ML20045D374

LER 93-008-00:on 930520,determined That TS SR Not Satisfied for Stack Flow Indicator,Per Amend 137 Issued on 910307. Caused by Lack of Attention to Detail.Calibr & Functional Test Procedures developed.W/930621 Ltr

ML20045D374
Person / Time
Site:	Fort Calhoun
Issue date:	06/21/1993
From:	Blessie W, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-008, LER-93-8, LIC-93-0066, LIC-93-66, NUDOCS 9306280300
Download: ML20045D374 (5)

Text

_ _ . _ _ _ _ _ - _

Omaha Public Power District P.O. Box 399 Hwy.75- North of Pt. Calhoun Fort Calhoun. NE 680234399 402/636-2000 June 21, 1993 LIC-93-0066 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

Subject:

Licensee Event Report 93-008 for the Fort Calhoun Station Please find attached Licensee Event Report 93-008 dated June 21, 1993. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B). If you should have any questions, please contact me.

Sincerely, W h. .

W. G. Gates Vice President WGG/jrg Attachment c: J. L. Milhoan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector INP0 Records Center L50005 '

45.5129 9306280300 930621 5 PDR ADOCK 0500 S

NRCFORMSee U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 315odo4

&4 EXPIRE 8 5/31/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WrrH THIS UCENSEE EVENT REPORT (LER) LT^g ngE 9 QQUE, E 5

o ,HH I

"^

RMAIM AND RECORDS MANAGEMENT BRANCH (MNBB 77t4), UA NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 205554001, AND TO (See reverse for required number of digits / characters for each block) EEEN[U $A GTON, FACILrnf NAME(1) DOGNET NUMBER (ig PAGE l3)

Fort Calhoun Station Unit No. 1 05000285 10F 4 TITLE (4)

Failure to Implement Surveillance Requirement for Stack Flow Indicator EVENT DATE (5) LER NUMBER (6) REPORT NUMBER (7) OTHER FACluTIES INVOLVED (8)

MONTH DAY YEAR YEAR MONTH DAY YEAR S N 8 FACILrTY NAME DOCKET NUMBER 05 20 93 93 --

008 --

00 06 21 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR 8: (Check one or more) (11) 1 MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 100 20 405(a)(1)(ii) 50 se(c)(2) 50.73(a)(2)(vii) l OTHER 20.405(a)(1)(iii) X 50.73(a)(2)(l) 50.73(a)(2)(viii)(A) Abst et

{pecif 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) p, y 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

UCENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (include Area Code)

William J. Blessie, Shift Technical Advisor (402) 533-6896 COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER O PRDS CAUSE SYSTEM COMPONENT MANUFACTURER N S SUPPLEMENTAL REPORT EXPECTED (14) M NTH DAY YEAR EXPECTED YEB SUBMISSION (if yes, complete EXPECTED BUSMISSION DATE) X NO DATE (15) l ABSTRAOT (Umit to 1400 spaces, i.e., approximately 15 single-spaced typewritten ilnes) (16)

As a result of issues discussed at a May 20, 1993 Plant Review Committee (PRC) meeting, it was determined that Technical Specification (TS) Surveillance Requirement 3.12.1(2)b(iv) had not been satisfied and that the failure to implement this Surveillance Requirement was reportable. This specification required the Laboratory and Radioactive Waste Processing Building (LRWPB) exhaust stack flow rates to be calibrated and functionally tested at a refueling frequency. This requirement was associated with TS Amendment 137 which was issued March 7, 1991. The LRWPB exhaust stack flow instrument loop was installed as a part of Modification MR-FC-88-121.

l The root cause of this event was determined to be lack of attention to detail. The various departments and personnel involved in this event failed to review Modification MR-FC-88-121 and TS Amendment 137 in sufficient detail to ensure all required procedure updates and new procedures were identified and developed.

