IR 05000254/1990016

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Enforcement Conference Repts 50-254/90-16 & 50-265/90-16 on 900905.Violation Noted.Matters Discussed:Failure to Take Prompt Corrective Action to Resolve Deficiency in 1/2 Emergency Diesel Generator Cooling Water Pump Flow
ML20059J657
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 09/11/1990
From: Danielson D, James Smith
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20059J639 List:
References
50-254-90-16-EC, 50-265-90-16, NUDOCS 9009200105
Download: ML20059J657 (29)
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i ! U. S. NUCLEAR REFILATORY COMMISSION < REGION III' ' Reports'No. 50-254/90016(DRS);50-265/90016(DRS) ! Docket Hos: 50-254; 50-265 Licenses No. DPR-29; No. DPR-30

Licenree: Commonwealth Edison Company.

!

Opus West III 1400 Opus Place . ' Downers Grove, IL 60515 i , facility Name: Quad Cities Station - Units 1 and.2 , ! Meeting At: U. S. Nuclear Regulatory Connission

Region III Office.

~ Glen Ellyn, IL 60137, Meeting Conducted: September 5, 1990 l Type of Meeting: Enforcement Conference ! Inspector-Mb h 9//f/.00 ! ud. F. Smith Date ' t Approved By: M7bM W S // _90 D. H. Danielson, Chief Dat6 ' Materials and Processes Section l

M_eeting Sunnary

Meeting on September 5, 1990 (Reports No.'50-254/90016(DRS); ho. 50-265/90016(DRS)) , Matters Discussed: Apparent violation of 10 CFR 50,-Appendix B, Criterion XVI:

Failure to take prompt corrective' action to-resolve a deficiency in the 1/2 EDG cooling water pump flow. The specific deficiency is described on Pages 2

through 5 of HRC Inspection Reports No. 50-254/90010(DRS)andNo.

50-265/90010(DRS).

3ased on a review of the information presented by- . the-licensee and of the NRC Enforcement Policy, the NRC Region Ill; staff . i determined that escalated enforcement actions were not warrante( and categorized.

j the discrepancy as a Severity Level IV violation.

. ! ., h l i ' l . [' khf2{'g CK 05000254 05 9007.13 - L-Q PDC l

[ .o .g ' DETAILS- ' 1.

Enforcement Conference Attendees 'Conmionwealth Edison Company (CECO) D. Galle, Vice President, BWR Operations T. Barber, Regulatory Assurance P. Barnes, Licensing Administrator R. Bax, Station Manager D. Gibson, Regulatory Assurance Supervisor N. Kalivianakis, General Manager - T. Kovach, Nuclear Licensing D. Legles, Regulatory Assurance P. Manning, Nuclear Quality Programs . K. Peterman, Regulatory Assurance Su')ervisor R. Querio, General Manager, Quality ?rograms K. Ramsden, Reactor Systems' Engineer M. Schreim, BWR Systems Design Engineer G. Spedi, 'roduction Manager.. R. Stols, Licensing Administrator R. Tsai, Safety Analysis Engineer Sidley and Austin S. H. Trubatch, Attorney U. S. Nuclear Regulatory Commission (U. S. NRC) > A. B. Davis, Regional Administrator, Region?ll! H. Miller, Director, Division of Reactor Safety, Region 111-C. Pederson, Director, Enforcement-& Investigation Coordinator Staff,- Region 111 L. 01shan, Project Manager, Nuclear Reactor' Regulation, HQS J. Smith, Reactor Inspector, Division of Reactor S#fety Region 111 R. Lerch, Project Engineer, Division of Reactor Projects, Re D. Hartland, Reactor Engineer, Division of Reactor P.rojects,gion III Region 111 R. Langstaff, Reactor Inspector, Division of Reactor Safety,-Region 111.

2.

Enforcement Conference The Enforcement Conference was held to discuss'the apparent violation . of10CFR50,AppendixB(DRS)andNo. Criterion XVI.-identified in NRC Inspection Reports No. 50-254/90010 50-265/90010(DRS).

In opening the, conference, the NRC stated the purpose of the conference, presented a brief-description of the events that led to the apparent violation, and summarized the inspection findings (See Enclosure 3). -- The licensee was requested by.

the NRC to discuss the following:

l

i l - . The onsite review approval of a procedure which would leave one of

two essential systems without water.

i The 1989 internal SSf1 of the 1/2 EDG which did not disclose the !

problem of. inadequate' output from the 1/2 EDG cooling water pump.

[ The corrective actions to related findings of the 1989 SSFI which j

'did not disclose the 1/2 EDG cooling water pump problem.

The failure to analyze the consequences of operating the-system !

without ECCS room cooler.

~The temperature profile of the ECCS roo.as and the effect of operating i ' the component with no cooling from the 1/2 EDG cooling pump.

l The licensee presented.the results of their review concerning the apparent [ violation and presented their analysis of the topics for discussion l previously identified. _ in addressing their analysis, f,he. licensee stated ' their corrective actions initiated to preclude repetition of the' apparent violation and to ensure the proper regulation of the 1/2 EDG cooling-waterpumpflowinthefuture.JSeeEnclosure4) i 3.

NRC Review

The NRC staff considered the information p esented at the Enforcement - Conference regarding the reasons for the apparent violation, and the~ r safety significance, and determined t6.e following:- The failure to recognize the significance of the perceived 1/2 EDG- !

cooling water pump flow deficiency was not a deliberate _ nor a .; conscious decision, but rather a technical oversight.

! i

The onsite review of the abnormal operating procedure did not fully ! recognize that the 1/2 EDG cooling water pump was needed to satisfy , , single failure criteria.

