ML17318A748
| ML17318A748 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/12/1980 |
| From: | INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML17318A750 | List: |
| References | |
| NUDOCS 8005130754 | |
| Download: ML17318A748 (11) | |
Text
nald
'C.
Cook 1979 Annual Re ort.8605 ps'Oeratin Unit 1:
The unit operated at essentially 100% with minor outages and reductions for repairs and surveillance until the Cycle III-'IVrefueling outage which started April 6, 1979.
The outage was extended to perform testing of anchor bolts per IE Bulletin 79-02, and repairs to feedwater pipe cracks discovered on May 19, 1979.
The unit was returned to service on July 18th and again operated almost contin-uously at full power until shutdown on October 27th due to'nverter malfunction and reactor coolant pump coupling misalignment.
The unit returned to service November 11 and continued at full power until December 24 when shut-down as a result of significant nonconformances identi-fied relative to IEB 79-14.
The unit remained shutdown through the end of the year.
~
Unit 2:
The unit operated at essentially 100% with minor outages and reductions for repairs and surveillance until May 19 when shutdown for repairs to cracks in feedwater piping.
The unit was returned to service July 3 and again oper-ated at virtually full power through October 19 when shutdown for Cycle I-II refueling.
This major outage was extended through the end of the year as a result of significant nonconformances identified relative to IEB 79-14.
Ins ection and Enforcement March 30, 1979-A corporate management meeting was held to discuss trends in the Licensee's performance.
July 31, 1979-A Corporate management meeting was held to discuss a schedule, techniques, and procedure for replacement of feedwater elbow welds
'on Unit 2.
Also discussed were areas of disagreement and concern regarding welds in question, and results of analysis of the nozzle ciacks.
-~
Inspection/Branch Noncompliance Sanction Points Type of Noncompliance 79-02/02 Safeguards 79-03/03 FF&MS 79>>04/04 RO & NS 79-5/05 RO & NS 79-7/06 RO & NS 79-11/08 RO & NS 1 Infraction 2 Deficiencies 1 Infraction 1 Infraction 2 Infractions 1 Infraction 2 Infraction 10 4
10 10 20 10 20 Security Security Failure to conduc t drill.
Failure to implement procedures Failure to follow procedures.
Security Failure to follow procedures PNSRC Review 79-13/10 RO & NS 4 Infractions 40 Failure to follow procedures PNSRC Review 79-14/11 FF & MS
-2 Infractions 20 Inadequate air sampling Inadequate follow on WBC.
79-15/12 RC & ES 79-17/13 FF & MS 7/15 Safeguards 1 Infraction 1 Infraction 1 Infraction 2 Deficiencies 10 10 10 Failure to follow procedures.
Chlorine Discharge Security Security 79-23/20 RO & NS 2 Infractions 20 Failure to follow procedures PNSRC failure to review 79-24/21 RO & NS 79-26/24 FF & MS 2 Infractions 1 Infraction 20 10 Failure to follow procedures Solid radioactive waste handling.
79-28 RO&NS 1 Deficiency Failure to follow procedures
~Summar RO & NS Totals 0-In&actions 14 Deficiencies 2
Sanction Points 142
( 1978 Total - 224 )
RC & ES Totals Infractions Deficiencies Sanction Points 1
0 10
( 1978 Total - 10 )
FF & MS Totals Infractions Deficiencies Sanction Points 5
0 50
( 1978 Total - 12 )
Safe uards Infractions Deficiencies Sanction Points 2
4 28
( 1978 Total - 42 )
1979 Total 230
( 1978 Total - 288
)
C.
Ins ector's Evalution of Licensee Performance Problem Areas And Recommendations for Next Year.
The licensee has shown improvement this past year in terms of total number of LER's and items of noncompliance.
Response
to TMI "Lessons Learned" and the resulting upgrading of training, design, etc., is generally favorable.
Continued emphasis must be placed on reducing the number and percentage of personnel errors through improved coordination/communication, attention to detail, and better integrated systems training.
Administratively, the inspector expects to see vast improvement in the timely closeout of Condition Reports and audit Corrective Action Requests.
Si nificant Personnel Errors Unit 1 February 18, 1979 (LER 79-007/03L-0);
Charging Pump Suction Valve left closed following surveillance test.
February 23, 1979 (LER 79-009/03L-0);
Both Diesel-Generators inoper-able on two separate occasions, once for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once for 7
'minutes.
March 4, 1979 (LER 79-016/03L-0);
Both Containment Isolation Valves used for instrument sampling left open.
November 15, 1979 (LER 79-058/03L-0);
Two of three auxiliary feed-water flow paths made inoperable at same time during maintenance.
