ML20039B370
| ML20039B370 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/14/1981 |
| From: | Shaller D INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| RO-SI-05, RO-SI-5, NUDOCS 8112220589 | |
| Download: ML20039B370 (3) | |
Text
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L*:;",, IN0 LANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PIANT P.O. Box 458 Bridgman, Michigan 49106 (616) 465-5901 December 14, 1981 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating' License DPR-74 Docket No. 50-316 Special Report No. SI-05
Dear Mr. Keppler:
The purpose of this letter is to forward to you the attached Special Report in compliance with Appendix A, Technical Specifications, Section 3.5.2, Emergency Core Cooling Systems.
Sincerely, g))1 NU.' / j n, N(/
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~s D.V. Shaller pg Plant Manager 8
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R.S. Hunter cn R.W. Jurgensen NRC RO:III Resident Inspector R.C. Callen MPSC PNSRC J.F. Stietzel E.L. Townley H.M. Chadwell W. La.rallee - EPRI 811222o509 811214~
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s INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT Operating License: DPR-74 Docket No.:
50-316 Special Report: SI-05 SAFETY INJECTION ACTUATION - OCTOBER 20, 1981 Conditions Prior to Occurrence The Reactor was in Mode 4 with the Reactor Coolant System being maintained 0
at approximately 380 psig and 252 F.
The unit was in the process of making preparations for heat-up and the RCS was still borated to Cold Shutdown Concentration. All Control and Shutdown Rods were fully inserted.
Description of Occurrence C & I Technicians were perfonning surveillance test procedure THP.4030.STP.145 on the Solid State Protection System, Train B, " Testing Memory Circuit".
The Safety Injection occurred when a step in the procedure was missed which would have prevented the Safety Injection Signal from being introduced into the ci rcui t.
Designation of Cause of Occurrence As stated in the " Description of Occurrence", a surveillance test on Train B of the S.S.P.S. was being performed.
The memory test switch was not placed in the "Off" position as stated in step 7.19.6 of the procedure. When the
" Input Error Inhibit" switch was placed in the " Normal" position, a safety injection actuation occurred due to system parameters during the startup conditions exceeding their actuation values.
Analysis of Occurrence The.following is a list of major items that were reviewed for their safety implications:
(a) Reactor Coolant System Cooldown Rate The Reactor Coolant System temperature was 2520F at the time of injection and remained at this temperature during the injection.
(b) Thermal Effects of Safety Injection During this occurrence, the Centrifugal Charging Pump injected to the Reactor Coolant System through the safety injection path for a period of 18 minutes.
During this time, approximately 2,700 gallons of borated water with an initial temperature of 1650F was injected. This is the fifth inadvertant safety injection into the Reactor Coolant System and conservatively would constitt '.. less than 3.2/10,000 of allowable cycles.
The total accumulated cycles to date are 12.45/10,000.
I (c) Effects on the Emergency Core Cooling System Pir ing (ECCS)
The piping and supports in the ECCS were given a thorough visual inspection to determine if any mechanical damage was experienced during the safety injection. There was no e t.dence of any i
mechanical damage or abnormal movements of the piping.
Corrective Actions The C & I Supervisor for the crew involved in performing this surveillance test has had informal meetings with his people, to impress upon them the importance of performing in a deliberate and careful manner when working in the S.S.P.S. cabinets.
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