ML20082T125

RO SI-07/08:on 831104,steam Line Pressure Safety Injection Signal Switch Placed in Reset Instead of in-block Position. Train B Safety Injection Occurred.Caused by Personnel Error. Operator Counseled

ML20082T125
Person / Time
Site:	Cook
Issue date:	12/05/1983
From:	Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
RO-SI-07-08, RO-SI-7-8, NUDOCS 8312150168
Download: ML20082T125 (7)

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,,,,,, IN0 LANA & MICHIGAN ELECTRIC _ COMPANY DONALD C. COOK NUCLEAR PLANT .--

P.O. Box 458, Bridgman, Michigan 49106  :

(616) 465-5901 a

December 5, 1983

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Mr. J.G. Keppler, Regional Administrator - ,

United States Nuclear Regulatory Commission c Region III -

799 Roosevelt Road l__

Glen Ellyn, IL 60137 $

k Operating License DPR-74 Docket No. 50-316

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Special Report Nos. SI-07/08 ,

Dear Mr. Keppler:

J As defined in Technical Specification Section 6.9.2, the Donald g C. Cook Nuclear Plant is submitting two Special Reports in 2 compliance with Appendix A Technical Specifications Section - 3.6.2, Emergency Core Cooling System. g Sincerely, e.t.dhegs S Plant Manager t

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/bab h Attachment i cc: John E. Dolan -

M.P. Alexich _

R.F. Kroeger 1 H. Brugger C E.R. Swanson, RO:III '-

R.C. Callen, MPSC PNSRC .,

J.F. Stietzel -

E.L. Townley m K.R. Baker g R.O. Bruggee, EPRI ^

5 8312150163 831205 PDR ADOCK 05000316 7~

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INDIANAfAND MICHIGAN' ELECTRIC COMPANY

. DONALD C. COOK NUCLEAR PLANT.

' Operating License: DPR-74 Docket No.: 50-316 Special Report: ESI-07

, m SAFETYtINJECTION ACTUATION ~- NOVEMBER 4, 1983_

Conditions ~Pri'or to Occurrence

- The Reactor was in Mode 4 with the Reactor Coolant 1Syst'em at about 333*F.and1900 psig, iThe unit!wasfin the process of heating up in.

preparation',for Reactor.startup. The RCS was still borated to cold shutdown: concentration and all control rods and shutdown rods were Lfully inserted.

Description of Occurr'ence iC3 &: I Technicians 'were performing surveillance test procedure .

~2-THPi4030.STP.180 on the~ Reactor Trip Breakers. While.,communi-cating through, headsets,.a C-:&.I= Technician.behind the control

room panels instructed _a: Reactor.._ Operator.?t'o, block the pressurizer pressure S.I. signal. :The operator-put the switch to the reset

~ position instead of the block position and a Train B Safety..

InjectonLoccurred.

Desihnation of Cause of Occurrence

- As sta'tedfin~the " Description-of Occurrence", a surveillance test

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iof;the' Reactor Trip Breakers was being performed. While intending to'--block the pressurizer pressure S.I. signal, the operator ~went

.to reset)instead of block'and a Train B Safety Injection occurred due Lto low pressurizer pressure.

[ ,cAnalysis-of Occurrence' i The1following is a: list of. major items that were reviewed for their safetyiimplication':

E(a) . ; Reactor Coolant System Cooldown Rate

,- The1 Reactor ~ Coolant System was at 332*F at the~ time.of the injection and remained ~at.the temperature during the y;

injection.

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(b) Thermal Effects of Safety Injection During this occurrence, the East and West Centrifugal Charging Pumps injected into'the Reactor Coolant System through the Boron Injection lines (1h" nozzles) for a period of two minutes.

The maximum flow one pump can put through these lines is 470 GPM (T.S. 4.5.2.h). With two pumps _ operating the maximum total injection into the RCS is 1880 gallons. The injection of 1880 gallona corresponds to a 6.2 minute injection of the design base used in'the-FIRL Report F-C4542 which calls for two charging pumps each having a flow rate of 150 GPM. This is the seventh inadvertent safety injection.into the Reactor Coolant System and conservatively constitutes 3.1/10,000 of allowable cycles.

This is conservative from the fact that the design temperature ofxthe primary coolant is 540'F while the primary coolant tem-perature_at.the time of this injection was 332*F, which would

. result in lower temperature gradients than design. Also, the maximum-injection-flow of 470 GPM required by Tech Spec 4.5.2.h is. verified at zero RCS pressure. The pressure at the time of the injection was 900 psig, which would have caused a. flow less than 470'GPM. The total accumulated cycles to date are 18.15/10,000.

(C) Effects on the Emergency Core Cooling System Piping The piping and supports in the ECCS were given a thorough visual inspection to determine if any mechanical damage was enperienced during the safety injection. There was no evidence of any mechanical damage or abnormal movements of

.the piping.

