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Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plan for Next Four Months & Historical Listing of Plant Issues Called PIM Encl
	ML20196F292
Person / Time
Site:	Catawba
Issue date:	11/23/1998
From:	Ogle C; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Gordon Peterson; DUKE POWER CO.
References
	NUDOCS 9812070004
	Download: ML20196F292 (43)
	v • d • e

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o November 23, 1998 I

Duke Energy Corporation ATTN: Mr. G. R. Peterson Site Vice President l

Catawba Nuclear Station 4800 Concord Road York, SC 29745

SUBJECT:

INSPECTION PLAN - CATAWBA

Dear Mr. Peterson:

On November 2,1998, the NRC staff completed an inspection resource planning meeting. The staff conducted this review for all operating nuclear power plants in Region 11 to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the staff has moved to February 1999 because of the agency's shift i

to an annual Senior Management Meeting cycle.

i This letter advises you of our planned inspection effort resulting from the inspection planning

_ meeting. We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite. Enclosure 1 details our inspection plan for the next four months. We have provided the rationale or basis for each inspection outside the core inspection program so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.

i During this scheduling cycle, we will continue to focus some of our discretionary inspection effort i

on the resolution of open inspection items. Therefore, we may conduct additionalinspections, l

which are not listed in Enclosure 1, to close open inspection items that are ready to be resolved.

We will notify you at least three weeks before the start of these inspections.

The NRC's general policy for reactor inspections is that we will announce each inspection, unless announcing the inspection could compromise the objectives of the inspectors. Therefore, we may not have included some specific inspections in Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced. contains a historicallisting of plant issues called the Plant issues Matrix (PIM). The PIM includes only items from inspection reports or other docketed correspondence between the j

NRC and Catawba. This material will be placed in the Public Document Room.

OFFICIAL COPY

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9812070004 981123 PDR ADOCK 05000413 G

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We willinform you of any changes to the enc!osed inspectic 5 plan. If you have any questions, please contact me at (404) 562-4510.

l Sincerely, Orig signed by Charles R. Ogle Charles R. Ogle, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 50-413 and 50-414 License Nos. NPF-35 and NPF-52

Enclosures:

1. Inspection Plan

2. Plant issues Matrix cc wiencis:

G. D. Gilbert Regulatory Compliance Manager Duke Energy Corporation 4800 Concord Road York, SC 29745-9635 Paul R. Newton Duke Energy Corporation 422 South Church Street Charlotte, NC 28242-0001 Michael McGarry, Ill, Esq.

Winston and Strawn 1400 L Street, NW Washington, D. C. 20005 North Carolina MPA-1 Suite 600 P. O. Box 29513 Raleigh, NC 27626-0513 V. R. Autry, Director Division of Radioactive Waste Management S. C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 cc w/encls cont'd: (See page 3) l l

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l DEC 3

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cc w/encls cont'd:

Richard P. Wilson, Esq.

L. A. Keller, Manager Assistant Attorney General Nuclear Regulatory Licensing S. C. Attorney General's Office Duke Energy Corporation l

P. O. Box 11549 526 S. Church Street l

Columbia, SC 29211 Charlotte, NC 28201-0006 Michael Hirsch Mr. Steven P. Shaver l

Federal Emergency Management Agency Senior Sales Engineer l

500 C Street, SW, Room 840 Westinghouse Electric Company i

Washington, D. C. 20472 5929 Carnegie Boulevard, Ste. 500 Charlotte, NC 28209 North Carolina Electric Membership Corporation Distribution w/encis:

P. O. Box 27306 P. Tam, NRR Raleigh, NC 27611 R. Carroll, Ril C. Ogle, Ril Karen E. Long C. Payne, Ril Assistant Attorney General PUBLIC N. C. Department of Justice i

P. Box 629 NRC Resident inspector Raleigh, NC 27602 U.S. Nuclear Regulatory Commission 4830 Concord Road l

Saluda River Electric York, SC 29745 l

Cooperative, Inc.

P. O. Box 929 Laurens, SC 129360 County Manager of York County York County Courthouse York, SC 29745 Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651 l

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CATAWBA NUCLEAR STATION INSPECTION PLAN i

INSPECTION PLANNED j

PROCEDURE /

TEMPORARY TITLE OF INSPEC E N MPE OF INSPECMON -

INSPECTORS DATES COMMENTS INSTRUCTION IP 71714 COLD WEATHER PREPARATIONS 1 (RI) 12/98 Regional Initiative -

j seasonal region-wide initiative i

IP 71001 LICENSED OPERATOR 1

11/98 Core - Requal Examinations REQUALIFICATION PROGRAM l

EVALUATION IP 61701 COMPLEX SURVEILLANCE 3

2/99 Regional Initiative - In IP 71707 PLANT OPERATIONS (ESF depth review of operation.

maintenance, and l

WALKDOWN) surveillance of an ESF system.

Vertical slice i-IP 62707 MAINTENANCE OBSERVATION j

inspection as a followup to ice condenser and auxiliary building ventilation issues.

IP 92902 CLOSEOUT OF VA SURVEILLANCE 2

3/99 Regional Initiative - to RELATED OPEN ITEMS reduce backlog of open items IP 92902 CLOSEOUT OF MAINTENANCE 2

2/99 Regional Initiative - to RELATED OPEN ITEMS reduce backlog of open items IP 92903 CLOSE00T OF ENGINEERING 1

3/99 Regional Initiative - to RELATED OPEN ITEMS reduce backlog of open items IP 81700 PHYSICAL SECURITY PROGRAM 1

3/99 Core FOR POWER REACTORS uma cm un.ww Page 1 of 2

. INSPECTION PLANNED PROCEDURE /

TEMPORARY TITLE OF INSPECTION MPE OF INSPECTION -

INSPECTORS DATES COMMENTS INSTRUCTION IP 84750 RADI0 ACTIVE WASTE SYSTEMS, 1

12/98 Core WATER CHEMISTRY.

1/99 CONFIRMATORY MEASUREMENTS AND RADIOLOGICAL ENVIRONMENTAL MONITORING IP 86750 SOLIO RADI0 ACTIVE WASTE MANAGEMENT AND TRANSPORTATION OF RADI0 ACTIVE MATERIALS IP 83750 OCCUPATIONAL RADIATION 1

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PLANT ISSOE MATRIX P 95: 1

CATAWBA By Primary Functional Area Funcilonal Template Date Source Areo ID Type Codes item Description 10/23/1998 1998009-02 Prt OPS NRC UR1 Pit IC An unresolved item was opened concerning potentlolly bodequate procedures which may not have ensured the Sec:

See:

per@ty o stondby Mdown focMy durbg cerich eveh Gech 032 plC))

Tet i

i 1

j 10/06/1998 19984 04 4 0 Prt OPS Ucensee LER Pit 3A Error During Togout Causes De-energization of Vitol Bus and Actuallon of Low Temperature Overpressure Protection l

Sec:

j Ter-09/26/1998 1998009 Prk OPS NRC POS Prt2A No problems weie Identlflod durin0 the Inspector's review of the Econsee's proOrom for testing of Americon Society of Sec-Soc: 23 Mechanical EngineersSection XI Closs 2 and 3 tonef volves. The Econsee's Iniflotive of on increased testing frequency i

for robot volves demonstrated o commitment io safety. (Section M2.2: (POS-2A. 20))

Ter:

r 1

~ 09/26/1998 1998009-01 Pit OPS NRC eel Prk 1A Two examples of on apparent violotion were identified concerning im follure to folow clearance procedures. Both Sec'-

Sec m. w to caused by human error and involved improper implementallor of stollon logout procedures assocloted with the 1

nuclear service wolor system and the emergency dieset Generotor. One event resulted in a told loss of nuclear service t

4 Ter:

{

water flow to both unlis for three minutes. the other resulted in a blo.:kout of essentid bus 2ETB for about 30 i

Ibis opporont violation will remoln open for o roosonoble time io o!!o v the Icensee to deve!op corrective actions.

