ML20198A771
| ML20198A771 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/02/1998 |
| From: | Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 9812170120 | |
| Download: ML20198A771 (32) | |
Text
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December 2, 1998 South Carolina Electric & Gas Company ATTN: Mr. Gary J. Taylor Vice President, Nuclear Operations Virgil C. Surnmer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065
SUBJECT:
INSPECTION PLAN - V. C. SUMMER NUCLEAR STATION
Dear Mr. Taylor:
On November 2,1998, the NRC staff completed an inspection resource planning meeting. The staff conducted this review for all operating nuclear power plants in Region 11 to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the staff has moved to February 1999 because of the agency's shift 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 provided the rationale or basis for each inspection outside the coreinspection program so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their tagoing and continuous nature.
Duribg this scheduling cycle, we will continue to focus some of our discretionary inspection effo t on the resolution of open inspection items. Therefore, we may conduct additional inspWlons, which are not listed on Enclosure 1, to close open inspection items that are ready
' to be resolved. We 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 radiological protection areas, and these inspections may not be announced.
Enclosure 2 contains a historical listing 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 South Carolina Electric & Gas Company. This material will be placed in /
the Pub'ic Document Room.
OFFICIAL COPY 9812170120 981202 PDR ADOCK 05000395 G PDR
$0/
p SCE&G 2 We willinform you of any changes to the enclosed inspection plan. If you have any questions, please contact me at (404) 562-4550.
l Sincerely,
- Orig signed by Robert C. Haag I l
[
Robert C. Haag, Chief i Reactor Projects Branch 5 ;
Division of Reactor Projects i L
Docket No. 50-395 i License No. NPF-12 ,
- l. .
Enclosures:
- 1. Inspection Plan
- 2. Plant issues Matrix l
cc w/encis.:
R. J. White - !
- Nuclear Coordinator Mail Code 802 i l S. C. Public Service Authority 1 Virgil C. Summer Nuclear Station I
- P. O. Box 88
' Jenkinsville, SC 29065 J. B. Knotts, Jr., Esq. l
- Winston and Strawn 1400 L Street, NW Washington, D. C. 20005-3502 I Chairman Fairfield County Council P. O. Box 60 Winnsboro, SC 29180 Virgil R. Autry, Director
! Radioactive Waste Management Dureau of Solid and Hazardous ,
E. Waste Management l S. C. Department of Health -. J and Environmental Control l l
2600 Bull Street -
l . Columbia, SC 29201 L
( :
cc w/encis.: Continued see page 3 p
l
s
! SCE&G 3 l
! cc w/encis.: Continued R. M. Fowlkes, Manager - ;
Operations - (Mail Code 303) '
South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station
(. P. O. Box 88 Jenkinsville, SC 29065 l- April Rice, Manager L Nuclear Licensing & Operating Experience (Mail Code 830) l Virgil C. Summer Nuclear Station
, P. O. Box 88 l Jenkinsville, SC 29065 l
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l SCE&G 4 Distribution w/encis.:
L. Plisco, Ril R. Aiello, Ril N. Economos, Ril P. Fillion, Ril G. Kuzo, Ril W. Stansberry, Ril M. Padovan, NRR PUBLIC NRC Resident inspector U.S. Nuclear Regv:atory Commission Route 1, Box 64 Jenkinsville, SC 20066 OFFICE Ril:DRP Ril:DRP SIGNATURE K)/A M,p NAME PHOPKINS LGARNER DATE 12/ /98 12//h/98 12/ 198 12/ 198 12/ /98 12/ /98 12/ /98 s,urrr -
YES NO dfEd NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECf)RD COPY DOCUMENT NAME: G:\SUMPLAN 1
O e
V. C. SUMMER INSPECTION PLAN INSPECTION TITLE / PROGRAM NUMBER OF PLANNED TYPE OF INSPECTION!
PROCEDURE / AREA INSPECTORS INSPECTION COMMENTS TEMPORARY DATES INSTRUCTION mmmmmmmmmmmmmmmm- -
IP 81700 PHYSICAL 1 JANUARY 1999 CORE SECURITY PROGRAM FOR POWER REACTORS IP 92903 FOLLOWUP - 1 JANUARY 1999 REGIONAL INITIATIVE -
ENGINEERING SNUBBERS AND PIPE SUPPORTS IP 92903 FOLLOWUP - 1 MARCH 1999 REGIONAL INITIATIVE -
ENGINEERING OPEN ITEM FOLLOWUP NON-INSPECTION 1 MARCH 1999 MAINTENANCE ACTIVITY TRAINING FOR RESIDENT STAFF Enclosure 1
- - _ __ = _ _ = _ __ ___ _
Page: 1 of 5 Date: 12/02/1998 United Statss Nucinar R:gulatory Comm. .ission ume: mse2 region u PLANT ISSUE MATRIX -
SUMMER By Primary Functiond Area >
Functional Temploie Tote Source Areo ID Type Codes Item Description 10/10/1998 1998008 Prt ENG Ucensee NEG Prt 4B The use of the engineering technicci A record (TWR) process to resolve o meter cohbrotion deficiency was Sec' Sec. "
inoppropriate in that the verification review process was circumvented. The licensee identified ihe failure to provide o verification review ond initiated a nonconformonce notice (NCN) which allowed for o second party Ter: verificction of the meter collbration in the NCN disposition.
t 09/05/1998 1998007 Pri: ENG NRC POS Prt 3A The snubber reducticn program was generolfy performed well. The computer input dato in the stress cdculation Sec'- Se W reviewed occurotely reflected the pipe icyout drowings. The modfications completed in the field were constructed in occordance with the drawirgs issued.
Tec
\
09/05/1998 1998007 Prt ENG NRC POS Prt 48 The licensee's use of the Engineering Information Request /Technied Work Record (TWR) process to resolve o Sec*- sex Turbine Driven Emergency Feedwater Water (TDEFW) pump test defichncy was less rigorous than other processes for resolving test deficiencies. The TWR did not require o verifl cation to be performed and documented. Good Tec Quolity Assurance oversight and identification of a test deficiency resolution issue was observed ;
09/05/1998 1998007 Prt ENG NRC POS Prt 4B The licensee s root cause evoluotion of gas intrusion into the A train Residuct Heat Removd System was thorough Sec- Sm M and identified the proboble causes of the problem. The proposed corrective actions odequately oddressed the probable causes.
Tec 09/05/1998 1998007 Prt ENG NRC POS Prt 4B The licensee did on exceBent root cause onolysis for foilures of Pocific Scientific Shock Arrestor mechanicd M* Sec SB snubbers. Dissemination of failure onofyses findings were transmitted to the industry b o timely manner ,
Tec ,
I 09/05/1998 1998007 Prt ENG NRC POS Prt 4C The licensee adhered to their setpoint control program in moking a change to the low flow s( point on the Sec-
- See: 2B primary coolant letdown monitor. The revised setpoint was in agreement with the assumption. mode in the Find ;
Sofety Andysis Report.
Ter:
09/05/1998 1998007-02 Prt ENG NRC URt Prt 4A incorrect pipe displacements shown on the pipe support drawings for the snubber reduction progrom.
See: See:
Ter:
t 10/10/1998 1998008 Prt MA!NT Ucensee NEG Prt 2B Prior to February 10.1996, the licensee foiled to perform surveillance testing of engineered safety feature Sec'- Sec*- ctivated carbon in verbatim compliance with their TS requirements. This deficiency was licensee identified and promptly corrected. Accordingty, the NRC is exercising discretion in occordance with Section VI.B.6 of the Tec Enforcment Policy and refraining from issuing a citation for this Severtiy Level IV violation Enclosure 2 Item Type (Compliance. Followup Other). From 09/01/1998 To 12/02/1998 '
i
. . _ _ _. m .
