ML18219B529

05/16/1978 Letter Licensee Event Report of Containment Spray Pump Switches Not in Automatic Standby Position as Required by Technical Specification 3.6.2.1

ML18219B529
Person / Time
Site:	Cook
Issue date:	05/16/1978
From:	Dolan J American Electric Power Service Corp
To:	James Keppler NRC/IE, NRC/RGN-III
References
LER 1978-026-00
Download: ML18219B529 (10)

Text

'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOl'IING MATERIAL 50-316 REC: KEPPLRR J G ORG: DOLAN J E DQCDATE: 05/16/78 I4RC IN 8r. I'l Pl JR DATE RCVD: 05f31/78 DOCTYPE: LETTER NGTARI ZFD: 140 COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICFNSEE EVENT REPT (RO 50-316/78-026) ON 05/02/78 CQNCERNING A.

tlODE CHANGE FROM MODE 5 TO MODE 4 WAS MADE WITH THE CONTAINtlENT SPRAY PUMP CGI4TROL SWITCH IN THE PULL TO I OCKOUT POSITION. THUS MAKING PUMPS INOPERABLE AND VIOLATING TECH SPEC 3. 6 PLANT NAME: COOK UI4IT 2 REVIEI JFR INITIAL: X JQ DISTRIBUTOR INITIAL'~

~>>~H>~l~>~><H>>>++++~>> DISTRIBUTION 0,- THIS MATERIAL IS AS FOLLOWS NOTES:

SEND 3 COPIES OF ALL MATERIAL TO IhE ED REEVES-1 CY ALL l"IATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)

FGR ACTION: BR ' KNIEL<>>W/4 ENCL INTERNAL: REG F <<W/EI4CL NRC PDR++W/ENCL E~>>W/2 ENCL MIPC~~W/3 ENCL IPPGL I TO~>>W/ ENCL HOUSTQN4<W/ENCL NQVAK/CHECK+~W/ENCL EEB++W/ENCL KNIGHT<<~W/ENCI PLANT SYSTEMS BR++W/ENCL HANAUER~+W/ENCL TEDESCO+~W/ENCL E ISEI4HUT+<WfENCL REACTOR SAFETY BR+~W/ENCL ENGINEERING BR+>W/ENCL VOLLMER/BUNCH+wW/ENCL KREGERfJ. CGLLINS4+WfENCL ROSA~~W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ST. JOSEPH MI4 ~W/ENCL TIC~~W/ENCL I

NS C+ %W/ ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUB'.PITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78152009 SIZE: iP+4P+iP Ae HHHf CHf %%%%8HHf 0b5l W0>>+SHHf SHHH>>0>> WW%%%%% TI-IE END %%%W%%%%%8H>>%%4%4%%%%%%%%

n AMERICAN jELECYHIC POWER Service Corporation 2 Broadway, New York, N. Y. l0004 (212) 422.4800 JOJIÃ E. DOLEÃ Senior Ecccniicc Vice Prccident May 16, 1978 Engineering Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 co RE,cG~E'0 Mr. J. G. Keppler, Regional Director NIAYlg( 1>78 Office of Inspection and Enforcement /egg gJQEhk lEGUUgggg U.S. Nuclear Regulatory Commission gONUh15510'g Region 799 III Roosevelt Road t5$ %stleli-Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

This letter provides the written followup report to our verbal report made to NRC Region Mr. K. R. Baker on May 3, 1978, which was also confirmed by III Inspector, letter from Mr. D. V. Shaller to you on May 3,'978. At that time we reported that when Unit No. 2 entered Mode 4, the Containment. Spray Pump switches were not in the automatic standby position as required by Technical Specification 3.6..2.1. The attached enclosure is submitted in fulfillment of the requirement of Technical Specification 6.9.1.8 to provide prompt notification with written followup for an event of this nature.

Very truly yours, ohn E. Dolan JED:clb Enclosure cc: R. C. Callen G. Charnoff P. W. St'eketee 781520090 R. J. Vollen I R. Walsh R. W.

V. Shaller' Jurgensen'.

Bridgman 23 1978 MAY

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1 1

May 16,1978 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 ENCLOSURE This report provides a complete explanation of the circumstances surrounding this event.

a) Descri tion Of The Event:

Xn Cold Shutdown (Mode 5) the normal position of Containment Spray System (CTS) Pump Switches is in the "Pull to Lockout" position. This is done to prevent inadvertent acutation of the CTS while in Mode 5 or 6.