(Sections O1.2 and O1.3: (eel-1 A, 3A))

1 09/15/1998 1998013 Prt OPS NRC NEG Pit 4A The siored ico chemical sompHng technled specification (T.S.) was not sufficiently specific and worrontea hiprovement Soc-

Sec, io rnore cicorty oddress T.S. hient h the octud specificollon. No immedote operability concerns were identified.

i (Section MI.6) 1 Ter:

I 09/15/1998 1998013 Prk OPS NRC POS Prt 2A Fhd materid condtlon of the Unit 1 ice condenser was adequote to support operabiaty of the Ice condenser systern.

Sec: MAINT See: SC AppEcoble ice condenser Technicd Spec!ficollon surveillances were opg:ropriately identifed and successfully -

corrected. (Section M1.7)

Ter:

C9/26/1998 1998009 Prt MAINT NRC NEG Prt 20 A non-clied violation wasiden!!flod hvoMnD he Inoporobi!!!y of one channel of the overtemperature detto t

t pr ure a clor protection function for Unit 2. (Section M8.3; (NCV-5A, SC NEG-28, 40))

Sec:

Sec: 40 lor-d ENCLOSURE 2

item Type (Compliance, Followup,Cther), From 04/27/1997 To 02/13/1999 4

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vinicu atuies INucieus nt:sguiusury commission Tiinx iSiiih4

nogion 11 PLANT ISS.0E MATRIX Pogr 2 of 9 CATAW8A By Primary functional Aroo Functionot Temploto D010 Source Area ID Type Codes Itom Doscription C9/26/1998 1998009 Pit MAINT NRC POS Prt2A The licensee's progrom for mdafononco and testing of reactor coolont system pressure boundary vdves was Soc-Soc: 20 cceptoblo. Rovlow of lookogo testing dato and machinery history indicated good material condition of theso lsolation boundarios. (Section M2.1: (POS-2A. 20))

Tor:

09/26/1998 1998009 Prt MAINT NRC POS P:t 20 in generof. maintenance and surveillonce octMties observed and reviewed durin0 the inspection period wero Soc-See: 3A porIormed well, with proper odherenco io procedural comptionce, equipment colibtotion. and radiation protoction requirements. (Section M1.1: (POS-20,3A))

Ter 09/26/1998 1993009 Prt MAINT NRC SIR Prt 2B hservice examinollon octMiles observed were performed in a skillful manner. Discon!!nultles were property recorded S oc'*

Soc: 30 ond evoluoted by knowledgeoble examincts ushg opproved procedures. No findings adverse to qual;ty were identified during tho examhotions observed. (Section M t.3: (SIREN-28. 38))

Tor.

09/26/1998 1998009 Prt MAINT NRC SIR Prt 2B Erosion / corrosion oxomination and engineerin0 octMiles woro conducted in on excellent manner durin0 the Unit 2 Soc-Soc: 30 end-f-cyclo 9 refueling outo00. Loy-out of O' ids en components were propor, the non-destructivo examination Oxominors were skBlful h conducting the ultrasonic examinotions ond onOlneering evoluoted the dato b on effective Ter:

monnor. (Soction MI.4 (STREN-20.30))

09/26/1998 1998009-03 Prk MAINT NRC NCv PatSA A non-cited violation was identiflod invoMng the inoporobility of one chonnel of the overtemperature detto See:

Soc: SC t mp r turo r clor profection function for Unit 2. (Soction M8.3: (NCV-5A SC. NEG-28. 48))

Tor:

09/15/1998 1998013 Prt MAINT NRC WK Prt SA An overon wooknoss was identified with inillot scopino of problems and thorouOhness of liceneeo inspections compieled durh Soc

Soc: 3C D the 0u1000 for flow chonnol doOrodollon. foreign motorlot hirusion, and motorlot condition of ice condenses boskcts. Licensoo monogoment's follure to confirm the lhoroughness of contractor personnel to provide o proper Tor: 2A scoping of problems contributed to this weakness. After problems were identified by the NRC in coch of those oroot Icensoe responso to the problems was considered odequate. (Sect!on M1.1) 09/15/1998 1998013-01 Prt MAINT NRC eel Prt SA An opporont violation of 10 CFR Pori 50. Appondix 0. Critorion XVI was identiflod for failure to identify and conoct See:

Soc: SC sigrillconi Ice condonsor flow block 000. (Soction M1.2.b.1)

Tor: 2A Itom Type (Cornp!!anco.Fo lowup.Othor), From 01/27/1997 To 02/13/1999

veint:ru osuies Nucieur xegulatory commission 4

~6iiis'3aT4 T

i negion n PLANT ISSUE MATRIX Pogs: 3 of 9 l

CATAWBA 8y Primary [uncilonal Aroo t

Functional Temploto Dole Source Area 10 Type Codes

!!om Descrip!!on a

l 09/15/1998 1998013 42 Prt MAWT NRC URI Prt 2A An unresolved itern was Idontillod concerning post Ice condenser flow blocko0e operately. (Section M1.2.b.5)

Sec:

Sec: 3A j

Tec 5A i

09/15/1998 1998013-03 Prk MAINT NRC eel Pat 2D An opporont violoilon of lochnical specificollon 4.5.2.c was identified for failure to conduct odoquoto visuoi debris See:

Soc: 2A cHms W W 1 cmtoht NHm W) i Ter:SA 4

09/15/1998 1998013 4 4 Psh MAINT NRC URI Prt2A An unresolved llom was identified concerning foreign motorial effects on the Unit 1 contointnent emorgency coro j

Sec:

coonng system m@ chm W.3) 1 Ter:

1 09/15/1998 1998013 Prh MAINT Ucensee POS Pit 50 immedlote Icenseo corrective actions for the flow chamel blockoge probiern including a forced unit shutdown and See: ENG Soc:

extensivo clooning of the offected oreo, were considered odequale to support restort of the unit. (Section MI.2.b.5)

]

Ter:

i 09/15/1998 1998013 Prt MAINT NRC' POS Prt SC Corrective actions taken for the ice condensor bosket dentin 0 and deck door bolting issues was odoquote to support Sec: ENG See:

resW of the unn.(SecHons W A md W.5) i Ter:

l a

. 09/15/1998 1998013

- Pit MAINT NRC NEG Prh2A The Econsoo's ofloris to orcludo foreign materlot from the ice condonsor durin0 previous outo0es had not boon

]

See: OPS Sec.

d quote os evidonced by the amount of dotwls found during a Unit I forced outo00. At the ent* of the inspection, iconseo sensi1Mty in the creo of foreign material exclusion in the Ice condenser had improved. (Soction MI.3) l Ter:

i

-- 09/15/1998 1998013 Prt MA1NT NRC NEG Prt SA The identification of a high number of stuck baskets in Boy 5 and the mass increase of other baskets during the 1997 Urut Sec: OPS See: 2A refue InD oulogo were odditional opportunttles to identify and corroct the stonificant condition adverso to quality. ~

(Soction M1.2.b.6)

Tor:

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. Item Type (Compliance.Foilowup.Other). From 04/27/1997 To 02/13/1999 -

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PLANT ISSOE MATRIX.

