ML20044D851

LER 93-005-00:on 930415,discovered That RCIC Steam Line Flow - High Timer Function Never Performed on Monthly Basis. Caused by Failure to Include Test in Initial Procedure Development Process.Procedures revised.W/930517 Ltr

ML20044D851
Person / Time
Site:	River Bend
Issue date:	05/17/1993
From:	Booker J, England L GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-005, LER-93-5, RBG-38516, NUDOCS 9305210020
Download: ML20044D851 (6)

Text

- --

GULF STATES UTILITIES COMPANY ,

4V!R BE ND $Y ATeON PO5T Dre tcf Box 220 si FR ANCisvtLit. LouStANA 70775 ARE A CODE f.D4 035 60M 34f. 6051 May 17, 1993 RBG- 38516 i File Nos. G9.5, G9.25.1.3 ,

l U.S. Nuclear Regulatory Commission Document Control Desk ,

Washington, D.C. 20555 I Gentlemen: ,

f River Bend Station - Unit I  ;

Docket No. 50-458 ,

Please find enclosed Licensee Event Report No.93-005 for River Bend Station - ,

Unit 1. This report is submitted pursuant to 10CFR50.73.

Sincerely, 7

.l'$1/MLL7 i

J. E. Booker _  ;

Manager - Safety Assessment ]

and Quality Verification  :

River Bend Nuclear Group ,

ki W* $d9-641 LAE/JPS/FRC/DCH/CLM/kvm I

I i

DOUGSn e99 s

9305210020 930517 PDR S

ADOCK 05000459 PDR l

~

cc: U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 i St. Francisville, LA 70775 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 ,

Mr. C.R. Oberg Public Utility Commission of Texas 7800 Shoal Creek Blvd., Suite 400 Nonh Austin, TX 78757 Department of Environmental Quality Radiation Protection Division P.O. Box 82135 Baton Rouge, LA 70884-2135 ATTN: Administrator I

+

b P

h i

e 5

i F

l NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB MO. 3150-0104 j rusa EXPIRES 5/31/95 ES'uATED BURDEN PER RESPONSE TO COMDLY W'H THis INFORMATON COLLECTION REQUEET: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) cOMMEuTS REGuce BURDEN EsTuATE 10 me ,NronMA1c4 AND RECORDS MANAGEMENT BAANOH (MNBS T7141, UA NGOLEAR REGULATORY COMM:SSON. W ASM% TON, DC 20555 0301. AND TO i THE PAPERWORK REDUCTION PROJECT Q150-0104). OFFCE OF +

(See reverse for required number of d@ts/cnatacters for each block) M A.NAGEMENT AND BUDGET, WASHINGTON. OO 205n F ACBUTV NAME (1) DOCKET NUMitEfi(2) PAGE p)

RIVER BEND STATION 05000 458 10F 4  !

" i* >

MADEQUATE SURVEILLANCE TEST PROCEDURE FOR REACTOR CORE ISOLATION I COOLING STEAM FLOW-HIGH TIMFR FUNCTION EVENT DATE (5) LER NUMBER (6 -

REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) f' MOUE % RA' M f AciUTY NAME DOCKET NUMBEH McNm nu vE4a vtAR o,gg og, uOsm DAY YEAR 05000 t

f ACiUTY NAME DOCKET NUUSER 04 15 93 93 - 005 -

00 05 17 93 05000 OPERATING  ;

TH!S REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR O (Check one or more)(11)

MODE (9) 1 20 402(b) 20 405(c) 50.73(a)(2)0v) 73.71(b) i POWER 20.405(a)(1)p) 50.36(c)(1) 50.73ta)(2)(v) 73.71(c) f LEVEL (10) 100 20.405 min)pi) 50.36(c)(2) So.73(a)(2)(vii) oTHER I 20 405ta)p)(m) X 50.73(a)(2)6) 50.73ta)(2)(viii)(A) preci*y m Abspect l

Wow and in Tent, NRC 20 405 ray 1)Ov) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Form 366A) 20 405(a)(1)tv) 50 73(a)(2)hsi) 50.73(a)(2)(x) l LICENSEE CONTACT FoR THIS LER (12) ww TLamost NuustR pnoon Area coce; l L.A. ENGLAND, DIRECTOR-NUCLEAR LICENSING (504) 381-4145 lf COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) i cAust tvn M comovs' vtNar Ac'unER 5 g[

B cAust sys'tu COMPONENT MANUFACTURER i

i t

4 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MOW DAY iLA9 ,

O yEs

" SUBMISSloN l e yn. cm.we t et c'to sasMssoa DATEi E l 4_ DATE (15)

. ABSTRACT ! Lim:t to 1400 s. paces. i e . approximately 15 single-spaced typewritten lines) (16)  !

l .,

a 3 On April 15, 1993 with the plant at 100 percent power (Operational Condition 1) during a logic -

system functional test procedure review program, it was discovered that the reactor core isolation  !

