ML20196F290
| ML20196F290 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 11/23/1998 |
| From: | Ogle C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Barron H DUKE POWER CO. |
| References | |
| NUDOCS 9812070003 | |
| Download: ML20196F290 (46) | |
Text
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November 23, 1998 Duke Energy Corporation ATTN: Mr. H. B. Barron Vice President McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
INSPECTION PLAN - MCGUIRE
{
Dear Mr. Barron:
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 ll 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 to an annual Senior Management Meeting cycle.
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.
During this scheduling cycle, we will continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, 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.
Enclosure 2 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 NRC and McGuire. This material will be placed in the Public Document Room.
OFFICIAL COPY 9812070003 DR 981123 -
\
g ADOCK 05000369 PDR s
_ - . - . . = . - - - . _ _ _ _ . _
l .
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DEC 2 We willinform you of any changes to the enclosed inspection plan. If you have any questions, <
please contact me at (404) 562-4510.
Sincerely, Orig signed by Charles R. Ogle Charles R. Ogle, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 50-369,50-370 '
Enclosures:
- 1. Inspection Plan ,
- 2. Plant issues Matrix i cc w/encis:
Michael T. Cash Regulatory Compliance '
Duke Energy Corporation 12700 Hagers Ferry Road Huntersville, NC 28078-8985 L. A. Keller, Manager Nucisar Regulatory Licensing Duke Energy Corporation 526 S. Church Street Charlotte, NC 28201-0006 ;
Paul R. Newton Logal Department (PB05E) :
Duke Energy Corporation 422 South Church Street Charlotte, NC 28242 J. Michael McGarry, Ill, Esq.
Winston and Strawn 1400 L Street, NW Washington, D. C. 20005 Mel Fry, Director >
Division of Radiation Protection N. C. Department of Environmental '
Health & Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721 l
l cc w/encis: (See page 3) i I
l l
DEC 3 cc w/encls cont'd:
County Manager of Mecklenburg County 720 East Fourth Street Charlotte, NC 28202 Steven P. Shaver Senior Sales Engineer Westinghouse Electric Company 5929 Carnegie Boulevard, Suite 500 Charlotte, NC 28209 Dr. John M. Barry, Director Mecklenburg County Department of Environmental Protection 700 North Tryon Street Charlotte, NC 28203 l
Karen E. Long i Assistant Attorney General ;
N. C. Department of Justice ,
P. O. Box 629 l Raleigh, NC 27602 l
l Distribution w/encls: l L.Plisco, DRP l
F. Rinaldi, NRR l C. Ogle, Ril E. Lea,Ril l C. Payne, Ril l PUBLIC l NRC Resident inspector I U.S. Nuclear Regulatory Commission i 12700 Hagers Ferry Road Huntersville, NC 28078-8985 I
n OfflCE Ril:D Q g R!l:DRR) RI M RS R il,:DRS f Ril:DRS ,
SIGNATURE .l[} M (pdu /;/)/19//E~ ?/f/'
NAME PFrecfick' son:s KlandiK M Kb4rr Cbeliste TPeebles DATE 11/ ih /98 11/_\h /98 11/ ( 7 /98 11/ f 7 /98 11/ / / /98 11/ /98 11/ /98 COPY? YES NO (YES i NC (YEM NO 'dTy NO Vf$ ) NO YES NO YES NO OFFICIAL RECORD COPY V DOCUMCNT NAME: G:\MCG1RSM. 11 l
[4CGUIRE NUCLEAR STATION INSPECTION PLAN -
INSPECTION PLANNED PROCEDURE / NUMBER OF INSPECTION TEMPORARY TIEE TYPE OF INSPECTION -
INSPECTORS DATES COMMENTS INSTRUCTION IP 71714 COLD WEATHER PREPARATIONS 1 (RI) 12/98 Regional Initiative -
seasonal region-wide initiative INITIAL OPERATOR LICENSE 3 1/99(prep)
EXAMINATIONS Initial Examinations 1/99 2/99 IP 73753 INSERVICE INSPECTION 3/99 1 Core - Inspection during Unit 2 outage.
IP 62700 MAINTENANCE IMPLEMENTATION 1 3/99 Regional Initiative - Unit 2 RF0 ice condenser inspection. Focus on ice condenser corrective actions. design changes, surveillances and material condition.
IP 83750 OCCUPATIONAL EXPOSURE 3/99 1
Core - focus on radiological controls during outages.
IP 81700 PHYSICAL SECURITY PROGRAM 1 2/99 Core FOR POWER REACTORS IP 60853 ONSITE FABRIC.ATION OF 1 12/98 Regional Initiative -
COMPONENTS AND CONSTRUCTION OF AN ISFSI ISFSI construction (DRS review) um, o,,, t_.m e Page 1 of 1 Enclosure 1
_____._.__.....i . .
~
Region 11 Unit;d Stat:s Nuclear R;gulatory Commission C'Sl.'i2 PLANT ISSUE MATRIX Page: 1 of 5 MCGUIRE By Primary Functional Area Functional Template Date Source Area ID Type Codes item Descripflon
- 10/03/1998 1998009 Prt OPS NRC NEG Pit 3B The qudity control process for evducting tre licensed operator requotfication program blonnud written examootion 3 , * $g~. failed 1o identify several weaknesses, As o result, the written examination was a poor tool to distinguish o competent .
operotor from on incompetent operator. (Section 05.1)
Ter:
10/03/1998 199S0 @ Pri: OPS NRC POS Prt 3B in general. the training stoff and operations stoff performed effective evoluotions of the licensed operators during Sec- Sec. requalification program examinations. (Section 05.2)
Ter:
10/03/1998 1998009 Prt OPS NRC POS Prt 48 Design and function of the auxiliary building droh system during the fire protection flooding event was consdered Sec- Sec. dequate. No safety 4 elated equipment was adversely offected. (Section O2.1)
Ter:
10/03/1998 199800941 Prt OPS NRC IFl Prt 3B Trocidng of Corrective Actions for Procedure Wecknesses in Two ARPs for Rod Insertion Limits and the Monud Estimated Sec- Sec, Critied Boron Calculation (Section O3.1) .
Tet 10/03/1W8 199800902 Prt OPS NRC !F1 Prt 1A Two crews of licensed operators were evoluoted as unsatisfactory and removed from Icensed duties pending Sw SE:3B remediction. This action was taken based on unsatisfoctory performance during simulator scenarios. An inspector fonowup item was identified perdng NRC review of corrective actions for licensed operators' inability to perform o Tet 5A monud estimated criticd boron cdculation. (Section 05.3) 10/03/1998 1998009 Pri: OPS NRC POS Prt 1B Operotors' response to the loss of a Unit 2 600 voit motor control center. 2EMXG. was excellent. Immediate actions t n werm mpt. e.