' The safety significance of this vio1'ation is. limited in that analysis

showed that, under conditions of no flow from the 1/2 EDG cooling water pump, the temperature in the ECCS. rooms would. remain within-acceptable limits for at least four days, during which. time the i cooling water problem could be resolved (The NRC inspector confirmed

that the throttling of-the 1/2 EDG cooliag water pump _which caused tN indication of a flow deficiency in 1986 is; removed by a separate , operation at the completion of the inservice test procedure which i required the throttling. Without this throttling, the.1/2 EDG cooling water pump is capable of providing. adequate cooling for both the 1/2 EDG and the affected unit's ECCS-room coolers.)- q u

c ' v v -

. . While the. safety significance of this matter is limited.uthe manner in which it progressed is disturbing. A substantial number of responsible personnel were exposed to anomalous information presented in connection with a revision to an' abnormal operating procedure intended to resolve.

the problem, however there was little questioning of the basis for the revision or of the consequences of the use of the revised procedure in an emergency..Significant improvements in the' areas" of personnel training, procedure review, corrective action program,'and Technical Specifications as identified in the-licensee's presentation.(Enclosure.4), are warranted ~ zand will be carefully followed by the NRC stiff:in future inspections.

4.

Enforcement Action AnapparentviolationofLNRCrequirementswasidentifiedduring:the-inspection.- This apparent violation was described in Inspection Reports; 'No. 50-254/90010(DRS) and No.. 50-265/90010(DRS);however,.a,Noticeof Violation was not issued with that report pending NRC review of information-presented by the licensee at the Enforcement Conference. 'As~ stated above in Section 2, the licensee did not present information that would cause~ the NRC to reconsider its. findings.Therefore, the Notice of Violation is being issued witn this report.

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LOVADCITIESSTAIJ@i . DFORCDUT COWEPalCE ' ' - .

FA!l.URE TO PROVIDE Pf0 PT CORRECTIVE ACTION.

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SEPTBiBER 5, 1990.

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SEPTDTER 5,1990' j ' i = .

OP0ll!)G RD%RKS 'A. B. DAVIS - , PEG 10llAL ADMItllSTRATOR - ! - + i lifTRODUCTORY C0tBITS 11. J. MILLEP, DIPECTOR

-DIVISION OF REACTOR SAFETY)

1E0illCAL ISSUES

J; F SMITil, REACTOR ltGPECTOR-

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MATERIALS & PROCESSES SECT 101

J DIVIS10ll 0F PEACTOR SAFETY , - LICB GEE RESPQlSE C0tDAEALTil EDISoll C0tFAIN l

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POTDiTIAL VIOLATIQt > i ) ' - , i .! . .i

, -. BE LICOGEE LEAMED OF A DEFICIBlCY Ill TIE FL0il CAPICITYl0F THE . .a ' -

, . > - y < ! 1/2 EDG C00Lil0 WATER Pt.tP IN MAROL1906, AND.TOOK N0 EFFECTIVE ' j ' , u

, , ACT101 TO CORRECT BE DEFICIBlCY lMIL' JttlE 1990', THIS IS C0tEIDDED ! ' u.

o - ':; ,. . TOBEAPOT81TIALV10LAT10tIDF10CFR50,APPBlDIXB',CRITER10NXVI,-

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' 1, 03/17/86:- R0lRINE TEST ll01CAED lilADEQUAE EDG PUFP FLQI < i j; <, ADN00MALOPERATilsPROCEDUREilASCHAllGEETOPREVEllT

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- 2, 07/87~ > -

' FEEDl!0 BOTH 1/2 EDG A!D ECCS R004 COOLERS FROM 11E - '

1/2 EDG' C00LillG llAER PLW.

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06/29/89 - 00AD CITIES SSFI 0F Tile 1/2 EDG (SSI Oll-89-01) ilAS ' '

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11. 0G/06/90-~ . PLAll T0 !!NESTIGATE EDG C00Lil0 PlW PRDBLEM ilAS: . INITIATED, ! l ! . r ! . . . - ! 5.

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....# 3 ' ps . u .. CQKD16 , OlEITE IEVIBf APPROED A PROCEDURE 18110110VLD LEAVE QE OF B0

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ESSOfflAL SYSEMS tilB10lff C00LillG \\lATER.

1989 SSF1 DlD ICT DISCLOSE 1/2 EDG C00LIllG llATER PLM) PROBLEM,.

~ CORRECTIVE ACTIQ 1 TO TilREE RELATED FINDIllGS IllllE 1989 SSFI DID

10T DISCLOSE TIE 1/2 EDG C00LillG llATER PLM) PROBLD).

OPERATIQ10F BiE SYSTEM WIBI0lfT ECCS ROOM COOLERS tlAS 10T AtlALYZED.-

TTJPERATURE PROFILE OF ECCS ROOMS WAS Ull20#1 AllD lilE EFFECT OF OPERATillG

C0FF0ElffS Ill BE ECCS ROOMS WITil 10 C00LillG FROM TiiE 1/2 EDG C00LIllG IWPtlASLt!!30#1.

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f DCOSSE_i ., , SEPTEMBER 5,1990 QUAD CITIES 1/2 DIESEL GENERATOR COOLING WATER PUMP ENFORCEMENT CONFERENCE AGENDA

  • INTRODUCTION D,GALLE'
  • OVERVIEW OF EVENT G. SPEDL
  • SAFETY SIGNIFICANCE K. RAMSDEN
  • SSFI1/2 EDG P. MANNING
  • CONCLUSIONS / CORRECTIVE ACTIONS G. SPEDL
  • OVERALL CONCLUSIONS D.GALLE'

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. _.. __.

-. - -. -.. - _.. _. - _ _ - _. - -. -... - - - _ -

. ! - t - . ' CEOO OVERVIEW

l A VIOIATION OCCURRED IN THAT QUAD CITIES PERSONNEL i l FAILED TO TAKE EFFECTIVE ACTIONS TO RESOLVE AN l APPARENT FLOW DEFICIENCY IN THE 1/2 DGCWP.

f I '

THE 1/2 DGCWP WAS PHYSICALLY CAPABLE OF PROVIDING l l SUFFICIENT COOLING FLOW TO THE 1/2 EDG AND THE ECCS { ROOM COOLERS BASED ON A 1990 TEST. A PROCEDURE ! ' CHANGE, HOWEVER, LIMITED THE USE OF THE 1/2 DGCWP.

' ! APPARENT CAUSE , '

.

