ML20045E516

LER 93-003-00:on 930529,found That Room Temperature Readings Were Not Performed Due to Missed TS Surveillances.Procedure 14001-2 Was Revised & Personnel disciplined.W/930628 Ltr

ML20045E516
Person / Time
Site:	Vogtle
Issue date:	06/28/1993
From:	Mccoy C, Sheibani M GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LCV-0041, LCV-41, LER-93-003-03, LER-93-3-3, NUDOCS 9307020167
Download: ML20045E516 (4)

Text

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Georgia Power y ;cge:.,, [ T 7:; [k l OL MCIO fYRIT(C .V If.'fU June 28, 1993 LCV- 0041 Docket No. 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: , VOGTLE ELECTRIC GENERATING PLANT LICENSEE EVENT REPORT ROOM TEMPERATURE READINGS NOT PERFORMED MISSED TECHNICAL SPECIFICATION SURVEILLANCES in accordance with the requirements of 10 CFR 50.73, Georgia Power Company submits the er. closed report related to an event which was discovered on May 31,1993. Sincerely, C. K. McCoy CKM/NJS

Enclosure:

LER 50-425/1993-003 xc: Georgia Power Company Mr. J. B. Beasley Mr. M. Sheibani NORMS U. S. Nuclear Reculatory Commission , Mr. S. D. Ebneter, Regional Administrator

• Mr. D. S. Hood, Licensing Project Manager NRR Mr. B. R. Bonser, Senior Resident Inspector, W? tie ,

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g m 366 u.5. hlLUvt hwJLAWM WPM 5idh ArrM U 50-5104 i LICENSEE EUENT REPORT (LER) FALiti61 hAkt (1) D0 cati humoth (2) Fit i til VOGTIE ELECIRIC CENERAT1tK; PIANT - UNIT 2 05000425 1 l0rl3 TITLE (4) ROOM TDiPERA'IURE READINGS IK7f PERREMED - MISSED TECHNICAL SPECIFICATI0t1 SURVElllANCES EVEhI DATE (5) LER huMBER (6) REFORT OATE (7) OTHER FACILITIES Ihv0LVED (8) M0hIn OAY YEAR YEAR SEQ hvM REW 40hlN DAY YEAR FACILITY NAMES DOCKE1 huMBER(5) 05000 05 29 93 93 003 00 06 28 93 05000 OPERAT m I"35 "Ef0"I 35 5' "3 IED P'"5"^"I IU I"E "E0"I"E"E"I5 Of 10 'f" Ill) MODE (9) 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) POUER - 20.405(a)(1)(1) ~ 50.36(c)(1) ~ 50.73(a)(2)(v) ~ 73.71(c) LEVEL 99 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER (Specify in 20.405(a)(1)(iii) T 50.73(a)(2)(1)

• 50.73(a)(2)(viii)(A) Abstract below) 20.405(a)(1)(iv) -

50.73(a)(2)(ii) - 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) LICEh5EE CONTACT FOR TNIS LER (li) NAME TELEFN0hE humbER 4REA CODE MDIDI SHEIBANI, NUCLEAR SAFETY AfD COMPLIANCE 706 826-3209 COMPLETE OhE LIhE FOR EACH FAILURE DESCRIBED IN THIS REF0kT (13) R PCRT R P RT CAUSE SYSTEM CCMPONENT gE

                                   %AhhUFAC-      gppOS                 CAUSE SYSTEM    COMPONENT    j FANUFAC-5UFFLEMEhlAL REPORT EXPECTED (14?                                                     MDhlN   OAY   YEAR EXPECTED 2

SUBMISSION DATE (15) '

    ] YES(If yes. complete EXPECTED SUEMISSION DATE)               ] NO AB5TRACI (16)