Page: 2 of 5
- Dofe: 12/02/1996 United Stat:s Nuclear Ragulatory Comm. .ission roe: msu2 Region n PLANT ISSUE MATRIX .
SUMMER By Primary Functional Area Functiono! Temp! ate Date Source Area ID Type Codes Item Description
- 10/10/1998 1998008 Prt MAINT NRC POS Prt 2B Observed engineered safeguards transformer differentiot retoy testing was satisfactory and performed in ,
Sec: Sec:3B cmhe WesW @mmts. h pasmneMM we h%m oN % '
Tec 10/10/1998 1998008 41 Prt MAINT NRC NCV Prt 2B Preventative maintenance activities were not established for the turbine driven emergency feedwater (TDEFW)
Sec~* See:48 cwen%me @ cmder N remm on mW h e oN wmmM system. The IDEFW pump foiled to reoch fuD speed during surviellonce testing due to on 1/P converter failure.
Tec 09/05/1998 1998007 Prt MAINT NRC POS Prt 1A The inspectors concluded that the licensee had oppropriotely considered potential piant risks and cho!!enges ,
Sec: See:5B before proceeding with maintenance on a pressurizer pressure fransmitter, ,
I Tec i i
09/05/1998 1998007 Prt MAINT NRC POS Prt 28 The review of service water surveillance test procedures reveofed that Operation and Mointenance Standards Sec*- Sec, (OM) Port 10 was fully implemented for volves in this system other than pressure relief volves. Problems with ;
pressure relief volve testing were discussed in LER 50-395/9800540 Tec 1 h 00/05/1998 1998007 Prt MAINT NRC POS Prt 2B An observed Anticipofed Transient Without Scram (ATWS) Mitigating System Actuation Circuitry (AMSAC)
See: Sec. operational test was performed in accordance with the approved procedure and the results met the ;
occeptonce criteria Tec i
09/05/1998 1998007 Prt MAINT NRC POS Prt 28 No concerns were identified during maintenance on the Heating Ventilation and Air Conditioning chillers and Sec- ~ Sec: M circuit breakers instrument colibrations: and volve testing. Control room persomel were routinely informed of i the status of ongoing maintenance activities. Maintenance personnel odhered to procedures. L Tec
! 09/05/1998 1998007 Prk MAINT NRC POS Prt 2B Following observations and reviews of surveillance testing for venting the Residual Heat Removal System the -
Sec: Sec:3A cias agreWm konsee NN systs was essWWed of got NohWe tests were thorough.
Tec ,
5 4
09/05/1998 1998007 Prt MAINT NRC POS Prk3A Corrective maintenance activities to investigate and correct the cause of the B Charging Pump inboord "
Sec~* me wm a s Usf e e te ces wm prope@oW Wmp See: 2B l shaft alignment was performed in a skillful manner, and pump vibrofion and post maintenance testing were Tet 38 oppropriotely conducted. -
v item Type (Compliance, Followup,Other), From 09/01/1998 To 12/02/1998 i
Poge: 3 of 5 Dote:12/02/1996 Unit:d Statss Nucinar R gulatory Comm. .ission rme: i6:Si:32 negion n PLANT ISSUE MATRIX .
SUMMER - By Primary Functional Areo '
Functiono! Template Date Source Area ID Type Codes item Description ,
07/05/1998 1998007-01 Prt MAINT NRC eel Prt2B Missed Technical Specification surveiRonce requirement to vent the rest 3uo! heof removal pump cosings. As port Sec- Sec. of the followup for tNs issue, the inspector will review tr =, LCR the licensee is planning to submit.
Tec ;
10/10/1998 1998008 Prt OPS NRC POS Prt 3A Operotions personnel took timely and oppropriate actions os required by Technical Specification 3.4A
- Relief t Sec- Vofves," n response to a leaking power operated relief volve Sec M Ter 10/10/1998 1998008 Prk OPS NRC POS Prt SA The Nuclear Sofety Review Committee (NSRC) meeting was in comptionce with TS 6.5.2 requirements for meeting Sec' Sec. '
quorurn NSRC Chairmon porticipation, and meeting agendo. The protions of the meeting observed by the 'f inspectors were technico!!y and performance oriented <
Tec t 09/05/1998 1998007 Prt OPS NRC NEG Prt 1 A The Station t og Book was not being maintained in the detoit that was recommended by the guidelines Sec-
- Sec. -
- established in me applicable station odministrative procedure in order to provide a complete and occurate record of plant Nstory. ,
Ter 09/05/1998 1998007 i Prk OPS NRC NEG Prt 3A A procedurc odherence Concern was identified concerning the waste line flush offer a waste monitor tonk 3,c, ' 3 ' .
release. When ensuring a demineralized water pump was operating. on operator did not explicitly verify this fact but utilized Ns knowledge that o pump was normally operating cod the foct that his turnover did not indicote 1 er otherwise.
09/05/1998 1998007 Pri: OPS NRC POS Prt IA A review of two sofety-related togouts for the B Centrifugo! Chorging Pump and the B Steam Generotor ;
Sec- Sec. blowdown sompte contoiment isolation volve found that they were property prepared and implemented. '
Tec i
09/05/1998 1998007 Pri: OPS NRC POS Prt 2A A system wolkdown found that the Component Cooling Wofer System and the Chilled Wotor System were in o l
Sec' Sec.~ condition to perform thelr design functions for normat and occident conditions. Plant housekeeping around the '
systems was good and components labeling was occurote.
Ter:
09/05/1998 1998007 prt OPS NRC POS Prt 3A The inspectors found the Intermediote Building operator and the Aux!!Iory Building lower level operotor to be Sec: See:3B knowledgeable and familiar with lin3ir ossgned duties and responsibilities during the conduct of rounds. I Tec Item Type (Compliance, Followup.Other), From 09/01/1998 To 12/02/1998 I
Page: 4 of 5 United States Nuclear R3gulatory Commission Dole:12/02/1996 -
nme; a:Si 32 eegion !! .
PLANT ISSUE MATRIX .
. SUMMER By Primary Functional Area Functiord Tempk2te Date Source Area ID Type item Description Codes "
09/05/1998 1998007 Pi PLTSUP NRC POS Pd IC The normal rodological practices and controls observed dunng the conduct of tours and a specific review of a B '
g $g 3 Chorging Pump Room hedth physics survey and anotysis of swipes were found to be acceptable.
Tec 09/05/1998 1998007 Prt PLTSUP NRC POS Prt IC Security personnel oppropriately demonstrated iteir response capabillfies and possessed oppropriote Sec- '
Sec: 38 cm @ M W @e m Medr@ M N WW% w phes, e of deadly force. ond armed response tactics.
Tec 09/05/1998 1998007 Prt PLISUP NRC POS Pd IC An offer hours fire drm. which included offsite participatiort demonstrated the drm objectives. The drill critique S
Sec M identifed severcl areas for enhancement.
Tec 09/05/1998 1998007 Prt PLISUP NRC STR Prt 1C The conduct of security and safeguards activities in access authorizotlort clorm stations, communications, Sec-
- Sec'. protected creo occess control of personnel, packages and materld, and vehicles were being implemented occording to regulatory requirements and Physico! Security Plan cvn u din ents. The access authorization Tec program was a strength to the security progrom.
1 09/05/1998 1998007 Prt PLISUP NRC STR Prt IC The security testing and maintenance program odequately ensure the reliobility of the security equipment and Sec: MAINf Sec:2B devices. The personnel search equipment, perimeter intrusion detection olds, and ossessment aids functioned Tec occording to the Physical Security Plan and implementing procedures. The closed circuit television images were excellent and considered a strength in tre security proQrom.
