ML20196G943

Advises of Planned Insp Effort Resulting from Insp Planning Meeting,Completed on 981102.Details of Insp Plan for Next 4 Months Encl

ML20196G943
Person / Time
Site:	North Anna
Issue date:	12/02/1998
From:	Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 9812080164
Download: ML20196G943 (30)

Text

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December 2, 1998 Virginia Electric and Power Company ATTN: Mr. J. P. O'Hanlon Senior Vice President - Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060

SUBJECT:

INSPECTION PLAN - NORTH ANNA POWER STATION

Dear Mr. O'Hanlon:

On November 2,1998, the NRC staff completed an inspection resource planning meeting. The staff conducted this review fer all operating nuclear power plants in Region ll to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performanca 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 4 months. We have prov;ded 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 inspect;ons, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. 'Ne will notify you at least 3 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 on Enclosure 1, such as in the security and radinlogical 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 NRC and Virginia Power and Electric Company. This material will be placed in ths Public Document Room.

1 0FFICIAL COPY

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9812000164 981202 PDR ADOCK 05000338 G

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VEPCO' 2

We will inform you of any changes to the enclosed inspection plans. If you have any questions, please contact me at (404) 562-4550.

Sincerely, Orig signed by Robert C. Haag Robert C. Haag, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 50-338,50-339,72-16 License Nos.: NPF-4, NPF-7, SNM-2507 Enciosures:

1. Inspection Plan

2. Plant issues Matrix cc w/encis.:

J. H. McCarthy, Manager Nuclear Licensing and Operations Support Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 W. R. Matthews Site Vice President North Anna Power Station -

. P. O. Box 402 Mineral, VA 23117 E. S. Grecheck Site Vice President -

Surry Power Statiori Virginia Electric & Power Company 5570 Hog Island Road

' Surry, VA 23883 Executive Vice President Old Dominion Electric Cooperative 4201 Dominion Boulevard Glen Allen, VA 23060 cc w/encls continued: See page 3 l

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VEPCO 3

cc w/encis.: Continued l

Virginia State Corporation Commission f

Division of Energy Regulation i

P. O. Box 1197 I

Richmond,VA 23209 County Administrator l

Louisa County P. O. Box 160 Louisa, VA 23093

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Donald P. Irwin, Esq.

j Hunton and Williams.

j 951 E. Byrd Street Richmond, VA 23219-4074 i

State Health Commissioner Office of the Commissioner Virginia Department of Health P. O. Box 2448 Richmond, VA 23218 Attomey General Supreme Court Building 900 East Main Street Richmond,VA 23219 l

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VEPCO 4

Distribution w/encls:

L. Plisco, Ril R. Aiello, Ril P. Fillion, Ril R. Gibbs. Ril W. Stansberry, Ril -

F. Wright, Ril N. Kalyanam, NRR PUBLIC NRC Resident inspector U.S. Nuclear Regulatory Commission 1024 Haley Drive Minera!, VA 23117 NRC Resident inspector U.S. Nuclear Regulatory Commission Surry Nuclear Power Station 5850 Hog Island Road Surry, VA 23883 1

l OFFICE Ril:DRP Ril:DRP SIGNATURE

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NAME PHOPKINs LGARNER DATE 12/ /98 1h/98 12/ /98 12/ /98 12/ /98 12/ /98 12/ /98 COPY 7 YES NO 4S) NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD CoIY DOCUMENT NAME: G:\\NAPLAN

W NORTH ANNA INSPECTION PLAN INSPECTION TITLE / PROGRAM NUMBER OF PLANNED TYPE OF INSPECTION /

PROCEDURE /

AREA INSPECTORS INSPECTION COMMENTS TEMPORARY DATES INSTRUCTION mummmmmmmmmmmmmmmmmm 4

JANUARY 1999 NON-INSPECTION Y2K AUDIT ACTIVITY BY NRR AND REGIONAL STAFF IP 92903 FOLLOWUP -

1 JANUARY 1999 REGIONAL INITIATIVE-ENGINEERING SSEl FOLLOWUP IP 83750 OCCUPATIONAL 1

FEBRUARY 1999 CORE RADIATION EXPOSURE IP 92904 FOLLOWUP - PLANT 1

FEBRUARY 1999 REGIONAL INITIATIVE -

SUPPORT REVIEW FIRE PROTECTION MANUAL ACTUATION DESIGN IN EMERGENCY SWITCH GEAR ROOM

Page: 1 of 6 Date: 12/02/1996 I United States Nuclear R;gulatory Commiss.uin Time: i6:s02, negion si PLANT ISSUE MATRIX NORTH A.JNA By Primary Functional Areo Funcitono Template Date Source Areo ID Type Codes item Description 10/03/1998 1998008 Prl' ENG NRC NEG Prl: 4C in the Maintenance Rule recovery plan, the limited discussions of condition monitoring of seiect systems, the Sec~-

Sec SC omission of certain components b the PRA model and, the poor technicaljustification of the rsec.ulation system's success criterio were negative observations.

Tec 10/03/1998 1998008 Prf: ENG NRC POS Pri: SC Rodiant energy shields b the Unit 1 confonvnent were properly modified to address the Thermo-Log Sec:

Sec: 2B cesMy h Tec 10/03/1998 1o98008 Pri: ENG NRC STR Prl: 4C The licensee occomplished sufficient corrective actions under the Maintenance Rule recovery pion to conclude 3,c.

3,c. g that the Molntenance Rule goal setting and performance criteria for the systems in the probabilistic risk ossessment ( PRA) model were consistent with their safety significance. The risk ranking methodology was o Tec strength.

10/03/1998 1998008 &2 Pri: ENG Ucensee NCV Prl: 20 A non-cited violation was identified for Unit 1. Train A reactor vessellevet Indico' ion system (RVLIS) dynamic flow -

u Sm

Sec, range indication not being property normolized.

Ter:

09/26/1998 1998005 Pr! ENG NRC NEG Prl: 4C The licensee's process for screening potential changes to determine if a 10 CFR 50.59 safety evoluotion was Sec-Se required coes not include on independent review of the initial safety screening.

A Tec 09/26/1998 1998005 Pri: ENG NRC NEG Prl: SA A weakness in it e licensee's self-ossessment was identified due to lock of consistency h the methodology, 3,c, 3,c, reporting of resu.ts, documenting identified deficiencies and trocking corrective actions.

Tec 09/26/1998 1998005 Prl: ENG NRC NOED Prl: 4A Two examples of failure to update the UFSAR were identified. Discretion was exercised for this violation of 10 CFR 3,c.

$g.

50.71(e) and was not cited (EA 98-500).

Tec f

07/26/1998 1998005 Prl: ENG NRC POS Prl: 4A Design ond installation of AFW efectricot equipment was in accordance with good industry proctices, NRC Sec:

Sec:

reirements and N EceMng boss h AM system meets N We fobe cMeh Tec I

k ltem Type (Compliance,Foltowup,Other), From 09/01/1998 To 12/02/t998 t

Page:. 2 of 6 Dole: 12/02/1998 United Stat:s Nuclear R;gulatory Commission Timeo6:s0:29 Region il PLANT ISSUE MATRIX NORTH ANNA By Primary Functional Area Functional Template Date Source Areo ID Type Codes item Description 07/26/1998 1998005 Prt ENG NRC POS Prt 4A The electrical calculations reviewed were found to be occurate and consistent with Icensing commitments. The

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3,c.

electrical calculation qudity was good.

Ter:

07/26/1998 1998005 Prt ENG NRC POS Prt 4A instrument setpoint calculations used on opproved methodology and considered oppropriate sources of Instrumentotton inaccuracies.

3,c.

3,c.

I Tet I

09/26/1998 1998005 Prt ENG NRC POS Prt 4C The design control procedures complied with the requirements of 10 CFR 50.59 and 10 CFR 50. Appendix B.

[

Sec-Sw.

Criterion E1. The Instructions / checklist for preparation of 10 CFR 50.59 safety evoluotions were hdepth and thorough. The design control program / procedures are good.

Tet 07/26/1998 1998005 Prt ENG NRC VeK Prl: 4A The quality of AFW mechanical design calculations was poor. Numerous dscrepancies were identifed between Sec-Sec.

v ri us design calculottons and design documents. Cdculation quality was identifed as a weckness.

