT TO AEP:NRC:1147A DONALD C. COOK NUCLEAR PLANT CORRECTED ANNUAL OPERATING REPORT PAGES 02g7 9i.03' 910""~ggO
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3.0 STEAM GENERATOR IN-SERVICE INSPECTION 3.1 UNIT 1 INSPECTION
SUMMARY
One hundred percent of the tubes in all four steam generators of Unit 1 were bobbin coil eddy current inspected. All tubes were tested utilizing a 0.720 inch diameter probe with the exceptions of rows 1 through 4 U-bends that would not allow a 0.720 inch probe to pass. A 0.700 or 0.680 inch probe was used for the U-bend inspections only.
The bobbin coil test frequencies used were as follows:
400 kHz as the prime test frequency.
200 kHz and the 100 kHz as supplemental frequencies.
10 kHz as the locator frequency A total of 170 tubes were removed from service following this inspection due to the eddy current results. Appendix A provides inspection details concerning the indications found in each tube and whether or not the tube was plugged.
3.2 UNIT 2 INSPECTION
SUMMARY
Six and one-half percent of the tubes in Unit 2 steam generators were inspected using the same method and test frequencies described for Unit 1 inspections.
All tests were conducted with a 0.720 inch diameter probe with the exception of three tubes in steam generator 23, located in Rows 1 and 2.
These three tubes were tested with a 0.700 inch probe.
No degradation or pluggable indications were found.
STEAM GENERATOR NUMBER 12 ROW COL INDIC LOCATION PLUGGED ROW COL INDIC LOCATION PLUGGED 35 44 32% AV1 + 0 IN NO 27 71 DI TEH + 20.6 IN YES 35 44 25% AV2 + 0 IN NO 38 72 244 AV3 + 0 IN NO 45 44 144 2SPC + 0 IN NO 38 72 28% AV4 + 0 IN NO 45 44 144 1SPC + 0 IN NO 36 74 15% 1SPC + 0 XN NO I 12 46 DI TEH + 17.8 IN YES 37 74 DI 4SPH + 0 IN NO 23 47 DX 1SPH + 0 IN NO 37 74 DI 1SPC + 0 IN NO 38 47 DI 2SPH + 0 IN NO 21 76 DI 1SPH + 0 IN NO 43 47 194 AV1 + 0 IN NO 37 76 154 2SPC + 0 IN NO 37 76 DI 1SPC + 0 IN NO 11 48 DI 2SPH + 0 IN NO 35 77 274 1SPC + 0 IN NO 14 48 DRI TEH + 2.5 XN YES 36 77 334 2SPC + 0 IN NO 13 51 DI TEH + 21.1 IN YES 37 77 334 1SPC + 0 IN NO 18 52 DI 1SPH + 0 IN NO 28 78 DI 1SPH + 0 IN NO 34 54 264 AV4 + 0 IN NO 33 78 22%'SPC + 0 IN NO 37 54 394 AV4 + 0 IN NO 34 78 15%'SPC + 0 IN NO 3 55 DI 1SPH + 0 IN NO 31 79 28> 2SPC + 0 IN NO 31 79 114 1SPC + 0 IN NO 36 55 41% AVl + 0 IN YES 29 82 274'SPC + 0 IN NO 19 43 23 57 60 61 DI 2 1+o DI 1SPH + 0 1SPC + 0 1SPH + 0 IN IN IN NO NO NO 30 15 23 82 86 86
'I 254 35%
2SPC +,"0 TEH +
14%'SPC 20.