I l
l Item Type (Compliance. Followup,Other), From 09/01/1998 To 12/02/1998
Page:;- 5of 5 - Dolo:12/02/1998 United Stat s Nuclear R:gulatory Comm. .ission v e- msu2 -
PLANT ISSUE MATRIX: .
By Primary Funcilonal Area
+
I i
Legend -
Type Codes- Temploie Codes: Functional Areas-BU Bunetin 1A Normd Operations OPS Operations CDR Construction IB Operations During Transients MAINT Maintenance -
DEV Deviation 1C Programs and Processes ENG Engineering eel - Escalated Enforcement item 2A Equipment Condition PLTSUP Plant Support IFI inspector foaow-up item 28 Programs and Processes OTHER Other LER Ucensee Event Report 3A Work Performance LfC Licensing tssue 3B KSA MISC. Miscellaneous 3C Work Environment MV Minor Violation 4A Design ,
NCV NonCited Violation 4B Engineering Support NEG Negative 4C Progroms and Processes NOED Notice of Enforcement Discretion 5A identificotion NON Notice of Non-Conformance SB Anotysis -
P21 Port 21 SC Resolution POS Positive ID Codes: l SGI Sofeguard Event Report NRC NRC SIR Strength Self Self-Reveded I URI Unresolved item !
VIO Licensee Licensee Violation WK Weckness Eels are apparent vidations of NRC Requirements that are being considered for escdoted enforcement action in Occordance with the "Generd Statement of Poacy and Procedure for NRC Enforcement Action"(Enforcement Policy). NUREG-1600. However, the NRC has not reached its find enforcement decision on the issues identifled by the Eels and the PtM entries may be modified when the find decisions are mode.
UR!s are unresolved items obout which more information is required to determine whether the l'. sue in question is on acceptoble itern o deviatiort a nonconformance, or o !
violation. A URI moy dso be o potential violation that is not likely to be considered for escdoted enforcement oction. However, the NRC has not reached its fool conclusions on <
the issues, and the PIM entries moy be mocf*M wt'en the finot conclusions are mode. !
1 t
item Type (Compliance. Followup.Other) From 09/01/1998 To 12/02/1998
+
C% United Stat:s Nucirr Regul; tory Commi=idn
(%)
PLANT ISSUES MATRIX
..... by SALP Functional Area .
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA ID'd SOURCE (s) ISSUE (s) SMM CODES IOPERATIONS F7 MEW'l 7/25/93 Positive tR 98-06 NRC The inspectors found the Auxiliary BuNing Lower Operator to be taiowledgeable and familiar rith his assigned duties and responsibilities during his rounds. Good self-1 234 5 checking and proper communication with the control room was noted.
AOOOOO B 00000 7/25/98 Negative cO 000 IR 98-06 NRC Following the discovery of voiding in the A train Residual Heat Removal System, the licensee's initial corrective action to vent the gas and restore the system was 1 234 5 incomplete in that the RHR pump was not run. When the A train RPR pump was run two days later additional gas problems were observed. The licenser initiated a root AGGOOO cause evaluation to determine the cause of the voiding. B DDDDO 7/25/98 Positive IR 98-06 cO 000 NRC Operators acted promptfy in response to a circulating water pump trip, and prevented a more significant challenge to plant operatior 1 234 5 A 00G00 s30000 6/27/98 Positive c0 000 IR 98-05 NRC A review of corrective action for three equipment storage violations concluded that there had been significant improvement in the storage and control of materialin the 1 234 5 plant-AOOOOO a00000 6/27/98 Positive c0 008 IR 99-05 NRC The procedures used for the Operating Experience (OE) program were adequate in providing details for processing OE information. The Or program successfutty 1 234 5 processed, evaluated and dispositioned OE information .nto station programs and procedures. A OOOOO B 00000 6/27/98 Positive IR 9845 c0 000 NRC Management's commitment to improving operations was demonstrated by efforts to improve operational practices, procedures and programs through bench marking 1 234 5 j
visits by operations personne8 to other power plant fac3ities-AOOOOO ;
a00000 cE 000 FROM; 10/1/97 TO:8/3t/98 Page 1 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98 l
SUMMER 02-Dec-98 DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/27/98 Positive IR 98-05 NRC Ouality Assurance (OA) audit program procedure OSP-106 met applicable 1 234 5 requirements in 10 CFR 50 Appendix B, Critetton XVitt. The procedure provided sufficient instructions to perform audits which would independently assess plant programs and provide meaningful feedback to plant management. A sampling of A OOOOG five OA audits in the operations and engineering areas revealed that the QA audits B OOOOO were performed in accordance with the procedures. Audit Fnding closure documentation was readily available and justified that audit findings had been O OOO satisfactorily addressed.
6/27/98 Positive IR 98-05 NRC Root cause analyses were thorough and technically valid. Corrective actions 1 234 5 adequately addressed equipment, procedure and program problems, as well as, human performance issues. Corrective actions were tracked until completed. AOOOOO s00000 c0 000 6/27/98 Positive IR 98-05 NRC A review of Shift Supervisor and Shift Technical Adviser logs revealed that Condition 1 234 5 Evaluation Reports (CERS) and Nonconformance Notices (NCNs) were being written as required. Closed CERs and NCNs indicated items were being satisfactorily addressed.
A OOOOG B 00000 cO 000 6/27/98 Negative IR 98-05/lFI 98005-01 LICENSEE While licensee personnet demonstrated ownership of the corrective action program, 1 234 5 needed improvements have been identified in the Condition Evaluation Reporting process. Corrective Action Request (CAR) OA-CAR-91 1 (dated May 27 and June 8,1998) stated the station had a number of CERs which had exceeded the AOOOOO established disposition date for corrective actions. Additionally, corrective action B D0OOO due dates had not been established for some CERs.
O OOO 6/27/98 Positive IR 98-05 NRC A licensed operator simu!ator requalification exam scenario observed was 1 234 5 chaffenging and well conducted. The examination critique was thorough and provided a comprehensive assessment of crew and individual competencies. A OOOOO e00G00 cO 00O ,
6/27/98 Positive IR 98-05 NRC A detailed system walkdown of the Emergency Diesel Fuel Oil Transfer System, the 1 234 5 Spent Fuel Pool Cooling System, the Control Room Ventilation System, and the Reactor Make-up (Emergency Doratior') System found that these systems were property aligned per system drawings and procedures. Material condition of A OGOOO components and housekeeping were good, and component labeling was adequate. B OOOOO ;
c0 00O ,
6f27/98 Positive IR 98-05 NRC Licensee actions in response to a control room alarm on liquid radiation monitor, RM-L1, Primary Coolant Letdown Monitor, were adequate to ensure that the failed fuel 1 23 4 5 detection function of the monitor was being met. Redundant means for performing RM-L1's function of detecting a Chemical and Volume Control System line break A GGOOO ;
outside containment were available. 8 OOOOO c0 00O i FROM: 10/1/97 TO:8/31/98 Page 2 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98 i
SUMMER O2-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 5/29/98 Positive IR 98-03 NRC Automatic EFW start signals were in agreement tJith the design and licensing basis. 1 234 5 Manual operator actions necessary to mitigate abnormal or accident conditions were specified in written procedures consistent with the design and licensing basis. A OOOOO B 00000 cG 000 5/16/98 Positive IR 98-04 NRC Observed licensed operator simulator requalification exam scenarios were 1234 5 challenging and well conducted. Examination critQ es were thorough and provided a comprehensive assessment of crew and individual competencies.