PERSONNEL OVERLOOKED CERTAIN DESIGN FUNCTIONS OF ' , o THE 1/2 DGCWP. IT WAS RECOGNIZED THAT THE 1/2 DGCWP ' i SUPPORTED OPERABILITY OF THE 1/2 EDG. IT WAS NOT i l RECOGNIZED THAT THE 1/2 DGCWP WAS REQUIRED TO SUPPORT

BOTH THE 1/2 EDG AND THE ECCS ROOM COOLERS GIVEN A f SINGLE FAILURE OF THE DGCWP ON THE UNIT DIESEL.

! , , L CONTRIBUTING FACTORS

DIESEL GENERATOR COOLING WATER IS NOT i f REFERENCED IN TECH SPEC /UFSAR.

l 1/2 DGCWP IS SUPPORT SYSTEM FOR 1/2 EDO.

  • i 1/2 DGCWP NOT NORMAL SUPPLY TO ECCS ROOM

+ , COOLERS.

,

SAFETY SIGNIFICANCE MINIMAL SAFETY SIGNIFICANCE IN THAT ECCS EQUIPMENT OPERATION CAN BE ACCOMMODATED FOR 4 DAYS WITHOUT

ROOM COOLERS. THIS IS BASED ON AN ANALYSIS COMPLETED SUBSEQUENT TO DISCOVERY OF THE VIOLATION.- /scl:ID230:2 ! - - . . ..- -. ... - -... -. . .- .. - . -.. -.. =. -. . :

- _ - - _ _ _ . , .' ., . ODGCWP U-1 U-1/2 U-2 DGCWP DGCWP l p , p - - -

J .

- 5 7 5 7 5 7

s 2,1

1 mumm [[ D/G D/8 RHR 1A/B' RHR 2A/B = - ,, RHR 20/D l RHR 10/D== -

3 Y '" N b LPCS 1A LPCS 2A = - s LPCS 1B LPC8 2B = - i . HPCI 1 "" ' HPCI2 - Diesel Generator Cooiing' Water System (Normal U-1, U-2,1/2 Cooling Water Flow Path) i - - _ - _ - _ _ - - _ _ _ - - _ - _ - - _ _ -. _ _ - _ - _ _ _ _ - - _ - _ _ _

-- - _ - -. - - -.. . - _ -. - - - - - _ _ - _. - - _. -..- _-________ - ' DIESEL GENERA 10E ODOLING WAN EMM DESIGN BASIS o , DESIGN BASIS ,

UFSAR APPENDIX B STATES THAT "THE ECCS INDIVIDUAL SYSTEMS THEMSELVES ARE DESIGNED TO VARIOUS LEVELS OF COMPONENT l REDUNDANCY SUCH THAT NO SINGLE ACTIVE COMPONENT ) FAILURE IN ADDITION TO THE ACCIDENT WILL NEGATE TrIE

REQUIRED EMERGENCY CORE COOLING CAPABILITY," i I.

OTHER FACTORS l g ' DGCW SYSTEM IS NOT REFERENCED IN THE TECH SPEC OR FSAR.

i-BY INFERENCE THE DGCW SYSTEM SUPPORTS ONSITE POWER AND

ECCS ROOM COOLING WITH SINGLE ACTIVE COMPONENT FAILURE.

, L

DRRIGN REQUIREMENTS , S&L SPECIFICATION 2380.

i !

I EDG HEAT EXCHANGER REQUIRES 900 GPM' COOLING

' !' WATER FLOW AT 95 DEGREES F.

i , ECCS ROOM COOLERS REQUIRE 404 GPM COOLING

WATER FLOW AT 95 DEGREES F,

i i S&L SPECIFICATION 2317: '

i f DGCWP'S DESIGN FLOW RATE CAPACITY IS 1804 GPM.-

h j . ALL DGCWPS ARE IDENTICAL AND PURCHASED UNDER THE

SAME SPECIFICATION.

-

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.. ________ _.___._.__ . _ _. _. _ _... _ _. _. _ .. _. _ _. _. _. _ _. _. _ _, . . CHRONOLOGY i l l PRE-

1978 ALL FUNCTIONS OF THE 1/2 DGCW SYSTEM WERE NOT i l INCLUDED IN STATION OPERATING PROCEDURES.

, l

! , l 09/18 ABNORlWAL OPERATING PROCEDURE (QOA 5750-14) FOR i ' l LOSS OF ECCS ROOM COOLERS IMPLEMENTED.

, -

THE PURPOSE OF THE PROCEDURE WAS TO l

  • -

PROVIDE AN ALTERNATE SOURCE OF COOLING , ' ' FOR ECCS ROOM COOLERS IN THE EVENT OF A-LOSS OF A UNIT DGCWP.

. ? 06/86 DGCW SYSTEM SPECIAL TEST (1-80) PERFORMED:. l ! PURPOSE IS TO ESTABLISH A VALID LINEUP FOR

, THE IST CHECK VALVE TEST.

LINEUP INCLUDED FLOWPATH FROM THE 1/2 - DGCWP TO BOTH THE 1/2 EDG HEAT- " l EXCHANGER AND THE UNIT I ECCS ROOM - . COOLERS.

. . , i , /scl:ID230:4 .. - . - - - - -- - - - -. - - -. -... -.. -. -. - -.. _ - -

- - e . .- CHEDNOIDGY 062510DENDED) A FLOW DEFICIENCY WAS IDENTIFIED IN THE 1/2

DGCWP OUTPUT TO THE EDG HEAT EXCHANGER (825 GPM VS. 900 GPM DESIGN).

THE FLOW DEFICIENCY WAS REVIEWED AND

DISPOSITIONED: INFORMAL CALCULATION: - 826 GPM INCREASES COOLING WATER.

TEMPERATURE BY 3.5 DEGREES (96 TO 99.5).

EDG TRIP SETPOINT FOR HIGH COOLING

WATER TEMPERATURE IS 190 DEGREES F.

THE ISSUE WOULD BE FURTHER INVESTIGATED AS

PART OF ANOTHER ONGOING EVALUATION OF DGCW SYSTEM FLOW RATES.

! /sc):ID230:5 _ _.