See: ENG Sec: 3A ccMmce @ Wes. WW24 Ter-10/03/1998 1998009 Prt OPS NRC NEG Pvt 2A Routine maintenance and surveH)once activities were adequately completed. A negative observation was identified in See: MAINT See: 3A the initial diagnosis and resolution of problems with the emergency diesel generator indcotiry lights for the 2A Ter: emergency diesel generator fuel of booster pump. Specifically, the pump was out of service. due to o inpped power l supply brecker, for at least two weeks without resolution. The problem did not offect the err =. dip icy stort copobility of !
the dieset. (Section M1.1)
ENCLOSURE 2 Item Type (Compliance. Followup.Other). From 10/01/1997 To 11/02/1998 l
' "' ^ ^ ~
Unit;d Stat s Nucl;or R;gulatory Ccmmission
Ew,.$'3![i2 Region 11 Page: 2 of 5 PLANT ISSUE MATRIX MCGUIRE By Primary Functional Areo Functional Template Dole Source Area ID Type Codes item Description ' '
10/03/1998 1998009 Prt OPS NRC POS Prt 18 Operations and chemistry personnel odequately responded to the auxiliary buildng floodng event. The Dcensee's See: PLTSUP See:48 system modfMm to W on W mM m N cWcmoWng WotxWN was WW to ,
correct the problem (Section O2.1)
Ter:
l 10/03/1W81998009 Prt MAINT Self NEG Prt 2A Efforts to repair moin feedwater pump high bearing temperatures were unsuccessful due to material condition 3 ,*, 3 *, problems preventing establishment of the work boundary. The secondary plant equipment performance and prevent'rve maintenance octivities to molntoin tellobility were hsufficient to support the planned maintenance Tet octMties. (Section M2.1) j 10/03/1998 1998009 Prt MAINT Se!f NEG Prt 2A A material condition deficiency resulted in a substantial glycol leak in the Unit 1 ice condenser. (Section M2.3) P See: Sec:
Tec 10/03/1998 1998009 Prt MAINT NRC POS Prt 3A Maintenance and engineering personnel response to on ice condenser ethylene gtycol leck from o domoged air .
Sec: ENG Sec:48
' '" O P "* ' "
(Section M2.3)
Ter:
10/03/1998 1998009 Prt ENG NRC POS Prt 4B The engineering support actMties for the loss of power to the Unit 2 600 voit motor control center 2EMXG displayed 3,c 3,c. excellent engineering knowledge, performance, and Judgement. (Section E2.1)
Tet 10/03/1998 1998009 Pri: ENG NRC POS Pri: 58 The Scensee's evduction of inspectors
- concerns regarding potentid contoirrnent integrity impact from the
$g~. $ combustion of ethylene g!ycol off-gas (formaldehyde) under postulated design basis occident conditions was !
odequate. (Section M2.3) l Tet i
i 10/03/1998 1998009 44 Prt ENG NRC IFI Prt 48 The design calculations for the spent fuel cask concrete pod and related structures were odequately performed in 3 ,*. 3,c occordance with industrid standards. One inspector followup item was identified for the discrepancies in the design calculations. (Section E8.2)
Tet SB item Type (Compliance, Followup,Other). From 10/01/1997 To 11/02/1998
Region ll Unit d Stat:s Nuclear R gulatory Commission DEi2'"'
Pogo: 3 of 5 PLANT ISSUE MATRIX MCGUIRE By Primary Functional Area Functional Template Dofe Source Areo ID Type Codes llem Description
- 10/03/1998 1998009 03 Prt ENG NRC IFl Prt 4A immediate Ecensee evoluotions of a corroded hydrogen Ene within the Unit I refueling water storage tank suction See:PLTSUP Sec 48 piping trench were odequate. An hspector follow-up item was identi' led to review the potentid for safety concerns ,
due to the hydrogen line proximity to the refueling water storage tank. (Section M2.2)
Ter:
10/03/1998 1998009 Prt PLTSUP NRC WK Prt 1C A fire protection system leak occurred due to poor materid condition wtSch offected equipment operation in the Se - - Sec M uxiliary building. The leak could have been prevented through visud inspection of the subject gland type Joint. Other Indicators of fire protection system poor material condition were leukoge post isolation volve IRF156 and material ,
Ter: SA deficiencies in its indicoting mechanism, which resulted in the volve being found in the wrong positiort as discovered during event response. Both problems chdienged the fire protection system functionality in the auxiliary building and posed a potential personnel and flood hozord for system operoflon and maintenance. (Section O2.1) 10/03/1998 1998009-05 Prl: PLTSUP NRC IFl Prt 1A Severd degraded conditions of the fire protection system were observed during the inspectors wolkdowns of the Sec., See: 2A system. An inspector followajp item was identified for potential overpressurization of piping in the safe shutdown factity.
Overall material condition of the fire protection system was considered adequate; ofttwugh several problems were Tot SA identified. (Section F2.1) 09/22/1998 1998014 Prt PLTSUP NRC POS Prt 1C The background investigation process odequately developed and verified the background elements before granting :
Se Sec. unescorted access (Section SI).
Ter:
j 09/22/1998 1998014 Pri: PLTSUP NRC POS Prt IC The psycholog! col evductions of applicants were property administered and supervised (Section SI).
Sec: Sec:
Ter:
09/22/1998 1998014 Prt PLTSUP NRC POS Prl: IC The behovlord observation progrom was implemented according to Icensee cui nu Jims its and regulatory See: See: '*4#8**" * "" )'
Ter:
1 09/22/1998 1998014 Prt PLTSUP NRC POS PrtIC The grandfathering. reinstatement, updating. transfer, and tenporary unescorted access authorization elements were efficientry maintoined and proficientty wn vivuud (Section S1).
3 3 ,c, Tec Item Type (Compliance. Followup,Other), From 10/01/1997 To 11/02/1998
Unitcd Stat:s Nucinar R gulatory Commission E "'3lf2 Region 11 PLANT ISSUE MATRIX Pa*: 4 *' S i MCGUIRE By Primary Functional Areo !
Functional Template Date Source Area ID Type Codes item Description
- 09/22/1998 1998014 Prt PLTSUP NRC POS Prt1C The protection of personalinformation by the Access Services Group was odequate (Section SI).
1 Sec: Sec-
- I Ter:
i 09/22/1998 1998014 Prt PLTSUP NRC POS Prt1C The licensee had implemented and stoffed on organizohon that was capable of monoging and implementing the See: See: 3C A cess ANdon We rWres kte S4 Ter:
f W/22/1998 1998014 Prt PLTSUP NRC STR Prt IC The documentation o.X1 management of the denial, revocation, and appeals process was o strength in the Access Au gram @ch SI).