A OOOOO a00000 c0 000 5/16/98 Positive IR 9841 NRC The knowledge level and performance of the auxiliary buildits upper level operator 1 234 5 during routine rounds and minor evolutions were good. The observed scope of the operator rounds was effective to ensure that potential equipment problems were identified.
A OOGOO 8 00000 ;
cO 000 .
5/16/98 Positive IR 98-04 NRC A detailed system walkdown of the reactor building spray system found that the 1 23 4 5 system was able to perform its design functions 8or accident conditions. Valves were property aligned per system drawings and operating procedures. Component tabeling was correct. A GGOOO OOOOO cO 000 5/16/98 Negative IR 98-04 NRC Annunciator response procedure actions were not adequately reviewed when a liquid 1 2 3 4 5 radiation monitor alarmed and diverted reactor makeup wm storage tank flow to a '
recycle holdup tank, resulting in an unexpected high level tn the recycle holdup tank.
Based on previous observations of operator response to annunciators, this appeared A OOGOO to be an isolated occurrence. B DD00O c0 000 5/16'98 Positive IR 98-04 NRC A pre-test briefing for a feedwater flow control valve test was thorough, clear and 1 234 5 i detailed. Operators were aware of plant response and specific parameters to monitor during the test.
A GOGOO ,
8 00000 CD 000 5/16/98 Positive IR 98-04 NRC '
The licensee adequately compensated for a postulated accident scenario irevolving a 1 23 4 5 secondary system pipe break outside containment. Control room operators were adequately prepared, by means of hardware changes, revisions to operating procedures and additional training, to respond to the postulated accident within the A OOOOO assumed time. B DDGOO c0 000 FROM: 10/1/97 TO: 8/31/98 Page 3 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
-SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 5/16/98 Positive IR 98-04 NRC Communications during shift tumovers were clear with a free exchange of ideas.
Management was present for several of the tumovers.
1 23 3 5 A 00000 B 00000 cO 000 4/4/98 Positive IR 98-02 NRC The knowledge level and performance of the intermediate building operator during 1 234 5 routine rounds were good. The observed dieset generator compensatory actions for a failure of the A DG local annunciator panel were effective to ensure dieset operability. The observed scope of the operator rounds was effective to ensure that AOGOOO
- potential equipment problems were identified. B OOOOO cO 000 4/4/98 Positive IR 98-02 NRC Compensatory actions for an emergency feedwater isolation issue were satisfactor:ty 1 23 4 5 implemented. On several occasions during the inspection period, the inspectors verified the operator stationed at the control room evacuation panels was attentive and knowledgeable of the required actions to be taken in response to a faulted A OOGOO steam generator. B OOOOO c0 000 4/4/98 Negative IR 98-02 NRC A review of four administrative control programs implemented by Operations 1 234 5 identified inattention to or lack of awareness of administrative control details in three of the programs. The specific examples were: not recognizing an engineering evaluation should have been updated when the work scope char $ged; not caution A OOOOO tagging three non-safety related valves; and not revising an operating administrative procedure when painUng criteria were revised.
B OOOOO O OOO 4/4/98 Positive IR 98-02 NRC Operators acted promptly in response to a deaerator re!ief valve lifting and 1 234 5 prevented a more significant challenge to plant operation. In order to reduce deaerator pressure and reseat the relief valve, the shift supervisor directed a power A OGGOO B 00000 c0 000 2/21/98 Positive IR 98-01 NRC During an emergency drill in the control room simulator for a loss of all AC power. 1 234 5 operators exhibited good control and communications while implementing emergency operating procedures.
A OOOOO B 00000 cO 000 2/21/98 Positive ;R 98-01 NRC A detailed sptem walkdown found that the emargency feedwater system was able 1 234 5 to perform its design functions for normal and accident conditions. No misaligned valves were identified and component labeling was adequate.
A OGOOO B 00000 c0 000 FROM: 10/1/97 TO: 8/31/98 Page 4 of 22 FOR PUBLIC RELEASE Last IJpdated: 9/5/98 !
_ _ _ _ _ _ _ _ _ _- _ _ - ~ - , ~ -
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/10/98 Positive IR 97-14 NRC No problems or concems were identified with the licensee's program for cold 1 23 4 5 weather protection. All requirements of procedures goveming preparations for severe weather had been completed. The inspectors performed a walkdown on the level sensing lines associated with the condensate storage tank and refueling water A GGOOO storage tank and found the insulation and heat tracing in good condition. B OOOOO c0 000 1/10/99 Positive IR 97-14 NRC Operators responded promptly to a pressurizer spray valve controtter matfunction 1 234 5 and prevented further challenges to plant.
A 0G000 sB0000 cO 000 1/10/98 Positive IR 97-14 NRC Plant start-up following the TS required shutdown for the inoperab!e A DG was 1 234 5 conducted safely. Good control and communications were observed in control room. Control rod movement was controued and closely monitored. The operations crew performir g the reactor startup had practiced the evolution on the simulator prior A CCUCC to takirg the shift. B OOOOO cO 000 1/10/98 Positive IR 97-14/LER 98-001 NRC A TS required plant shutdown to Mode 5 due to inoperable A DG was conducted in 1 234 5
- accordance with applicable procedures. Good communication techniques and coordination between operators were observed.
A GOGOO s00000 c0 000 11/29/97 Positive IR 97-13 NRC An observed Nuclear Safety Review Committee (NSRC) meeting met Technical 1 234 5 Specification requirements and provided constructive review and feedback to plant management. The NSRC discussed issues associated with snubber testing results-charging pumps, and main condenser cleaning.
A OOOOG OOO c0 000 11/29/97 Positive IR 97-13 NRC The Plant Safety Review Comrnittee (PSRC) reviews following the refueling outage 1 234 5 were thorough and comprehensive, and focussed on safety. Prior to entering Mode 4, hot shutdown, Mode 2, startup, and during power escalation, the PSRC conducted a comprehensive readiness review to ensure the plant was prepared for entry into A OOOOG the next phase cf restart. B CD000 cO DOO 11/29/97 Positive IR 97-13 NRC A review of licensee's overtime policy during the RFO concluded that the policy 1 234 5 adhered to the adm!nistrative controls in TS and stat'on administrative procedures -
for extended periods of shutdown for refueling. A OOOOO s00000 c0 000 FROM: 10/1/97 TO: 8/31/93 Page 5 of 22 FOR PUBLIC RELEASE Last updated: 9/5/98
SUMMER 02-Dec-9a DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/29/97 Negative IR 97-13/NOED 97-2-003 NRC A redew of the licensee's actions to obtain a NOED for the A DG concluded that the 1 234 5 rw % was not adequately prepared to respond to questions on info. that was necessary for the NRC to raake a well considered decision in granting discretion-For example, the licensee had not planned for implementing compensatory actions AOOOOO and licensee participants in an initial teleconference call did not include an operations perspective or senior licensee management.
B OOOOe CO OOO 11/29/97 Negative IR 97-13 NRC Control room operators relied on a cold calibrated Pressurizer level instrument with Work Request (WR) tag attached that indicated the meter was not accurate.
1 234 5 Instrument repairs had been completed earlier but the WR tag had not been removed. Operators failed to question the reason for the tag on the primary RCS AOOGOO levelindication. B OOOOO c0 000 11/29/97 Positive IR 97-13 NRC A containment inspection was conducted prior to entry into Mode 4. There was no 1 234 5 L ose debris in the containment which could be transported to the Residual Heat F,emoval (RHR) System and Containment Spray (CS) sumps and cause restriction of pump suction during a LOCA.