On May 31, 1993, the reactor operator (RO) was reviewing completed surveillances of room temperature readings, and he noticed that only one page of readings had been taken when there had previously been two pages. His investigation found that three rooms containing main steam isolation valves (MSIVs) had not had their temperature readings taken since 2300 EDT on May 29, 1993, when a revision to Procedure 14001-2, " Shift Area Temperature Log," deleted these rooms from the required listing. This represented unit operation in a condition prohibited by the Technical Specifications, since these room temperatures are required to be determined at least once per 12 hours. Temperature readings were then logged for the three rooms at 0547 EDT on May 31, 1993, and were found to be satisfactory.  ; The cause of this event was a cognitive personnel error by initiating a premature revision of Procedure 14001-2. Procedure 14001-2 had been revised prior to the completion of a design change and the appropriate change to the Technical Specifications. The design change was for the installation of temperature sensors and alarms which would automatically annunciate high temperature conditions in the rooms involved. However, the installation of the sensors and a change to the Technical Specifications had not been campleted. After temperature readings were taken for the rooms involved and found to be satisfactory, Procedure 14001-2 was revised to include the three rooms.

I gam u.s. muum nwum wmam ungwugeggom i LICENSEE EVENT REPORT (LER)  ! TEXT CONTINUATION  ; FACILITY NAME.(1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3) f YEAR SEQ hum REV -{

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V0GTLE ELECIRIC CENERATIM PIAVI - UNIT 2 05000425 93 003 00 2 or 3 i IEXT A. REQUIREMENT FOR REPORT This report is required per 10 CFR 50.73 (a)(2)(i) because the unit operated I in a condition prohibited by the Technical Specification (TS) requirements . when surveillance tasks were not performed every 12 hours as required by  ! TS 4.7.10. } B. UNIT STATUS AT TIME OF EVENT l i

                                                                                                             -1' At the time of the discovery of this event, Unit 2 was operating at 99 percent of rated thermal power. There was no inoperable equipment that                       !

contributed to the occurrence of this event. .; C. DESCRIPTION OF EVENT j On May 31, 1993, the reactor operator (RO) was reviewing completed surveillances of room temperature readings, and he noticed that only one page  ! of readings had been taken when there had previously been two pages. His j investigation found that three rooms containing main steam isolation valves l (MSIVs) had not had their temperature readings taken since 2300 EDT on May } 29, 1993, when a revisior to Procedure 14001-2, " Shift Area Temperature Log," I deleted these rooms from :he required listing . This represented unit operation in a condition prohibited by the TS, since these room temperatures are required to be determined at least once per 12 hours. Temperature readings were then logged for the three rooms at 0547 EDT on May 31, 1993, and were found to be satisfactory.  : i D. CAUSE OF EVENT F The cause of this event was a cognitive personnel error by initiating a t premature revision of Procedure 14001-2. Procedure 14001 2 had been revised prior to the completion of a design change and the appropriate change to the -j Technical Specifications. The design change was for the installation of temperature sensors and alarms which would automatically annunciate high , 4 temperature conditions in the rooms involved. However, the installation of  ; the sensors and the change to the Technical Specifications had not been [ completed. Personnel responsible for revising the procedure failed to exercise a questioning _ attitude and failed to perform an adequate review i prior to revising the procedure. There were no unusual characteristics of i the work locations which contributsd to the occurrence of the inadequate  ; procedure revision process by the Georgia Power Company personnel involved.  ! P h f I h i A i v

A icm .ru u.5. hJLLUM nLWduel M#M55M An%tvb OPO NG 31ir-DiO4 (6-83) EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME.(1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3) a VEAR SEQ hDM REV V0GTLE EIELTRIC GENERAT1tK; PIRTT - UNIT 2 05000425 93 003 00 3 0F 3 l IEx1 E. ANALYSIS OF EVENT Although readings were not taken in the rooms involved for more than 2 days, workers installing the temperature sensors did not notice any marked temperature increase from the normal temperatures of 90 degrees F to 100 degrees F. Had the temperature approached the TS maximum of ' 115 degrees F, it is likely that workers would have known. Furthermore, no incidents occurred which required the MSIVs to perform their safety related function. Based on these considerations, there was no adverse effect on plant safety or on the health and safety of the public as a result of this event. F. CORRECTIVE ACTION

1. Temperature readings were taken for the rooms involved and found to be satisfactory. Additionally, Procedure 14001-2 was revised to include the three rooms.

2. Appropriate personnel involved have been disciplined on the importance of the procedure revision process and the use of closed loop communications.

G. ADDITIONAL INFORMATION

1. Failed Components None

2. Previous Similar Events None

3. Energy Industry Identification System Code Main Steam System - SB -

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