Ten r

e 09/26/1998 1998005 4 1 Prt ENG NRC VIO lV Prt 4C A violation was identified for failure to construct the Unit 1 AFW pipe supports in occordance with the design l

Sec:

Sec:

1. N 'M***"IS-Tet 09/26/1998 1998005 42 Prt ENG NRC VIO IV Prt 2A The material cond! tion of piping and housekeeping in the AFW pipe tunnels was very poc.. A violation was See: MAINT Sec:SC identified for failure to take effective corrective action to oddress corrosion problems in the Unit 2 AFW pipe funnel identified previously in September.1996.

Tec 09/26/1998 1998005-03 Prt ENG NRC VIO lV Prt 2B A violation of 10 CFR 50.55(o) was kjentifed for foilure to include safety-related AFW pipe supports installed in the

$,c. MAINT Sec.

AFW pipe tunnels in the 151 program.

Tet 10/03/1998 1998008 Prl: MAINT NRC POS Prl: 2A A slow stort test surveillance of the 2H emergency diesel generator met procedural and technical specification Sec'-

Sec: 2B requiremen s. Oveoil testing was corefutty and property performed. A work request to repair a fuel oil doy tank switch was oppropriately Issued.

l Tet l

r item Type (Compliance. Followup.Other). From 09/01/1998 To 12/02/1998 t

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

Page: 3 of 6 Dole:12/02/1996 United States Nuclear Regulatory Comm. ion iss um.: i6:so:29 Region il PLANT ISSUE MATRIX NORTH ANNA By Primary Functional Area Functional Template Date Source Areo ID Type Codes item Description 10/03/1998 1998008 Pri: MAINT NRC POS Prt 2B Observation of the new IJ EDG fon/ hub ossemth and review of the completed work pockage and associateci test reds coteN MonWWocemnt was prope@ psfamed See:

Sec:

Tec t

in/03/1998 1998008 Prt MAINT NRC POS Prt 2B Inservice examination octMties were performed in a skillful manner. Discontinuities were property recorded and Sec-Sen evoluoted by knowledgeable examiners using opproved procedures. Records for the C steam generator tube eddy current examinations and piping component flow occeleroted corrosion uffrosonic exominchons were Tec complete, and evductions/occeptance of examination results were conducted in accordance with opplicable procedures, technicd specificofions and industry standards.

I 10/03/1998 1998008 Prl: MAINT NRC POS Prl; 4B The licensee performed wdkdown inspections of service water system stainless steel piping os required to idenhfy,

Sec' Sm 58 through-wolllookogs caused by microbiological induced Corrosion (M!C). Radiographs were taken as required I

to monitor MIC growth in the system. Improvements in chemicd oddtion were being investigated and four Ter: 2A fout kh diameter 316L stainless steel lines on both units were planned to be replaced with improved materids in late 1998 and during 1999.

09/26/1998 1998005 Prt MAINT NRC NEG Prt 2D AFW pump surveillance test procedures permitted operation of the pump inexcess of the piping design pressure Soc-M and reDef vovte setpoint during surveillance testing.

Tec i

i 09/26/1998 1998005 Prt MAINT NRC POS Prt 2A The mater!d condtion of AFW equipment and components examined was good as well as housekeeping in the Sec-Sec-gener I creos around equipment and components in the AFW pump houses and moin steam volve houses.

i Ter:

09/26/1998 1998005 Prt MAINT NRC POS Prt 2A The molntenance of the auxiliary feedwater system components hos been good. The AFW system hos t

"C' P' Sec:

See: 2B Tec f

09/26/1998 1998005 Prt MAINT NRC STR Pri: 2A The mo!ntenance progrom for the 4 kV circuit breakers was considered a strength. This conclusion was based on Sec-Sm a go d procedures, refurbishment of breakers of ten-year maximum intervds, and the exce!!ent proctice of periodlC funCilond testing of all Control Circuit devices.

i Tec 10/03/1998 1998008 Prt OPS NRC POS Prt 1 A Technicd specification (TS) requirements for core otterations were satisfied during the upper internois removd Sec-Se fr m the reoctor vesset. The core citerations checklist property reflected TS requirements.

t Tec l

Item Type (Compliance. Followup Other) From 09/01/1998 To 12/02/1998 m

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Poge: 4 of 6 Dofe: 12/02/1996 United Stat::;s Nuclear R:gulatory Commission

- l Time:i6:s0 m negion in PLANT ISSUE MATRIX NORTH ANNA Dy Primary Functional Area Functional Template Date Source Areo ID Type Codes item Description 10/03/1998 1998008 Pri: OPS NRC POS Prt 1 A The Unit I residuct heat removd system was property ofigned and in good condition. System components

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3,c.

reflected plant drowings and operating procedures and were property labeled.

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Ter:

10/03/1998 1998008 Prt OPS NRC POS Prl:1A The Unit i shutdown for refueling was carefu!!y performed. Shutdown octivities were performed in occordance Sec:

Sec:30 with plant procedures. Operofors had received specid shutdown training which propored them wet.

Ten

\\

10/03/1998 1998008 Prt OPS NRC POS PrtIB Operator response to errotic automatic operation of the B steam generator moln feedwater regufoting volve P

"PU Sec*-

See: 2B were effective os evidenced by continued sofisfactory automatic operation of the MFIN for the remainder of Ten the inspection period.

10/03/1998 1998008-01 Prt OPS Ucensee NCV Prt 3A A non-cited violation was identf.ed for fatture to properly position two isolation vdves ossociated with the reactor Sec*-

Sec M coolant system (RCS) level standpipe. The volves were closed when they should have been open which caused RCS standpipe level to be fou!ty. Although the Rcensee had not begun the drain down evolution when the Ter:

problem was identified and corrected, the inspectors were concerned with the event because two operators e

had signed the procedure os completed when the action to ensure ffw vdves were open was not performed 10/03/1998 1998008 Prt OPS NRC POS Prt IB The ' Unit 2 reactor trip and subsequent startup activities were carefully controlled. The operating crew was Sec: MAINT Sec: 2A well-prep red for the unit restort. AB systems and components operated as designed.

Ter:

10/03/1998 1998008 Prt OPS NRC POS Prt 2A At the beginning of the Unit I refueling outage. containment conditions were good in that contoinment cootings See: MAINT Sec:

were intact. boron deposits were minimal and areas were typically free of dirt and debris.

Ter:

I 09/26/1998 1998005 Prt OPS NRC NEG Prt 4C A weakness was identified in the licervee's process for completion of operablity evoh>otions. The final operobrity See: ENG See: 5B evofuation which determined the effect of missing pipe supports on the operability of the AFW system was not completed unta more than six weeks offer the initid missing support was identified.

Ten 7

5 09/04/1998 1998301 Prt OPS NRC NEG Prt 38 During the initial Rcense examination operating tests, weoknesses were noted in the crecs of determining foil

(

Sec-Sec*.

pipe temperature with a leaking PORV. identification of radiological posting requirements, reluctanco of ROs to l

take manuol action without SRO prior opprovat and the willingness nf two of the four crews to enter Techn! cot i

Tec Specification 3.0.3 when.'t was preventoble.

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ltern Type (Compliance, Followup.Other) Frorn 09/01/1998 To 12/02/1998 I

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Page: 5 of 6 Unit;d Stat:s Nuclear R;gulatory Commission Dole: 12/02/1998 nme: i6:so:29 Region si PLANT ISSUE MATRIX NORTH ANNA By Primary Functional Areo Functional Template Date Source Areo ID Type Codes item Description 07/04/1998 1998301 Prt OPS NRC POS Prt 3A Control room activities were observed during the examination validotion and examination weeks. The operator.s 0

3' Sec:

Sec: 1A Ter:

09/04/1998 1998301 Pri: OPS NRC POS Pri: 3B Fourteen of fifteen condidates possed the initial Ecense eromination. Overoll performance on the operating test Sec-SM M was satisfactory with strengths noted in the areas of 3-way communication, crew briefs and annunclotor response procedure usoge Tec 09/04/1998 1998301 Prt OPS NRC POS Prt 38 in general the examiners found the os-submitted written Ecense irfiol examination und operating tests met the S -

Sec K requirements of NUREG-1021 with one exception in the oreo of JPM followijp questions which was noted to need improvement. The examination quality was improved as compared to the 1996 examination submittol.