A GGOO O 8 00000 cO 000 11/29/97 Positive IR 97-13 NRC Reactor core reload activities and low power physics testing were conducted with 1 234 5 good control and communication between reactor engineering and operations personnet. The inspectors observed positive control of each fuel assembly from the spent fuel pool to the assigned location in the reactor vessel.
A OOOOO
, OGO cO 000 11/5/97 Positive IR 97-13 NRC The reactor startup following the refueling outage was conducted safely. The control 1 234 5 room supervisor, reactor operator, and the engineers present closely monitored reactivity changes. The approach to criticality was controlled and deliberate.
A OOOOO '
B 00000 c0 000 10/18/97 Positive tR 97-12 NRC The independent Safety Engineering Group (ISEG) review of the outage schedule 1 23 4 5 and outage activities contributed to plant safety during the refueling outage. The ISEG review identified changes in the outage schedule that could enhance safety and reduce potential risk. A OOOOO B 00000 c0 000 10/18/97 Positive IR 97-12 NRC A Nuclear Safety Review Committee (NSRC) meeting met TS requirements and 1 234 5 i provided constructive review and feedback to plant management. The NSRC discussions included significant plant operational events, the results of management watchstanding in the control room, the on-site deficiency reporting system, and the A OOOOO engineering plant system performance status report preparation process. B OOOOO .
cO 00O FROM: 10/1/97 TO: 8/31'98 Page 6 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER c2-Dec-98 w
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES
- 10/18/97 Positive IR 97-12 NRC The licensee closely monitored the key safety functional areas and property 1 234 5 assessed potential risks to plant safety during the outage. The licensee protected specific equipment trains and power sources and monitored valve lineups-Operators were aware of the status of the safety functional areas.
AOOOOO OOO cO 000 10/18!97 Negative IR 97-12 NRC During the shutdown for the refueling outage Tavg was reduced below the minimum 1 234 5 temperature for criticality for approximately eight minutes. This was due to an '
excessive number of steam drains in the secondary plant left in service during the power reduction ~ AOOOOO sOOOOO cO 000 10/18/97 Positive !R 97-12 NRC During plant manipulatk>ns involving a moisture separator reheater test, the 1 234 5 operators maintained positive control of the plant. Key plant parameters were monitored closety during steam flow changes.
A OOOOO B 00000 c0 000
[MAINTENANCENT Nl i 7/25/98 Positive IR 98-06 NRC Observation of a service water to emergency feedwater cross connect valve functio' 1 234 5 test and a reactor building exhaust filtration system test revealed good communications, proper calibration of the test equipment, and procedural sdherence. A OOGOO OOO cO 000 7/25/98 Positive IR 98-06 NRC Observed maintenance activities on a component cooling water system pump 1 23 4 5 '
breaker, a service water system temporary feak repair, and fabrication and welding of main steam system piping were conducted using the appropriate procedures.
tools, and techniques. The maintenance technicians were knowledgeable and A OOGOO demonstrated good work practices. B OOOOO c0 000 6/27/98 NCV IR 98 05/NCV 98005-03 LICENSEE A non-cited vio!ation of Technical Specification 4.0.5 was identified for failure to 1 234 5 adequate!y implement inse:vice Test (IST) requirements for the testing of pressure relief devices in the second ten year IST interval which started January 1,1994. A OOOOO B 00000 I c0 000 6/27/98 NCV IR 98-05/NCV 98005-02 LICENSEE A non-cited violation was identified for failure to perform Technical Specification 1 234 5 required t.he .:.c' checP., on Post Accident Monitoring System neutron flux intermediate range enannels N!-35 and NI-36.
A OOOOO '
B 00000 cO 000 FROM: 10/1/97 TO: 8/31/98 Page 7 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec48 DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/27/98 Strength IR 98-05 NRC The licensee's periodic Maintenance Rule assessment report provided suffdent 1 23 4 5 detait to demonstrate that the !!censee had adequately evafuated performance, condition monitoring, associated goals and preventive maintenance activities for Structures, Systems, and Components within the scope of the Maintenance Rule.
AOOOOO The licensee's assessment met the requirements of NUMARC 93-01 and paragraph B OOOOO (a)(3) of 10 CFR 50 65 and is a strength that resulted in significant improvements in the Maintenance Rule Program. O OOO 6/27/98 Positive IR 98-05 NRC The corrective maintenance fo!!owing an A Diesel Generator (DG) trip on high 1 234 5 crankcase pressure was performed such that the potentia! causes of the trip were identified and corrected. Strong system engineering support to maMtenance was observed during the repair effort Clear management involvement was exhibited in A OOOOO the maintenance review before declarir:g the A DG operable. B OOOGO cO GOG 6/27/98 Positive IR 98-05 NRC Observations of centrifugal charging pump, reactor core flux mapping, and solid 1 234 5 state protection system surveitlance testing revealed good communications. self-checking, and procedural adherence.
AOOGOO s00000 c0 000 6/27/98 Positive IR 98-05 NRC Observed maintenance activities on a centrifugal charging pump, an emergency 1 234 5 feedwater flow transmit'er, the service water intake structure, and a component cooling water pump were conducted using the appropriate procedures, tools, and techniques. The maintenance technicians were knowledgeable and demonstrated A CCCCC good work practices. B OOOOO cO 000 Sf29/98 Positive !R 98-03 NRC Surveillance test procedures reviewed for the EFW system effectively implemented 1 2 3 4 5 the design and licensing basis.
A 00000 B 08000 c0 000 5/29/98 Positive IR 98-03 NRC Material condition of EFW equipment and components, and housekeeping in the 1 23 4 5 areas around equipment and compenents was very good. Maintenance of the EF.V system cornponents has been effectively implemented. The EFW system has performed reliably.
A OOOOO B 00000 c0 000 5/16/98 VIO IR 98-04 NRC A violation was identified involving a failure to promptly identify that actuation logic 1 234 5 testing was not adequately testing the high-high steam generator level circuitry and for a failure to promptly perform the test on each solid state protection system train. A OOOOO B 03000 c0 000 FROM: 10/1/97 TO: BfJ1/98 Page 8 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec-98 DATE TYPE (s) SEC. SFA ID'd SOURCE (s) ISSUE (s) SMM COCES 5/16/98 Positive IR 98-04 NRC A review of Turbine Driven Emergency Feedwater (TDEFW) pump survei!!ance procedure revisions and test results concluded that the revised surveillance was 1 234 5 adequate to verify that the TDEFW pump would meet design requirements. A review of previous testing results conc!uded that the pump had been meeting design A OOOOO requirements.
B DDDGO 5/16/98 Positive IR 98-04 cO 000 NRC Observed battery testing was satisfactory and performed in accordance with survelflance requirements. A weekly battery cell inspection, due to a damaged post 1 234 5 seat, met the monitoring criteria specified by engineering.
AOOOOO a00000 5/16/98 Positive IR 98-04 cO 000 NRC in response to previous failures of the A diesel generator governor, the licensee appropriately considered diesel generator testing frequency and established suitable 1 234 5 goals to demonstrate diesel generator reliability.
AOOOOO s00000 5/16/98 Positive IR 98-04 cO 000 NRC Observation of service water piping uttrasonic testing and maintenance on a reactor trip breaker identified no concems. Good werk practices and techniques were 1 234 5 observed. The technicians were knowledgeable of their tasks.