Poga:6 of 9 CATAWBA By Primary Functional Area Funcnonal Temploie Dola Source Asso ID Type Codes !!em Description 08/15/1998 1998008-04 Pit ENG NRC NCV Prt 4C.

A non-cited violot!on was identified concerning a 1996 non-compliance with Technled Specificotton 3.4.6.1 due to the mssi n f Regu t ry Guide 1.45 related computer points for EMF-38 and EMF-39 during the design of the operator cid

' Sec*-

See: SA computer replacement modificotton. (Section E8.2; (NCV-4C: POS-5A))

Tec 08/15/1998 1998008 45 Pit ENG NRC NCV Pit 4A A non-cited violation was identified concernin0 o 1996 nc.icomptionce with Tectvvcot Specificotton 3.4 6.1 duo io o Sec*-

Sec:48 m ns e c

r le is tM cMhnt 2m W @nt sump WewforN subsysterrt (Sec!1on E8.3: (flCV-4A.48: POS-5A))

Tor 04/16/1998 1998 001-00 Prt ENG Ucensee LER Prt 2A IS 3.0.3 ENTRY DUE TO AN INOPERADLE ANNULUS VENT SYSTEM WHILE SECURITY DOOR OPEN FO See:

Soc: 48 Ter:4C 03/16/1998 1998 004-00 Pit ENG Ucensee LER Pat 4C MISSED TS SURV ON CR AREA VENT SYSTEM ACTUATION INSTRUMENTAI!ON. JNCORRECT MOD

. $g.

3 REQUIREMENTS IN THE AFFECTED IS (MODES 1-4 VS ALL MODES)

Tec 10/12/1998 1998 41S 4 0 Pit PLTSUP Ucensee LER Prt 28 Terminated Vendor Employee Entered the Protected Area due to o Computer Interface Mdfuertion See:

Sec:

Tec 09/26/1998 1998009 Prt PLISUP NRC POS

' Prh IC The Econsoe's emergoney preparedness progrom was bein0 molntoined in a high state of operational roodiness.

(SectW WSC)

Sec:

Tec G9/26/1998 1996009 Pit PLTSUP

.NRC SIR PrtIC Rodocclive motorial was labelod appropriately, and creos were property posted. (Secilon RI.1; (STREN-lC))

Sec:

Tec

' 11em Type (CompCance Followup,Olher), From 04/27/1997 To 02/13tt 999

ururea mares Nuclear Regulatory Commission isiiM367~

Rogion 11 PLANT ISS.UE MATRIX Pog2:7 of 9 CATAWBA By Primary Functional Area Functional Temploto Dola Source Area ID Type Codes Itom Description 09/26/1998 1998009 Prt PLISUP NRC SIR Prt IC Rodollon work octMiles were planned: todlotlon worker uocos wero bein0 mdntoined wel below regulotory limits ond the Ecmsoo was con:W to m& exposures os low as mosmoW o@do. (Secen RI.1: (SIRMCl)

Soc:

Tor:

07/26/1998 1998009 Prt PLlSUP NRC SIR Prt IC Personnel do'imotry dovices woro oppeoptiotely worn. (Soction RI.1: (STREN-1C,3D))

See:

Soc: 30 Tor-09/22/1998 1998014 Prt PLISUP NRC POS Pit IC The bock round invesilgotion process odoqualoly developed and verified the background elomonts before Orantin0 0

unescorled access (Section SI).

See:

Sec:

Tor:

09/22/1998 1998014 Prt PLISUP NRC POS Prl: IC The psychologicd evductions of opplicants were property admin! stored and supervised (Section SI).

Sec:

Soc:

Tor:

09/22/1998 1998014 Prt PLISUP NRC POS Prk IC The behcMord observation program was implomented according to Econsoo commitments and regulotcry requiromonts (Soction SI).

See:

Soc:

Tor:

09/22/1998 1998014 Prt PLISUP NRC POS Prt IC The grandfathering. reinstolemont, updating. transfer, and temporary unescorted occess authodzation elements were See:

See:

officiently maintoined and proficiently mono 00d (Soction SI).

Tor:

09/22/1998 1998014 Prt PLISUP NRC POS Prt 1C The prolection of persond Information by the Access Services Group was odequote (Soction SI).

Sec:

See:

Ter-9 ftom Type (Compitance.Fouowup.Othor), From 04/27/1997 To 02/i3/1C99

1 vs sinou usuics INuvacun steguiunviy vulillitiddlull Tima: 15:38:14 Rooion 11 PLANT ISSOE MATRIX Pogo:8 cf 9 l

CATAW8A By Primary Functional Area Functional Template i

Dole Source Area ID Type Codes item Description 1

09m/19981998014 Prt PLTSUP NRC

.POS Prt IC Personal access authorization records were maintained according to the Access Authorization ProOrom commitments l

See:

Soc:

andteW toryre@ements@cthSI).

Tec l

09/22/1998 1998014 Pat PLISUP.

NRC POS Prt IC The Bcenseo had implemented and stoffed on orOonization thol was copoble of monoOin0 and knplementing the Sec:

See: 3C Access MMoMgom ie@emis (SectM).

Tec i

09/22/1998 1998014 Prt PLISUP NRC POS Prt SA AucBis of the Access Authorization Pro 0 rom were thorough, concise, and timely (Section SI).

i Soc:

Sec:

4 Tec 07/22/1998 1998014 Prt PLTSUP NRC STR Prh IC The documentation and monogement of the denlol revocollon, and appeals process was o strength In the Access

$g,

$g Authort:-cllon Program (Section SI).

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CATAWBA 23+ou-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID*d ISSUE (s)

SMM CODES 6/5/98 Negative IR 98-06 NRC insufficient operator and engineering staff training resulted in insufficient knowledge 1 2 34 5 level relative to operation of the digital controffer for the condensate booster pump recirculation valve (1-CM-127), auxiliary feedwater pump suction temperature design A OOOOO timits, and operator actions required to identify, correct, and mitigate the consequences of the unplanned and unexpected condensate booster pump high D 00000 recirculation flow rate to the Upper Surge Tank. The resulting UST high temp.

condition caused the AFW system to be inoperable for approx. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

O OOO 6/5/98 Negative IR 98-06 NRC Operations Tactardcal Memorandum 97 01 was used to compensate for inadequate 1 2 34 5 procedures Instead of revising the procedures. The licensee did not complete a timely evaluation of station procedures and subsequent procedure revisions.