Corrective Actions The operator involved was verbally reminded of the importance of his job and to slow down and make certain the actions he takes are correct. Also routed a copy of the condition report associated with this incident to all licensed operators.

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' SAFETY INJECTIONS (Table 6'from Technical Report F-C4542)

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'Un it 2 Usage- Accompanying

-This Cumulative Conditions No. Da t'e - 7 Time Cycl e '. Usage and Comments

~1 03-01-78 1 .00015 ' 00015

. 2: 08-04-78 1.5 .00018 .00033

.3 '01-06-79 1 41 .00032 .00065 "

4- .06-28-80 4.0 .000275 .000925 5 .10-20-81 10 .00032 .001245 "B" Train Only

'6; 03-29-82 2.0 530 gpm .00019 .001435 "A" Train Only

(.00026) (.001505)-

'7: 11-04-83 ~ : 2 0 940 gpm .00019 .001625 "B" Train Both Parts

(.00031) (.001815)

8. 11-04-83 1-'O 470 gpm .00014 . .001765 "A" Train

(.00017) (s001985)

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t INDIANA AND MICHIGAN ELECTRIC COMPANY.

DONALD C. COOK NUCLEAR PLANT Operating License: DPR-74 Docket No.: 50-316 Special Report: SI-08 SAFETY INJECTION ACTUATION - NOVEMBER 4, 1983 Conditions Prior to Occurrence The Reactor was in Mode 4 with the Reactor Coolant System at about 332*F and-900 p .g. The unit was in the process of heating up in preparation for .ceactor startup. The RCS was still borated to cold shutdown concentration and all control rods and shutdown rods were fully inserted. A Train B Safety Injection had occurred hour prior to this actuation.

' Description of Occurrence

.C & I Technicians were performing surveillance test procedure 2-THP 4030.STP.180 on the Reactor Trip Breakers. Due to a. mis-understanding of the procedure, the steamline pressure S.I. signal was not blocked prior to putting the input error inhibit switch to normal and a Train A Safety Injection occurred.

Designation of Cause of Occurrence As stated in the " Description of Occurrence", a surveillance test of the Reactor Trip Breakers was being performed. The steamline pressure S.I. signal was not blocked as required by a note in the procedure. When the input error inhibit switch was placed in the normal position, a Safety Injection Actuation occurred due to low steamline pressure.

Analysis of Occurrence The following is a list of major items that were reviewed for their safety implication:

(a). Reactor-Coolant System Cooldown Rate The Reactor Coolant System was 332*F at the time of injection and remained at the temperature during the injection.

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1 (b) Thermal Effects of Safety Injection i

During this occurrence, the East' Centrifugal Charging Pump injected into the Reactor Coolant System through the Boron Injection lines (l " nozzles) for about 1 minute.

The maximum flow one pump can put through these lines is 470 GPM (T.S. 4.5.2.h). Therefore,.the maximum total injection into the RCS is 470 gallons. The injection of 470 gallons corresponds to a 1.6 minute injection of the design base used in'the FIRL Report F-C4542 which calls for two charging pumps each having a flow rate of 150 GPM. This is the eighth inadvertent safety injection into the Reactor Coolant System and conservatively constitutes 1.7/10,000 of allowable cycles.

This is. conservative from the fact that the design temperature of the primary coolant is 540*F while the primary coolant at-the time of this injection was 332*F, which would result in lower. temperature gradients than design. Also, the maximum injection flow rate of 470 GPM required by Tech Spec 4.5.2.hl is verified at zero RCS pressure. The-pressure at the time of the-injection was 900 psig, which would have caused a flow less than 470 GPM. The-total accumulated cycles to date are 19.85/10,000.

(C) Effects on the Emergency Core Cooling System Piping

-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 evidence of any mechanical damage or abnormal movements of the piping.-

Corrective Actions Procedure 2-THP 4030.STP.180 was revised to make the note, which said to block the S.I. signal, to require a signoff for the action which is unique to performing the procedure with the reactor shut-down.

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, SAFETY: INJECTIONS.

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. Usage  : Accompanying This Cumulative Conditions .

- No. Datef4 Time' Cycle. Usage- and Comments

1; 4. :03-01-78' -1 --.00015 .000151

2. 108-04-78. -1.5 ~ .00018 .00033 23: 06 14 .00032 .00065 14 06-28-80: 4.0 .000275 .000925

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5' 210-20-81. -18 . 00032' .001245 "B" Train Only' 6 [03-2982- 1 2 W 530 gpm .00019'. .001435 "A" Train Only '

(.00026).(.001505) 1r 11-04-83: L2 0 940lgpm .00019 .001625.. "B" Train Both Parts

(.00031)';(.001815)'

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13 11-04-83 il 0-470 gpm .00014 . . 001765 "A" Train ~.

(.00017) '(.001985)l T

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