Sec: Sec:
Ter:
08/27/1998 1998014 Pri: PLTSUP Nr<C POS Prt IC Persono! occess authorization records were maintained according to the Access Authorization Program commitments Sec- Se, nd regulatory requirements (Section SI).
Ter:
08/27/1998 1998014 Prt PLTSUP NRC POS Prl: 5A Audits of the Access Authorization Progrom were thorough, concise, and timely (Sec.'%n SI).
See: See:
Ter:
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES
!CPERATiONSP4 %GEl 9/21/98 VIO IR98-08 LICENSEE A violation with two examples was identified for failure to adequately vent emergency 1 234 5 core cooling system piping as required by plant procedure and Technical Specifications. The first example of the violation was caused by the licensee's failure to designate the proper vent valves used during system restoration. (Section A OOOOO E2.1) B O00OO cO 000 9/21/98 Negative IR98-08 NRC Operators failed to maintain the required minimum reactor cootant system everage 1 234 5 temperature for criticality during an operator induced primary temperature transient.
Operator performance was weak for not adequately controlling secondary (turbine loading) conditions to satisfy Technical Specification required minimum temperature A OOOOO for criticality during routine plant operations. (Section 04.1) D OOOOO cO 000 9/21/98 Negative tR98-08 NRC Material condition was adequate with the exception of an NRC icentified, 1 234 5 malfunctioning condensate drain for the steam supply to the Unit 1 turbine driven auxiliary feedwater pump. One negative observation was identified for the frequency of continuous drain inspections (only once per three refueling outages). (Section A OOOOO O2.3) B 000OO cO 000 9/21/98 Positive IR98-08 NRC Accessible components of the Unit 1 auxiiiary feedwater system were property.
aligned. (Section O2.3) 1 23 4 5 A 00000 B 00000 c0 000 9/21/98 Positive IR98 -08 1.!CENSEE Following the identification of an auxiliary building ventilation design issue, the 1 23 4 5 ficensee's immediate corrective actions to address the issue and its associated Technical Specification requirements were adequate (Section O2.2 A OOOOO B 00000 cO 000 8/7/98 Negative IR 98-07 NRC Three negative findings were identified during review of reactor coolant system 1 234 5 draindown activities: (1) the special pre-job briefing was not as detailed as previously observed midloop pre-job briefings; (2) the licensee planned, but did not perform, an unnecessary draindown to midtoop; and (3) a weakness was identified for a AOOOOO procedure that was not correctly updated to reflect the new steam generators' spill over tevei~
B D000O c O. OOO FROM: 10/1/97 TO: 11/23/98 Page i of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 4/24/98 Positive SAOV 9844 NRC The audits and assessments reviewed were effective in identifying problems and 1 234 5 areas for improvement in the licensee's corrective action program. Corporate regulatory audits were effective in promoting change at the McGuire Nuclear - A .O O O O O .
Station. Self-assessments at the site level were effective in finding process deficiencies and investigating new program chmes. B OOOOO cO 000 4/24/98 VIO SAOV 98-04 NRC A violation was identified for two exampfes of failure to meet corrective action 1 234 5 program procedural requirements for problem report initiation timeliness.
A 00000 B 00000 cO 000 4/24/98 Positive SAQV 98-04 NRC The licensee's problem investigation process program met the requirements of 10 1 234 5 CFR 50, Appendix B, Criterion XVI, Corrective Action.
A 00000 ,
sD0000 cO 000 4/24/98 Positive 98-04 NRC The licensee had identified the necessary contingencies and corrective actions to 1 234 0 address each workaround.
A 00000 s00000 cO 000 4/24/98 Positive SAOV 98-04 NRC The workaround problem resolution list was managed by qualified operations 1 234 5 t personnel with a proactive approach to resolving deficiencies. 4
~
A 00000 s3O000 cO DOO !
4/24/98 Pcsitive SAOV 98-04 NRC The licensee appropriately identified and documented operator workarounds. 1 204 5 A 00000 s00000 cO 000 4/18/98 Negative MAINT 98-03 NRC The material condition of roofs on some buildings housing safety-related and 1 234 5 important to safety equipment as poor and created conditions that could challenge safety system operability. Numerous rain water leaks continue to challenge plant operations personnel to identify and mitigate the effects of the leaks before plam
~A OOOOO equipment is adversely affected. Ucensee actions were prev 5usly established to correct the identified roofing problem.
aOOOOO i O OOO FROM.10/1/97 TO: 11/23/98 Page 5 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3/2T98 Positive 98-03 LICENSEE Operations'immediate response to an electro-hydraulic centrol fluid leak on the Unit 1 234 5 1 main turbine emergency trip header was good. Prompt actions prevented a potential fire and possible transient on the plant. g .O O O O O .
B 00000 cO 000 3/21/98 Positive 98-03 LICENSEE Maintenance activities associated with a steam leak temporary repair on 1SC36 1 234 5 were adequately performed. Power reduction and fiange repair were conducted in a safe manner. The licensee was taking a proactive approach to resolving an identified negative secondary eqiupment trend.
A OOOOO OOOOO c0 000 3/21/98 Positive 98-03 LICENSEE Operator identification and response to a steam leak on Urdt I reheat stop valve 1 234 5 1SC36 was good.
A 00000 B 00000 cO 000 3/7/98 Positive MAINT 98-02 NRC Accessible components of the Unit 1 and Unit 2 containment spray systems were 1 234 5 property aligned. Material condition was adequate with the exception of valve 2NS380.
A OOOOO s00000 cO 000 3/T98 Negative ENG 98-02 NRC The licensee's efforts to identify *he root cause of the loss of motor control center 1 234 5 2MXA were inconclusive.
A 00000 e00000 cO 000 3/3/98 Positive MAINT 98-02 SELF Operators responded promptly and appropriatefy to the loss of motor cc.itrol center 1 234 5 2MXA.
A00000 a00000 cO 000 2/23/98 Positive 98-02 NRC An NRC Identified discrepancy between reactor trip breaker train actuation times 1 234 5 was appropriately addressed by the licensee.
A 0000 0 s00000 cO 000 FROM: 10/1/97 TO: 11/2398 Page 6 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 I
t DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) l SMM CODES 1/24/98 URI 97-20; URI 97-20-01 NRC An unresolved item was identified for several design issues related to the refueling 1 234 5 water storage tanks and whether stratification could have affected past operability of each unit's tank. -
A OOOO O e00000 cO 000 1/24/98 Positive 97-20 NRC The licensee made proper determinations regarding reportability of three events 1 234 5 during the report period. Operator response to the event involving loss of both trains of the control room ventilation system was appropriate.