A OOOOO D 00000 cG 000 6/5/98 Negative IR 98-06 NRC Operating procedures and instructions were inadequate,in that they not provide 1 23 4 5 specllic guidance: for cperation of the digital contrciler; for identifying, correcting, and rnitigating the consequences of the unplanned and unexpected condensate AOOOOO booster pump high recirculation flow rate to the upper surge tank; and for response to upper surge tank high tamperature alarms and their effect on AFW pump D DOOOO operabiitty.

cG OOO 6/5/98 Positive IR 98-06 NRC The combination of emergency procedures, abnormal procedures, and Operations 1 23 4 5 Technical Memorandum 97-01 provided sutliclent instructions to the operators to maintain adequate water supply to the auxiliary feedwater pumps and thereby AOOOOO maintain adequate Net Positive Suction Head while preventing steam binding of the AFW pumps.

D 00000 cG 000 SG3/98 Negative IR 98-05 LICENSEE An improper controller set point on condensate booster pump recirculation valve 1 234 5 1CM-127 caused the Unit 1 Upper Surge Tank inventory to exceed the design temperature and temperature limits assumed in the licensee's accident analyses-A GOOOO An Augmented tospection Team responded to the event; their inspection activities and findings are documented in NRC Inspection Report 50-413.414/98-06.

D 00OOO cO 000 4/11/98 Strength ENG 1R 98-03 NRC The Itcenses has effectively implemented its operating experience feedback 1 2 34 5 program, as demonstrated by daily discussions in management meetings and resolution of pertinent plant issues through the corrective action program.

A OOOOG a00000 c0 000 4/11/98 Negative IR 98-03 NRC The observed active simulator examination did not challenge operators on the use of 1 2 3 4 5 Technical Specifications. Also, the use of three-part communications during the obsarved scenario was not consistently reinforced as it has been during actual A OOOOO control room activities. Ucensee management Indicated that other simulator scenados have involved and will continue to involve performance measures in the B GOGOO area of TS implementation.

O OOO FROM: 10/t/97 TO: 11/23/98 Page 3 of 20 FOR PUBLIC RELEASE Last Updated: G/t4/s3

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SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 2/2t/98 URI 1R 98-01; URI 98-01-01 NRC Control room operators appropdately identi5ed and (v stad a fault in the control 1 23 4 5 room ventilation system. An Unresolved item was opened pending NRC review of the basis for assuming that the control room ventilata system is allowed to be A OOGGO Inoperable for five rninutes tonowing a safety injection, radiation release within the plant, or a chlorine leak.

B OOOOO cO 000 2/9/98 PosiUve MAINT IR 97-15 NRC Unit i refueling activities were performed without incident and in accordance with 1 23 4 5 governing procedures.

A 00G00 aG0000 cG 000 2fs/98 Positive IR 97-15 NRC Operator performance dudng reactor and turbine startup was good as evidenced by 1 2 3 4 5 proper procedure use, communications and coordinatiort A00000 a00000 cG 000 2/9/98 Positive IR 97-15 NRC in general, the conduct of routine operations, including piant shutdown and startup 1 234 5 acovities associated with the Unit 1 refueling outage were professional and safety conscious.

A GGGOO a00000 cO 000 2 9/98 Negauve SAQV IR 97-15 NRC Inspectors concluded that Rooding the Unit 1 refueling cavity with two inoperable 1 23 4 5 charging pumps would have increased the margin to boiling and would not have sufficiency diluted the reactor coolant system boron concentration to erode the AOOOOO required shutdown margin. However, theTS did not allow the licenses to transfer water from the RWST to the RCS at their respecuve boron concentrations. Hence, B 00000 PORC's conclusion that the operation did not involve a positive reactivity change was inappsops! ate.

G OOO 2/9f38 Posiuve IR 97-15 SELF Operators appropriately manuaDy tripped the Ut reactor (while shtadown) in 1 234 5 compliance with TS following loss of indication for a shutdcwn bank control rod.

A 0000 0 0 GOGOD c0 000 2;3/98 Weakness IR 97-15; URI 97-15-01 SELF Human performance weaknesses related to an inadvertent injecGon of safety 1 23 4 5 InjecUon systern water into the reactor coolant system were identified as an unresolved ilem.

AGOOOO aO0000 cO 000 FROM: 10/1/97 TO: 11/23/98 Pago 5 of 29 FOR PUBLIC RELEASE Last updated: 9/t4/9a

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CATAWBA 23-Nov-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 6/22/98 NCV 1R 98-05. NCV 98-05-02 LICENSEE A non-cited violation was identified for fa!!ure to have adequate procedures for 1 234 5 testing containment air retum and hydrogen skimmer fans.

A 00000 a00000 c0 000 6/22/98 Negative IR 98-05 NRC Labeling problems encountered during nuclear service water system flow testing 1 23 4 5 were Indica 0ve of a persistent equipment labeling problem.

A00000 a00000 cG 000 6/22/98 Positive IR 98-05 NRC Ucensee efforts to monitor and trend Nuclear Service Water system performance 1 2 3 4 5 were Indicative of a desire to identify and correct degradation before operability was impacted.

A OOOOO B 0G000 cO 000 4/11/98 eel ENG IR 98-03; LER 414/98-02 LICENSEE Eight apparent violations were identified concoming survcillance testing of the 1 234 5 aux!!!ary building ventilation system. These apparent violations involved noncompliances with the requirements of TS 3.7.7; 10 CFR 50. App. B. Crit. XI(Test A OOOOO Control) and Crit XVI(Corr acts); 10 CFR 50.71(a); and TS 6.8.1.a. The scensee's iden!!!! cation of a March 16,1998, test failure was a good observation, but the B DGOOO licensee exhibited nonconservativa decision-making concaming surveillance test lailures, the implications for system operability, and TS action statement entry. The O

OOO Unit 2 A. train VA system surveillance test failures did not reveat evidence that the system's abully to perform its safety function was degraded.

2/21/98 NCV la 98-01, NCV 98-01-03 UCENSEE One Non-Cited Violation was identified for the failure to follow maintenance 1 2 3 4 5 procedures which resulted in an unapproved aluminum packing spacer being installed in the Unit 18 steam Denerator main feedwater regulating valve.

AOGGOO a00000 cO 000 2/31/98 Positive IR 98-01 NRC The licensee's scaifolding program was in compliance with the requirements of Title 1 234 5 29 Code of Federal Regulations Part (CFR) 1926. Safety Standards for Scaffolds Used in the Construction; Final Rule. With the exception of a discrepancy identified A OOOOO between actual intarnal contamination levels and the amount posted, radiological handling and storage ci scaffolding material was adequate.

B DGOOO cO 000 FROM: 10/1/97 TO: 11/23/98 Page 10 of 29 FOR PUBLIC FtELEASE Last Updated: 9/14/98

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CATAWBA 23-Nov-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 2/9/98 NCV IR 97-15; NCV 9715-04 l

LICENSEE An NCV was identiflod for failure to property test safety-related logic circulls for 1 234 5 leedwater isolation and P-10 source range block permissives.

A00000 a08000 c0 00O

{

2/3/98 Negative IR 97-15, Uni 97-15-03 LICENSEE An unresolved item was identified conceming anti-reverse rotation devices not being 1 23 4 5 installed on the Unit 1D reactor coolant pump motor before it was installed dudng the December 1997 refueling outage.