+ 0 IN 6
IN IN IN NO YES NO 43 61 DI 2SPH + 0 IN NO 23 86 1SPC + 0 NO 44 62 23% 2SPC + 0 IN NO 24 86 454 2SPC + 0 IN YES 42 63 27%'44'V3 + 0 IN NO 7 89 DI 2SPH + 0 IN NO 42 63 AV4 + 0 IN NO 16 89 DI 2SPH + 0 IN NO 42 64 144 1SPC + 0 IN NO
'9 89 DI 1SPC + 0 IN NO 18 65 DI 1SPH + 0 IN NO 13 90 104 1SPC + 0 IN NO 42 65 174 AV1 + 0 IN NO 6 91 304 1SPC + 0 IN NO 41 66 DI 2SPC + 0 IN NO A-6
STEAM GENERATOR NUMBER 14 ROW COL INDIC LOCATION PLUGGED ROW COL INDZC LOCAT10N PLUGGED 8 30 DI TEH + 20.9 IN YES 44 39 374 4SPC + 0 IN NO 32 30 DI 1SPH + 0 IN NO 42 40 DI 2SPH + 0 IN 'O 34 30 DI TEH + 20.7 IN YES 29 41 DI 1SPH + 0 IN 37 30 DI TEH + 20.5 IN YES 38 41 DI 1SPH + 0 IN NO 42 30 23% 1SPC + 0 IN NO 42 41 DI 1SPH + 0 IN NO 5 31 DI 2SPH + 0 IN NO 45 41 194 2SPC + 0 IN NO 41 31 134 1SPC + 0 IN NO 46 41 164 2SPC + 0 IN NO 32 32 DI 1SPH + 0 IN NO 21 43 DI 1SPH + 0 IN NO 42 32 38+o 1SPC '+ 0 IN NO 44 43 DI 2SPC + 0 IN NO 12 33 29+o 2SPH + 0 IN NO 46 43 244 2SPC + 0 IN NO 38 33 DI TEH + '20.4 IN YES 10,45 DI 1SPH + 0 IN NO
, 30 34 DI 1SPH + O'N NO 17 45 DI TSH + .5 IN YES 44 34 274 1SPC + 0 IN NO 41 45 23+o AV3 + 0 IN NO 41 45 18>o AV4 + 0 IN NO 17 35 32+o TSH + ~ 5 IN YES 16 46 DI TSH + 1.1 IN YES 33 44 35 35 DI 1SPH + 0 194'SFC + 0 IN IN NO NO 22 46'I TEH + 21. 2 IN YES 33 46 24% AV2 + 0 IN NO 44 36 26+o 1SPC + 0 IN NO 33 46 344 AV3 + 0 IN NO 33 46 26+o AV4 + 0 IN NO 45 36 164 1SPC + 0 IN NO 42 46 DI TEH + 20.8 IN YES 17 37 DI 1SPH + 0 IN NO 46 46 19% 2SPH + 0 IN NO 29 37 DI 1SPH + 0 IN NO 38 48 18'SH + 42 ~ 8 IN NO 38 37 DI 2SPH + 0 IN NO 32 49 DI 2SPH + 0 IN NO 44 37 39 2SPC + 0 IN NO 46 49 DI 1SPH + 0 IN NO
- 45. 37 14'SPC + 0 IN NO 45 37 16'SPC + 0 IN NO 8 50 DRI TEH + 2.4 IN YES 29 39 DI 1SPH + 0 IN NO 12 50 DI 1SPH + 0 IN NO 38 39 DI 1SPH + 0 IN NO 46 50 DI 1SPH + 0 IN NO A-13
STEAM GENERATOR NUMBER 14 ROW COL INDIC LOCATION PLUGGED ROW COL INDIC LOCATION PLUGGED 23'1 DI 1SPH + 0 IN NO 26 26 69 69 154 16>o AV1 + 0 IN AV2 + 0 IN NO NO 45 51 134 2SPC + 0 IN NO 18 70 DI 1SPH + 0 IN NO 18 52 DRI TEH + 2.1 IN YES 31 70 DI 1SPH + 0 IN NO 18 54 DRI TEH + 2.2 IN YES 30 73 DI 1SPH + 0 IN NO 44 55 DI 2SPH + 0 IN NO 33 73 DI 1SPH + 0 IN ~ NO 30 57 DI 1SPH + 0 IN NO 30 57 DI 3SPH + 0 IN NO 39 73 164 2SPC + 0 IN NO .