-

. CHRONORDGY(CONTINUED) OMI6 SPECIAL TEST (1-80 REV.1). DGOWP FLOW TEST: PURPOSE

INVESTIGATE IF THE SYSTEM COULD BE FLOW - BALANCED TO REDUCE STRESSES ON THE PUMP AND MOTOR BY MEASURING FLOW RATES THROUGH THE COMPONENTS AND BY THROTTLING FLOW THROUGH EACH - COMPONENT.

VERIFY THAT THE 1/2 DGOWP ACHIEVES - ADEQUATE FLOW TO COMPONENTS BY THROTILING VALVES TO ACHIEVE DESIGN FLOW RATES TO BOTH THE.1/2 EDG AND THE UNITS ECCS ROOM COOLERS.

TEST CANCELLED PRIOR TO COMPLETION:

THROTTLING OF SYSTEM VALVES WAS NOT' - PRACTICAL SINCE THEY HAD TO BE NEARLY CLOSED TO PROVIDE NECESSARY FLOW. ONLY-A PORTION OF THE UNIT 1 TEST WAS COMPLETED.

THE FLOW DEFICIENCY CONCERN FROM THE 06/86'

TEST WOULD HAVE BEEN RESOLVED BY THIS TEST HAD THE 1/2 PORTION OF THE TEST BEEN COMPLETED.

.

/scl:ID230:6 ' I m

. . CHRONOLOGY (OONTINUED) 08/86 THE DGCWP FLOW R ATE SURVEILLANCE TEST (QOS 6600-6 AND S-3) WAS REVISED BASED ON THE 06/86 SPECIAL TEST AND PERFORMED:

IT ESTABLISHED IST REFERENCE DATA FOR THE 1/2 DGCWP.

THE PROCEDURE REQUIRED THAT THE PUMP

DISCHARGE VALVE BE THROTTLED DURING THE TEST TO ESTABLISH A STANDARDIZED D/P FOR THE PUMP. THIS WAS DONE TO IMPROVE-TRENDING OF PUMP AND VALVE PERFORMANCE.

  • TEST RESULTS WERE:

1160 GPM TO THE 1/2 EDG.

- 730 GPM TO THE 1/2 EDG WITH UNIT 1 ' - COOLERS VALVED IN.

760 GPM TO THE 1/2 EDG WITH UNIT 2 - COOLERS VALVED IN.

! ' THE TEST RESULTS WERE REVIEWED AND

APPROVED AS ACCEPTABLE FOR IST.- THE 1/2 DGCWP DISCHARGE VALVE WAS.

  • RETURNED TO FULL OPEN AT THE COMPLETION '

OF THE TEST.

/scl:ID230:7 . ..

_ _... _ _ _. _ _. _ _ _ _. _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ - _ _ _ . ? CHRONOIDGY(CONTINUED)

-

! OIW86 THE DGCWP FLOW RATE SURVEILLANCE TEST (QOS , 6600-6 AND S-3) WAS PERFORMED: THE SURVEILLANCE RESULTS REQUIRED THAT AN

. OPERABILITY EVALUATION BE PERFORMED.~-

f THE UNIT 1 OPERATING ENGINEER (OE)

EVALUATED THE TEST RESULTS AS ACCEPTABLE l BECAUSE THE PUMP PROVIDES SUFFICIENT FLOW ) TO SUPPLY DESIGN REQUIREMENTS OF THE 1/2 EDG.

]

THE OE FOCUSSED THE OPERABILITY l - EVALUATION ON THE 1/2 EDG BECAUSE IT IS IN THE TECH SPEC.

a THE OE RECOGNIZED THAT THE IST - , PROCEDURE RESULTED IN THE

INOPERABILITY OF THE 1/2 EDG WHILE THE - , l SYSTEM WAS LINED UP TO PROVIDE COOLING l ' FLOW TO BOTH THE 1/2 EDG AND THE ECCS. ROOM COOLERS.

', , THE OE DID NOT RECOGNIZE THAT THE 1/2

DGCWP DISCHARGE VALVE WAS , THROTTLED DURING THE TEST. - , , i - , ! j i !

i . /scl:ID230:8 ..... . .... -.. - . . . .. - . . . . . .

- . ..__._.

. - - - - -. -. -.. _ - . _ _ _ - _ - -. . _ _ _ _ . . . . , . CHRONOLOGY GMMHODNTINUED) , i e \\ AN OPERATIONS DAILY ORDER WAS WRITTEN

STATING THAT THE 1/2 DGCWP SHOULD NOT BE

i VALVED IN TO EITHER UNIT'S ROOM COOLERS. IF THE VALVES FROM THE 1/2 DGCWP TO EITHER UNITS ROOM COOLER ARE OPENED, THE 1/2 EDG SHOULD BE CONSIDERED INOPERABLE.

, , THE PORTION OF THE ISTTEST WHICH INVOLVED ~ l

, i TESTING OF THE CROSS-TIE CHECK VALVE WAS SUSPENDED.

[ -t I ,.

! . ! , P t l '

, w . t , F /scl:ID230:9

' . -..- . -. .... .. .. .. .... - -.. - -. .. -.. ~ =. -

. - - _ -.. -. -. _. - - . - .. _ - - - . ? e , JA&am A i. . 07/87 THE DGCWP FLOW RATE SURVEILLANCE TEST (QOS 6600-6 AND S-3) WAS FORMALLY REVISED.

<

1/2 DGCWP TEST WAS INCORPORATED INTO THE

UNITS' PUMP TEST.

A NEW PROCEDURE WAS APPROVED FOR CHECK

VALVE TESTING.

.

THE TEST CONFIGURATION IS THE SAME AS ' - THE PREVIOUS TEST WITH THE 1/2 DGCWP i S SUPPLYING FLOW M BOTH THE EDG AND ECCS ROOM COOLERS.

i AN OPERATOR IS NOW STATIONED AT THE q - ISOLATION VALVE BETWEEN THE 1/2 DGCW.

SYSTEM AND THE UNIT ECCS ROOM COOLERS TO CLOSE THE VALVE IN THE EVENT THAT , THE 1/2 EDG RECEIVES AN AUMMATIC START j SIGNAL.