AOOOOO s00000 4/4/98 Positive IR 98-02, IR 97-14, cO 000 NRC A licensee assessment and failure cause determination reports of four A diesel IR 97-13 generator failures between November 11.1997 and December 30,1997, adequately 1 ?. 34 5 identified the root causes and corrective action. Licensee *s efforts to identify and correct problems with A DG governor were thorough and comprehensive. A OOOOO OOO 4/4/98 Negative IR 98-02 cO 000 NRC Reactor coolant pump (RCP) seal water f!ow transmitter preventive maintenance was performed adequately. A review of maintenance procedures for sidiar RCP 1 234 5 seat water flow transmitters identified procedures with revisions eight years apart. OOOOO f'
Although the older revision was performed adequately, the inspectors considered it a poor practice to not revise all applicable procedures together. B OOOOO 4/4/98 Positive IR 98-02 c0 000 NRC A pre-job briefing for a moisture separator reheator performance test was thorough, clear and detailed. Expecte i plant response was oiscussed. The briefing was 1 234 5 conducted by the engineer 'n charge.
A OOOOO a00000 cO 000 FROM: 10/1/97 TO: 8/31/98 Page 9 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98 1
__-___a
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 4/4/98 Positive IR 98-02 NRC Observed surveillance activities on the service water system, reactor building 1 234 5 cooling, iodine removal system, and diesel generators were conducted satisfactorily and in accordance with applicable procedures. Good planning for the tests was evident and communications during the tests were effective.
A OOOOO OOO cO 000 4/4/98 Positive IR 98-02 NRC Observed maintenance on a component cooling water pump, a molded case circuit 1 234 5 breaker, and a diesel generator identified no concems. Good work practices and techniques were noted.
A OOGOO s00000 cO 000 2/21/98 URI 1R 98-01/URi 98001-01 NRC An unresofved item was identified pending a review of SSPS TS operability and 1 234 5 LER 98-003, IR-98-02 testing requirements associated with portions of the feedwater isolation logic circuit As reported in LER 90-003, on March 19.1998, the licensee determined that the feedwater isolation circuit had not been adequately tested.
A OOOOO OOOOO cO 000 2f21/98 Positive IR 98-01 NRC ~
Maintenance activities associated wth the B dieset generator, the A charging pump, 1 23 4 5 the turbine driven emergency feedv4ter pump, and the train A sequencer were performed in accordance with appkable procedures. Good maintenance practices and coordination of work activities were noted.
A OOOOO B 00000 cO 000 1/10/98 NCV 1R 97-14 LICENSEE A non-cited violation was identified conceming the failure to implement the 1 234 5 requirements of the foreign material and debris controt procedure. A utility knife was dropped into the spent fuel pool wiWe attaching a lanyard cord.
A OOGOO s00000 c0 000 1/10/98 VIO IR 97-14 NRC Violation for Failure to Follow Procedures on two occasions. Mechanical ? 23 4 5 maintenance technicians performing preventive maintenance on the Motor Driven EFW pump failed to initial and date the Prerequisites Complete and Limits and Precautions Reviewed steps at the completion of each step. Licensee failed to meet A OOOOO the specified criteria for the storage of a portable air monitoring cabinet mounted on B OOOOO wheels in the vicinity of safety-related service water system equipment. '
O OOO 1/10/98 Positive fR 97-14 NRC Weekly A DG surveillance testing met TS requirements for increased frequency of 1 234 5 testing. Post maintenance surveillance testing provided adequate assurance that the A DG was operable.
A OOOOO s00000 c0 000 FROM.10/1/97 TO: 8/31/98 Page 10 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/10/90 Positive IR 97-14 NRC Maintenance activities on CCW pump speed switch and breaker, failed DG indicator 1 234 5 famp, and a RCP thermal barrier flow sensing circuit were conducted in accordance with approved procedures and performed in a professional and competent manner. AOGGOO a00000 cO 000 11/29/97 VIO IR 97-13/ LER 97-004 NRC Although the missed snubber surveillan e was identified by the licensee, the 1 234 5 corrective actkm taken was not sufficiently comprehensive to prevent recurrence. A violation was identified for failure to conduct TS required snubber inspections. This resulted in failed snubbers being ur detected for an additional 18 months.
AOGOOO OGOOO cO 000 11/29/97 Negative IR 97-13/ LER 97-004 NRC The combination of two unrelat 4 snubber failure problems in one event report. LER 1 234 5 97-004. showed a lack of sensitivity to the issues being discussed. This combination of the two problems tended to minimize the importance of both problems. A OOOOO OOOOO c0 000 11/29/97 NCV IR 97-13/ LER 97-005 LICENSEE Non-Cited Violation: C Centrifugal Charging Pump vibration was in the alert range 1 234 5 during fu!! flow testing conducted during RFO-8. The licensee failed to recognize that this vibration level required doubling the normal 18 month test frequency to a nine month test frequency.
A OOOOO OGOOO cO 000 11/29/97 Positive IR 97-13 NRC The licensee's flow accelerated corrosion program has been doing a good job of 1 234 5 finding and replacing a'fected piping components.
A 00000 g00000 c0 000 11/29/97 NCV IR 97-13/LER 97-006 UCENSEE A non-cited violation was identified for failure to meet an eight hour 1 S requirement 1 234 5 to demonstrate the operability of AC offsite sources with a DG inoperable.
A 00000 B 00000 c0 000 11/29/97 URI 1R 97-13/ URI 97013-02 UCENSEE Deficiencies in the method used to document snubber test results were identified in 1 234 5 a OA generated Condition Evaluation Report (CER). The licensee made no changes in their testing process as a result of this CER. An URI was identified pending further review. A CCCCC OOOOO ,
c0 000 FROM: 10/1/97 TO: 8/31/98 Page 11 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/29/97 Positive IR 97-13 NRC Nine observed surveillance tests were performed satisfactorily and in accordance 1 234 5 with approved procedures. Personnei conducting the tests demonstrated a good levelof knowledge.
A OOOOO a00000 c0 000 11/29/97 Positive IR 97-13 NRC The maintenance performed to repair a head gasket leak on the letdown heat 1 234 5 exchanger was adequate. The use of a new style gasket and an increase in botting torque resulted in a successful repair.
A OOOOO t a00000 c0 00O ;
11/29/97 Positive IR 97-13 NRC The maintenance task to set the upper internals into the reactor vessel was 1 234 5 performed in a professional and deFberate manner. The pre-job briefing for mis task was detailed, thorough and included discussions on ALARA concems and industry experience. A OOOOO OOOOO c0 000 11/29/97 Negative IR 97-13 NRC Five Centrifugal Charging Pump sea! failures occurred during the period of August 1 234 5 20,1997 to November 1,1997. Three of the five failures were attributed to inappropriate maintenance activities. The applicable procedure and technical manual did not contain sufficient detail to successful!y replace the seals.
A CCCCC s00000 cO 00O ;
10/18/97 Positive IR 97-12/LER 96-04 LICENSEE The licensee determined that the Motor Driven EFW pump flow control valves were 1 23 4 5 >
leaking past their seats. The licensee's inspection of the emergency feedwater flow control valves reveafed some pitting and foreign material. The valves were machined and reassembled. Repair work was conducted in accordance with the A OOOOO maintenance procedure requirements. B D0000 c0 000 10/18/97 Positive IR 97-12 NRC t The work associated with A DG jacket water and intercooler heat exchangers was 1 234 5 effective in determining the overall condition of the tubes and gave reasonatsle assurance that they were capable of performing their safety-related function s. AOOOOO ;
B OOOf O cO 000 10/18/97 NCV IR 97-12 LICENSEE A non-cited violation was identified for a failure to correct!y implement the requirements of a maintenance procedure during DG maintenance. An incorrect tool 1 234 5 was used tc clean carbon deposits from a piston. The job supervisor noticed the use of the incorrect tool and corrected the technician. The licensee took adequate A OOOOO corrective action. B OOOOO c0 00O FROM: 10/1/97 TO: 8/31/98 Page 12 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98 i
_________________________a__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____-_m ___ -_ _ __ _ _m. - _ ___ -__
SUMMER 02-Dec-98 DATE TYPE (s) - SEC.SFA SOURCE (s) ID'd
_ ISSUE (s) SMM CODES 20/189. Positive IR 97-12 NRC Fourteen observed maintenance tasks were conducted in a ccmpetent and professional mannar. All of the work was performed with the work package present 1 234 5 and in use. Proper radiological controts were used when required.
