05000254/LER-1993-013

LER 93-013-00:on 930729,identified Deviation from TS & Reg Guide 1.52 Requirements for Methyl Iodide Testing of Charcoal Sample Canisters.Caused by Failure to Implement Proper Canister Testing.Canisters Tested by Nucon

ML20056G971
Person / Time
Site:	Quad Cities
Issue date:	08/27/1993
From:	Bax R, Harms M COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.052, RTR-REGGD-1.052 LER-93-013-04, LER-93-13-4, RLB-93-110, NUDOCS 9309080017
Download: ML20056G971 (5)

LER-2093-013,

Event date:
Report date:
2542093013R00 - NRC Website

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G 22710 206 Avenue North Cordova, Illino:s 61242-9740

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Telephone 309/654-2241 RLB-93-110 l

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August 24, 1993 l l

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U.S. Nuclear Regulatory Commission  ;

Document Control Desk Washington, DC 20555

Reference:

Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One j Enclosed is Licensee Event Report (LER)93-013, Revision 00, for Quad Cities Nuclear Power Station.

This report is submitted in accordance with the requirements of the Code of i Federal Regulations, Title 10, Part 50.73(a)(2)(i)(B). The licensee shall report any operation or condition prohibited by the plant's Technical Specification.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION kY4 R. L. Bax Station Manger RLB/TB/pim Enclosure cc: J. Schrage i T. Taylor INP0 Records Center NRC Region III 1

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STMGR\11093.RLB f 9309080017 PDR 930824 C S ADOCK 05000254Q PDR Q

. LICENSEE EVENT REPORT (LER) Form Rev. 2.0

'ecchty Name (1) Docket Number G) Page (3)

Quad Cities Unit One 0 p p p p p f p i pf p p Inle (4)

Control Room HVAC Chartoal Canister Testing Devia:ed From Tech Spec Evera Date (5) LLR Nurnber (6) keport Date (7) Other Focahues involved th)

Month Day Year ) car Sequential Revision Momh Day Year Fecahty Docket Numberts)

Number Number Names Quad Ciues Urut 2 0 p p p p p f f 0 p 2 p 9 p 4 p -

O p p .-

O p 0 p 2 p 9 p 0 p p p p l l l UPERATING TH15 kLPukI 15 $UBMTrf ED PUR$U ANT lu THE it JJULAIAtLN15 Of: 10Cf R MODE (9) 1 Check one or more of the following) (1I) 4 20.402(bj 29.405(c) 30.73(a)QJov) 73.71(b)

Puw LR 20 405(a)(I)(i) 50.36(c)(I) 50.73(a)(2)(v) 73.7)(c)

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LEVEL 20 405(a)(1)(ii) 50.36(c)(2) 50.73(a)G)(vii) Other (Specify (10) I p p 20 405(a)(1)0ii) T50.73(a)(2)6) 50.73(a)G)(viii)(A) in Abstract 20.405(s)(1)0v) 50,73(a)(2)Gi) 50.73(a)(2)(viii)(B) below and in 20.405(a)(1)(v) 50.73(a);2)(i 50.73(a)(2)(x) Text)

LICENSEE CONl ACT Fuk lt(15 LLR (11)

NAME 1LLLIHONE NUMBER l

UtEA CODE Michac! Harms. System Engineer Ext. 2159 3 p p 6 p p l.p p p p COMPLEIL ONE LINL Fuk LACH COMK)NLNT F ALLURL DL5CRibED LN THis REPuRT (13)

CAUSE 5) STIA4 COMPON ENT M AN U F ACT UkER REPuRT ABLL CAU5L 5YSTLM COMPuNENT M AN U F ACT URLk kEPORTABLE TO NPRDS TO NPRDS

^ l l I I I I I I I I I I I I I I I I I I I I I I I I SUPPL 13tLNT AL kLPURT LXPLCILD tid) Expected Month Day Year Submission

]YES (If yes, complete EXPECTED SUBMISSION DATE) K NO Date (15) l l l AESTRACT (Lamit to 1400 spaces, t.e., approumately fifteen ample-space typew ritten hnes) (Iti)

ABSTRACT:

On July 29, 1993, at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, Unit One and Two were in the RUN mode at 100 and 32.1 percent of rated core thermal power, respectively. At this time, a possible deviation from Technical Specification and Regulatory Guide 1.52 requirements for methyl iodide testing of charcoal sample canisters was identified. Through discussions with Nuclear Consulting Services, Inc. (NUCON), the Control Room [NA] (CR) ventilation system engineer verified that a deviation had occurred. On July 30, 1993, the Shift Engineer (SE) decided that the deviation was reportable per 10CFR50.73(A)(2)(i)(B).