Ter:

6 5

10/03/1998 1998008 Prt PLTSUP NRC POS Prt IC The licensee maintained on effective program for the control of Equid and gaseous radiooctive effluents from l

Sec-

Sec, the plant. The amount of actMfy released from the plant in liquid and gaseous effluents hos remained stable l

over the lost severd years and the rodiction doses resuffing from those releases were o small percent of i

Tec regulatory Emits.

10/03/1998 1998008 Prt PLTSUP NRC POS PrtIC The licensee had compiled with the sompting. onofyticd and reporting requirements for the tod;ological f

Sec-

Sec, environmental monitoring pr gram, the environmental sompting equipment was being weg maintained. and the monitoring program was effectively implen ented.

Tec t

10/03/1998 1908008 Prt PLTSUP NRC POS Prt IC The licensee s water chemistry control program for monitoring pnmary and secondary water quality had been

~

Sec-Sec x Implemented in accordance with technical specification requirements and the Electrical Power Research Institute guidelines for pressurized water reactor water chemistry. The licensee responded wet to unexpected i

Tec elevoted dose rates during the April 1998 refueling outoge by developing and imp lementing on effective program to reduce personnel exposure.

I item Type (Compliance. Followup.Other). From 09/01/1998 To 12/02/1998

Page: 6 of 6 Unit;d States Nuclear R;gulatory Commiss. ion Time: i6:soa, Dole:12/02/1998 PLANT ISSUE MATRIX By Primary Functional Areo i

Legend Type Codes:

Template Codes:

Functional Areas:

BU Bulletin 1A Normd Operations OPS Operoflons CDR Construction IB Operoflons During Transients MAINT Maintenance DEV Deviation IC Programs and Processes ENG Engineering

^,

eel Escolated Enforcement item 2A Equipment Condition PLTSUP Plant Stoport IFl Inspector follow-up item 2B Programs and Processes OTHER Other LER Ucensee Event Report 3A Work Performance UC Ucensing issue 3B KSA MISC Miscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 48 Engineering Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion SA identification NON Notice of Non-Conformance SB Analysis P21 Port 21 SC Resolution POS Poslftve ID Codes:

SGI Sofeguard Event Report NRC NRC STR Strength Self Self-Revealed URI Unresolved item i

Ucensee Ucensee VIO Violation WK Weckness

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Eels are opporent violations of NRC Requirements that are being considered for escdoted enforcement oction in accordance with the T,enerd Statement of Policy and Procedure for NRC Enforcement Action'(Enforcement Policy). NUREG-1600. However, the NRC has not reached its find enforcement decision on the issues identified by the Eels ond the PIM entries may be modfied when the final decisions are mode.

l URis are unresolved items about which more information is required Io determine whether the issue in question is on acceptable iterrt a deviation, o nonconformance, or o violation. A URI may also be o potential violation that is not likely to be considered for escolated enforcement action. Howmer, the NRC has not reached its finoi conclusions on the issuess and the PIM entries may be modfied when the find conclusions are mode.

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NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 8/10/98 Positive IR 98-04 01.2 NRC Tag outs for the hydrogen ana!yzer and the feedwater and charging systems were 1 234 5 property performed. All components were in their required positions and were property labeled. The scope of the tag outs was appropriate for the v.t rk performed.

A OOOOO a00000 cO 000 6/29/98 NCV IR 98-03 04.3 SELF An NCV was identified for failure to properly align the fiquid waste system. An 1 23 4 5 operator improperty marked procedure steps as not applMable which resulted iri the failure to rep;sition two radioactive liquid waste system valves.

A OOOOO s00000 cO 000 6/29/98 VIO IR 98-03 04.1 LICENSEE A VIO was identified for failure to property implement a system tag out. A drain 1 23 4 5 valve in the outside recirculaton spray system was mistakenly opened and tagged in lieu of the required drain valve in the residual heat removal system. Nso, operators AOOOOO failed to initiate corrective actions when the problem was initially discovered.

OOO cO 000 6/23/98 Positive

!R 98-03 01.3 NRC The Unit 2 reactor startup and subsequent power ascension were well controlled.

1 234 5 Operators received focused training on startup activities prior to the actual startup.

Personnel congestion in the control room during the power ascension was noted.

A OOOOO a00000 cO 000 6!29/98 Positive IR 98-03 01.2 NRC TS requirements, including those for source range neutron flux monitor and 1 234 5 containment integrity, were met during core onload acitivities. Core onload was c' refully controlled by knowledgeable personnel.

A OOOOO a

B 00000 cO 000 5,18/98 Positive MAINT IR 98002 02.3 NRC AT T HE BEGINNING OF THE UNIT 2 REFUELING OUTAGE, CONTAINMENT 1 23 4 5 CONDITIONS WERE GOOD. CONTAINMENT COATINGS WERE INTACT, BORON DEPOSITS WERE MINIMAL, AND AREAS WERE TYPtCALLY FREE OF AOOOOO DEDRIS AND DIRT.

OOOOO cO 000 5/18/98 Positive IR 98002 02.1 NRC OPERATOR RESPONSE TO A FEEDWATER TRANSIENT-A LOSS OF PROPER 1 234 5 UNIT 1 FEEDWATER HEATER CASCADING OPERATION - WAS IN ACCORDANCE WITH PLANT PROCEDURES-A OOOOO B B0000 c0 000 FROM: 10/1/97 TO: 8/31/98 Page 2 of 19 FOR PUBLIC RELEASE Last Updated: 9/21/98

NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 5/18/98 VIO IR 98002 012 SELF A VIOLATION WAS IDENTIFIED FOR A LICENSED OPERATOR'S FAILURE TO 1 234 5 PERFORM A TEST PROCEDURE STEP. AN INSIDE RECTRCULATION SPRAY PUMP WAS INADVERTENTLY STARTED AFTER THE OPERATOR USED A OOOOO' INFORMATION ON A MAGNETIC SIGN TO COMPLETE A STEP IN L!EU OF ACTUALLY PERFORMING THE STEP. THE LICENSEE INITIALLY FAILED TO B OOOOO RECOGNIZED THAT THE LACK OF PROCEDURE GUIDANCE ON THE USS OF MAGNETIC SIGNS WAS AN IMPORTANT CONTRIBUTOR TO THE VIOLATION.

O OOO 4rN98 Positive MAINT IR 98001 04.1 NRC TECHNICAL SPECIFICATION REQUIREMENTS WERE MET WHEN A UNIT 1 1 234 5 SERVICE WATER PUMP WAS REMOVED FROM SERVICE. OPERATOR S WERE KNOWLEDGEABLE OF LIMITING CONDITION FOR OPERATION AND A OOOOO REOUIRED SYSTEM PRESSURES.

s00000 cO 000 4/3/98 Positive IR 98001 01.4 NRC THE DECISION TO REMAIN AT A REDUCED POWER LEVEL WHILE THE B 1 234 5 CONDENSATE PUMP WAS REPAIRED DEMONSTRATED CONSERVATIVE MANAGEMENT OVERSIGHT BY AVOIDING PLANT CONFIGURATIONS THAT AOOOOO COULD CAUSE STEAM GENERATOR TRANSIENTS OR CHALLENGE THE PLANT'S OPERATION B OOOOO cO 000 2/23/98 Positive IR 97012 04.1 NRC TRAINING EFFECTIVE IN PREPARATIONS OF AN OPERATOR WHO 1 234 5 PERFORMED LOCAL OPERATION OF TRIP AND BYPASS BREAKERS.

OPERATOR DISPLAYED GOOD TECHN!OUES; HOWEVER, COMMUNICATION A OOOOO WAS INFORMAL.

s00000 c0 000 2/23/98 Negative IR 97012 E2.1 NRC AUXILIARY OPERATOR KNOWLEDGE OF THE UNIT 2 AUXlLIARY FEEDWATER 1 234 5 TERRY TURBINE STEAM SUPPLY VALVE LEAKAGE NEEDED IMPROVEMENT.

GREATER EQUIPMENT HEALTH AWARENESS REQUIRED-A OOOOO B 00000 cO 000 2/23/98 Positive ENG 1R 97012 O2.1 NRC FREEZE PROTECTION PROCEDURES WERE THOROUGH AND EFFECTIVELY 1 234 5 IMPLEMENTED. OVERALL CONDITION OF THE HEAT TRACE SYSTEM WAS ADEOUATE. ENGINEERING EVALUATED LONG STANOING HEAT TRACE AOOOOO SYSTEM DEFICIENCIES AND INITIATED EFFORTS TO IMPROVE SYSTEM PERFORMANCE.