1 ,, /scl:ID230:10 . l ., -,.., - -....,. ,,- _., _ _ - .,_.m.

,. _.. - -, .._ ._,.+,,.._..,,..,,,,,,-m, .y.

..m m_, + _.+,..,.... - ~...,, _...,

_. _... _ _ _ _ _.... _ _. ___ _ _ _._ _. _. _. _. _... _ _. _ _ _ _ _... _. _. _. _.. _.. _ _ _ _ .. . , CHRONOLOGY (CONTINUED) ! l l i l OW88 PROCEDURE (QOA 575014) FOR LOSS OF ECCS ROOM ' COOLERS WAS REVISED.

i THE INTENT WAS TO PROVIDE INFORMATION TO

THE OPERATORS REGARDING 1/2 EDG j . ' OPERABILITY IN THE EVENT THAT NORMAL COOLING TO THE ECCS ROOM COOLERS WAS LOST.

A CAUTION WAS ADDED TO THE PROCEDURE: '

THE 1/2 EDG WOULD BE INOPERABLE WHEN - THE UNIT ECCS ROOM COOLERS WERE VALVED INTO THE 1/2 DGOWP.

IF THE 1/2 EDG WAS RUNNING, DO NOT VALVE j - IN THE ROOM COOLERS.

i . THE CAUTION DID EFFECTIVELY ELIMINATE ONE

> STEP OF THE PROCEDURE, BUT DID NOT DEFEAT , THE PURPOSE OF THE PROCEDURE WHEN FULLY IMPLEMENTED.

, , . l <

, . z l l ' /scl:ID230:11 . -.. .-. -. ......... - .. -....... . _,....,.... -.. -..... -. ,,. _,.. s.

_,. ...~.,.m...-.. e.,-- y.-- .,., -e.-. ,,..

-... -.- - - - -. - - _- -. __ --- . .. -_- -. - -.. . _..,, . -. . ~ CHBONOIDGY 04/88 (CONTINUED) ' , ONSITE REVIEW (OSR) OF QOA 5750-14:'

i OSR BELIEVED THE 1/2 DGCWP COULD NOT. i - SUPPLY DESIGN FLOW TO THE 1/2 EDG WHEN: THE 2CCS ROOM COOLERS WERE VALVEu IN.' - ' OSR RECOGNIZED THAT THE 1/2 DGCWP. > - . SUPPORTED OPERABILITY OF THE 1/2 EDG.

. ~ y , 1/2 EDG IS IN THE TECH SPECS AND UFSAR,:

REASON FOR OSR~ APPROVAL OF QOA 5750-14: m - , OSR RECOGNIZED THAT THE 1/2 DGCWPl -[

COULD BE USED AS REDUNDANT j ' , . COOLING SUPPLY TO THE ECCS ROOM

' a COOLERS l ' ., ' OSR DID'NOT FULLY RECOGNIZE THAT

THE 1/2 DGCWP REDUNDANT COOLING . 1 o WATER TO THE ECCS ROOM COOLERS WASi NEEDED TO SATISFY SINGLE FAILURE

. ' . CRITERIA'. j s THE 1/2 DGCWP IS NOTIN THE TECH .j - SPECS OR UFSAR.

L 'i THE 1/2 DGCWP.IS NOT THE NORMAL ._ ' - SUPPLY TO THE ECCS ROOM COOLERS.

= t OSR DID NOT THOROUGHLY REVIEW THE /

BASIS FOR THE PROCEDURAL CHANGE /scl:ID230:12 . . .. . . ... -., - ..... . a.. _ _ _.. _... . __ _. - -. _ _ _ _ _. _, ... _ _.. _... _... _ _ _ _ _...._. . x.

. r CHBONOIDGYlOONTINTED) ., , , I l 0690 NRC PERFORMS AN ' INVESTIGATION OF AN

- ALLEGATION CONCERNING THE 1/2 DGCWP.

] ~ l

- e ' A POTENTIAL DEFICIENCY IN THE 1/2 DGCWP'S - j l

u l ABILITY TO FULFILL THE COOLING l REQUIREMENTS OF THE EDG AND THE ECOS ROOM i L.

COOLERS WAS CITED.' r ' ? , I STATION REVIEW OF THE DEFICIENCY WAS J

- PROMPT AND THOROUGH: - ' .,

. TEST PROCEDURE REVIEWED (IDENTIFIED

- f THROTTLED VALVE).. l-DEMONSTRATED THAT THE DGCW SYSTEM - ! - WAS CAPABLE OF PROVIDING DESIGN FLOW g ,

i RATES TO BOTH THE 1/2 EDG'AND A UNITS: ECCS ROOM COOLERS SIMULTANEOUSLY.'- . REVISED THE APPROPRIATE PROCEDURES, - , u L , ,, , p f

.

n h.- . <; - s e I

l t

i !

, , i-i /scl:ID230:13 i e i;. .- . .-, . ., - - - ,. -... -.

-. . ._- - . - - . _. - -.. - - _ - - - . - ... _ - _. -... .

  • :

. .

i SAFETYSIGNIFJCANCE OFEVENT <

. l'

THE 1988 REVISION TO PROCEDURE QOA 5750-14 COULD HAVE

i ' RESULTED IN THE FOLLOWING LIMITING SCENARIO DURING As ] l-POSTULATED LOCA EVENT- ' s ' FAILURE OF THE UNIT DGCWP AND'THE ASSOCIATED UNIT - - DIESEL GENERATOR..

REQUIRED ECCS LOADS WOULD BE SUPPLIED BY 1/2 EDG.. ,- ' THE 1/2 DGCW SUPPLY.TO THE UNIT ECCS ROOM

COOLERS IS NOT PERMITTED BY PROCEDURE.

R J THE ESSENTIAL CONCERN IS LONG TERM HEATUP OF THE

CORNER ROOMS.

, THERE ARE NO SHORT TERM TRANSIENT EFFECTS (I.E., PEAK

CLADDING TEMPERATURE, CONTAINMENT RESPONSES, ETC.)

j .!