AOGGOO a0G000 cO 000 2/3/98 Weakness IR 97-15 NRC The licensoa continued to demonstrate a weakness in the area of welding certain 1 23 4 5 production welds. Some woldors lacked the necessary skills to produce radiography quality wolds as evidenced by the need for repeated repairs during fabrication AOOGOO activities. The in-processing group had not been able to satisfy the need for l

expodanced welders in time for training prior to the outage.

aOOGOO cO 000 2/9/98 Positive IR 97-15 NRC The observed steam generator eddy current activity was well managed and 1 234 5 executed in accordance with appHcable procedures. Technical personnel doing data acquisition wore qualilled to perform their assigned tasks. The !!conses took a A OOGOO proactive approach to raso!ve the problem of build-up in steam generator tube inner surfaces. The eddy current inspection pian for this outage met code and industry aOOGOO standards.

c0 000 2/9/98 Positive OPS IR 97-15 LICENSEE A natural circuladon test performed on U1 successfully dernonstrated the ability to 1 23 4 5 cool the plant without forced RCS liow following the replacement of the U1 steam generators in 1996.

A OGOOO a00000 cO 000 12/19/97 Positive IR 97-14 NRC Now fuel movement activities to support the upcoming Unit I refue!!ng outage were 1 23 4 5 performed weD.

AGOGOO a00000 cO 000 12/19/97 Positive IR 97-14 NRC Survo!!!ance activilles observed by the inspectors Irvolved good workmanship, 1 23 4 5 proper use of procedures, good radiological practices, and proper management of TS action statements.

AGOGOO a00G00 cO 000 FROM;.10/1/97 TO: 11/23/98 Pago 12 of 29 FOR PUBLIC RELEASE Last updated: 9/14/98

. CATAWBA 23-Nov-98 DATE TYPE (s)

SEC SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 10/11/97 MISC SAOV IR 97-12 NRC A 52-day discrepancy between the Event Date and the Report Data for 1.ER 50-1 234 5 413/97-06 which reported survelitance testing deficiencies was the result of insufficient information contained Ir: the LER-A OOGOO a00000 cO 000 10/11/97 Negative ENG IR 97-12; IFl 97-12 01 NRC The inspectors were concemed with the number ci recent leaks in the NSW 1 23 4 5 System. An inspector Followup !!em was opened to address inspector concems with continuing teakage problems with the Nuclear Service Water system.

AOGOOO e0000G cO 000 10/11G7 Positive ENG IR 97-12 NRC Licensee's failure investigation process for a second *1B" emergency DG test failure 1 234 5 was methodical and appropriate. A more aggressive investigation followtig an ear!!ar failure could have resuited in a true root cause versus an " apparent

toot A OGOOO cause being identified.

OGOOG cO 000 10/11/97 Negative IR 9712 SELF The licensea responded appropriately to a choker failure that occured during spent 1 234 5 fuel pool welt gate man!putation in the cask pit area of the spent fuel pool However, examples of poor practicos were notad during the inspectors

review, including skill' A GOGOO of-the-craft selection of padding material and an administrative error associated with the litt plan documentation.

8 OOOOO cO 000

[EffGINEE51RG

.- 1 P4 e;l 9/14/98 Negative IR 98-08 NRC Deliciencias have been Idantilled with previous licenses event reports over the last 1 23 4 5 two years for which licensee personnel have inillated corrective actions to improve the quality of reports subrni;ted to the NRC. (Section E8.3;[NEG-4C])

A OOOOO a00000 cO 000 9/14/98 NCV 1R 98-08, NCV 98-08 05 LICENSEE A non-cited violation was ident!!ied concerning a 1996 non-compliance with 1 234 5 Technical Specification 3.4.6.1 due to a nonconservative calculation of the rate of change for the containment floor and equipment sump level monitoring subsystem-A OOOGG (Section E8 3; [NCV.4A,4D; POS-SA})

OOO c0 000 9/14/98 NCV IR 98-08, NCV 98-08-04 NRC A non-cited viola'lon was identified concerning a 1996 non-compliance with 1 2 3 4 5 Technical Specification 3.4.6.1 due to the omission of Regulatory Guide 1.45 related computer points for EMF-38 and EMF.39 during the design of the operator aid AOOOOG computer replacement modificatiort (Section E8.2;[NCV-4C; POS-5Al)

OOOOO c0 080 FROM: 10/1/97 TO: 11/23/98 Page 13 of 29 FOR PUBLIC RELEASE Last updated: 9/14/9a

' ATAWDA C

23-Nov-93 DATE TYPE (s)

SEC, SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 9/14/98 UR!

IR 98-08, URt 98-08-03 NRC An unresolved item was opened pending additional NRC review of the basis for 1 23 4 5 installing portable alt sampEng equipment with tygon tubing. (Section E3.1;(URI-4A,40,5C))

A OOOBD B 00000 cO 008 7/28/98 NCV 1R 98-07, NC / 98-07 06 LICENSEE A non-ciled violauon was identified concerning the Inoperability of the Unit 1D steam 1 234 5 generator main steam isolation valve between March 1995 and August 1S96.

(Section E8.2; l1 A,2A - NCV; SC - POS])

A GBDDD B 00000 cO 000 7/28/98 VIO IR 98-07. VIO 98-07-05 NRC A vlotation was ident!!ied for failure to take prompt correcuve act!ons to prevent 1 23 4 5 recurrence of a significant condition adverse to quality for the May 7,1998, upper surge tank over-temperature event. (Section E8.1 [5A, SC - VIOD AOOOOO a00000 cO 000 7/28/98 Positive IR 98-07 NRC The Econsee took conservative actions regarding Technical Specification Limiting 1 23 4 5 Condition for Operation entry lo!!owing the identification of a pirvhcle leak in two-inch euxiliary feedwater tempering flow piping. The leak was effectively repaired during A SOOOO the subsequent Unit 1 forced outage. The licensee's short and long-term corrective actions were adequate. (Section E2.1 [40,1A, SC - POSD B OOOeO c0 000 6/22/98 URI ENG IR 98-05, URI 98-05-04 NRC An unresolved item was identi!!ad related to a potentially inadequate engineering 1 2 3 4 5 technical evaluation concoming the operating time of the Emergency Diesel Generator without coonng water. This issue was not safety significant but exhibited AOOOOO poor Engineering performance.

g ggg cO 000 6/5/98 Positive IR 98-06 NRC Following the May 7,1998, UST high temperature event, the Scensee's 10 CFR 1 2 34 5 50.59 safety evaluatiott was adequate for the isolation of CM-127.

A 00000 B 00000 cO 000 6/5/98 Negative IR 98-06 NRC Relative to the previous UST high temperature events, the engineering staff 1 23 4 5 demonstrated a poor questioning attitude and a lack of rigor its the pe:1ormance of two 10 CFR 50.59 safety evaluations (July 1996 and August 1997), root cause AOOOOG evaluations and the determination of corrective actions. This resulted in the engineering staff falling to recognl e the safety system (AFW) and non-safety B OOOO8 system (condensate) interactions and the impact of those interactions on AFw system operability.

cO OOG FROM: 10/1/97 TO: 11/23/98 Page 14 of 20 FOR PUBLIC RELEASE Last Updated: 9/t 4/98

. CATAWBA 23-NowSS DATE TYPE (s)

SEC. SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 6/588 Negative IR 98-06 NRC Root cause determinations for several previous occurrences of high upper surge 1 234 5 tank overheaung, which had occurred since January 20,1996, were inadequate and resuued in ineffective correciive actions.