The apparent cause of this event was a lack of understanding by the present and previous system engineer of the sample canister testing criteria.

The corrective actions were to investigate the incident, decide reportability, and ship additional sample canisters to NUCON for further testing. A procedure change request was submitted and the system engineer qualification card was updated.

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i L3CENSEE EVENT REPORT t'LER) TEXT CONTINU ATION Form Rev. 2.0 F ACLUTY NAME (1) DUCKEl NUMBER (2) LLR hUMBER (0) PAGE(3)  !

Ycar Sequennal Revision Number Number Quad Citie: Unit One 0 p p p p p p p 9 p -

0 $ p 0 p 2 lOF p p TEXT Energy industry idenu6 canon System (L115) codes are idenu6ed m ine sexi as (XX)

PLANT AND SYSTEM IDENTIFICATION:

General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.

EVENT IDENTIFICATION: Control Room HVAC charcoal canister testing deviated from Tech -

Specs.

A. CONDITIONS PRIOR TO EVENT:  ;

Unit: One Event Date: July 29, 1993 Event Time: 0845 Reactor Mode: 4 Mode Name: RUN Power Level: 100%

i This report was initiated by Licensee Report 254/93-013.  !

RUN (4) - In this position the reactor system pressure is at or above 825 psig, and ,

the reactor protection system is energized, with APRM protection and RBM interlocks  !

in service (excluding the 15% High flux scram). l B. DESCRIPTION OF EVENT:

On July 29, 1993, at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, Unit One and Two were in the RUN mode at 100 and 32.1 percent of rated core thermal power, respectively. At this time, the Control Room [NA) (CR) ventilation system engineer identified a possible deviation from Technical Specification and Regulatory Guide 1.52 requirements for methyl iodide testing of charcoal sample canisters for'the air filtration unit (AFU). Earlier, on July 23,1993, the charcoal adsorber [ ADS] trays and all eight sample canisters for l the CR AFU were replaced during planned maintenance and testing. During discussions  ;

with Nuclear Consulting Services, Inc. (NUCON) on July 29, 1993, the system engineer observed that the station had shipped an insufficient amount of canisters to be tested in both November, 1991, and July, 1993. Regulatory Guide 1.57. requires that when a filter train is composed of two 2 inch charcoal beds in series, both an upstream and downstream sample must be sent for laboratory analysis so that they may be tested as a combined 4 inch aggregate bed depth. By sending only one canister each time, only 2 inches of the total 4 required were being tested.

The discussion with NUCON also revealed that when the test canister was removed and sent for testing in 1991, the system engineer requested it be tested at 30 degrees Celsius (deg C) and 70 percent relative humidity (RH). Technical Specification section 3.8.H.2.c. requires that the test canister be tested at 130 deg C and 95 j percent RH. '

LER254593\013.WPF l

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• UCENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 F ACILfiY N AML (1) DOCKL~I NUMbLR Q) LER SUMBLR to) PAGE0)

) ear Sequenual kevmon Number Number Quad Cines Unit One 0 p p p p p p p 9 p -

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O p 3 pF p p IEXT Energy ladustry idenh6 canon System (LilS) codes are idenu6ed in me icxt as [XXj The system engineer's investigation into the cause of this event identified that in November,1990, a third sample canister was removed from the AFU and was tested to 30 deg C and 70 percent RH. This test was not required and appears to have been done in  ;

preparation for the more stringent testing standards that the station is planning to 1 incorporate into its Technical Specifications. However, the removal of this canister l left only one canister installed in the AFU. Soon after this testing was completed, a new system engineer assumed control of the system. When another test came due in 1991, the system engineer removed the installed canister. Since this depleted the supply of installed sample canisters, the charcoal adsorber trays and canisters had to be replaced by Mechanical Maintenance (MM). MM replaced all of the charcoal adsorber trays. However, only one of the eight sample canisters was installed because of poor work instructions in the work package and a lack of understanding by the system engineer of the sample canister testing requirements. The system was returned to service in this configuration.