. . I _ el.

y l-l

q . r L /sclilD230:14 L

' <,

, : A.- SAFETY SIGNFICANCE (CONTDRJED) l l FCCS ROOM THliiEMAL RESPONSE FORMAL STUDY OF ECCS ROOM HEATUP

IN PLAN. TESTING - DYNAMIC MODELING~OF CORNER ROOMS - p

KEY FEATURES OF ANALYSIS

a-BOUNDING HEAT LOADS UTILIZEDe - ONE-SIDED HEAT CONDUCTION TO WALLS - SEVERE INITIAL CONDITIONS. ' - ., RESULTS: VENTILATION IS NOTNEEDED FOR RHR PUMP

I ROOMS DUE TO NATURAL CONVECTION EFFECTS FROM STAIRWELLS'AND OPEN EQUIPMENT HATCHES ' - , IMPACT ON EVALUATION j

i HPC'! ROOMS WOULD BE ACCEPTABLE - RHu PUMP ROOMS WOULD BE ACCEPTABLE - ' CORE SPRAY PUMP ROOMS WOULD BE OF CONCERN - !. . ! . .! j i /scl:ID230:15

.._ _. _ ___.... _._ _ _ _ ....___ __ - _ _ _ _. _ _. _ _ _ _. _. _. _ _.. _.. _. _. ., L , f. : - . L SAFETY SIGNIFICANCE fOONTINUED) ' ' l . BEST-ESTIMATE CAIfUIATION - LPCS ROOMS ! ..

.TO ASSESS THE SAFETY SIGNIFICANCE l A BEST ESTIMATE

ANALYSIS OF PUMP ROOM HEAT UP WAS PERFORMED l

KEY ASSUMPTIONS UTILIZED ' , - , t CONSERVATIVE BEST-ESTIMATED HEAT LOAD.

THROUGH-WALL HEAT CONDUCTION-- j

j RESULTS OF CALCULATIONS r

E.Q. LIMITING TEMPERATURES WOULD BE ACHIEVED ONLY ! - AFTER APPROXIMATELY ABOUT 4 DAYS OF CONTINUOUS : OPERATION . -o ! CONCLUSIONS , t l .r ! < L .. ' EXTENDED OPERATION OF ECCS EQUIPMENT WITHOUT ROOM:

. COOLERS CAN BE ACCOMODATED.

. P ' THERE IS SUFFICIENT TIME TO ALLOW RESTORATION OF

> POWER AND NORMAL COOLING PATH PRIOR TO REACHING - ! POTENTIAL ECCS FAILURE TEMPERATURE LIMITS.. ,, THE SAFETY SIGNIFICANCE IS LIMITED.

L

l ./scl:ID230:16 .l = - - - - . - ... . .. -..... .,. .-. -- a:.. u...., -. -

- ..-, , ' SAMETY SYHTEM PUNCTIONAL INSPECTION-1 14 EMBEGENCY DIESEL GENERATOR

CECO COMPLETED A SSFI ON QUAD CITIES U2 EMERGENCY '

DIESEL (EDG) IN MAY,'1989 ' SCOPE OF THE SSFI:- ' EXAMINED THE DESIGN AND FUNCTIONALITY OF THE. ! - U2 EDG AS WELL' AS SUPPORT SYSTEMS AND ' j , COMPONENTS WHICH HAVE THE POTENTIAL TO - DEGRADE THE SYSTEM THROUGH THEIR FAILURFn , .) , THE SSFI REVIEW OF THE U2 DGCWP SYSTEM INCLUDED - $ ONLY THOSE ASPECTS WHICH SUPPORTED OPERABILITY-- ' OF THE U2 EDG. THE SUPPORT FUNCTION TO THE ECCS'- ROOM COOLERS WAS NOT WITHIN THE SCOPE OF THE SSFI.. . THE QOA PROCEDURE FOR LOSS.OF ECCS ROOM - COOLERS WAS NOT REVIEWED SINCE IT WAS NOT AN -

EDG PROCEDURE.. j i I

CONCLUSION: CECO WOULD NOT EXPECT THAT THE SSFI WOULD

- HAVE DISCLOSED THIS FLOW DEFICIENCY SINCE THE ] ' U2 DGCWP REVIEW FOCUSSED ON;THE COOLING 4

WATER PUMP AS-A SUPPORT SYSTEM TO THE EDG..

, .

i ! - ! i /scl:ID230:17 ' m 3J

_ _ _ _ ___ _ __ __ _ _ _ _ _ _. _. _ _ _ - - - _ _ _ _ _ _... _. _ _ _ _ _ _ _ __ _ _ _ _.-_.. -_ - _ .:.t .l sSFI(CONTINUED)

. SSFI DEFICIENCY 13 - ISSUE H

REQUIRED' CORRECTIVE ACTIONS ARE NOT ALWAYS - BEING ACCOMPLISHED

s CORRECTIVE ACTIONS CONTAINED IN THE

DEVIATION REPORT FOR FAILURE OF 1/2 DIESEL

FUEL OIL TRANSFER PUMP WERE NOT PERFORMED; , l RESPONSE TO AN INPO DOCUMENT ON IMPROVING 1 .

' EDG RELIABILITY WAS NOT DEVELOPED ~ ' STATION RESPONSE:

- , THE STATION PERFORMED THE'PREVIOUSLY: L - , COMMITI'ED ACTIONS TO TEST THE AUTO-TRANSFERL ' LOGIC ! ., , THE STATION IS WORKING TO REDUCE THE NUMBER - OF OVERDUE ITEMS THROUGH OVERVIEW BY. UPPER ' MANAGEMENT .;

CONCLUSION < WHILE THIS SSFI DEFICIENCY DID NOT SPECIFICALLY - IDENTIFY THE NEED FOR CORRECTIVE ACTIONS-ASSOCIATED WITH THE APPARENT FLOW DEFICIENCY, A- . NEED WAS IDENTIFIED TO ENHANCE THE STATION.' L CORRECTIVE ACTION PROGRAMS.