A OOOOO s80000 cO DOO 12/13/97 Strength SAQV 97-18 NRC The inspectors concluded that the licensee's performance during core afterations for 1 234 5 McGuire Unit 2 Cycle 12 was gond. Adequate training was provided and appropriate emphasis was placed on nuclear and personnel safety. Material condition of the fuel handling equipment supported a safe core reload with minimal interruption.
-AOOOOO e00000 cO 000 12/13/97 Positive SAQV 97-18 SELF Reviews of licensee actions to implement cold weather preparations at N- este were 1 234 5 acceptable. Nuclear Gystem Directive 317 was issued which provided addifice.1 structure and delineated responsibilities for freeze protection. Procedures for verifying critical plant systems prior to exposure to predicted extreme cold weather AOOOOO and the monthly surveillance were good and provided additional assurance of operational readiness for cold weather conditions. ConMruction of an enclosed and B DOOOO heated room containing the new Unit 2 refueling water storage tank level O OOO transrrutters was a substantialimprovement in refueling water storage tank freeze protection reliability. Freeze protection activities were initiated and completed in a timely manner. Overall, the inspectors concluded that the licensee's efforts to effectively protect plant equipment and systems from freezing conditions had improved.
12/1T97 Weakness 97-18 LICENSEE The licensee identified a number of problems with initial operation of the residual 1 234 5 heat removal system during No Mode maintenance and testing, initial documentation of the problems was unclear; however, subsequent engineering reviews determined no permanent damage was sustained by the residual heat AOOOOO removal pumps. Subsequent system testing at the end of the outage further verified system operability. Several proce-*w Nsions were identified to preclude future B OOOOO events. The inspectors concluded that the overall coordinatiort procedure O OOO application, and oversight of system operation during No Mode conditions was weak.
12/13/97 Weakness 97-18 LICENSEE Operators missed several earlier opportunities to ident. mispositioning during routine 1 23 4 5 control board walkdowns. The licensee's immed. corrective actions wer approp and overall containment integrity deter. not to have been compromised. (TC:1 A,3A) A OOOOO sD0000 cO 000 FROM: 10/1/97 TO: 11/23/98 Page 8 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/1/97 Positive MAINT 97-17 NRC General material condition and housekeeping of the Unit 2 ice condenser system 1 234 5 appeared good. Observed Unit 2 maintenance activities were being accomplished with established procedures. The licensee's evaluation and monitoring of Unit 1 ice bed temperature anomalies and floor temperature alarm were adequate.
AOOOOO.
OOOOO cO 000 11/1/97 Negative ENG 97-17, LER 369/97-10 NRC The licensee reported a potential non-conservatism in a Technical Specification in accordance with the requirements of 10 CFR 50.72. The administrative limits 1 234 5 established to compensate for the potential non-conservatism in Technical Specifications related to power versus f!ow prohibited operation area appeared to be A OOOOO adequate. aOOOOO cO 000 11/1/97 Positive 97-17 NRC in general conduct of operations was professional and safety conscious. 1 23 4 5 A 00000 a00000 cO B00 10/2/97 Positive MAINT 97-17 NRC Operators maintained adequate focus during the U2 outage shutdown and 1 234 5 responded appropriately to rod control equipment malfunctions during the evolution.
A 00000 sG0000 cO 000 10/1/97 Positive MAINT 97-15 LICENSEE The inspectors conch;ded that the licensee's identificalN of moisture in the Unit 1 1 234 5 turbine driven auxiliary feedwater pump local control pa a was good. Corrective actions taken for the degraded condition were appropriate. At the end of the inspection period, the licensee was continu!'g to evaluate other potential corrective A OOOOO i actions to preclude future events. aOOOOO cO 000 10/1/97 Positive SAOV 97-15 NRC inspectors' ob.servations of planned Nuclear Safety Review Board meetings 1 2 3 4 5 concluded that the Nuclear Safety Review Board was providing good oversight of the facilities' operation.
AOOOOO a00000
~
cO 000 fMAINTENAECN Tl 9*21/98 Positive IR98-08 NRC The program manual for the second ten year inservice testing interval contained the 1 23 4 5 elements of the applicable Americal Society of Mechanical Engineers /American National Standards institute Operations and Maintenance Code Standards. (Section M3.1)
A OOOOO aD0000 cO 000 FROM; 10/1/97 TO: 11/23/98 Page to of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/21/9Q Positive IR98-08 NRC Inspections of the Unit 2 ice condenser intermediate deck doors boiting and upper ice basket flow passeges were completed. Intermediate deck doors were free of ice 1 234 5 and observed flow passages were clear. No operability concems or Technical Specification non-conformances were identified. (Section M2.2)
A .O O O O O OOOOO cO 000 9/21/98 Positive IR98-08 NRC Repairs to correct the failed throttie vafve actuator stem were effective and 1 234 5 appropriate precautions were taken to minimize adverse impacts during the retum to service. (Section M2.1) A OOOOO e00000 cO 000 9/21/98 Negative IR98-09 SELF A repet#tive failure of a Unit 1 main turbine throttle valve occurred (Section M2.1) 1 234 5 A 00000 s00000 cO 000 a27/98 Positive IR 98-11 NRC Maintenance supervision responsible for servicing the IC exhibited a high degree of 1 234 5 oversight and accountability for performing quality work. (Section M1.1)
A 00000 sD0000 cO B00 8/27/98 Positive IR 98-11 NRC The licensee's use of an IC rotating team approach which utilized aggregate 1 234 5 experience in servicing all four [McGuire and Catawba] of the licensee's IC units promoted an increased awareness of critical maintenance and survemance practices. (Section Mt.1)
AOOOOO OOOOO ;
cO 000 8/27/98 Positive IR 9t-11 NRC IC Technical Specifications (TS) survoittance requirements were being met and in 1 234 5 many cases exceeded minimum TS requirements. (Section Mt.2)
A 00000 a00000 t cO 000 8/27/98 Positive IR 98-11 NRC Inspections for rnissing or broken screws were being performed in a conservative 1 234 5 manner by adequatefy trained personnel. Supervision was present for guidance as needed and the level of licensee oversight was appropriate for the activity. (Section
"'I A OOOOO o0000O cO 900 FROM: 10/1/97 TO: 11/23/98 Page 11 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
McGUIRE 23-Nov-98 DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 8G7/98 Positive IR 98-11 NRC Damaged ice baskets were effectively identified and appropriate repairs were performed. (Section M1.3) 1 234 5 A .O O O O O -
B 0G000 cO 000 827/98 Negative IR 98-11 NRC Damaged ice baskets were effectively identified and appropriate repairs were perfonned. (Section Mt.3) 1 234 5 A 0G000 a00000 cO 000 8G7/98 Pos:tive IR 98-11 NRC The inspectors noted a relatively high cur ent sensitivity in this area as evidenced by the absence of debris and unnecessary tools in and around the work area and the 1 234 5 work effort to remove accessible debris from the IC. (Section M t.4) AOGOOO B 00000 cO 000 8/27/98 Negative IR 98-11 NRC The licensee's efforts to exclude foreign material from the IC during previous 1 234 5 outages had not been rigorous as evidenced by the amount of debris found during this outage. (Section M1.4)
A OOOOO s00000 cO 000 8/27/98 Positive IR 98-11 NRC Appropriate resources and management attention were being applied to support 1 234 5 activities associated with maintaining the Unit 1 IC system and its associated sub-systems in an operable state. (Section M t.1)
AOOOOO a08000 cO 000 8#S8 MISC IR 98-07 NRC The licensee's evaluation of the protec$ve coating used on the refueling water 1 234 5 storage tank interior surfaces and the calculations performed to determine acceptance criteria for operability were satisfactory.