A OOOOO e00000 c0 000 6S98 Negative IR 98-06 NRC Insufficient Trending of the high maintenance requirements on valve CM-127 and the 1 2 3 4 5 Problem invesugation Process (PlP) forms which involve the upper surge tank or CM 127 resulted in the failure to detect the potential adverse conditions and system ACCCCC Interactions between the AFW and Condensate systems.

a00000 cO 000 6/5/98 Posidve IR 98-06 NRC The Ucenses initiated a Significant Event Investigation Team (SEIT) and performed a 1 23 4 5 detailed and thorough root cause analysis of the May 7,1998. UST h!gh temperature event. The team reviewed the SEIT findings and recommendations and assessed A OOOOO them to be candid probing arti conservative.

OOO cO 000 6/E!98 Postuve IR 98-06 NRC The team concluded that, although there were limited UFSAR references to the 1 2 3 4 5 AFW system temperature assumptions, the UFSAR description was adequate as Indicated by secondary references in the alarm response procedure and design A OOOOO basis document. The licensee initiated an action item to assess the impact of the elevated AFW temperature on UFSAR accident analyses.

B OOOOO cQ 000 6/538 Posiuve IR 98-06 NRO The Ucensee's analysis of potential safety /non-safety interactions for auxiliary 1 234 5 leedwater supply sources adequately idenGiled potenual mechanisms for increasing source temperatures above the value used in licensing basis accident analyses.

A OOOGO Appropriata recommendatloas were provided to practude an inadvertent auxiliary feedwater supply source temperature inciease above the design basis limit of 138 B OOOOG degrees F.

C O OOG 6/5/98 Negative IR 98-06 NRC The regulatory significance of the Upper Surge Tank high temperature event was 1 23 4 5 high prompting the.iuation of an augmented inspection team because a safety.

related system desegned to mitigate the consequences of an accident was rendered A OOOGO Inoperable by the mispositioning of a single nonsafety-related component, ICM-127. The Ucenses has taken appropriate actions to provide reasonable assurance B OOOOO that this event wit! not recur in the future.

O OOG 6/5/98 MISC IR 9S-06 NRC The actual safety significance of the Upper Surge Tank high temperature event was 1 2 3 4 5 minor in that 1) the auxillary feedwater system was inoperable for a relallvely short t!me (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ). 2) the AFW system was not called upon to perform its AOOOOO Intended safety function, and 3) during the uma of inoperability, the AFW tvmps remained functional but degraded (sull aval!able to provide water to the steam 0 0OOOG generators. There was a reduced heat removal capacity for the AFW system during this event.

O OOO FROM: 10/1/97 TO: 11/23/98 Page 15 of 29 FOR PUBLIC RELEASE Last Updated: 9/14/98

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CATAWBA 23-Nov-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 2/31/98 MISC IR 98-01 NRC An inspector Followup Item was opened to assess the licensee's dose analysis 1 2 3 4 5 calculation for smergency core cooling system leakage outsido containment after discrepancies were identified between assumptions made by the licensee and those A OOOOO discussed in the Updated Final Safety Analysis Report.

OOOOe c0 000 2/3/98 Positive IR 97-15 NRC Outage-rotated rnodifications for main steam isolation valve control circuitry and low 1 2 34 5 steam Une pressure safety injection signals were conducted appropriately.

A 00000 aC000e c0 000 2/9/98 NCV IR 97-15; NCV 97-15-05 LICENSEE A non-cited vlotation was identified related to failure to perform adequate TS 1 23 4 5 survelHance testing of emergency core cooling system check valves due to an inadequate procedure.

AOOOOO B 00000 cO 000 2rW98 Strength SAQV IR 97-15 NRC The 1997 Updated Final Safety Analysis Report revision was in compliance with 10 1 234 5 CFR Part 50 il. A strength was noted concerning the incorporation of pertinent changes to the revision.

AOOGOO a00000 cO 000 2/9/98 Negative IR 97-15 NRC A minor concem was identified concerning engineering documentation of operability 1 2 34 5 determinations.

A00000 a00000 c0 000 2/9/98 Positive IR 97-15 NRC in general, engineering support of Urst 1 outage activities was good.

1 234 5 A 00000 a00000 c0 000 2/2/98 MISC IR 97-300 NRC The examiners identified one unresolved item associated with the four site 1 234 5 Emergency Dieso! Generators. Given the error identified in the simulator diesel lubricating od low pressure trip logic, an engineering evaluation is needed to confirrn A OOOOO that the planrs EDG tubricating oil

low-low pressure

trip logic was property built to des!gn specifications, B OOOOO c0 000 FROM: 10/1/97 TO: 11/23/98 Pege 17 of 29 FOR PUBLIC RELEASE Lest Updated: 9/14/98

CATAWBA 23-Nov-98 OATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 12/19S 7 NCV MAINT IR 97-14; NCV 97-14-04 LICENSEE A NCV was identified concoming the use of aluminum separators in high efficiency 1 234 5 particulate alt filters located inside containment A00000 a00000 cO OGO 12/19S 7 URI 1R 97-14; URI 97-14-03 LICENSEE Remote manual closure capability existed for dual function containment isolation 1234 5 valves; however, the action involved resetting the emergency diesel generator load sequencer, an action requiring further evaluation to be conducted under the above AOOOOO URI.

B 00000 c0 000 12/19S 7 URI IR 97-14; URI 9714-03 LICENSEE A URI was idanulled concerning containment penetrations associated with steam 1 234 5 supply unos to both units' turbine-driven aux. leedwater pumps, which were not in compilance with Title 10 CFR Part 50. App. A, General Design Criterion 57. The AOOOGO licensee had submitted an exemption request concerning this issue to the NRC during the previous inspeclim report period.

B OOOOO c0 000 10/11/97 Posit!ve IR 97-12 NRC The Ecensee's digital opticallsolator testing activides have been appropriate to 1 23 4 5 identify degrading DOI resistors. Plans to modify the MSIV contio1 circuitry to alleviate the slngle failure vulnerabiuly to inadvertent valve closure of the MSlVs A OGOOO should be effective in reducing the risk of unneccessary reactor trips.

OGG cO 000 10/11/97 Positive IR 9712 NRC The Beansee's completed and planned actions to determine the root cause of two 1 2 34 5 recent Main Generator *20* Power Circuit Draaker failures were adequate.

Increased monitoring of the associated solenok! valve was appropriate Plans lo AOGOOO replace the valve alter two months of service were considered conservative.