Corrective actions will include developing calibration and functional test procedures, and establishing a requirement for a verification of procedure changes which are developed to address a TS amendment.

l l

l l Nna rOnu me em I

'NRC FORM 306A U.S. NUCLEAR RELULATORY COMMISSION APPROVED BY OMB NO. 3150 olo4 P82) EXPIRES 5/31/95 -

EESAON E N A UCENSEE EVENT REPORT (LER) '

Tuxr conuNUATION EREcEEuEr"dENos"nD"sYS W?###"e**2#=aiiaCa a MANAGEMENT AND BUDGET WASHINGTON,DC 20503.

l FActRY NAhE!(t) DOOMET NUMIER R (ER NUMBER M PAGE R MR N MEER UMB Fort Calhoun Station Unit No. 1 05000285 '

93 -- 008 -- 00 TEXT (if more space is required, use additional copies of NRC Form 366A) (17)

BACKGROUND TheChemistryandRadiationProtection(CARP)-BuildingandRadioactiveWasteProcessing Building (RWPB) are two structures recently built as part of Fort Calhoun Station (FCS) improvements. Their ventilation systems use a common exhaust stack that is independent from other plant ventilation systems. The exhaust stack is equipped with its own radiation monitors, designated as the Laboratory and Radioactive Waste Processing Building (LRWPB)ExhaustStackParticulate,IodineandNobleGasMonitors(RM-041, RM-042andRM-043,respectively).

RM-041/042/043 monitor a continuous sample stream from the LRWPB exhaust stack. In order to obtain a representative sample of particulate and iodine activities released from the LRWPB exhaust stack, isokinetic flow is required through the sample nozzles.  ;

To achieve the isokinetic flow, a minimum flow rate of 8000 cfm (cubic feet per minute) is required out the exhaust stack. To ensure the exhaust flow meets the minimum acceptable flow rate, the flow rate indicated by LRWPB Exhaust Stack Flow Indicator / Transmitter FIT-6699 and/or its associated plant computer point F6699, is periodically monitored and recorded.

EVENT DESCRIPTION l

On May 6, 1993, at 0820, with FCS at approximately 52% power (Mode 1) following a short duration planned outage, RWPB ventilation was discovered secured. The cause was determined to be a malfunction of an air compressor,-in the RWPB, which supplies air pressure to the air operated dampers. CARP Building ventilation was still in service.

The Auxiliary Building Operator and the Shift Chemist noted that the flow indicated by FIT-6699 was approximately 7600 to 7800 cfm. The Shift Supervisor was informed, and CARP Building ventilation was shut down to secure any release through the LRWPB stack.

Compressed air was restored, and the RWPB and CARP Building ventilation systems were restarted. FIT-6699 then indicated a flow rate greater than 8000 cfm.

System Engineering was informed of the low flow indication and began an investigation.

An action plan was developed to support the investigation and resolution of the low flow indication. As part of the action plan, Maintenance Work Order (MWO) 931505 was initiated to measure system air flows for the RWPB and CARP Building ventilation systems, using a hot wire anemometer.

Measurements taken on May 13, 1993, indicated that air flow from the CARP Building

! ventilation system alone was greater than 8,000 cfm (measured flow was 10,607 cfm). It was also determined that FIT-6699 was indicating a significantly lower flow rate than measured by the hot wire anemometer.

NPS FORM 36tiA @D2)

L .. - _ _ .__ . - _ , -,_

NRC FORM 306A U.S. NUCLEAR RELULATORY COMMI8SION APPROVED BY OMB NO. 318o4104 74 EXPlRE8 5/31/96 UCENSEE EVENT REPORT (LER)

EmEE

• E85 "aN I=E j TEXT CONDNUAVON E ECOF EMANA M BB 74)

TF P RWORK P E (3 1 OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON,DC 20503, FACRJTY NAME (1) DOOMET NUMBER R LER NUMBER R PAGE R

• " "'"'*7 uuueE EE Fort Calhoun Station Unit No. 1 05000285 93 -- 008 -- 00 TEXT (If more space is required, use addthonal copies of NRC Form se6A) (17)

The action Committee (plan and20, PRC)onMay results 1993 (with of accomplished FCS in Mode 1 at tasks 100%were power). discussed In response with tothe a Plant Rev]

PRC request, a review was performed of Technical Specifications associated with the system. It was determined that Surveillance Requirements of Technical Specification (TS) 3.12.1(2)b(iv), which required a refueling frequency calibration of FIT-6699, had not been satisfied. The failure to implement this Surveillance Requirement was determined to be reportable. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B).