D DDDOO cO 000 1/12/98 Positive ENG IR 97-11 M1.3 NRC A UNIT 1 CONTROL ROOM CHILLER PUMP AND VALVE TEST MET TECHNICAL 1 234 5 SPECIFICATIONS REQUIREMENTS. TEST INSTRUMENT WAS CALIDRATED.

PROCEDURES WERE FOLLOWED AND INDEPENDENT VERIFICATIONS WERE A OOOOO CORRECTLY PERFORMED.

OOOOO cO 000 FROM: 10/1/97 TO: 8/31/98 Page 3 of 19 FOR PUBLIC RELEASE Last updated: 9/21/98

NORTH ANNA c2-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 12/1/97 Positive MAINT IR 97-09 07.1 NRC THE DEVIATION REPORT (DR) ASS!GNMENT REVIEW TEAM AIDS IN THE 1,34 5 EFFECTIVE RESOLUTION OF DEVIATION REPORTS. REPEAT DRS AND MAINTENANCE RULE DRS WERE IDENTIFIED AND TASKED TO THE PROPER A OOOOO ORGANIZATIONS FOR ACTION.

B 00000 c0 OGO-12/1/97 Positive MA!NT 1R 97-09 01.5 NRC THE LICENSEE PROFERLY IMPLEMENTED AND ADHERED TO THE 1 234 5 COMPENSATORY ACTIONS DISCUSSED IN THE NOTICE OF ENFORCEMENT DISCRETION ISSUED ON OCTOBER 29.

A GOOOO B 00000 cO 000 11/24/97 Positive IR 97-08 04.1, M1.5 NRC LICENSED OPE 9ATORS, SHIFT TECHNICAL ADVISORS AND SCHEDULERS 1 234 5 UNDERSTAND!N0 OF THE R!SK ASSESSMENT TOOLS FOR REMOVAL OF EOUTPMENT FROlw SERVICE WAS GOOD.

A GOOOO s00G00 cO 000 11/24/97 Positive IR 97-08 04.1 NRC LICENSED OPERATORS UNDERSTOOD THEIR SPECIFIC DUTIES AND 1 234 5 RESPONSiDfLITIES FOR IMPLEMENTING THE MAINTENANCE RULE.

A00000 a00000 cO 000 10/20/97 Positive PLT SUP IR 97-07 O2.1 NRC THE OVERALL CONDITION OF THE AUXfLIARY SHUTDOWN PANELS WAS 1 234 5 GOOD. DIENNtAL TRAINING ON THE AUXiltARY SHUTDOWN PANELS WAS THOROUGH.

AOOOOO B 00000 cO 000 10/20/97 Positive IR 97-07 01.3 NRC UNIT 1 SAFEGUARDS OPERATOR SUCCESSFULLY COMPLETED 1 234 5 SURVEfLLANCE REQUtREMENT. THE OPERATOR WAS KNOWLEDGEADLE OF SAFEGUARD OPERATOR ROUND DUTIES AND PERFORMED ROUTINE A OOOOO ROUNDS PROPERLY.

g cO 000 10/20/97 Positive PLT SUP IR 97-07 01.2 SELF LICENSEE AGGRESStVELY PURSED THE ORIGIN OF SMOKE DISCOVERED 1 234 5 ON AUGUST 20 AND ESTABLISHED AN HOURLY FIRE WATCH UNTIL THE PRODABLE CAUSE FOR THE SMOKE WAS IDENTIFIED ON AUGUST 23.

A OOOOO a00000 cO 000

!MAINTEUANUE 'IN5NPdl I

FROM: 10/1/97 TO: 8/31/98 Page 4 of 19 FOR PUBLIC RELEASE Last Updated: 9/21/98

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NORTH ANNA 02-Dec 98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 5/18/9@

Positive IR 98002 M1.2 NRC THE CHANNEL FUNTIONAL TEST FOR POWER RANGE INSTRUMENTS N41 1 234 5 AND N42 MET TECHNICAL SPECIFICATION REQUIREMENTS AND WAS CAREFULLY PERFORMED. THE TECHNICIANS UTILIZED SELF-CHECKING AOOOOO-PRACTICES.

OOOOO cO 000 5/18/98 Positive ENG IR 98002 Mt.1 NRC WORK PERFORMED ON A UNI f 1 MAIN FEEDWATER PUMP. THE SOLID 1 23 4 5 STATE PROTECTION SYSTEM, AND THE 2H EMERGENCY DIESEL GENERATOR (REPLACEMENT OF FAN BLADES) WAS PROFESSIONAL AND AOOOOO THOROUGH. WORK INSTRUCTIONS WERE PRESENT AND WERE USED.

MAINTENANCE SUPERVISION AND ENGINEERING PERSONNEL MONITORED B DD000 THE JOBS.

cO OOO 5/18/98 Negative OPS IR 98002 01.3 SELF A UNIT 2 REACTOR COOLANT SYSTEM DRAINDOWN PROBLEM RESULTED 1 234 5 FROM A LACK OF ATTENTION TO DETAIL BY WORKERS WHO HAD LEFT A PIECE OF TAPE ON A VENT FLANGE. THIS TAPE BLOCKED A TEMPORARY A OOOOO VENT LINE PATHWAY DUR!NG INSTALLATION OF THE VENT LINE.

OPERATIONS DETERMINED THAT THE REACTOR VESSEL WAS NOT B BOOOO PROPERLY VENTING DURING INITIAL DRAINDOWN OPERATIONS.

OPERTIONS ANALYSIS OF THE IMPROPER VENTING WAS APPROPRIATE.

CO OOO 4/3/98 Positive IR 98001 Mt.3 NRC OVERALL UNIT 1 CHARGING PUMP MAINTENANCE ACTIVITIES WERE GOOD.

1 23 4 5 ENHANCEMENTS IN MAINTENANCE WORK PRACTICES WERE IMPLEMENTED DURING PUMP SEAL REPAIR. THESE INCLUDED A DEDICATED PROCEDURE AOOOOO READER TO OVERSEE THE EVOLUTION AND PERFORMANCE OF THE SEAL REBUILD IN A BETTER WORK ENVIRONMENT, A DECON BUILDING ROOM B DDDOO VERSES THE PUMP CUBICLE.

c0 000 4GS8 Positive OPS IR 98001 M1.2 NRC THE OPERABILITY TEST FOR THE STEAM GENERATOR PORV'S WAS

• 23 4 5 PROPERLY PERFORMED. TS AND OTHER TECHNICAL REQUIREMENTS WERE SATISFIED.

1. CDGOO 3 00000 cO 000 43'98 Positive OPS IR 98001 M1.1 NRC COMMUNICATIONS. SELF-CHECKING PRACTICES. AND PROCEDURES 1 234 5 ADHERENCE DURING THE UNIT 1 TRAIN B SOLID STATE PROTECTION SYSTEM TEST WERE GOOD.

AOOOOO e00000 cO 000 2/23/98 Negative IR 97012 E2.1 NRC AUXILIARY FEEDWATER STEAM SUPPLY LINE STEAM TRAPS, WHIC'H 1.2 3 4 5 REMOVE CONDENSATE JURING PUMP OPERATION, WERE NOT lN THE PREVENTIVE MAINTENANCE PROGRAM.

p.OOOOO aD0000

O OOO FROM: 10/1/97 TO: 8/31/98 Page 6 of 19 FOR PUBLlC RELEASE Last Updated: 9/21/9 8

NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 2/23/98 Positive OPS IR 97012 M1.2 NRC MAINTENANCE ASSOCIATED WITH THE N31 SOURCE FtAI4GE INSTRUMENT 1 234 5 WAS PROPERLY PERFORMED BY KNOWLEDGEABLE l&C TECHNICIANS.

A00000' s00000 cO 000 2/23/98 Weakness IR 97012 Mt.2 NRC DURING TESTING OF DELTA-T/TAVE CHANNEL. INSPECTORS NOTED 1 234 5 COMMUNICATIONS BETWEEN TECHNICtANS AND SELF-CHECKING PRACTICES COULD DE IMPROVED. FORMAL APPROACHES NEEDED.