OOG c0 000 lMi!ARW50 iip?OTIT ^ 4 E ; *ir l 9/14/98 Positive tR 98-08 NRC The licensee's radiological protecuon performance was adequate. (Section Rt.1; 1 2 3 4 5 (POS 1AD A20000 a00000 cO 000 7/28S 8 Positive IR 98-07 NRC The licensee's'fira protection impairment and survel:!ance program imptementation 1 23 4 5 was good in that impaired Gro protecuon features had been restored to service in a timely manner. (Secuan F8.2;[2A,28 - POSj)

AOEOOO a09000 cO 000 FhlOM: 10/1/97 TO: 11/23/98 Page 18 of 29 FOR PUBLIC RELEASE Last Updated: 9/14/98

+

CATAWBA 23-Nov-98 ISSUEks)

DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd SMM CODES 7/28/98 Posidve IR 98-07 NRC The Econsee compIIed with the guidance provided by NRC's Generic Letter 86-10 1 23 4 5 when the Era protection equipment operability and surveillance requirements were removed from the Catawba Technical Specifications and relocated in the Catawba AOOOOO Selected License Commitments. (Section F82;(4C-POSI)

OOOOO C O 000 7/28/98 Positive IR 98-07 NRC The 1998 Triennial Fire Protection Audit of the facility's Ere protection program was 1 234 5 Comprehensive and ellective in Identifying Era protection program performance to plant management. (Sectim F7.1;(SA - POSI)

AOOOOB e00000 cO 000 7/28/98 Positive IR 98-07 NRC The fire brigade orga112ation and dria program met the requirements of the site 1 234 5 procedures. The performance by the fire brigade as documented by the Econsee's driu evaluations was good. (Section FS.1;[1C,3D Pos])

AOOOOO t; 0 0 0 0 O c9 000 7GB/98 Positive IR 98-07 NRC The maintenance inspection and surveillanca test program for the emergency eight-1 2 3 4 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months battery Rghting system was sufficient to ensure that the emergency Hghting performance criteria established in the Updated Final Safety Analysis Report and 10 AOOOOO CFR 50, Appendix R were met (Section F3.3;[2D - POSj)

OeOOO c0 000 7/28/98 NCV IR 98-07, NCV 98-07-08 LICENSEE A r.crec!!ad violation was identified for failure to conduct the required inspection of 1 2 3 4 5 Bro hose gaskets. (Secuon F3 2;[2D - NCV; SC - POSI)

A 00000 o00000 cO 000 7/38/98 Post!Ivo IR 98-07 NRC The scope end content of the inspecdon and surveillance test program procedures 1 2,3 4 5 for the !!re protecuon hose stations and standpipes were sufficient to ensure that the Era protection design and survel!!ance water How requirements specified in the A OOOOO Updated Final Safety Analysis Report were meL (Section F3.1;[tC.POS)]

OOOOO cB 000 7c8/98 NCV IR 98-07, NCV 93-07-G7 LICENSEE A non-cited violadon was identi!!ed for laliure to maintain required fire barrier 1 2 34 5 penetraGon seafs operable between areas containing redundant safe shutdown equipment (Section F2.4;[4A NCV;SC POSI)

A OOOOO a00000 c0 00G FROM: 10/1/97 TO: 11/23/98

@ ig of 29 FOR PUBLIC RELEASE Last Updated: 9/14/98

CATAWDA 23-Nou-SS DATE TYPE (s)

SEC. SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 7/28/98 Positive IR 98-07 NRC The low number of inoperable or degraded fire protection components indicated that 1 234 5 appropriate emphasis had been placed on the maintenance and operability of the fire protection equipment end components. Impaired fire protection components had A OOOOO been restored to service in a Umery manner. (Section F2.3;[2D - POS])

OOOOO cO 000 7G8/98 Positive IR 98-07 NRC Sulficioni procedural guidance was provided to verify that the reactor coolant purnp 1 2 3 4 5 on collection Sufficient procedural guidance was provided to verify that the reactor coolant pump o8 collection tanks were normally maintained empty and that the plant AOOOOO operators could Identify an oil teak from the lubrication system of any one of the reactor coolant pump motors and take appropriate action. The reactor coolant pump B OOOOO on collecuon system met the performance criteria of 10 CFR 50. Appendix R, Section til.O. (Section F2.2;[1C - POS. CG OOO 7G8/98 Positive tR 98-07 NRC The physical separation of the redundant fire pumps was we9 maintained and met 1 234 5 the criteria described in the Updated Final Safety Analysis Report. (Section F2.1; 14 A - POS]) A OOOGO a00000 c0 000 7/28/98 Positive IR 98-07 NRC The general material condition of the fire pumps and the fire protection water supply 1 23 4 5 was good. (Section F2.1;[2A - POS]) A 0000 0 n00000 cO 000 7G8/98 Positive IR 98-07 NRC The observed level of plant housekeeping reflected good organization and 1 2 3 4 5 cleanliness practices on the part of plant workers. (Section F1.2;[3A - POS]) A00000 a00000 c0 000 7/28/98 Positive IR 98-07 NRC The implementat!an of procedural requirements for using and storing transient 1 234 5 combustibles in safety-related areas was good. The mater!al condition in the plan! Indicated that the various plant departments were property implementing their AOGOOO responsibifilles for combust:ble material control (section F1.2;[2A - POS]) OOOOO c0 000 7G8/98 Positive IR 98-07 NRC During 1997 and 1998, there were a low number of incidents of fire within safety-1 234 5 slgnificant plant areas. When fires occurred. licensee personnelidentified and extingutshed the !!re in a limCly manner and prevented the fires from spreading to AOOOOO other equipment or cables. (Section F1.1;(30 - POS]) OOOOO cO 000 FROM: 10/1/97 TO: 11/23/98 Page 20 of 29 FOR PUBLIC RELEkSE Last Updated: D/14/98

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CATAWBA 23Eov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/22G8 Positive IR 98-05 NRC The licensee was proficienUy tralning the security force and conducting weapons 1 23 4 5 requalification according to the Training and Qualification Plan and regulatory requiromants. A OOOOO a00G00 cO 000 6/22/98 Posdive IR 98-05 NRC Responses by Die security organization to security threats, contingencies, and 1 234 5 routine response situations, including drills, were consistent with the security procedures and the approved Physical Security Plan-A OOOOO a00000 cO 000 6/22/98 Pos!tive tR 98-05 NRC Security personnel possessed the knowledge to carry out their assigned duties and 1 234 5 responsibilities, including response procedures, use of deadly force, and armed response tactics. A OOOOO a00000 c0 000 6/22/93 Positive IR 98-05 NRC Saleguards plan and procedure documentation compiled with 10 CFR Part 50. 1 2 34 5 Changes to sections reviewed in the Physical Security Plan did not decrease the effectiveness of the Physical Security Plan. AOOOOO a00000 cG 000 6/22/98 Positive IR 98-05 NRC Intrusion detection systems, sit elliumination and assessment aids were found 1 2 3 4 5 functional, we# maintained, and ellective. A 09000 a00000 c0 000 6/22/98 Positive IR 98-05 NRC The licensee used good compensatory measures that ensured the reliability of 1 2 3 4 5 security related equipment and devices. A 00000 aD0000 c8 000 4/11/98 Positive IR 98-03 NRC Primary chemistry sampling activities were observed to be in compilance with 1 234 5 procedures and proper controls were in place for protection from potential radiological and safety hazards. Acceptance criterla contained in procedures were AOOOOO consistent with Technl. cal Specifications. OOOOO c8 000 9 FROM: 10/1/97 TO: 11/23/98 Page 22 of 29 FOR PUBLIC RELEASE t.ast Updated: 9/14/98