Unit 2 October 17, 1979 (LER 79-035/03L-0);
Two of three auxiliary feed-water flow paths made inoperable at same time during maintenance.
November 14, 1979 (LER 79-038/03L-0);
Boron injection flow path made inoperable when being used as charging pump boration flowpath during maintenance.
November 1,
1979 (LER 79-042/03L-0);
Both diesel-generators made inoperable at same time during modification and termination of cable.
November 13, 1979 (LER 79-045/03L-0);
Containment integrity breached during refueling operations due to maintenance activities.
E.
Summar of Un 1
oned Radioactive Releases Unit 1 - None Unit 2-Event Date: February 24, 1979 Event Number:
79-001/04X-0 Event
Description:
Unplanned release of low level gaseous activity from a moisture separator reheater (MSR) safety valve, which lifted at a setpoint lower than normal for no apparent reason.
The release lasted for approximately 35 minutes and involved Sodium - 24 contaminated steam.
The N
24 was being used at the time as a
atracer in the secondary system to identify leaks.
Actual release conce~(ration was ca/gulated to be 1.15 x 10
<>~
Ci/cc N
The applicable Technical Specif-cation limit for Na
" in air to an unrestricted area is 5 x 10 9/
$i/cc.
The total release was 6.99 x 10 Ci at a rate which was 0.231 of allowed Tech-nical Specification limits.
F.
Number and Character of Re ortable Events
- l. 1979 Totals:
Unit 1 - 67 Unit 2 -54.
Total - 121 2 ~Te Personnel Error Procedure MGMt Total Exceeding Safety Limit Significant Release or Overexposure 0
Loss of Entire Engineered Safeguards Major Breakdown of Manage-0 ment Controls Resulting in Degraded Plant Safety
Control Rod M smanipulations 0
Release or Overexposure 0
Slightly Above Limits 0
0 0
Does Not Exceed LCO but Results in Potential Degradation of Reactor Systems or Structures Loss of Portion of Safety System or Engineered Safeguards Reduction in Effectiveness 4
of Safety System or Engineered Safeguard Unscheduled Release
'Below Limits:
- 1. Potential to exceed'imit
.0 2.
No Potential to exceed Limit G.
Summar of Ins ections Re ort Number Manhours Onsite T
e Ins ection Unannounced 50-315/79-01 50-316/79-01 20 Radiological Environmental Yes Protection 50-315/79-02 50-316/79-02 118 Security No 50-315/79-03 50-315/79-03 27 Emergency Plan No 50-315/79-04 50-315/79-04 159 Resident Inspection Yes 50-315/79-05 50-316/79-05 197 Resident Inspection Yes 50-315/7 9-06 50-315/79-07 50-315/79-06 28 Inservice Inspection Security Yes Yes
~,
4
50-315/79-08 50-315/79-09 50-315/79-10 50-316/79-07 50-315/79-11 50-316/79-08 50-315/79-12 50-315/79-13 50-316/79-10 50-315/7 9-14 50-316/79-11 50-315/79-15 50-316/79-12 50-315/79-16 50-316/79-09 50-315/79-17 50-316/79-13 50-315/79-18 50-316/79-14 50-315/79-19 50-316/79-15 50-316/79-16 50-315/79-20 50-316/79-17 50-315/79-21 50-316/79-18 10 32 28 96 230 43 168 19 70 138 27 16 87 Snubbers 0-Investigation of Allegations Followup on Feedwater Cracks Resident Inspection IEB 79-02 Followup Resident Inspection TMI Followup Radiation Protection Program Followup on Feedwater Cracks Followup on IEC 78-08 Security Management Meeting on Feedwater Cracks Followup on IEB 79-02, 79-04, 79-14 Resident Inspection Nonradiological Environmental Protection Program Resident Inspection Yes No
'No Yes Yes Yes Yes No Yes Yes Yes Yes No Yes Yes 50-315/79-22 50-316/79-19 50-315/79-23 50-316/79-20 98 Followup on IEB 79-0),
79-14 Resident Inspection Yes Yes 50-315/79-24 50-316/79-21 50-315/79-25 50-316/79-23.
50-316/79-22 50-315/7 9-26 50-316/79-24 50-315/79-27 50-316/79-27 50-315/79-28 134 36 32 34 32 22 0<<
Resident Inspection Investigation of Allega-tions.
Inservice Inspection Rad Waste System Inves tiga tion of Allega tions Reactor Physics Yes Yes No No No Yes Inspection numbers 79-25 and 79-26 on Docket 50-316 were not used.
Inspection number 79-27 was the final inspection for this Docket.
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