While returning, Unit, 2 into operation after a planned.

outage:, at 0431 hours0.00499 days <br />0.12 hours <br />7.126323e-4 weeks <br />1.639955e-4 months <br /> on May 2, 1978, the Unit progressed from Mode 5 to Mode 4 (Hot Shutdown). When Mode 4 was entered the switches for the Containment, Spray Pumps had not been moved from the "Pull to Lockout" position which prevents the pumps from starting, to the "Neutral" (Auto-matic Standby) position which permits the pumps to start automatically on demand. This action was in violation of Appendix "A" Technical Specification 3.6.2.1 which re-quires "Two independent containment spray systems shall be operable with each spray system capable of taking suction from the RWST and transferring suction to the containment sump." This specification is applicable to Modes 1, 2, 3, and 4.

b) Cause Of The Event:

The primary cause of this event, was a procedural inadequacy with a secondary cause being personnel error.

Operating Procedure 2-0HP-4021.001.001 Revision 0 "Plant Heatup from Cold Shutdown to Hot Standby" was being used to control the heatup. The Operating Procedure was ambiguous and deficient. The procedure did not include a specific signoff that all the requirements for entering Mode 4 are completed. Procedure step 6.11.2 states "Verify completion of Checkoff Sheet 5.2." Checkoff Sheet 5.2 is a listing of all the required surveillance testing that must be current or completed prior to entering Mode 4. This listing did not require that, the CTS pump switches be placed in the automatic standby position.

b) Continued Procedure step 6.17 states "Align the safeguards system for standby readiness by completing the valve lineup sheet for 2-0HP-4021.008.002 (ECCS) and 2-0HP-4021.009.

001 (CTS)." Again, completing the valve lineup sheets would not have assured the pump switches were placed in the automatic standby condition. Combining the re-quirements for the entire Emergency Core Cooking (ECCS),

'which is not, required until just prior to entering Mode 3, and the CTS, which is required prior to entering Mode 4, was confusing to the Operator.

The Unit Supervisor (US) in charge of Unit 2 Control Room and the Shift Operating Engineer (SOE) who is the shift supervisor did not comply with Technical Speci-fication 3.6.2.1 prior to entering Mode 4. Both of them were aware of the Containment Spray System (CTS) pump switches being in the "Pull to Lockout" position. The US was aware that the required surveillance testing to assure Operable CTS pumps had been conducted and that if an accident should have occurred he could have placed the pumps switches in the required position and the pumps would have started as required. The US and the SOE mistakenly thought, that the CTS pumps were not required until later in the heatup.

c) Corrective Action Taken At Time Even't Wa's'i'scovered:

The event was discovered at 0800 by the next shift, who had just assumed responsibility. The SOE was immediately informed and the heatup was stopped. RCS temperature was maintained between 310oF and 330oF. The ACTION statement of the Technical Specification 3.6.2.1 states: "With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the in-operable spray system to OPERABLE status within the next.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With the Operators knowing they were in excess of specification 3.6.2.1 they then applied Technical Specification 3.0.3 which states: "In the event a Limiting Condition for Operation and/

or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the specifi-cation, the facility shall be placed in at least'OT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are'ompleted that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery.

Exceptions to these requirements shall be stated in the individual specifications."

c) Continued With the heatup stopped the operators were aware that they could cool down the Unit using the Residual Heat Removal System (RHR) to less than 200oF (Cold Shutdown) in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Thus the decision was made not to-cool down since the Unit was in Hot Shutdown (Mode 4), which is already lower than Hot Standby (Mode 3), and there were approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> before a cool down had to be initiated. A confirmatory valve lineup for the CTS system was completed at 0920 on May 2, 1978. The valve checkoff sheets verified that the CTS system was in fact lined up correctly since no discrepancies were found. The CTS pump switches were then placed in "NEUTRAL" and the heatup continued.

A temporary change was written to the Operating Procedure to clarify that the CTS system must be OPERABLE prior to entering Mode 4.

d) Safet Evaluatio'n'f the Event The containment spray system serves two principal safety functions. They are prevention of containment overpressurization and iodine removal following a loss of coolant accident.

Specific analyses have not been performed with respect to con-tainment overpressurization for the postulated accident initiated at the maximum temperature and pressure as low as that occurring during the worst conditions of this event (330oF, 400 psig). However, a simple comparison of the total stored energy in the Reactor Coolant System at these conditions to the total energy absorption capability of the ice condenser indicates that more than sufficient heat absorption capability existed within the ice condenser to alleviate the requirement for initiation of sprays to keep the containment from overpressurizing.

With respect to iodine removal capability, it must be recognized that the plant was in its power ascention and had not yet operated at conditions exceeding 50% power. A conservative analysis, assuming zero ice condenser efficiency, has been per-formed on the same basis as reported in the final safety analysis of the Donald C. Cook Nuclear Plant. This analysis did not take credit'for either the minimal fission products that had been generated in Unit 2 up to this time nor the minimal fuel damage that would have occurred for a loss of coolant accident initiated at 330 F. The results of this analyses showed that the operator would have had at least 25 minutes to restore the containment spray before doses would have exceeded those specified in 10 CFR Part 100.