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CATAWBA 23 h 9a DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 2/9/98 VIO 1R 9715; VIO 9715 06 NRC A violation was klantified for failure to revise radiaiton work perrnits to reflect 1 234 5 changes In dress out specifications that arose from changing radiological conditions. A CCCCC a00000 1 cG 000 2/9/98 Strength - IR 97-15 NRC The licensee demonstrated strong mangement support in the area of ALARA as 1 2 3 4 5 indicated by source term reduction efforts such as replacement of stelt!!e valve seats, ellecuve chemical shutdown process for the current outage, and by ACCCCC establishing challenging exposure goats. The inspectors viewed the overa!! ALARA program as a strength. O OGOOO cO GOO 2/2/98 VIO OPS IR 97 300, NRC The examiners identified one violation associated with the Dcensee's failure to 1 234 5 conduct periodic training and evaluation of security officers qualified as Safe l Shutdown Facility Operators. When tested one year after quallficanon, with no AOOGOO requall!! cation training conducted, four of seven security officers examined failed their tests. The examiners concluded that the licensee failed to property implement D 0000O a systems approach to training for this program to ensure that the selected security l officers could adequately and safely pedorm the function of Sale Shutdown Fac!!ity G OOO Operator il called upon. '"""* VIOLATION WITHDRAWN"""** 2/2/98 Negative tR 97-300 NRC The examiners identified that the Alert and Site Area Emergency action levels for 1 2 34 5 Event Category 44.1.9,

Natural Disasters and Other Hazards.* of RP/0/N5000/01, were not clearty and specifically written to achieve the results expected by licensee AOOOOO managment for property classifying a hurricane event.

OOOOO cG 000 2/2/98 Weakness IR 97 300 NRC The examiners identified that a weakness existed in the facility's contamination 1 234 5 control and monitodng procedures that could attow workers to unknowingly remove potentially cross-contaminated hand carried items from the RCA after being checked A OOOOO in the Small Article Monitor, a00000 cO 000 2/2/98 Negative IR 97-300 NRC On two occasions, the examiners noted poor personnel radiological monitodn9 1 23 4 5 practices at the Radiological Control Area exit. A 00000 a00000 cB GOD 12/30/97 Positive tR 97-15 NRC Emergency response acuvities were conducted well during the Notification of 1 23 4 5 Unusual Event on December 30,1997. Attention to detall was warranted concerning the use of wide-range versus narrow-range plant indication during events. A OOOOO a00900 c0 000 FROM: 10/1/97 TO: 11/23/98 PaDe 25 of 29 FOR PUBLIC RELEASE Last updated: 9/14/98

CATAWBA 33-Ne98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 12/19/37 Positive LR 9714 NRC The EOF located in downtown Charlotte, NC and its associated equipment were in 1 2 34 5 good repair and condition. Emergency communication and plant computer equipment in the TSC was in good working order. AOOOOO e00000 cO 000 12/19/97 Negadve IR 97-14 NRC An example of poor performance was identified rciated to a radiological control area 1 23 4 5 l boundary being compromised. This rninor discrepancy was immediately corrected by plant personnel and properly addressed by licensee management. AOOGOO a00000 cO 000 12/19/97 Strength SAQV IR 97-14 NRC The ucensee was effecuvely conducung formal Radiation Protection and Chemistry 1 2 34 5 audits as required by TS and completing corrective acUons in a timely rnanner. A 00000 e00000 cO 000 12/19/37 Strength IR 97-14 NRC The licensee had properly Irnplemented procedures to maintsin an effecuve program 1 23 4 5 to rnonllor and control liquid and gaseous radioacuve effluents to lirnit doses to members of the public. Projected offsite doses resulting from those effluents were AOOOOO we5 within the Hmits specified in the TSs. ODCM and Tide 40 CFR Par 1190. OOOOO c0 000 12/19197 Strength IR 97-14 NRC The licensee's water chemistry control program for monitoring primary and 1 23 4 5 secondary water quality had been implemented, for those parameters reviewed,in accordance with the TS requirements and the Stauon Chemistry Manual for PWR A OOOOO water chemistry. 8 00000 CG 000 12/19197 VIO IR 97-14; V!O 97-14 05 NRC One violation was idenufled for failure to provide current dose rate information on a 1 234 5 radioacuve materiallabel as required by Title 10 CFR, Part 20.1904(a). A 08000 a00000 c0 000 12/19/37 Strength IR 97-14 NRC The Dcensee was meeting established goals for radioacuve waste generated. 1 23 4 5 Radiological facility conditions and housekeeping in radioacuve waste storage areas were observed to be good. AOGOOO a00000 c0 000 FROM: 10/1/97 TO: 11/23/98 Page 26 of 29 FOR PUDLIC RELEASE Last Updated: 9/14/98

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.' CATAWBA 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/1197 VIO tR 97-12; VIO 413.414/97-NRC Two violauons of the access controls for personnel were idanulled. The violations 1 2 34 5 12-02 and VIO 9712-03 concemed control of access to the protected area. Badges for terminated employees were not deactivated or the badges for active ernployees were exiting the ACCCCC PA. uncontrolled (from la Section 2.2). OOOO9 cO 000 10/11/97 Positive IR 97-12 NRC Access controls for vital areas were in comp!!ance with the Physical Security Plan. 1 2 3 4 5 A 0 0 0 0 0-a00G00 cO 000 10/11/97 Positive IR 97-12 NRC The Ucensee used compensatory measures that ensured the re!! ability of security 1 234 5 related equipment and devices. A00000 u00000 cG 000 FROM: 10/1/97 TO: 11/23/98 Page 28 of 29 FOR PUBLIC RELEASE Last Updated: 9/14/98

CATAWBA 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMM Template Codes: SALP Functional Areas: ID Code: 1A OPERATION PERFORMANCE - Normal Operations LICENSEE LICENSEE 10 OPERATION PERFORMANCE Operations During Transients ENG ENGINEERING NRC NRC IC OPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SELF SELF-REVEALED 2A MATERIAL CONDITION - Equipment Condition OPS OPERATIONS 28 MATERIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A HUMAN PERFORMANCE - Work Performance SAQV SAFETY ASSESSMENT & QV 30 HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE Work Environment 4A ENGINEERING / DESIGN - Design 40 ENGINEERING / DESIGN - Engineering Support 4C ENGINEERING / DESIGN-Programs and Processes SA PROBLEM IDENTIFICATION & SOLUTION - Identification 50 PROBLEM IDENTIFICATION & SOLUTION - Analysis SC PRODLEM IDENTIFICATION & SOLUTION - Resolution Eels are apparent vlotations of NRC requirements that are being considered for escalated enforcement action in accordance with the 'Generat Statement of Policy and Procedur NRC Enforcement Action * (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision en the issues identified by the Eels and the PIM entries may be modilled when the final decisions are made. Delore the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either ( the apparent violation or (2) request a predecisional enforcement conference. Unis are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violati However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made. FROM: 10/1/97 TO: 11/23/98 Page 29 of 29 4 FOR PUBLIC RELEASE Last Updated: 9/14/98 -.}}

ML20196F292

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