AOOOOO a00000 cO 900 2/23/98 Negative OPS IR 97012 M1.1 NRC THE PRACTICE OF USING PRIMARY GRADE WATER WHEN INSTALLING AND 1 234 5 REMOVING TEST GAUGES WAS AN EFFECTIVE MEANS FOR MINIMlZING THE POTENTIAL FOR SPREADING CONTAMINATION; HOWEVER, THE PRACTICE A OOOOO WAS NOT CONSISTENTLY IMPLEMENTED.

OOOOO cO 000 1/12/98 NCV IR 97-11 E1.1 L!CENSEE A NON-CITED VIOLATION WAS IDENTIFIED FOR TWO MISSED TECHNICAL 1 234 5 LER 338/97-009-00 SPECIFICATION REOUfRED SOLID STATE PROTECTION SYSTEM LOGIC SURVEILLANCE TESTS. THE LICENSEE IDENTIFIED THE DEFICIENCY AND A OOOOO TOOK APPROPRIATE ACTIONS.

OGOOO cO 000 12/1/97 Positive OPS IR 97-09 Mt.1 NRC REPAlR OF 1H EDG ENGINE COOLING FAN WAS EFFECTIVELY PERFORMED 1 234 5 AS EVIDENCED BY THE ACCEPTABLY LOW FAN SHAFT VIBRATION MEASUREMENTS AND NO LEAKAGE FROM RADIATOR DURING POST MAINT A OOOOO TEST.

B 000OO c0 000 11/24/97 Weakness ENG IR 97-08 M7.1 NRC THE LICENSEE DtD NOT HAVE A SYSTEMATIC APPROACH FOR CLOSING 1 234 5 OUT ITEMS IN SELF-ASSESSMENTS. THIS FAILURE TO TRACK AND FOLLOW-UP ON SELF-ASSESSMENT ITEMS WAS AN INDICATED WEAKNESS.

A OOOOO a00000 cO 000 11/24/97 Strength ENG IR 97-08 M7.1 NRC SELF. ASSESSMENTS OF THE MAINTENANCE RULE (MR) PPOGRAM WERE 1 234 5 THOROUGH AND A PROGRAMMATIC STRENGTH. THE ASSESSMENTS CONTINUED TO VALIDATE FAILURES TO ADEQUATELY IMPLEMENT THE MR-A00OOO PROGRAM R PROGRAM THROUGH IDENTIFICATION OF NUMEROUS FINDING AND NEEDED ENHANCEMENTS TO THE PROGRAM.

B DDDDD cO 800 FROM: 10/1/97 TO: 8/31/98 Page 7 of 19 FOR PUBLIC RELEASE Last Updated: 9/21/98

NORTH ANNA 02-Oec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 11/24/97 Positive ENG IR 97-08 M2.1 NRC IN GENERAL, WALKDOWN OF SSCs DETERMINED THAT THEY WERE BEING 1 234 5 APPROPRIATELY MAINTA!NED.

A 00000' s00000 cO 000 11/24/97 Strength ENG IR97-08 Mt.7 NRC THE STRUCTURES PROGRAM ESTABUSHED UNDER THE MAINTENANCE 1 234 5 RULE WAS COMPREHENSIVE AND EFFECTIVELY IMPLEMENTED.

A00000 e00000 cO 000 11/24/97 Negative ENG IR 97-08 M1.7 NRC ONE WEAKNESS CONCERN!NG THE APPROPRIATENESS OF THE 1 234 5 RELIABILITY PERFORMANCE CRITERIA FOR THE POST ACCIDENT HYDROGEN REMOVAL SYSTEM WAS IDENTIFIED.

A OOOOO aD0000 cO 000 11/24/97 Negative ENG IR 97-08 M1.6 NRC ONE WEAKNESS CONCERNING THE LOGGING OF FAILURES AGAINST THE 1 234 5 APPROPRIATE FEG FOR THE HIGH HEAD SAFETY INJECTION SYSTEM WAS IDENTIFIED.

AOOOOO aD0000 cO 000 11/24/97 Positive ENG IR 97-08 M1.6 M1.7 NRC IN THE MAINTENANCE RULE PROGRAM. EQUIPMENT RELIABfLITY AND 1 234 5 UNAVAILABlLITY DATA WERE BEING PROPERLY CAPTURED FOR THE STRUCTURES, SYSTEM, AND COMPONENT REVIEW.

A OOOOO eD0000 cO 000 11/24/97 Positive ENG IR 97-08 Mt.4 NRC THE APPROACH TO BALANCING RELIABILITY AND UNAVAILABILITY MET THE 1234 5 INTENT OF (a) (3) OF THE MAINTENANCE RULE.

A 00000 sD0000 cO 000 11/24/97 Positive ENG IR 97-08 M1.3 NRC THE PERIODIC EVALUATION PERFORMED BY THE LICENSEE MET THE 1 234 5 REQUIREMENTS OF SECTION (a)(3) OF THE MAINTENANCE RULE.

A00000 e00000 c0 000 FROM: 10/1/97 TO: 8/31/98 Page 8 of 19 FOR PUBLIC RELEASE Last Updated: 9/21/98

- -, -,,, - ~ ~ - - - -, _

_--,---,,------n--

NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 11/2497 Negative ENG IR 97-08 M1.2.b.4 NRC THE LICENSEE HAD NOT ESTABLISHED CONDITION MONITORING 1 234 5 PERFORMANCE CRITERIA FOR SEVERAL SSC's FOR WHICH THE PERFORMANCE CRITERIA WAS ZERO FAILURES.

A OO OO O-a00000 cO 000-11/24/97 Negative ENG IR 97-08 M1.1 NRC REQUIRED STRUCTURES, SYS, AND COMPONENTS WERE INCLUDED WITHIN 1 234 5 SCOPE OF THE MAINTENANCE RULE WITH THE EXCEPTION OF TWO STRUCTURES AND SEVERAL ANNUNCfATORS. ENFORCEMENT DISCRETION A OOOOO WAS USED REGARDING THESE DEFICIENCIES.

OOOOO cO 000 10/20/97 Weakness CPS IR 97-07 M1.7 SELF LICENSEE ADEOUATELY PERFORMED IMMEDIATE CORRECTIVE ACTIONS 1 234 5 TO CLEAR UNIT 2 OUTStDE RECIRCULATION SPRAY PUMP 2-RS-P-2A SEAL HEAD TANK ALARMS. CORRECTIVE ACTIONS TO PRECLUDE THESE A OOOOO ALARMS HAVE BEEN INEFFECTIVE AND THE FREQUENCY OF THESE ALARMS HAVE INCREASED.

B OOOOO c0 000 10/20/97 NCV IR 97-07 M1.6 LICENSEE LICENSEE ADEQUATELY PERFORMED NECESSARY CORRECTIVE ACTIONS 1 234 5 TO RESOLVE THE INADEOUATE MOUNTING OF AN OUTSIDE RECtRCULATION SPRAY PUMP SEAL COOLER.

AOOOOO g00000 cO 000 10/20/97 Positive OPS tR 97-07 M1.4 NRC OPERATOR ADEOUATELY MONITORED OPERATION OF THE SDO DIESEL 1 234 5 DURING THE QUARTERLY OPERADILITY TESTING. EXTERNAL CONDITION OF THE DIESEL SBO BUILD!NG HOUSEKEEPING WAS SUPERIOR.

A OOOOO B 00000 c0 000 10/20/97 Positive IR 97-07 M1.3 NRC REPLACEMENT OF THE N41 POWER RANGE DETECTOR GAIN ADJUSTMENT 1 234 5 POTENTIOMETER AND POST MAINTENANCE OPERABillTY TESTING WERE EFFECTIVE-A OOOOO e00000 cO 000 10/20/97 VIO IR 97-07 Mt.2 SL IV NRC THE TS 3.3.3.1 REQUIREMENTS WERE SATISFIED DURING THE CALIBRATION 1 234 5 OF THE A VENT STACK RADIATION MONITOR. A VIOLATION WITH TWO EXAMPLES WAS IDENTIF!ED FOR FAILURE TO FOLLOW APPROVED A OOOOO MAINTENANCE PROCEDURES.

OOOOO c0 000 FROM: 10/1/97 TO: 8/31/98 Page 9 of 19 FOR PUBL'C RELEASE Last Updated: 9/21/98

NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 10/20/97 Positive IR 97-07 Mt.1 NRC CONTROL ROOM AIR HANDLING MAINTENANCE WAS PERFORMED 1 234 5 SATISFACTORILY. MAINTENANCE PRACTICES BY WORKERS AND SUPERVISION WAS IN KEEPING WITH CLOSE PROCEDURAL ADHERENCE-AOOOOO e00000 cO 000' I5 GINSURlNIA D W M 5l 8/10/98 Negative IR 98-04 E3.1 NRC The licensee's statisticalty-based and engineering judgement operability 1 234 5 determination for the main steam radiation monitors was weak. Issues such as instrument sensitivity and instrument drift were not thoroughly addressed.