/scl:ID230:18 '- . - -, -. _ . - . .. -

-. .l , , l < ... . , , y SSFI(CONTINUED)

l ! SSFI DEFICTRNCY'18- , ISSUE j

SEVERAL INSTANCES OF TEMPCRARY ALTERATION, ! - WITHOUT SAFETY EVALUATION,WERE NOTED,

i 10' EXAMPLES WERE PROVIDED TO SUPPORT THE1 j:

' DEFICIENCY -

, STATION RESPONSE

s ',

, I CURRENT STATION ADMINISTRATIVE PROCEDURES? ! . REQUIRE THAT A SAFETY EVALUATION BE PERFORMED : PRIOR TO TEMPORARY ALTERATION IMPLEMENTATION ; - .i CONCLUSION '

  • -

, , . , THIS ISSUE IS UNRELATED TO THE APPARENT FLOW ' l

DEFICIENCY CONCERN BECAUSE IT DID NOT INVOLVE A - FAILURE TO PERFORM A SAFETY EVALUATION;FOR A > - RECOGNIZED TEMPORARY ALTERATION.LRATHER THE , FAILURE TO PERFORM A SAFETY EVALUATION AROSE ^ >, , FROM THE FAILURE TO RECOGNIZE THE DESIGN BASIS OF

l THE 1/2 DGCWP.

' y - j

-

x .1 /scl:ID230:19 I > -.... .

...- . -.. .

.. _ _ e.' , ' SSF1(COlHDIURD) SSFI CONCERN 14 ISSUE

ADEQUACY OF THE 1/2 DGCWP TO PROVIDE - ~ SUFFICIENT FLOWS UNDER ALL CONDITIONS TEST OR ANALYSIS WAS NOT AVAILABLE FORL

THE WORST CASE CONDITIONS (I.E. RIVER AT THE LOWEST LEVEL ~AND HIGHEST TEMPERATURE).

STATION RESPONSE

THE MAXIMUM COOLING WATER DEMAND WAS - - CALCULATED TO BE 1804 GPM.: THIS DEMAND IS:- WITHIN THE DESIGNED CAPACITY OF THE DGCW - SYSTEM.

A TEST IS TO BE DEVELOPED BY 11/89 IN ORDER TO - DEMONSTRATE THAT DEMAND COULD BE MET.. THIS TEST WAS TO INCLUDE THE FLOW! ' - CONFIGURATION OF THE 1/2 'DGCWP CROSS-TIED TO THE UNIT ECCS' ROOM COOLERS.

CONCLUSION

WHILE THE SSFI DID NOT IDENTIFY THE SPECIFIC - > DEFICIENCY, THE SSFI DID IDENTIFY A RELATED CONCERN. THE PROPOSED ACTIONS IN RESPONSE TO THE CONCERN WOULD.HAVE RESOLVED THE APPARENT FLOW DEFICIENCY.

/scl:ID230:20 _ _ _ _...

..--... ... ....-. _ - . . - _ _ _ - _ _ ____-- _ _ ___ ., o?

' f SSF1(CONTINUED) , i i OVERALL CONCLUSION ' THE APPARENT 1/2 DOCWP FLOW DEFICIENCY WOULD NOT.

- HAVE BEEN EXPECTED TO BE IDENTIFIED DURING THE . l CONDUCT OF THE SSFI.. , t THE SCOPE OF THE SSFI FOCUSSED ON THE SUPPORT - - FUNCTION OF THE 1/2 DGCWP TO THE 1/2 DG j , , i THE CORRECTIVE ACTION IMPLEMENTATION TO THE SSFI-

DEFICIENCIES WERE NOT TIMELY,L THE PROPOSED ACTIONS ~ ASSOCIATED W'ITH IDENTIFIED:

' SSFI CONCERN-14 WOULD HAVE RESOLVED THE APPARENT -

FLOW DEFICIENCY.

f \\ - i ., '

l

, J . t q 1' t.

, I , i ' \\ /scl:ID230:21 v , ., -.. . -..... .:- . .....-. :.... .. . .. :.-

- - - - ..... - _ _ _ -.. . -. -. -. _. --.. - _ -..- t ... .

, .

ADDITIONAL SSFI INFORMATION-- , . FURTHER PRIORITIZATION OF SSFI ISSUES IN 08/90

t THREE LEVELS OF PRIORITIZATION HAVE BEEN. ! - ' ' ESTABLISH 5D: A , HIGH POTENTIAL FOR AFFECTING

  • - -

OPERABILITY:

i E

B LOW POTENTIAL FOR AFFECTING OPERABILITY

> ? a C - NO POTENTIAL FOR AFFECTING OPERABILITY

(

i , ALL OPEN SSFI ITEMS HAVE BEEN PRIORITIZED:AND WILL

'a BE RESOLVED BASED ON THIS CRITERIA.1: m L <

THE STATION GOAL IS TO COMPLETE ALL "A". PRIORITY - ITEMS BY THE END OF 1990, t l l ! '! .-! ! -) !- -

[. .,

q

l: >- i !-. '

- l /scl:ID230:22

.2- .. . -. - ,.. , ....,. .,. , I,i _s , ,, .., -. -. ,, . y, ,,,,,,,. ~ -

. - _ - - - -. - - - - .- -- . - - -..,. -.. -.

3 ) i-.*: . CONCLUSIONS THE 06/90 TEST DEMONSTRATED THAT THE DESIGN -

FLOW RATES COULD BE ACHIEVED PROVIDED THAT-THE PUMP DISCHARGE IS NOT THROTTLED AND THE CROSS-TIE VALVE IS APPROPRIATELY-THROTTLED.

j q THERE WAS NO 1/2 DGOWP FLOW DEFICIENCY

- DURING NORMAL OPERATIONS.;THE APPARENT i

, FLOW DEFICIENCY WAS SIMPLY DUE TO - [ THROTTLING THE PUMP DISCHARGE VALVE < .; DURING IST TESTING.

> . s - THE ONSITE REVIEW DID NOT RECOGNIZE THAT THE _ (

h .1/2 DGCWP REDUNDANT COOLING WATER TO THE ECCS - - l ROOM COOLERS WAS'NEEDED TO SATISFY SINGLE u FAILURE CRITERIA. -

+ . ( THE ONSITE REVIEW DID NOT THOROUGHLY;

EVALUATE THE BASIS FOR THE PROCEDURAL CHANGE.