On July 30, 1993, the system engineer contacted NUCON again and arranged to have 2 new sample canisters sent for testing. These canisters were from the same batch of charcoal as the charcoal adsorber trays that were installed on July 23. The Shift l Engineer (SE) was notified and decided that a Licensee Event Report was necessary per l 10CFR50.73(A)(2)(i)(B).

On August 2, 1993, the two new sample canisters were shipped to NUCON for testing.

l These were tested to the appropriate Technical Specification and Regulatory Guide l.52 requirements. The results of this test showed an efficiency of 99.983 percent for the four inch bed depth.

C. APPARENT CAUSE OF EVENT:

This report is being submitted in accordance with 10CFR50.73(A)(2)(i)(B), which requires the licensee to report any operation or condition prohibited by the plant's l Technical Specifications.

The apparent cause of this event was a lack of understanding by the present and previous system engineer of the test criteria for the sample canister laboratory analysis. If the system engineers had known that both a downstream and upstream sample were required for all tests, a single sample canister would not have been left in the AFU following the additional test performed in 1990. If the new system engineer had understood this requirement in 1991, all eight sample canisters would have been installed. There would have then been two sample canisters for analysis in 1993. This lack of understanding also caused the system engineer to test the 1991 sample canister to acceptance criteria other than those specified in the Technical Specifications.

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. LICENSEE EVENT REPORT (LER) TEXT CONTINU ATION Form Rev. 2 0 j FACILITY NAME (1) DOCKET NUMBLR (2; LER huMBLR (t)) PAGE 0) i icar Sequenual kension Number Number Quad Catees Urut one O p p p l0 p p }4 9 p -

0 l1 p 0 l0 4 lOF p l4 i 1 LXT Energy lacustry idenufusuon System (Lil5) cases are idenuf.ed in the test as (n)

D. SAFETY ANALYSIS OF EVENT. j l

The safety significance of this event was minimal. All tests performed on the sample ,

canisters in the past have produced results of greater than 99 percent removal  ;

efficiencies. This includes the tests performed at 30 deg C and 70 percent RH. l Technical Specifications only require an efficiency of greater than or equal to 90 I i percent. From these results, it is likely that the charcoal adsorber trays that were  :

i installed when the insufficient testing was performed had a removal efficiency of i

greater than 90 percent. In addition, the test performed at 30 deg C and 70 percent i i RH is more conservative than the test performed at 130 deg C and 95 percent RH. This I J

is because any foreign material that would normally compete for adsorption sites on  !

the charcoal is essentially baked off in the 130 deg C test, making the charcoal l appear more efficient. This does not happen during the 30 deg C test.  !

E. CORRECTIVE ACTIONS

l The immediate corrective actions taken by the system engineer were to perform an investigation into the apparent Technical Specification deviation and then ensure ,

that the presently installed charcoal would be tested properly. After the work  !

i instructions in the work package were checked to ensure that they specified all twelve trays and all eight sample canisters. The work instructions in the work l 1

package were checked to ensure that they specified all twelve trays and all eight l sample canisters. After the investigation indicated a deviation had occurred, the SE 1

decided the reportability.

l Additional sample canisters from the newly installed charcoal were sent to NUCON for j testing. The testing was performed to the appropriate Technical Specification and '

Regulatory Guide 1.52 requirements. An efficiency of 99.983 percent was the result I of the test.

i A procedure revision request to QCTS 440-3, " Control Room Emergency Filtration System Removal of Charcoal Adsorber Test Canister," has been submitted that more clearly states that an upstream and downstream sample canister must be sent each time a test l is performed. The Control Room ventilation system engineer qualification card was i updated to mandate training on the sample canister and adsorber testing for all new

] system engineers. This will include an in-depth review of all regulations and

. Technical Specification sectior.s.

! F. PREVIOUS EVENTS:

There are no previous events where the AFU charcoal sample test canisters were not tested in accordance with the Technical Specifications and the appropriate regulatory q guides.

1 i G. COMPONENT FAILURE DATA:

i This event did not involve component failure.

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