A OOOOO a00000 cO 000 6/29/98 Positive IR 98-03 E1.2 NRC The licensee responded in a conservative manner to a recently discovered.

1 234 5 potentialty generic, reactor vessel head material problem.

A00000 s00000 cO DOO 5/18/98 NCV IR 98002 E6.2 LICENSEE THE SAFETY CONSEQUENCE OF AN INCOMPLETE P-8 SURVEILLANCE WAS 1 234 5 LOW BECAUSE THE P-8 LOGIC WOULD HAVE PERFORMED AS REQUIRED.

AN ASSOCIATED LICENSEE EVENT REPORT WAS ACCURATE AND TIMELY-AOOOOO CORRECTIVE ACTIONS TO PREVENT RECURRENCE WERE REASONABLE. A NON-CITED VIOLATION WAS IDENTIFIED.

B OOOOO cO 000 5/18/98 Positive IR 98002 E8.1 LICENSEE THE LICENSEE'S 10 CFR PART 21 EVALUATION FOR DETERM!NING 1 23 4 5 POTENTIAL DINDING DUE TO OVERSIZED AUXILIARY FEEDWATER TERRY TURBINE GOV VALVE STEMS WAS THOROUGH. THEY ALSO AOOOOO APPROPRIATELY DEMONSTRATED THE ACCEPTABILITY OF THE INSTALLED VALVE STEMS FOR CONTINUED USE.

B DDDDO cO 000 5/18/98 NCV IR 98002 E1.1 LICENSEE A NON-CITED VIOLATION WAS IDENTIFIED FOR INADEQUATE TEOT 1 2 34 5 PROCEDURES FOR UNIT 2 AND 2 "C" CHARGING PUMP UNDERVOLit.GE RELAY 27Z. A REQUIRED UNIT 1 TECHNICAL SPECIFICATION SURVEILLANCE AOOOOO WAS MISSED.

OOOOO cO 000 2/23/98 Positive IR 97012 E2.2 NRC LICENSEE PERFORMANCE IN OBTAINING REQUIRED CORE OPERATING 1 2 34 5 LIMITS REPORT INFORMATION FOR UNIT 2 WAS GOOD AND IN ACCORDANCE WITH APPROVED PROCEDURES. ENGINEERS WERE A OOCOO PROFICIENT WITH THE INCORE EQUIPMENT OPERATION AND FAMILAR WITH THE PROCEDURAL REQUIREMENTS.

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NORTH ANNA e

02-Dec-es DATE TYPE (s)

SEC. SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 1/12/98 Positive IR 97-11 E8.1 NRC RESULTS OF THE ROOT CAUSE EXAM: NATION FOR THE 1H EMERGENCY 1 234 5 DIESEL GENERATOR COOLING FAN FAILURE APPEARED REASONABLE.

FOLLOWUP ACTIONS FOR THC FAILURE WERE ACCEPTABLE.

AOOOOO.

a00000 cO 000-1/12/98 Positive IR 97-11 E2.S NRC INDEPENDENT SPENT CUEL STORAGE INSTALLATION CONCRETE PAD 1 234 5 CONSTRUCTION RECORDS AND RELATED DOCUMENTS WERE ADEQUATE.

CONCRETE TICKETS WERE WITHIN SPECIFICATION LIMITS. VENDOR AOOOOO SUBMITTALS FOR CONCRETE TRUCKS MET SPECIFICATION REQUIREMENT OOOOO cO 000 1/12/98 Posdve IR 9711 E2.4 NRC DURING INDEPENDENT SPENT FUEL STORAGE INSTALLATION 1 234 5 CONSTRUCTION CONCRETE WAS PLACED BY SKILLED PERSONNEL WITH GOOD WORKMANSHIP. THE CONCRETE WAS PLACED AND TESTED IN ACCORDANCE WITH SPECIFICATIONS AND INDUSTRIAL PRACTICES AND AOOOOO CODES.

D D0000 cO 000 1/12/98 Negative IR 97-11 E2.3 NRC INADEOUATE CONCRETE REBAR PLACEMENT WAS IDENTIFIED FOR THE 1 234 5 INDEPENDENT SPENT FUEL STORAGE INSTALLATION. REBAR AROUND THE LIGHT BOXES AND IN THE TOP MAIN REBAR LAYER WERE IMPROPER. THE AOOOOO INSPECTORS WERE CONCERNED WITH THE CONSTRUCTION PRACTICES AND OUALITY CONTROLS THAT ALLOWED THESE DEFICIENCIES TO B OOOOO OCCUR.

cO 000 1/12/98 Posittve IR 97-11 O12 NRC THE ENGINEERING EVALUATION TO ADDRESS H GH WATER t E4LS IN THE 1 234 5 HEATER DRAIN TANKS WHICH WAS LIMITING POWER TO 99% PROVIDED i

APPROPRIATE BASES FOR REDUCING THE NUMBER OF OPERATING CONDENSATE PUMPS FROM 3 TO 2. THE UNIT RETURNED TO 100% WITH AOOOOO SUFFICIENT FEEDWATER PRESSURE MARGINS TO PRECLUDE A B OOOOO FEEDWATER PUMP TRIP.

O OOO l

12/1/97 Positive MAINT IR 97-09 E4.1 NRC LICENSEE ADEOUATELY PURSUED OFF-CENTERL7 BORING OF STAINLESS 1 234 5 STEEL PIPING. NO PRIOR USE OF THE PIPING WAS FOUND DURING A HISTORICAL REVIEW OF 3/4 INCH SS PIPING PREFABRICATION.

A OOOOO a00000 cO 000 11/24'97 Negative IR97-08 E4.1 NRC SYSTEM ENGINEER'S UNDERSTANDING OF MAINTENANCE RULE AND ITS 1 234 5 IMPLEMENTATION WERE GENERALLY WEAK. VIRGINIA POWER MAINTENANCE RULE PROGRAM WAS CORPORATE DRIVEN WITH MINIMAL AOOOOO RELIANCE ON THE SYSTEM ENGINEERS FOR IMPLEMENTATION.

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NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 11/24/97 Positive IR 97-08 E4.1 NRC IN GENERAL, SYSTEM ENGINEERS' TECHNtCAL KNOWLEDGE OF THEIR 1 234 5 SYSTEMS WAS SOUND. RECENT REASSIGNMENTS CONTRIBUTED TO A LACK OF SYSTEM SPECIFIC KNOWLEDGE.

A OOOOO B 00000 c0 000 11/24/97 Negative OPS IR 97-08 M1.5 NRC SOME MAINTENANCE RULE FUNCTIONAL EQUIPMENT GROUPS DID NOT 1 234 5 RECEIVE A RISK INFORMED ASSESSMENT.

A 00000 B 00000 cO 000 11/24/97 Positive OPS IR 97-08 Mt.5 NRC THE LICENSEE HAD EFFECTIVELY IMPLEMENTED A COMPREHENSIVE 1 234 5 PROCESS FOR PERFORMING SAFETY ASSESSMENTS FOR ON LINE MAINTENANCE ACTIVITIES A OOOOO B 00000 cO 000 11/24/97 Weakness MAINT IR97-08 M1.2.b.5 NRC PRA KNOWLEDGE OF INTERVIEWED WORKING GROUP MEMDERS WAS 1 234 5 WEAK. DUE TO A LACK OF UNDERSTANDING OF THE NA PORTH ANNA PRA, THE MAINTENANCE RULE WORKING GROUP DID NOT APPEAR TO DE ABLE AOOOOO TO COMPENSATE FOR THE PRA'S LIMITATIONS. A PERMANENT PRA MEMBER WAS ASSIGNED TO THE WORKING GROUP DURING THE B OOOOO INSPECTION TO CORRECT THIS WEAKNESS.