~

I THE STATION DID NOT ADDRESS THE APPARENT PUMP
  • PERFORMANCE DEFICIENCY AND THEREBY IDENTIFY j

THE CAUSE OF THE LOW FLOW RATE.

! [ THE STATION ISSUED AN' OPERATIONS DAILY ORDER

I WHICH WAS IN CONFLICT WITH 'AN EXISTING.

[ PROCEDURE.

. J h RESOLUTION OF THE SSFI CONCERN HAS NOT BEEN ^ - TIMELY.

r , C

)

. ' F /scl:ID230:23 , [ ' . .. - -.2=. .. _ . -_ '

,,,, -......... - - - - , o*' ' OORRBDTIVE ACTIONS , DESIGN BASIS INFORMATION IMPROVEMENTS REBASELINE THE UFSAR

, 1990 ACTIVITIES - A REVIEW OF THE FSAR, RECENT SSFI'S AND

RECURRING LICENSING TOPICS WAS CONDUCTED TO IDENTIFY SYSTEMS AND ' ISSUES NOT SPECIFICALLY ADDRESSED OR ! LACKING INFORMATION IN THE CURRENT VERSION OF THE UFSAR THAT COULD - , POTENTIALLY AFFECT SAFE PIANT I OPERATION AND LICENSING COMMITMENTS.. ,I ,, DEVELOP AND INCORPORATE THE SYSTEM 'i '

DISCUSSION INTO THE 1990 UFSAR REFORMAT UFSAR TO REG. GUIDE 1.70,

BEGIN INFORMATION GATHERING FOR

" REBASELINE

1991 ACTIVITIES - '

COMPLETE INFORMATION GATHERING.

REWRITE UFSAR

COMPLETION OF REBASELINED UFSAR IS - EXPECTED BY 03/92 , /scl:lD230:24 .. - _...

, _. _ _ _ _._ _ _ _ _ _. _ _ _ -. _..

'

' l CORRECTIVE ACTIONS (CONTINUED) -l

l . b DRRIGN BASIR INFORM ATION TMPROVRMRNTS (CONTINURn) ,: i OPERABILITY MATRIX

' L SHORT TERM- -.

  • .

CORPORATE GUIDELINES HAVE BEEN ISSUED '

-TO ASSIST IN MAKING OPERABILITY: DETERMINATIONS. THE GUIDANCE FOCUSSES.

.; ON DESIGN BASIS INFORMATION AND INVOLVEMENT OF ENGINEERING. ' STATION ' - , l IMPLEMENTATION IS SCHEDULED FOR'12/90.E l A UFSAR REVIEW IS IN PROGRESS WHICH WILL :

  • -

' IDENTIFY ITEMS DESCRIBED IN THE UFSAR . BUT NOT LISTED IN TECH SPECE COMPLETION OF THIS REVIEW IS SCHEDULED L ' . FOR 12/90.

~ .

LONG TERM - - . ' THE DESIGN FUNCTIONS OF EACH-

SAFETY-RELATED SYSTEM WILL BE LISTED ~ . AND AVAILABLE FOR OPERABILITY ! DETERMINATIONS. THIS LIST IS SCHEDULED : FOR COMPLETION BY 12/92.

) i , I , , . /scl:ID230:25 J l a , - - - . . . . . .= -

, _ - _ - _. _ _. _ _ _ _ _ - _ -. ,.1 o : ' OORRECTIVE ACTIONS (OONTDRIED) ONSITE REVIEW IMPROVEMENTS

ONSITE REVIEW PROCESS FOR PROCEDURES THE PROCEDURE APPROVAL CHECKLIST WILL- -: - BE REVISED BY 11/01/90 TO REQUIRE R DOCUMENTATION OF DESIGN BASIS' RESEARCH; , ! A NUCLEAR OPERATION-DIRECTIVE (NOD) HAS j -- T3EEN DEVELOPED'AND WILL BE ISSUED BY - . b ' :10/01/90 TO PROVIDE MORE CONSERVATIVE ' . SCREENING CRITERIA FOR THE CONDUCT OFo 10 CFR 50.59 EVALUATIONS OF PROCEDURES.- ST ATION IMPLEMENTATION IS EXPECTED BY - 0101/91.- ! - ONSITE REVIEW PARTICIPANT TRAINING :

, .q STATION MANAGEMENT WILL REVIEW THIS i - , EVENT WITH AND PROVIDE GUIDANCE TO OSR' ' MEMBERS ON HOW TO HANDLE DESIGN BASI'S REVIEWS PRIOR TO COMPLETION OF:THE UFSAR REBASELINE.~ THIS WILL BE: ~ COMPLETED BY 11/01/90.

i

/scl:ID230:26 , - - - - _ _

r_ -- -- _ - . 4=q ' OORRECTIVE AM10NS (CONTINUED) ' OTHER CORRECTIVE ACTIONS THE OPERATIONS DAILY ORDER BOOK POLICY

WILL BE REVIEWED AND EVALUATED BASED ON - THE LESSONS LEARNED FROM THIS EVENT, THE REVIEW AND ALL NECESSARY CHANGES WILL BE COMPLETED BY 11/01/90.

, a

THE CRITERIA FOR PRIORITIZING SSFI ITEMS HAS

, BEEN REVISED TO REFLECT AN ITEM'S POTENTIAL l FOR AFFECTING' OPERABILITY. ALL OPEN SSFI' . ITEMS HAVE BEEN RE-PRIORITIZED BASED ON-

THIS CRITERIA.

) STATION CORRECTIVE ACTIONS PROGRAM

, AN ENHANCED' PROGRAM'WILL BE $ ' - - DEVELOPED AND IMPLEMENTED BY 12/01/90'

TO REVIEW, PRIORITIZE AND TRACK' ACTIONS:

IDENTIFIED DURING INVESTIGATION 'AND '

l REVIEW OF STATION EVENTS.. J , l ! ! ,

I- /sel:ID230:27 l , ' _..... . }}

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