cooling (RCIC) steam line flow - high timer function was not being adequately tested as required by I Technical Specification (TS) Surveillance Requirement 4.3.2.1 Table 4.3.2.1-1.5.b. This l surveillance is a monthly channel functional test that had never been perfonned on a monthly l frequency. Note that a quarterly channel calibration surveillance implemented all of the requirements except the monthly frequency. This report is submitted pursuant to j 10CFR50.73(a)(2)(i)(b) as a condition or operation pmhibited by the Technical Specifications. j i

The root cause of this event was the failure to include a monthly channel functional test in the initial i pmcedure development process. Additional investigation revealed that this condition was also missed i in subsequent reviews and revisions of these STPs. Corrective actions include revisions to the  !

appropriate STPs to implement the monthly channel functional test, training for responsible  !

personnel on this event, and retraining on the Technical Specification definitions for channel l

' calibration, channel functional and logic system functional tests. l VC FO4M 365 5 fc

I REQUIRED NUMBER OF DIGITS / CHARACTERS

• FOR EACH BLOCK , l 5

BLOCK NUMBER OF NUMBER DIGITS / CHARACTERS l 6

1 UP TO 46 FACILITY NAME i-2 DOCE NUMBER 3 IN ADDITIO 4 O 05000 3 VARIES PAGE NUMBER  ?

4 UP TO 76 TITLE .

0 ^

2 PER BL CK 7 TOTAL 6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 7 7 O M DATE -

2 PER BL CK UP TO 18 - FACILITY NAME .

O ^

8 TOTAL- DOCKET NUMBER 3 IN [' NTION TO 05000 9 1 OPERATING MODE

.l s

10 3 POWER LEVEL Il REQUIREMENTS OF 10 CFR

, CHECK BOX THAT APPUES UP TO 50 FOR NAME 12 LICENSEE CONTACT f 14 FOR TELEPHONE CAUSE VARIES [

2 FOR SYSTEM  !

13 4 FOR COMPONENT EACH COMPONENT FAILURE l 4 FOR MANUFACTURER ,

NPRDS VARIES S EM REPOM EFECTED CHECK BOX THAT APPLIES 15 2 PER BL CK n DS B SSION DATE I

i

[

I

+

i i l

+

f i

I B

f-

I NRC FORV 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 '

is sa EXPmES 5/31/95 EE44A43 BJRDEN PER RESPONSE TO COMPLY W'TM TM S 4 E$$$EGSElER #EE'M o""* ST2 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION Eu"M""j$'*81*jyS"-@"AU,*i%

THE PAPERWORK REDUCTON PR:MECT (3tS0-c104b OFFCE OF MANAGEMENT AND BJDGET, W AEHtNGTON, DC 20503 FAChJTY MAME (1) DOCFET NUMBER (2) LER NUMBER fel PAGE (3) bEQUENTAL REWSON NUMBER NUVBER 05000 458 -

RIVER BEND STATION 93 - 005 00 2 4 3

,w m, w.n . nuna. a. .~.w.w umn m; (m REPORTED CONDITION  ;

On April 15,1993 with the plant at 100 percent power (Operational Condition 1) during a logic f system functional test procedure review program, it was discovered that the reactor core isolation coaling (*BN*) (RCIC) steam line flow - high timer function was not being adequately tested as required by Technical Specification (TS) Surveillance Requirement 4.3.2.1 Table 4.3.2.1-1.5.b. i This surveillance is a monthly channel ftmetional test that had never been performd on a monthly  ;

frequency. Therefore, this repon is submitted pursuant to 10CFR50.73(a)(2)(i)(b) as a condition or -

operation prohibited by the Technical Specifications.

INVESTIGATION  :

A review of the STP history revealed that there has never been a monthly channel functional test for j the RCIC steam flow - high timer function. Surveillance test procedures STP-207-4294 and STP-  !

207-4295 satisfy all the requirements of this function but are performed quanerly. Surveillance test procedures STP-207-4536 and STP-207-4237 state in their purpose sections that they satisfy the i requirement for the monthly channel functional test. A~ review of the RBS Technical Specification  ;

cross-reference matrix showed that the matrix identified STP-207-4536 and STP-207-4237 as the i procedures which satisfied the surveillance requirements for the missed monthly channel functional - l test. These tests did not verify the operability of the timer itself, only the function of the steam line flow - high trip unit. These STPs have not satisfied the requirements since their origination in 1988. Prior to 1988, STP-207-4294 and STP-207-4295 were identified as satisfying the monthly surveillance requin ment; however, these STPs also did not meet the requirements for a monthly  !

channel functional test of the RCIC steam flow - high timer. Therefore, this condition existed since  ;

the original procedure development in 1985.