AOOOOO B 00000 10/2/97 Positive cO 000 IR 97-11 NRC Observed survei!!ance tests were performed satisfactorily and in accordance with applicable procedures. Crew briefings prior to performance of surveillance test 1 234 5 procedures were done well by the Shift Supervisor, Control Room Supervisor, and radiation protection personnel. AOOOOO OOO cO 000 IE G NEERINGi"WMMl 7/25/98 Positive IR 98-06 NRC I The licensee's root cause evaluation of service water building fan fai!ures was thorough and appeared to identify a common mode failure. The proposed corrective 1 234 5 actions were adequate to prevent recurmnce of the problem.
A OOOOO s00000 7/25/98 URI cO 000 1R 98-06 NRC An unresolved item was identiffwi conceming the lack of a safety evaluation, the use 1 234 5 of risk analysis, and the administrative controis for blocking open steam propagatim barriers.
AOOOOO a00000 6/27/98 MISC c0 000 tR 98-05, URI 96005-3 NRC A review of an Unresolved item conceming differences between the Final Sa'ety 1 234 5 Analysis Report (FSAR) and plant operating practices concluded that the practice of offloading the full core during each refue:ing outage did not represent a change to the facihty or a change to the procedure described in the FSAR and thus did not A OOOOO require a rev'ew pursuant to 10 CFR 50.59. B OOOOO 6/27/98 Positive c0 000 IR 98-05 NRC An observation of the Principal Engineering Review Group concluded that the review 1 2 3 4 5 served as a useful check of design input requirements (ANSI N45.2.11) that have the potential to impact the design basis of the plant.
A OOOOO aD0000 6/27/98 Positive cO 000 IR 98-05 NRC The licensee demonstrated good work practices, controls, and vendor oversight 1 234 5 during the disassembly and cut 4Jp of a fuel assembly skeleton for shipment off site.
A00000 sDOOOO c0 000 FROM: 10/1/97 TO: 8/31/98 Page 13 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6 M /98 Positive IR 9845 NRC A positive finding was identified concerning implementation of the 10 CFR 50.59 Program. Personnet assigned responsibility for implementing the program were 1 234 5 trained and procedural controls provided clear guidance for determination of an Unreviewed Safety Question,10 CFR 50.59 screerings/ evaluations performed for AOOOOO design changes were determined to be technically adequate. 8 OOOOO 5/29/98 Positive c0 000 IR 98-03 NRC The Design Basis Document (DBD) was a con prehensive consolidation of design 1 234 5 and licensing basis criteria for the EFW system. Numerous deficiencies in design documentation refsrences ws e self-identified and entered into a corrective action program for tracking and resolution. AOOOOO OOOOO 5/29/98 VIO cO 000 IR 98-03 NRC The first example of a violation was identified for failure to follow procedures for l
control of M&TE M that a required evaluation was not performed for an identified out-1 234 5 l
of tolerance M&TE instrument. The second example of a violation was identified for failure to fo!!ow the 10 CFR 50.59 screening procedure to determine if a design A OOOOO change required a 10 CFR 50.59 Safety Evaluation. The design change did not involve an unreviewed safety question.
B OOOOO O OOO 5/29/98 Positive IR 98-03 NRC An accurate EFW system hydrau!ic model provided assurance of design and 1 234 5 ficensing criteria that was not provided in the design calcu!ations.
A 00000 B 00000 5/29/98 Weakness cO 000 IR 98-03 NRC The quality of EFW design calculations wv mr. Although current licensee procedures for calculation developmr' 1 234 5 cequate, the design calculations prepared prior to 1995 were not reviewed as .nst these standards. Similar prcbiems with design calculation qual lty could apply to other safety-related systems.
A OOOOO OOO 5/16/98 NCV c0 000 IR 98-04 LICENSEE A non-cited violation was identified for a failure to prepare an adequate safety 1 234 5 evaluation. The safety evaluation for a test did not adequately assess the effects of increasing turbine first stage pressure on the high steam flow setpoint.
A OOOOO B 00000 5/16/98 NCV cO 000 IR 98-04 LICENSEE During a procedure review the licensee identified that the Fina! Safety Analysis 1 234 5 Report (FSAR) assumed the use of one letdown orifice during normal plant operation white two oriftes were used during normal plant operations. A non-cited violation was identified for a failure to establish adequate operating procedures to ensure that AOOOOO the plant was operated in accordance with the assumptions in the FSAR. 8 OOOOO cO 000 FROM: 10/1/97 TO: 8/31/98 Page 14 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
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SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/10/98 V!O tR 97-14 NRC Violation was identified for failure to perform a safety evaluation for modification to 1 234 5 reactor coolant system toop B hot leg wide range temperature indicator on the control room evacuation panel.
AOOOOO B 00000 cO 000 11/29/97 Weakness 'R 97-13 NRC The licensee's threshold for formal ioentification of problems for the auxiliary buildin9 1 234 5 leak detection system in their corrective action program was judged to be a ;
weakness.
A OOOOO t s00000 cO 000 11/29/97 Positive IR 97-13 NRC An engineering evaluation to determine the cause of five CCP seat failures was 1 234 5 complete and detailed and included a!! relevant facts. Reasonable conclusions were made based on these facts. The probable cause of three failures were described in detail while the cause of the remaining two failures was indeterminate.
A OOOOO cO 000 11/29/97 MISC IR 97-13 NRC Westinghouse informed licensee that operating fuel regions (nay potentia!!y exceed 1 2 3 4 5 the pellet-to-clad gap reopening design criteria. An analysis *or the most limiting fuel assemblies determined that gap reopening would not occur until a cycle 11 bumup greater than 7000 MWD /MTU. Based on a review of a fuel performance AOOOOO assessment the inspectors concluded that there was no immediate concem with the current cycle 11 fuel meeting the reload safety analysis.
B OOOOe O OOO 10/18/97 Positive IR 97-12 NRC A review of the FSAR fuel handling accident analysis assumptions that applied 1 234 5 during defueling of the reactor concluded that current operating practices and plant characteristics were consistent with the accident analysis assumptions.
A OOOOO B 00000 cO 000 10/18/97 Positive IR 97-12 NRC A modification prepared by Design Engr., impiemented in the fa!! 1997 outage, was 1 2 34 5 reviewed and found to meet the requirements for design control. The modification resolved the Thermo-Lag issue, an industry wide issue to fire protection requirements. A OOOOO OGO c0 000 10/18/97 Positive IR 97-12 NRC A safety evaluation for a thermal study of the SW pond concluded that installing a 1 234 5 plug in the interconnecting pipe between the SW pond and Lake Monticello, and installing temperature monitorlag devices did not constitute an unreviewed safety question. A OOOOO OOO c0 000 fPLANT SAUidORTNYYN FROM: 10/1/97 TO: 8/31/98 Page 16 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER O2-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 7/25/98 Positive IR 98-06 NRC The licensee had conducted a comprehensive audit of the program for packaging 1 234 5 and transportation of radioactive material as required by 10 CFR 71.137.
A 00000 B 00000 cO 000 7/25/98 Positive IR 98-06 NRC Training was provided to Radiation Protection personnet in accordance with the descriptions defineated in the licensee *s Radiation Protection Manual and Nuclear 1 234 5 Training Manual.