O OOO 11/24/97 Positive MAINT IR97-08 M1.2.b.5 NRC THE RIGOR AND DEPTH OF DISCUSSIONS DUR!NG AN ODSERVED 1 234 5 MAINTENANCE RULE WORKING GROUP MEETING WERE APPROPRIATE FOR THE MATTERS DISCUSSED-A OOOOO B 00000 cO 000 11/24/97 Weakness MAINT IR97-08 M1.2.b.2 NRC THE PLANT WAS BEING SAFELY OPERATED IN CONSIDERATION OF RISK.

1 234 5 M t.2.b.3, M1.2.b.4, M t.5 LICENSEE & NRC IDENTIFIED S!GNIFICANT PRODLEMS IN THE PRA.

DECAUSE OF THIS, THE TEAM COULD NOT DETERM!NE THE QUALITY OF A OOOOO MAINTENANCE RULE IMPLEMENTATION WITH REGARD TO RISK RANKING.

GOAL SETTING AND PERFORMANCE CRITERIA, AND ADEQUACY OF THE B OOOOO LICENSEE'S RISK ASSESSMENT TOOLS' cO OOO 10/20/97 Positive IR 97-07 E2.4 NRC INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) SOfL 1 234 5 COMPACTION AND TEST RESULTS WERE ACCEPTABLE. THE PROCEDURd5 USED AND THE WORK PERFORMED FOR THE SOIL COMPACTION OF THE A OOOOO ISFSI WERE ADEOUATE. LAB TESTS FOR THE SOIL COMPACTION DY VIRGtNIA POWER WERE RELIABLE.

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SMM CODES 10/20/97 Positive IR 97-07 E2.2 NRC LICENSEE HAS TAKEN THE NECESSARY ACTIONS TO REPAIR SUSPECTED 1 234 5 MICRODIOLOGICALLY INDUCED CORROSION (MIC) SERVICE WATER SYSTEM PIPING. LICENSEE APPROPRIATELY ADDRESSES THE ON GOING A OOOOO MIC ISSUE AND THE PROGRAM PERFORMS REPAIRS IN ACCORDANCE WITH THE ASME CODE. WHEN MIC WAS FOUND IN INCONEL WELD REPAIRS. TWO B DDDGO INCONEL WELD REPAIRS WERE SELECTED FOR MORE FREQUENT MONITORING ANDINSPECTIONS.

CO OOO 10/20/97 Positive IR 97-07 E2.1 NRC LICENSEE TOOK POSITIVE STEPS TO ADDRESS AN INDUSTRY ISSUE 1 234 5 INVOLVING SKID-MOUNTED EMERGENCY DIESEL GENERATOR PtPING WELDS.

AOOOOO e00000 cO 000 10/20/97 Positive IR 97-07 E1.1 NRC AUXILIARY FEEDWATER SYSTEM DESIGN BASIS DOCUMENT MADE A 1 234 5 SfGNtFICANT CONTRIBUTION TO UNDERSTANDING THE DESIGN BASIS FOR THE SYSTEM AND IS A USEFUL TOOL FOR ENGINEERS AND OTHER A OOOOO ORGAN!ZAT!ONS.

OOOOO I

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cO 000 IPLANT SUP3 ORT 75YY25Yl 8/18/98 Positive IR 98-07 P4.2.b.S NRC A thorough critique process was followed with a well-prepared presentation to site 1 234 5 management that summarized the rnost significant emergency preparedness exorcise observations.

AOOOOO eD0000 cB 000 8/18/98 Positive IR 98-07 P4.2.b.4 NRC The local emergency operations facility Recovery Manager and staff were effective 1 234 5 in providing timely emergency notifications, correct and timely protective area recommendations, and meaningful radiological reports to the state and counties.

AOOOOO s00000 cO 000 8/18/98 Positive IR 98-07 P4.2.b NRC The operations support center was effective in providing repair teams as directed by 1 234 5 the technical support center. Command and control of technical support center operations were proficient. The control room simulator crew property analyzed plant A OOOOO cuiJure and responded with timely and correct actions.

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SMM CODES 8/18/98 Negative IR 98-07 P4.2.b NRC Better intergroup communication within the technical support center wouk1 improve 1 234 5 development of miti,~ 0, strategies.

A00000 a00000 cO 000 8/18/98 Positive IR 98-07 P4.1 NRC The scenario developed for the exercise was effective for testing the integrated 1234 5 emergency response capability for the onsite and offsite emergency organizations.

A00000 B 00000 cO 000 8/10/98 Positive IR 98-04 S4 NRC The security force personnel possessed appropriate knowledge to carry out their 1 234 5 assigned duties and responsibilities, including response procedures, use of deadly force, and armed response tactics AOOOOO B 00000 cO 000 8/10/98 Positive IR 98-04 S1 NRC The licensee exhibited positive control of packages, personnel and vehicles entering 1 234 5 the protected area.

A0000O s00000 cO 000 8/10/98 Positive IR 98-04 S6 S7 NRC The licensee provided strong support for the Physical Security Program. The 1 23 4 5 effectiveness of licensee management relative to the security program was adequate. The licensee's program anafysis of documented security problems was AOOOOO adequate.

OOOOO cO 000 8/10/98 Positive MAINT IR 98-04 S2 NRC The licensee's security facilities and eaufpment were deterrnined to be very wett 1 234 5 maintained and reliable. The excellent maintenance support was the major factor to continued operability of the detection and assessment equipment.

A OOOOO B 00000 cO 000 8/10/98 Positive IR 98-04 R1.2 NRC The licensee had established procedures for Independent Spent Fuel Storage 1 234 5 instaffation related activities which were consistent with good radiological control practices and that those procedures were followed during preoperational testing.

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NORTH ANNA 02-Dec-98 DATE TYPE (s)

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SMM CODES 8/10/98 Positive IR 98-04 RI.1 NRC The licensee developed and implemented a comprehensive action plan for reducing 1 234 5 personnel exposure from the elevated dose rates in the plant foffowing the Unit 2 refueRng outage.

AOOGGO a00000 cG 000 8/10/98 Positive IR 98-04 R1.1 NRC Maximum Individual radiation exposures were controlled to levels which were well 1 234 5 within the licensee's administrative timits and the regulatory limits for occupational dose specified in 10 CFR 20.1201(a). There was an overali decreasing trend in the AOOOOO personnet exposuras and the licensee was generally successfulin meeting goals for ALARA.

aOOOOO cG 000 6/29/98 Positive IR 98-03 P2.1 P2.2 NRC Site emergency response facilities, equipment and the off-site siren system were 1 234 5 maintained satisfactority A 0G00 0 e00000 cG 000 6/29/98 Positive IR 98-03 P7.1 P7.2 NRC Emergency Preparedness aucits were comprehensive, organized, objective, and 1 23 4 5 satisfied the requirements in 10 CFR 50.54(t). Emergency Prepardeness drill comments were satisfactorify tracked and resolved in a timely manner.

A OOOOO 1

s00000 l

cG 000 S/29/98 Negative IR 98-03 P5.1 NRC Requ6 red Emergency Preparedness Shift Technical Advisor training and curriculum 1 234 5 had been omitted from the program guide for emergency prepardness training.

Actual training provided to the shift technical advisors was at an acceptable level.

AOOOOO Emergency Response Organization lesson plans contained sufficient information for position training.

sOOGOO cG 00O 6/29/98 VIO IR 98 03 Rt.2 l

LICENSEE The licenses had failed to perform an adequate radiological survey on a camera 1 234 5 prior to releasing the camera from the radiological control area, in that, the survey failed to detect the presence of contamination on the camera. A violation was AOOGOO identified for failure to conduct an adequate contamination survey.

OOO cG 00O 6/29/98 Negative ENG IR 98-03 Rt.1 NRC The licensee was generally successfulin meeting established as low as is 1 234 5 reasonably achievable goals but unexpected results from shutdown chemistry controls resulted in elevated dose rates from the reactor coolant system. The AGOOOO outage as low as is reasonably achievable goal was exceeded.

OOO cG 000

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NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 6/29/98 Positive IR 98-03 Rt.1 NRC Maxirnum individual radiation exposures were controlled to levels whic were well 1 234 5 within the licensee's adrninistrative lirnits and the reg'Jatory limits for occupational dose specified in 10 CFR 20.1201(a).

A OOOOO s00000 cO 000 6f29/98 Positive IR 98-03 Rt.1 NRC The licensee property rnonitored and contro!!ed personnel radiation exposure during 1 234 5 the Unit 2 refueling outage and posting of area radiological conditions were in accordance with 10 CFR 20.