Based on previous events, all personnel responsible for technical reviews of STPs were recently trained on the requirements for performing 10CFR50.59 applicability reviews which specifically covered use of the Technical Specification and USAR requirements; however the investigation i revealui that no formal training on the technical requirements for verification of channel functional test, chamel calibration, and logic system functional test (LSFT) requirements had been provided.

i

}

we roRu m n ea

NRC FOflM 366A U.S. NUCLEAR REGULATORY CoMMISSloN APPROVED BY oMB Ho. 3150-0104 maa ,

EXPIRES 5/31/95 EttMATED BJRDEN PER RESPONSE TO COMPLY W*H TH LICENSEE EVENT REPORT (LER) *C M E*Refs @ R3E,$"u M o'OE O 's'S TEXT CONTINUATION QvWS$7f$"gl'%5"R*dy3i';;8 m M THE PAPERWORK REDUCTION PROJECT Q153-C104), OFFCE OF MANAGEMEN'T AND BJDGET. WASHINGTON, DC 20503. i FACILITY KAME py DOCKET NUMBER p) L1R NUMBER (s) PAGE p) f sEasENTA resioN NUVBER NUVDER 05000 OF i RIVER BEND STATION 458 93 -

005 -

00 3. 4 !

Tm m ,, .,.c. . ,%,,a - --. c p. .=c wn asw o n ROOT CAUSE ^

The root cause of this event was the failure to include a monthly channel functional test in the initial  !

procedure development process for the identified STPs. A secondary causal factor was identified in i the failure of personnel performing previous procedure reviews and revisions to identify this  ;

condition. This causal factor was detennined by reviewing the actions taken by procedure reviewers i to verify Technical Specification confonnance during the procedure revision process. Discussions with some of the procedure reviewers revealed that, for procedure revisions, the purpose section of the procedure and the cross-reference matrix were used to verify that the procedure satisfied the  ;

surveillance requirement as stated in the applicable section of the Technical Specification. Only the specific changes were reviewed for impact on these requirements. Ensuring that the information -

within the body of the STP still contained the steps required to satisfy the surveillance l requirements was not a standard practice for all reviewers of procedure revisions until it was identified in the recent 10CFR50.59 training.

A review of previous LERs for similar events was conducted. This revealed that LERs89-003, 91-  ;

020,92-014, and 93-002 described similar conditions where STPs failed to satisfy the surveillance requirements as identified in the Te tmical Specifications. In each case, corrective actions were implemented to improve the review rmocess for verification of Technical Specification conformance.

CORRECTIVE ACTION i i

The immediate corrective action was the performance of STP-207-4294 and STP-207-4295 (quarterly channel calibration) to demonstrate operability of the timers. These STPs were -

successfully completed.

Smveillance test procedures STP-207-4536 and STP-207-4537 have been revised to include adequate.

steps to satisfy all requirements of a channel functional test. These STPs are scheduled to be performed on a monthly basis to satisfy the frequency requirements of Technical Specification  !

4.3.2.1 Table 4.3.2.1-1.5.a and b. These revisions have been completed as of 5/10/93. ,

i Personnel responsible for perfomling independent reviews and final approval of STP revisions will ,

be trained on the subject of this LER. Additionally, the subject and location of definitions in the  ;

Technical Specification for channel functional, channel calibration and LSFT's will be included. The N

P wRc roRv 3su na

,e .. -

h NRc FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 e s2; EXPIRES 5/31/95 FETIMATED BJRDEN PER RESPONSE TO COMPLY WM TM.S INFORMATCN COLLECTON REQUEST: %D NRS. FORWAC LICENSEE EVENT REPORT (LER) COMME.c6 REGueNG B;nOEN ESwcE TO T-E uORMec, S MA TEXT CONTINUATION AND Rg3vtRE, 73 OOC,yu33cy,w co NAGEMENT B,RANOH 3,iN3Tay,oc ,33ss (MNBB 7714},

,3e,,ty3 e U.S. NJ THE PADERWORK REDUCTON PROJECT QtSWO4:,, OFFCE OF MANAGEMENT AND BJDGET, WASHtNGTON, DC 23503 DOCS.ET huMBER (2) LAR NUMBER (ep PAGE (3}

7 ACILETY NAME (1) bE.QukNTAL HE v'5CN NuuBER NUMBE R .I OF RIVER BEND STATION 05000 458 ~

93 - 005 00 4 4 -

TLK1 (41 mwe space sa reerea sne eambore comes of NF1C form 36M) (17) expected completion date for this training is December 31,1993.

1 SAFETY ASSESSMENT l The Technical Specification surveillance requirements for the channel functional test of the RCIC steam flow - high timer were not satisfied at the frequency specified. However, the components were verified to be functioning properly everf quarter under the channel calibration STP. This -

provides confidence that the RCIC steam flow - high timers have not been inoperable and have been capable of performing their design basis function.

NOTE: Energy industry identification codes are indicated in the text as (*XX*).

I Z

4 l

1 1

1 l

NRO FORM M6A f5 92,