Due to the discrepancy between the flow rate indicated by FIT-6699 and the measured flow readings taken under MWO 931505, MWO 931553 was initiated to check and calibrate FIT-6699. The vendor technical manual was used since no calibration procedure existed for the instrument loop. The calibration was performed on May 24, 1993, and restored FIT-6699 and associated components to operation. At the completion of the procedure, 1 FIT-6699 was reading 27,800 cfm (for total flow rate from both RWPB and CARP Building ventilation systems), which was within 5 percent of the total flow rate (28,070 cfm) determined using the anemometer.

SAFETY ASSESSMENT This event had minimal nuclear safety significance. The lack of proper calibration and functional tests as required by the TS for the LRWPB exhaust stack flow instrument loop, provided the potential for inaccurate flow rate information from FIT-6699. FIT-6699 is l l used to ensure that an actual flow rate above 8000 cfm is maintained, in order to ensure isokinetic flow. A flow rate below 8000 cfm would result in a non-representative sample ,

being provided to RM-041/042/043. Measurements taken on May 13, 1993, indicated an l l actual flow rate greater than 8000 cfm, even with RWP8 ventilation secured. The as- ,

found condition of FIT-6699 (i.e., indicating lower than actual flow) was conservative  !

with respect to ensuring that minimum flow requirements were met.

CONCLUSIONS Technical Specification Amendment 137 was issued March 7, 1991. This amendment added Limiting Conditions for Operation and Surveillance Requirements (TS Sections 2.9.1(2)h and3.12.1(2)brespectively)whichaddressedtheLRWPBexhauststackmonitors. TS Section 3.12.1(2)b(iv) stated, in part, " ... the Laboratory and Radioactive Waste Processing Building Exhaust stack flow rates will be calibrated and functionally tested at a refueling frequency." Following receipt of the amendment, a review was initiated in order to assure that appropriate procedures would be revised or issued to address the amendment.

l Nne rOnu seeA pm l

L_- -

~ . .. - - -_ . . . - - . - .

NRC FORM 306A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-o101 l m . EXPIRES 5/31/95 ESilMATED BURDEN PER RESPONSE TO COMPLY WITH Tin UCENSEE EVENT REPORT (LER) lNg gDNM S T E O INF TEXT CONDNUATION ggsggNT,ggyn .N N D DUDG , ASH TON, FAOLfrY NAME (1) D00 MET NUMBER M l.ER NUMC"1 D PAGE M g SEQUENTIAL REVISION NUMBER NUMBER Fort Calhoun Station Unit No. 1 05000285 93 -- 003 -- 00 TEKT (if more space is required, use additional copies of NRC Form 306A) (17) l The LRWPB exhaust stack flow instrument loop was installed as part cf Mcdification MR-FC-88-121, and functional testing was completed June 12,19:)1. Constractica i Package Installation Procedure E-1 was accepted for operability on September 30, 1991, '

and this included FIT-6699. l l

A Root Cause Analysis (RCA) was performed following identification of the failure to I implement the surveillance requirement for FIT-6699. The RCA concluded that the root cause of this event was lack of attention to detail. The various departments and personnel involved in this event failed to review Modification MR-FC-88-121 and TS Amendment 137 in sufficient detail to ensure all required procedure updates and new procedures were identified and developed. l l A contributing cause was determined to be the failure to involve all appropriate 1 personnel (specifically the System Engineer responsible for ventilation systems) in the  !

implementation review for TS Amendment 137. I (Note: Technical Specification Amendment 152, issued March 25, 1993, has revised the Technical Specifications such that Sections 2.9.1(2)h and 3.12.1(2)b have now been .

superseded.)  !

CORRECTIVE ACTIONS The following corrective actions will be performed:

1. Calibration and functional test procedures for FIT-6699 will be developed and I implemented by September 15, 1993.

2. ProcedureN0D-QP-7,"FacilityLicenseChanges(FLCs)",willberevisedby August 31, 1993, to include a requirement for a verification that procedure changes developed to address a TS amendment are consistent with, and fully address the requirements of the amendment.

3. A review of a sample of Technical Specification Aacndments issued since 1990, will be performed by December 15, 1993, to determine if tha asscciated document revisions adequately addressed the requireicni.s of the amendments.

PREVIOUS SIMILAR EVENTS LERs93-001, 91-008,91-001, 89-002,88-008, 87-037 and 87-010 discuss events involving surveillance tests that did not meet TS surveillance requirements.

Nnoronu aceA m

.,e

,-l