AOOOOO s00000 cO 000 5/18/98 Positive OPS 1R 98002 F1.1 NRC THE FIRE TEAM PROPERLY RESPONDED TO A FIRE DRILL IN THE AUXILIARY 1 234 5 BOILER ROOM. FIRE TEAM MEMBERS WERE KNOWLEDGABLE AND FAMILIAR WITH THE FIRE FIGHTING EOUtPMENT. THERE WAS CONFUSION AOOOOO ABOUT THE PROPER RADIO CHANNEL TO USE. PROPER CONTINGENCY ACTIONS WERE PRESENTED DURING THE DRILL. THE COMMUNICATIONS B OOOOO PROBLEM WAS CORRECTED BY THE END OF THE INSPECTION PERIOD.

O OOO 5/18/98 Positive OPS IR 98002 R1.4 NRC THE LICENSEE PROPERLY MAINTAINED THE CONTROL ROOM EMERGENCY 1 234 5 HABITIABILITY SYSTEM AND PERFORMED REQUIRED SURVEILLANCES TO DEMONSTRATE SYSTEM OPERABILITY.

AOOOOO a00000 cO 000 5/18/98 Positive OPS IR 98002 Rt.3 NRC THE ON-SITE METEROROLOGICAL SURVE!LLANCE PROGRA'4 WAS 1 234 5 IMPLEMENTED IN ACCORDANCE WITH UPDATED FINAL SAFETY ANALYSIS REPORT COMMITMENTS AND TECHN! CAL SPECIFICATION REQUIREMENTS.

A OOOOO B 00000 cO 000 4/3G8 Positive IR 98001 S5.2 NRC SECURITY FORCE WAS TRAINED IN AN EXCELLENT MANNER.

1 234 5 A00000 g00000 cO 000 4/3/98 Positive IR 98001 S3.2 NRC RANDOM SAMPLE OF SECURITY PLAN tMPLEMENTING PROCEDURES AND 1 234 5 SECURITY CONTINGENCY PLAN IMPLEMENTING PROCEDURES ADEQUATELY MET THE PHYSICAL SECURITY PLAN COMMITMENTS AND AOOOOO PRACTICES.

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NORTH ANNA 02-Dec-98 DATE TYPE (s)

SEC. SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 4/3/98 Positive IR 98001 Rt.1 NRC POSTING AND CONTROL OF HIGH RADIATION AREAS WAS APPROPRIATE.

1 234 5 SURVEY MAPS USED TO INFORM WORKERS OF RADIOLOGICAL CONDITIONS WERE ACCURATE AND WERE POSTED PROPERLY. SEVERAL AOOOOO EFFECTIVE PRACTICES SUCH AS THE USE OF COLOR CODED DOSE RATE MAPS AND LOW DOSE WAITING AREAS INFORMED WORKERS OF B OOOOO RADIOLOGICAL CONDITIONS.

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O OOO 2/23/98 Positive IR 97012 Rt.1 NRC RADIOLOGICAL LIOUID CATCH CONTAINERS WERE MAINTAINED IN VERY 1 234 5 GOOD CONDITION AND THEY WERE PROPERLY SUSPENDED AND SUPPORTED IN ACCORDANCE WITH APPROVED PROCEDURES.

AOOOOO B 00000 cO 000 1/12/98 Negative OPS IR 97-11 F4.1 NRC FIRE DRILL WEAKNESSES WERE NOTED INVOLVING COMMUNICATIONS AND 1 234 5 UNFAMILIARITY WITH DONNING TURN OUT GEAR. DURING A SUBSEQUENT FIRE DR!LL, THE INSPECTORS NOTED THAT THESE WEAKNESSES HAD A OOOOO BEEN CORRECTED. PERSONNEL HAVE RECEIVED INCREASED TRAINING ON DONNING TURN OUT GEAR.

B DOOOO cB 000 1/12/98 Negative IR 97-11 P4.1 LICENSEE AN EMERGENCY PREPAREDNESS EXERCISE WAS ADEOUATE. ONE 1 234 5 OBJECTIVE INVOLVING TREATMENT OF INJURED PERSONNEL WAS PARTIALLY MET. LICENSEE PLANS TO PROVIDE INCREASED COMMAND AOOOOO AND CONTPOL TRAINING FOR FIRST AfD TEAM SCENE LEADERS.

OOOOO cB 000 1

12/1/97 NCV MAINT IR 97-09 R4.1 LICENSEE AN NCV WAS IDENTIFIED FOR PERFORMING INADEOUATE SURVEYS OF 1 234 5 HYDROGEN RECOMBINER BLOWER 1-HC-HC-1. THIS RESULTED IN THE SPREAD OF LOW LEVELS OF RADIOACTIVE CONTAMINATION INTO A NON' AOOOOO RADIOLOGICALLY CONTROLLED WORK AREA. LICENSEE COUNSELED RP TECHNICIANS, PRESENTED LESSONS LEARNED TO THE RP STAFF AND B OOOOO NOTED THAT CAREFUL SURVEY OF POTENTIAL RAD ITEMS WAS VERY IMPORTANT.

C B OOO 10/20/97 Negative MAINT IR 97-07 S2.1 NRC WHILE THERE WERE A NUMBER OF WORK REQUEST INVOLVING THE 1 23 4 5 SECURITY DIESEL GENERATOR, PROBLEMS DID NOT AFFECT OPERABILITY. HOUSEKEEPING IN THE AREA WAS ACCEPTABLE.

AOOOOO B 00000 ca 000 10/20/97 Positive IR 97-07 Rt.2 NRC LICENSE HAS EFFECTIVELY IMPLEMENTED A PROGRAM FOR 1 234 5 TRANSPORTATION OF RADIOACTIVE MATERIALS PURSUANT TO DOT AND NRC REQUIREMENTS.

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NORTH ANNA 02-Dec-98 m

DATE TYPE (s) jSEC.SFA SOURCE (s)

ID'd ISSUE (s)

SMM CODES 10/20/97 Positive ENG IR 97-07 F1.1 NRC SILICONE FIRE BARRIER PENETRATION SEALS INCTALLED AT NORTH ANNA 1 234 5 MEET DESIGN REQUIREMENTS. COMPREHENSIVE FNGINEERING EVALUATIONS AND SURVEILLANCE INSPECTIONS HAD BEEN PERFORMED AOOOOO TO VERIFY INSTALLATIONS MET THE INTENT OF THE DESfGN REQUIREMENTS.

B OOOOO cG 000~

10/7/97 Strength IR 9710 S2.5.1 NRC THE ENGINEERING STAFF HAS PERFORMED AN EXCELLENT ANALYSIS OF 1 234 5 THE VEHICLE THREAT. A SUPERIOR VEHICLE BARRIER WAS INSTALLED TO COUNTER THE THREAT. THE DARRIER WAS AT A DISTANCE TO PRECLUDE A OOOOO AN EXPLOSION FROM A BCMB-LADEN VEHICLE. PLANS AND PROCEDURES WERE ACCEPTABLE FOR IMPLEMENTING THE VEHICLE DARRIER SYSTEM.

B OOOOO cG 000 l

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SMM CODES SMM Template Codes:

SALP Functional Areas:

ID Code:

1 OPERATIONVERFORM NCE' NoridaIOperaIions'

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LtdENSEE]UCENSEE 18 OPERATION PERFORMANCE - Operations During Transients ENG ENGINEERING NRC jNRC 1C ; OPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SELF iSELF-REVEALED 2A j MATERIAL CONDITION - Equipment Condition OPS OPERATIONS 2B l MATERIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A 4 HUMAN PERFORMANCE - Work Performance SAQV SAFETY ASSESSMENT & OV (HUMAN PERFORMANCE - KSA 3D 3C : HUMAN PERFORMANCE. Work Environment 4A ! ENGINEERINGDEStGN - Design 40 J ENGINEERINGDESIGN - Engineering Support 4C,ENGINEERINGDESIGN - Programs and Processes SA iPROBLEM IDENTIFICATION & SOLUTION - Identification l PROBLEM IDENTIFICATION & SOLUTION - Analysis 50 SC PROBLEM IDENTIFICATION & SOLUTION - Resolution j

i Eels are apparent vlotations of NRC requirements that are being considered for escalated enforcement action in accordance with the " General Statement of Policy a NRC Enforcement Action" (Enforcement Polley), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the Eels and th entries may be modified when the firtal decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to eith 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 nonconforma 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.

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