A OOOOO aD0000 cO 000 8/7/98 NCV IR 99-07 UCENSEE A non-cited violation was identified for not providing sufficient procedural guidance for assembly of a Unit 1 main feedwater/ containment isolation valve actuator.
1 234 5 Current testing may not be effective in identifying actuator performance issues.
A OOOOO a00000 cO 000 FROM; 10/t/97 TO: 11/23/98 Page 12 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 4/18/98 Positive SAOV 98-03 LICENSEE Licensee rnanagement recognized an af terse trend in the pedormance of 1 234 5 secondary support systems, based on a number of recent problems related to the turbine genemtor and other support systems. A focused review was initiated to address the secondary equipment trend.
AOOOOO-OOO cO 000 323/98 Negative 98-03 SELF An electro-hydraulic control fluid leak occurred on the Unit 1 main turbine emergency trip header.
1 234 5 A 00000 s00000 cO 000 3/21/98 Negative 98-03 SELF A unit downpower was required to repair a steam leak on Unit 1 reheat stop valve ISC36.
1 234 5 A00000 s00000 cO 000 3/708 Weakness 98-02 LICENSEE Maintenance practices in applying sealant to containment purge valves was identified as a weakness that ultimately resulted in failure of lower containment 1 234 5 purge inlet isolation vafve 1VP88.
AOOOOO aO0000 cO 000 3/7/98 VIO 98-02; VIO 98-02-01 LICENSEE A second example of a violation of Technical Specification 6.8.1 was identified due 1 234 5 to maintenance technicians failing to follow station procedures for installation of lower containment purge intet isolaton valve 1VP8 seat ring ad;usting screw. The failure to follow established procedures resutted in 1VP80 being in a degraded A OOOOO condition. sOOOOO cO 000 3/7/98 Negative 98-02 NRC The licensee's documentation of repair activities associated with valve ICF35 was poor.
1 234 5 A 00000 s00000 cO 000 3/7/98 VIO 98-02; VIO 98-02-01 NRC One example of a violation of Technical Specification 6.8.1 was identified for failing 1 234 5 to establish adequate guidance instructions for the repair of the 1CF35 valve actuator. This resulted in degraded operation of the containment isolation valve.
A OOOOO aO0000 cO 000 FROM.10/1/97 TO: 11/23/98 Page 15 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 12/13/97 Positive 97-18 NRC The licensee's nondestructive examination unit continued to perform in a satisfactory 1 234 5 manner. Technicians had a good knowledge of plant equipment and procedural requirements. They performed their assigned tasks in a conscientious manner, and evaluated indications and documented findings with accuracy and clarity.
AOOOOO-s00G00 cO 000 12/13/97 Positive 97-18 NRC Both film and raciographic quality were satisfactory. Indications were evaluated 1 234 5 correctly and property documented. Housekeeping conditions in the daric room were satisfactory as was the storage of unexposed film and reagents.
A OOOOO a00G00 c0 000 12/13/97 Weakness 97-18 NRC Some progress was achieved in the fabrication of production welds during this 1 234 5 steam generator replacement project. However, the relatively high rejection rates and the apparent inability to use certain machine weld processes, with good results.
suggests that the licensee's technical expertise in welding contirPJOS to be a AOOOOO weakness. O OOGOO cO 00G 12/13/97 Positive 97-18 NRC Testing of the Unit 2 hydrogen igniters was performed well. Maintenance personnel 1 234 5 possessed good system knowledge. Procedure adequacy, execution, and overalt test coordination were considered excellent. All Unit 2 igniters exceeded the minimurn temperature requirements of Technical Sprefication 3/4.6.4.3(b).
AOOGOO s08000 cO GOD 12/13/97 URI ENG 0718; URf 97-18-02 LICENSEE Unit 1 containment isclation valve 1VP80 was property repaired and the suppo. ting 1 234 5 temporary modifications were adequate. However, during their review, the inspectors identified an Unresolved item regarding the use of a sealant in the valve that may not have received appropriate reviews for this application. Application of A OOOOO the sealant contributed to the failure of vafve IVP80. sOOOOO cO 000 12/13/97 Strength ENG 97-18 NRC Licensee's efforts to overhaul the emergency diesel generators ar'd improve onsite 1 234 5 emergency power reliability was excellent.
A OGOOO s00000 cO 000 12/13/97 Positive 97-18 NRC Inspections of the Unit 2 containment concluded that emergency sump area 1 234 5 cleanliness was adequate. Materials potential'y susceptibio to high energy releases during a deskJn basis event were adequately secured and debris dams and screens were installed to prevent complete blockage of containment sump screens. The A OGOOO licensee's material accountability and forsign material controis were considered B OOOOO good. In addition, the overall building material condition was considered good following the Unit 2 refueling outage. O OOO '
FROM: 10/1/97 TO: 11/23/98 Page 18 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/38
McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 12/1397 Positive ENG 97-18 NRC Routine testing activities were completed satisfactorily during the inspection period- 1 234 5 The successful completion of Unit 2 engineered safety features testing was indicative of well performed outage maintenance and excellent engineering test A .O O O O O -
support functions. Overall test coordination was considered good.
OOOOO cO 000 11/1/97 Negative ENG 97-17 NRC Initial test performance problems of the interior fire suppression loop piping did not 1 234 5 allow for valid data to be taken. The problems identified indicated that some fire suppression equipment may have limited preventive maintenance being performed. A OGOOO e00000
- c. O OOO 11/1/97 NCV 97-17; NCV 97-17-03 Nhu A NMCited Violation was identified for performing crane manipulation procedure steps out of sequence.