22 60 DI 1SPH + 0 IN NO 4 74 DI 2SPH + 0 IN NO 44 60 14% 3SPC + 0 IN NO 5 74 DI 1SPH + 0 IN NO 12 61 DI 1SPH + 0 IN NO 18 74 DI TEH + 20.6 IN YES 17 61 DI 1SPH + 0 IN NO 33 74 DI 1SPH + 0 IN NO 33 74 .,DI 2SPH + 0 IN NO 20 61 DI 1SPH + 0 IN NO 13 75 DI 1SPH + 0 IN NO
'30 61 DI 1SPH + 0 IN NO 33 75 DI 2SPH + 0 IN NO 43 61 31% 1SPC + 0 IN NO 35 75 24+o 2SPC + 0 IN NO 13 62 DI 1SPH + 0 IN NO 36 75 38% 2SPC + 0 IN NO 35 62 DI 1SPH + 0 IN NO 4 76 DI 2SPH + 0 IN NO AV2 + 0 IN 19 19 19 63 63 63 2 2~o 194 11%
AV3 + 0 IN AV4 + 0 IN 'O NO NO 17 18 76 76 DI DI TEH +
TEH +
20.9 IN 20.9 IN YES YES 6 65 DI 1SPH+ 0 IN NO 19 76 DI TEH + 20.6 IN YES 17 65 DI 1SPH + 0 IN NO 31 76 DI 'SPH + 0 IN NO 41 65 344 2SPC + 0 IN NO 33 76 DI 1SPH + 0 IN NO 19 66 15'V1 + 0 IN
+ 0 IN NO 76 1SPC + 0 IN 19 66 224 AV2 NO 36 21% NO 19 66 . 244 AV3 + 0 IN NO 23 . 77 DI TEH + 20.8 IN YES 25 66 DI 1SPH + 0 IN , NO 33 77 544 2SPC + 0 IN YES 34 67 DI TEH + 20.7 IN YES 23 78 DI 3SPH + 0 IN NO A-14 t
Docket Nos. 50-315 DISTRIBUTION:
and 50-316 NRC 5 L 1 lt
~~r P
MAR 2 i mg~ PD I I I-1 r/f JZwol inski PShuttl eworth TColburn ACRS(10)
EJordan PDIII-I Gray Mr. Milton P. Alexich, Vice President OGC Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
OPERATIONAL EVENTS WHILE SHUTDOWN The NRC has just issued Information Notice 91-22, "Four Plant Outage Events Involving Loss of AC Power or Coolant Spills," which addresses recent events that occurred during shutdown operations.
The chief purpose of this information notice is to notify each licensee that the high rate of precursor events to loss of decay heat removal during shutdown is a source of concern to the NRC. All of the events discussed in this information notice occurred during a one-week period in March 1991. Because of the potential for loss of a critical safety function in these and similar events, I believe a high level of management attention is required in the planning, coordination, and execution of shutdown operations.
While this information notice does not require specific licensee action or response, I urge you to give this important matter your personal attention.
Sincerely, Ori-ginal signed by, Thomas E. ),lurley Thomas E. Murley, Director Office of Nuclear Reactor Regulation cc: See next page OFC :LA PDIII-1 :PD PDIII- .D NRR NAME:PShuttleworth/$ g: Marsh :TM ey DATE: 03/~/91 /~: 3/$ I4/91 :0/ / 1 Document Name: COOK EVENTS LETTER
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++*++
Docket Nos. 50-315 and 50-316 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electr ic Power Service Corporation 1 Riverside Plaza Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
OPERATIONAL EVENTS WHILE SHUTDOWN The HRC has just issued Information Notice 91-22, "Four Plant Outage Events Involving Loss of AC Power or Coolant Spills," which addresses recent events that occurred during shutdown operations.
The chief purpose of this information notice is to notify each licensee that the high rate of precursor events to loss of decay heat removal during shutdown is a source of concern to the NRC. All of the events discussed in this information notice occurred during a one-week period in March 1991. Because of the potential for loss of a critical safety function in these and similar events, I believe a high level of management attention is required in the planning, coordination, and execution of shutdown operations.
While this information notice does not require specific licensee action or response, I urge you to give this important matter your personal attention.
Sincerely, Thomas E. Murley, f
Of ice of Nucl ear Reactor Regul ati on cc: See next page
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