As a result of the above analyses, it is concluded that the event cited herein would not have resulted in a situation which could have adversely affected the health and safety of the public.

e) Corrective Action Taken To Prevent Recurrence

1) Disciplinary action has been taken against the Unit Supervisor and Shift Operating Engineer who permitted the plant to enter Mode 4 in violation of the Technical Specification.

2) Operating Procedure 2-0HP-4021.001.001 is being revised to incorporate the required temporary change sheets to make it easier for the Operator to follow and further reduce the likelihood of recurrence.

Xn addition, for the charging, safety injection, RHR and containment spray systems, the procedure revision will include the requirement that immediately prior to entering an operational mode for which these systems must be operable, a check will be made of the Status Lights and Annunciator Panels in the Control Room to assure that the required valves and switches are indicated as being in the correct position.

3) Operating Procedures in the 2-0HP-4021.001.XXX series are overall plant coordinating procedures to control heatup, cool down and power operation. These procedures are used for sequencing when individual system procedures are to be completed. These procedures will be reviewed and revised as necessary to correct any deficiencies and to remove ambiguity.

f) Date of Full Com liance:

Operating Procedure 2-0HP-4021.001.001 will be revised prior to June 15, 1978.

The review and revision, if required, of the 2-0HP-4021.001.XXX series procedures will be completed by June 15, 1978.

g) A completed copy of the Licensee Event Report is attached below.

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NRC FORM 366 tl 77) 3008 7

CON'T /

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"*': I LICENSEE CODE

~O 14 IS LICENSEE EVENT REPORT 6

LICENSE NUMBER

~O 25 26 U. S. NUCLEAR REGULATORY COMMISSION IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI LICENSE TYPE

'~30 57 CAT 5$

0 OZR 'I::*" L'JX ' ' ' '

DOCKET NUMBER 68 69

' ' ' EVFNT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~02 UNIT 2 WAS IN PROCESS OF HEATING UP FROM MODE 5 TO MODE 3 ~ A MODE CHANGE FROM MODE 5 TO MODE 4 WAS MADE W TH THE CONTA NMENT SPRAY PUMP CONTROL S I I 4

WITCHES IN THE PULL TO LOCKOUT POSITION, THUS MAKING THE PUMPS INOPERABL

~DG E IN VIOLATION OF APPENDIX A TECH SPEC 3 6 2 1 THE ATTACHED LETTER FU 0 G LLY EXPLAINS THE EVENT AND POSSIBLE CONSEQUENCES'os 7 8 9 L>>IS SYSTEM CODE CAUSE CODE CAUSE SUBCODE

~8 COMPONENT CODE COMP.

SUBCODE LIS>>>>8 VALVE SUBCODE 80

~

~OB 7 8 9 10 LJS LJS 11 12 13 'IB 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION 3 EVFNT YE'AR REPORT NO.

Q LERIRO CODE TYPE NO.

~8 Q>> R<<<<[JOJS ~02 6 QZ ~01 QZ QO 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD4 PRIME COMP, COMPONENT TAKFN ACTION LIS>>JS ON PLANT METHOD ~OURS +22 LJSLIS 33 34 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS

'6 37 40 SUBMITTED LJS uS FORM SUB.

42 SUPPLIER LJS 43 44 MANUFACTURER 47 Q27 o THE CAUSES OF THIS EVENT WERE PROCEDURAL INADEQUACY AND PERSONNEL ERROR.

DISCIPLINARY ACTION TAKEN FOR UNIT SUPERVISOR AND SHIFT OPERATING ENGINE ER INVOLVED IN EVENT. COMPLETE REVISION AND UPDATE OF PROCEDURE TO CORRE

~8~

3 CT DEFICIENCY AND TO ELIMINATE AMBIGUITY 7 8 9 0 FACILITY METHOD OF STATUS TRPOWER OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q32 3008 9L'JS 7 10 ~

12 13 44

~A 45 Q3'PERATOR OBSERVATION ACTIVITY CONTENT 80 RELEASED OF RELEASE AMOUNT OF ACTIVITYQ35 G ~Z Q33 ~ZQ34 NA NA 7 . 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~II ~00 7 8 9 0

11 Q33 ~ZQ33 12 13 NA PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 3 ~OO O QRR 33A 7 8 9 11 12 80 LOSS Of. OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 B Z Q42 NA 7 8 9 10 80 PUBI.I o

ISSUED

~NQ44 CITY DESCRIPTION NA Q NRC USE ONLY 7 8 9 10 68 69 80 NAME OP PREPARER R S ~ KEITH PHONE (616) 465-5901