1 234 5 A 00000 s00000 cO 000 11/1/97 Weakness 97-17 NRC One weakness was identified for qualified crane operators not signing and dating in 1 234 5 i the procedures for the steps which they performed.
A0000G s00000 '
cO 000 11/1/97 Positive SAQV 97-17 NRC Licensee's development of a special fire protection system flow test in response to 1 234 5 NRC concems to assure operability was good.
A00000 e00000 cO 000 11/1/97 Strength 97-17 NRC The Inspectors confirmed through observation of project activities and discussions 1 234 5 t with licensee representatives, that the steam generator replacement project '
organization was effective in adequately planning and safely executing the Unit 2 steam generator replacement project effort AOOOOO OGO cO ODG 11/1/97 Strength SAQV 97-17 NRC Housekeeping around the steam generator replacement wNk project work area 1 234 5 showed significant improvement over the two previous Duke facihty steam generator replacement projects.
AOOOOO s00000 i cO 000 FROM: 10/1/97 TO: 11/23/98 Page 19 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
x v McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/1f97 Positive SAQV 97-17 NRC The steam generator replacement project was progressing well within the licensee's pre-established timetable. Cutting activities followed approved procedures and were 1 234 5 closely monitored. bfts of heavy components were well planned and implemented in a safe manner. A .O O O O O -
B 00000 11/1/97 Positive c0 000 97-17 NRC Volumetric and surface inservice inspection of designated welds were performed satisfactorily by qualified and well trained persor ,el following approved non-1 234 5 destructive examination procedures.
AOOOOO B 00000 11/1/97 Positive cO 000 97-17 NRC Welder performance qualifications were consistent with code requirements and were being closely monitored by cognizant licensee personnel. The weld filler metal 1 234 5 control program was well organized and capable of supporting steam generator replacement project welding. AOOOOO OOO 11/1/97 Positive 97-17 cO 000 NRC Minor Modification MM-8410 to replace certain isolation drain valves and associated piping in the reactor coolant system crossover pipe was being performed fnitowing 1 234 5 applicable code requirements. Prefabricated subassemblies and field we' '> -
exhibited good workmanship attributes and material records were retri~- ha and in AOOOOO order. Quality Controlinspections and visual examinations were performed as required. Engineering evaluations and input were appropriate.
B OOOOO 11/1/97 O OOO Negative ENG 97-17 LICENSEE Licensee actions in response to a potentially degraded auxiliary feedwater condition were acceptable. Reducing the acceptance criteria for vent flow in order to eliminate 1 234 5 AOOOOO an immediate concem was acceptable. The inspectors also concluded that any further reduction in continuous vent flow rates could challenge the auxiliary !
feedwater system during a standby shutdown system event and heightened monitoring and timely corrective actions were warranted to prevent future B OOOOO inoperability of these components. O OOO 11/1/97 Positive ENG 97-17 NRC The licensee's planned maintenance evolution for the 28 emergency diesel generator was weil imp!emented. Foreign material exclusion controls during the 1 234 5 i i
activities provided adequate protection for the open configuration of the engine. The subsequent surveillance testing activities performed were adequate to ensure AOOOOO equipment operability. B OOOOO 11/1/97 Positive cO 000 SAQV 97-17 NRC in general, monitored maintenance and testing activities were completed satisfactorily. Overall control of testing activities was good and indicative of 1 234 5 management oversight.
A OOOOO B 00000 cO 000 FROM.10/1/97 TO: 11/23/98 Page 20 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 8/27/98 Positive IR 98-11 NRC Dy observation of ice basket modification work, the inspectors verified that cunent 1 234 5 activities were being appropriately performed; that technicians were adequately qualified to perform their assigned tasks; and that the level of oversight provided by A .O O O O O the cont setor and the licensee was appropriate for the task. (Section E1.2)
OOOOO cO 900 8/27/98 Negative IR 98-11 NRC In general, previous mod 6 cations to the IC system have been completed in 1 234 5 accordance with approved modification procedures. However, the NRC identified two minor changes to the facility which were not performed in accordance with approved modification processes. (Section E1.2)
A OOOOO OOOOO cO 000 8/27/98 Positive IR 9811 NRC No significant inaccuracy problems with the Updated Final Safety Analysis Report 1 234 5 (UFSAR) were identified by the NRC. The licensee was continuing their UFSAR review and update in accordance with industry guidance. (Section E3.1) 3OOOOO sOOOOO cO 000 8/7/98 Negative IR 98-07 UCENSEE An operations performance weakness was identified for inacequate awareness of 1 234 5 shutdown plant conditions. Operations approved the tagout of the established shutdown boron injection flow path without verifying the availablity of an attemate
' " "*'"~ A OOOOO s000OO cO 000 8/7/98 NCV IR 98-07 UCENSEE A non-cited violation was identified for inadequate work instructions which 1 234 5 implemented the refueling water storage tank modification that inadvertently removed a Technical Specification required instrument from service-A OOOOO a00000 cO 000 8/7/98 Positive IR 98-07 NRC 10 CFR 50.59 safety evaluations for Unit 1 outage modifications were comprehensive and well detailed.
1 234 5 A 0000 0 g00000 cO 000 8/7/98 Positive IR 98-07 NRC The small engineering backlog indicated that appropriate resources and 1 234 5 management attention were focused on completing engineering activities.
A00000 s00000 cO 000 FROM: 10/1/97 TO: 11/23/98 Page 23 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 33-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 5/30/98 Positive 98-06 Lf0ENSEE A comprehensive and very detailed safety evaluation was performed by the 1 234 5 corporate nuclear engineering department to eva!uate suitability of new fuel that contained cladding contaminated with sodium chloride. The licensee's and fuel vendor's approach for addressing potential Nacl effects on fuel performance A .O O O O O included a rigorous examination of the issue with good consultation by independent industry fuel experts.
B OOOOO O OOO 4/24/98 Positive SAQV 98-04 NRC The licensee's Operating Experience Program was effective in capturing and 1 234 5 evaluating available information about industry events and problems from off-site sources including equipment vendors.
AOOOOO B 00000 cO 000 4/24/98 Positive SAOV 98-04 NRC The Top Equipment Problem Resofution Process has been effectively implemented 1 234 5 and managed to ensure resolution of equipment related problems that impact or may potentiaffy impact plant reliability and safety.
AOOOOO e00000 cO 000 4/18/98 NCV 98-03 LICENSEE A Non-Cited Violation was issued for the licensee's failure to update the McGuire 1 234 5 Updated Final Safety Analysis Report.
A00000 B 00000 c0 000 4/18/98 NCV 98-03 LICENSEE A Non-Cited Violation was identified forinadequate procedures that resulted in a non- 1 234 5 compliance with technical specifications for inoperable engineered safety feature instrumentation for refueling water storage tank level and the containment pressure control system.
A OOOOO OOO c0 000 4/18/98 Positive 99-03 NRC The licensee's safety evaluation of the removal of the remote operator for 2B 1 234 5 centrifugal charging pump discharge isolation valve 2NV232 was adequate.
A 00000 g00000 cO 000 4/18/98 NCV 98-03 UCENSEE A Non-Cited Violation was identified for failure to revise the Technical Specifications 1 234 5 to accurately reflect the references and methodology used in developing the core operating limits report.
A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/23/98 Page 25 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/1/97 Positive SAOV 97-17 NRC Good oversight of generic spent fuel pool storage issues was apparent. 1 234 5 ADOOOO B 00000 cO 000 11/1/97 Positive 97-17 NRC Overat!, the licensee continues to exhibit heightened awareness to reactivity events 1 234 5 and has a low threshold for classifying these as significant for root cause ana!yses to be performed-A OOOOO B 00000 cO 000 11/1/97 Negative 97-17 NRC NRC inspectors identified a discrepancy between the number of hydrogen igniters 1 234 5 insta!!ed and the number identified in Technical Specifications. No immediate safety or operability issues existed since plant procedures required testing allInstafled igniters. A OOOOO '
OOO cO DOO 11/1/97 Weakness 97-17 NRC Communications between engineering and operations regarding anticipated spent 1 234 5 fuel pool temperatures when isolating one spent fuel cooling pump were net effective. Adjustments to the required surveillance monitoring of the pool may also have been beneficial during periods of anticipated temperature increases, A OOOOO particularly when associa*M computer alarm points were unavaitable. B OOOOO cO 000 11/1/97 Positive 97-17 NRC The licensee performed adequate preparations, supporting calculations, and had 1 2 34 5 '
acceptable drawings and other documents to ensure the installation of the new short segment of guard pipe during the steam generator replacement project. A OOOOO B 00000 c0 00O ,
11/1/97 Positive SAOV 97-17 LICENSEE The licensee was currentfy conducting an extensive review of the safety to non- 1 234 5 safety interface of the auxiliary feedwater system, focusing on system design and operator required actions. In addition, the licensee was preparing to perform a root cause assessment of their latest component mispositioning data to continue t A OOOOO improve in this area. B OOOO cO 000 10/1/97 Positive 97-15 LICENSEE Licensee's evaluation of the emergency sump inventory issue recently identified at another ice condenser facility was good. The issue was determined to not tw a 1 23 4 5 concem at the McGuire facility.
A OOOOO B 00000 c0 000 FROM: 10/1/97 TO: 11/23/98 Page 28 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
McGUIRE 23-16v-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/1/97 Positive MAINT S7-15 LICENSEE No immediate safety issues existed for the potentially degraded SFP Region i 1 234 5 boraflex condition conceming boron densities below criticality analysis assumptions.
Licensee's evalustion was prompt and proposed actions to develop rnore restrictive fuel loading limits were appropriate to ensure that adequate criticality safety margins A OOOO O will be maintained. B OOOOO cO 000 10/1/97 URI SAQV 97-15; URI 96-04-02 LICENSEE Additional FSAR discrepancies conceming 1991,1992 modifications not 1 234 5 incorporated into the FSAR were identified as additional examples of UR! 96-04-02. .
A 0000 0 s00000 cO 000 10/1/97 Positive SAOV 97-15 NRC in general, the 1996 revision of the McGuire Updated Final Safety Analysis Report i 234 5 met the provisions of 10 CFR 50.71 and is therefore, currently in compliance with 10 CFR 50.71.
AOOOOO sD0000 c0 000 10/1/97 NCV 9715; NCV 97-15-02 LICENSEE A Non-Cited Violation was identified for the licensee's failure to evaluate the 1 234 5 suitability of the high efficiency particulate air filters prior to installing them in the Unit 1 and Unit 2 reactor buildings. The failure indicated a significant loss of control in preventing undesirable materialin the reactor building.
AOOOOO OOO c0 000
[Pl5NT SiiPPOFIT ~5 ?"
Sl 9/21/98 Positive IR98-08 NRC The chemistry management staff met the qualification requirements of Technical 1 234 5 Specification 6.3.1. Also, the chemistry technicians had been property trained for the duties they had been assigned as required by Technical Specification 6.4.
(Section R5.1)
A OOOOO OOOOO i cO 000 9/21/98 Positive IR98-08 NRC The meteorologicalinstrumentation had been adequately maintained and the 1 234 5 meteorological monitoring program had been effectively implemented. (Section R22) A OOOOO a00000 cO 000 9/21/98 Positive IR98-08 NRC Radiation and process effluent and environmental monitors were being maintained in 1 234 5 an operational condition to comply with Technical Specification requirements and Updated Final Safety Analysis Report commitments. (Section R2.1)
A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/23/98 Page 29 of 37 FOR PUBLlO RELEASE Last Updated: 9/2 t/98
McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/21/98 Positive IR98-08 NRC The licensee's water chemistry contre s program for ii.v Anna primary and secondary water quality had been effectively implemented, for those parameters 1234 5 reviewed, in aczcadae with Technical Specifications requirements and the Station Chemistry Manual for water chemistry. The collection of the samples was performed A .O O O O O in accordance with the licensee's chemistry sampling procedure. (Section R1.2) B DOOOO 9/21/98 Positive cG 000 IR98-08 NRC The licensee effectively maintained controls for radioactive materlat and waste processing. (Section R1,1) 1 234 5 A 0000 0 s00000 8/7/98 MISC cG 000 IR 98-07 NRC The respiratory protection program was being implemented as required by 10 CFR Part 20- Subpart H. Survey instrumentation had been adequately maintained.
1 234 5 A00000 B 00000 8/7/98 VIO cG 000 IR 98-07 NRC A violation was identified for failure to establish procedural guidance for degassing i 234 5 the Unit i volume control tank. This resulted in an unplanned, but monitored release to the environment.
AOOOOO s00000 8/7/98 Positive cO 000 IR 98-07 NRC The licensee was maintaining programs for controlling exposures as low as reasonably acheivable and continued to be effective in controlling overall collective 1 23 4 5 dose. All personnel radiation exposures to date in 1998 were below regulatory limits. AOOOOO B 00000 8/7/98 MISC cG 000 IR 98-07 NRC The licensee met 10 CFR 20 requirements for control of personnel rnonitoring 1 234 5 control of radioactive material, radiological posting, radiation areas, and high radiation areas.
AOOOOO a00000 8/7/98 MISC IR 98-07 cO 000 NRC The fire protection maintenance inspection and periodic test program was sufficient to verify operability of the auxiliary building fire protection water system.
1 234 5 A00000 s00000 cG 000 FROM: 10/t/97 TO: 11/23/98 Page 30 of 37 FOR PUBLIC RELEASE Last updated: 9/21/98 n .. .
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 5/30/98 Positive 98-06 NRC The licensee adequately complied with the access authorization and control of 1 234 5 personnel criteria of the Duke Power Company Nuclear Security and Contingency Plan Procedures. The Ecensee acted conservatively in reporting an access A .O O O O O -
authorization issue to the NRC.
OOOOO cO 000 4/10/98 Positive SAQV 98-03 NRC Readiness of the McGuire Emergency Offsite Facility to support a postulated 1 234 5 accident was good. The performance of a series of training drills to exerMe a new duty rotation for emergency manning was considered a continued example of proactive training in the area of emergency preparedness, incorporation of the AOOOOO Assistant Emergency Oper;tions FaciEty Director position was considered proactive B DDOOO in augmenting the emergency response effectiveness.
O OOO 4/18/98 Positive 98-03 NRC Locked high radiation doors were property controlled high radiation and 1 23 4 5 contamination areas were property posted, and radiological area survey maps were updated to accurately reflect radiological conditions in the respective areas.
A OOOOO e00000 c0 000 3/7/98 Positive 98-02 NRC Locked high radiation doors were property cont olled, high radiation and 1 23 4 5 contamination areas were property posted, and radiological area survey maps were updated to accurately reflect radiological conditions in the respective areas. AOOOOO e00000 cO 000 1/24/98 Strength SAOV 97-20 NRC A safeguards audit was thorough. complete, and effective in uncovering 1 23 4 5 weaknesses in the secondary system, procedures, and practices.
A 00000 sD0000 cO 000 1/24/98 Positive 97-20 NRC Random review of directives, plans, procedures, records, reports, and interviews 1 23 4 5 with appropriate individuals verified that safeguards procedures and documentation complied with 10 CFR Part 50. Changes to sections reviewed in the Nuclear Security and Contingency Plan did not decrease the effectiveness of the Plan.
AOOOOO OOO c0 000 t/24/98 Strength MAINT 97-20 NRC Maintenance 'and repair programs ensured the reliability of security related 1 234 5 equipment and devices. This area was considered a strerwfh in the security program. This was demonstrated by the responsiveness of dedicated maintenance personnel who repaired inoperable security equipment.
A OOOOO OOO cO 000 FROM: 10/1/97 TO: 11/23/98 Page 32 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/15/98 Positive 9841 NRC Based on the inspector's review of the vehicle barrier system procedures and 1 234 5 discussion with the licensee, the inspector concluded that the plans and procedures were acceptable for implementing the vehicle barrier system.
A .O O O O O -
e00000 cO 000 1/15/98 Positive 98-01 NRC The inspector determined that the licensee had installed the vehicle barrier at a 1 234 5 distance that would preclude an explosion from a bomb-laden vehicle from causing damage to vital targets required for the safe shutdown of the reactor.
A OOOOO ,
a00000 cO 000 1/15/98 Positive 98-01 NRC The inspector concluded that the vehicle banier system, using a combination of 1 234 5 gates, jersey barriers, cable rod system, cable, buildings, and terrain, was an acceptable barrier capable of stopping a design basis vehicle traveling at the established speed prior to the vehicle penetrating the protected area perimeter and A OOOOO causing damage to vital equipment. The inspector concluded that the engineering staff had performed an appropriate analysis of the vehicle threat and had installed G OOOOO an acceptable vehicle barrier to counter the threat. O OOO t 1/12/98 Positive 97-18 NRC The results of an unannounced emergency preparedness augmentation drill 1 234 5 Identified that all facilities were manned within the required times. A dri!! critique was performed and identified several minor areas for improvement. The driD confirmed the licensee's ability to fully staff the requimd emergency preparedness areas.
AOOOOO (Section P4.1) B D000O cO 000 12/13/97 Strength 97-18 LICENSEE Following identification of tampering at the Unit 2 containment personnel airlock seals, the licensee performed inspections of vital plant areas. No additional 1 234 5 indications of tampering were identified. Further reviews of this event were detailed in inspection Report 50-369.370/97-19. A OOOOO B 00000 cO 000 12/13/97 Dositive 97-18 NRC The results of an unannounced emergency preparedness augmentation drill 1 234 5 identified that all facilities were manned within the required times. A drill critique was performed and identified several minor areas for improvement. The dria confinned the licensee's ability to fully staff the required emergency preparedness areas.
A OOOOO g
c0 000 12/6/97 VIO 97-19, VIO 97-19-01 NRC The licensee failed to make the required one hour Event Notification to the NRC 1 234 5 Operations Center resulting in a violation.
A 00000 g00000 c8 000 FROM: 10/1/97 TO: 11/23/98 Page 34 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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McGUIRE 23-NoW.
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/1/97 Positive 97-12 NRC Licensee successfu!!y demonstrated its ability to implement the Radiological 1 234 5 Emergency Plan in response to a simulated accident.
A .D O G O G ~
B 00000 cG 000 10/1/97 Positive 97-15 NRC The licensee had effectively implemented a program for shipping radioactive 1 234 5 materials required by the NRC and Department of Transportation regulations.
A00000 B 00900 cG 000 ;
L l
l FROM: 10/1/97 TO: 11/23/98 Page 36 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
McGUIRE 2344ov-se DATE TYPE (s) SEC,SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMM Template Codes: SALP Functional Areas: ID Code:
1A OP5 RATION PERFORMANCE - Normal Operations LICENSEE UCENSEE 18 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 20 MATERIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A HUMAN PERFORMANCE - Work Performance SAOV SAFETY ASSESSMENT & OV 3B HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE- Work Environmert 4A ENGINEERING / DESIGN - Design dB ENGlNEERING/ DESIGN - Engineering Support 4C -ENG!NEERING/ DESIGN - Programs and Processes SA PRODLEM IDENTIFICATION & SOLUTION -Identification 58 PROBLEM IDENTIFICATION & SOLUTION - Analysis SC PROBLEM IDENTIFICATION & SOLUTION - Resoluton Eels are apparent violations of NRC requirements that are being considered for escalated enforcemetit action in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action"(Enforcement Policy) NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the Eels and the PIM entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
URis 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 violation.
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.
i FROM: 10/1/97 TO: 11/23/98 Page 37 of 37 FOR PUBLIC RELEASE Last Updated: 9/21/98
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