AOOOOO B 00000 c8 000 7/25/98 Positive IR 98-06 NRC There was an overall decreasing trend in the collective personnel exposures and the 1 2 34 5 licensee was generally successful in meeting established goals for *As Low As is Reasonably Achievable * (ALARA). Maximum individual radiation exposures were controlled to levels which were well within the licensee's administrative limits and the A OOOOO regulatory limits for occupational dose specified in 10 CFR 20.1201(a). B D000O c0 000 7/25/98 Positive IR 98-06 NRC A review of various radiologica! control practices found the electronic dosimeter 1 2 34 5 calibration, the C charging pump room survey results, and the control of locked high radiation areas and associated records to be appropriately performed and contro!!ed.
A OOOOO OOOOO cO 000 6/27/98 Positive IR S8-05 NRC Security compensatory sctions d-; ring plant work activities were sufficient to ensure 1 234 5 that the appropriate level of security for vital areas was maintained.
A 00000 B 00000 c0 000 6/27/98 Positive IR 98-05 NRC The licensee demonstrated the ability to respond effectively to an emergency, to 1 2 34 5 recognize and classify emergency action levels, and demonstrated the adequacy and proper utilization of the emergency response facilities.
A OOOOO B 00000 c0 000 6/27/98 Positive IR 98-05 NRC The water chem %try control program for monitoring primary and secondary water 1 2 34 5 quality had been implemented in accordance with the Technical Specification requirements and the Electric Power Research Institute guidelines for pressurized water reactor water chemistry.
A OOOOO ,
OOO CO 000 FROM: 10/1/97 TO: 8/31/98 Page 17 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-oec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/27/98 Positive IR 98-05 NRC The radiological environmental monitoring program was effectively implemented. 1 234 5 The licensee complied with sampling, analytical and reporting program requirements, and sampling equipment was being well maintained.
A OOOOO B 00000 c0 000 6/27/98 Positive IR 98-05 NRC The licensee maintained an effective program for the control of liquid and gaseous 1 234 5 radioactive effluents from the p! ant. There was an overall decreasing trend in the amounts of activity released from the plant in liquid and gaseous effluents and the radiation doses resulting from those releases were a small percent of regulatory A OOOOO limits. B OOOOO c0 000 6/27/98 Negative IR 98-05 NRC ttealth physics technicians and other workers did not meet management's 1 234 5 expectations conteming contarnination control practices during the conduct of work in posted contaminated areas.
A OOOOO a00000 c0 000 4/4/98 Strength IR 98-02 NRC Overa!! the licensee was effective in identifying, analyzing, and resolving security 1 234 5 related problems. The adequacy of corrective actions to prt* rent recurring problems was found to be excellent. There were strengths in the maintenance program of the security equipment and system that supported plant operations and safety.
A OOOOO OOO c0 000 4/4/98 Positive IR 98-02 NRC The total number of trained security officers and armed personnel immediately 1 234 5 available to fulfill response requirements met Physical Security Plan requirements.
One fuff-time member of the security organization who had the authority to direct security activities did not have duties that conflicted with the assignment to direct att A OOOOO activities during an incident. 8 OOOOO c0 000 4/4/98 Positive IR 98-02 NRC Management's administration of the security program was proactive and effective. 1 234 5 Station and security management had established organizational goals and objectw measures necessary to determine security effectiveness.
A OOOOO s00000 c0 000 4/4/98 Negative IR 98-02/lR 96-03 NRC Compensatory measures implemented to temporarily secure protected and vital 1 234 ~5 area vio!ations were still in place after two years.
A CCCCC e00000 c0 000 FROM: 10/1/97 TO: 8/31/98 Page 18 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
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SUMMER 02-Dec-98 DATE TYPE (s) SEC. SFA ID'd SOURCE (s) ISSUE (s) SMM CODES 2/21/bO Positive IR 98-01 NRC The licensee's actions following an inadvertent attempted introduction of a handgun into the protected area were appropriate. Security personnel demonstrated good 1 234 5 knowledge vid performance during this event.
AOOOOG (
g00000 2/21/98 VIO tR 98-01 cG 000 LICENSEE A violation was identified involving a lack of adequate programmatic controls for temporary shielding. Tempora'y shielding that remained in place for longer than six 1 234 5 months was not evaluated in accordance with engineering requirements.
AOOOOO g00000 11/29/97 Negative IR 97-13 cG 000 NRC Due to an unexpected formation of insoluble materials in the reactor coolant system.
1 the general area and contact dose rates during the refueling outage were generally 1 234 5 l
twice the levels achieved during the previous outage. This condition resutted in the l
ALARA goal being exceeded halfway through the outage.
AOOOOO OOO 11/29/97 Strength IR 97-13 cG 000 NRC The licensee used programs that will ensure the reliability of s'ecurity related equipment and devices. The testing and maintenance program was a strength in 1 23 4 5 the security program.
A OGOOO aDG000 11/29/97 Positive IR 97-13 cG 000 NRC The licensee's intrusion detection systems and assessment aids were functional.
well maintained, effective for both covert and overt penetration atternpts, and met 1 234 5 licensee commitments.
AOGOOO g00000 11/29/97 Positive IR 97-13 cG 000 NRC The licensee was complying with the criteria in the Physical Security Plan (PSP) and Security Plan Procedures for alarm stations and communication equipment. The 1 234 5 evaluation of the protected area access controis for packages and personnel revealed that the criteria of it'e Physical Security Plan were being followed. A OOOOO OOO 11/29/97 Positive IR 97-13 cG 000 NRC The licensee used compensatory measures that ensured the reliability of security related equipment and devices. This evaluation verified that the Ucensee employed 1 234 5 compensatory measures when security equipment failed or its performance was impaired. Observed security activities including cornpensatory measures were AOOGOO found to be acceptable during the increased refueling outags activity. 8 OOOOO cG 000 FROM: 10/1/97 TO: 8/31/98 Page 20 of 22 FOR PUBLIC RELEASE Last Updated: 9/598
SUMMER 02h98 -
DATE- TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/29/97 VIO tR 97-13 NRC A violation was identified for the failure to follow posted health physics requirements. An individual was observed using a chewing tobacco product in the 1 234 5 Radiation Control Area (RCA).
AOOOOO a00000 11/29/97 Positive c0 000 IR 97-13/lR 97-12 NRC Monitoring, control of personnel radiation exposure, and postings were in accordance with 10 CFR Part 20. Housekeeping in the RCA was very good.
1 234 5 Radiological controls were adequately implementedhnaintained during the increased work activity and significantly higher than expected dose rates of the outage.
AOOOOO OOO 10/18/97 Positive IR 97-12 cO 000 NRC Observation of fire protection inspection activities during the refueling outage concluded that adequate measures were implemented to control fire doors and 1 234 5 transient combustibles.
AOOOOO a00000 10/1887 Positive c3 000 IR 97-12 NRC Observation of an emergency drill conducted during the evening hours concluded that the site Emergency Response Facilities could be activated / staffed within one 1 234 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Personnel responding to the site were monitored for fitness-for-duty considerations. AOOOOO B 00000 10/1887 Positive c3 000 IR 97-12 NRC A pre-job briefing conducted prior to a Reactor Building (RB) entry to decontaminate the buik!ing was professional and comp!ete. Street clothes accessibility to the RB 1 234 5 was maintained at the beginning of the refueling outage.
A OOOOO a00000 c0 000 I
FROM: 10/1/97 TO: 8/31/98 Page 21 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98
SUMMER 02-Dec-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMM Template Codes: SALP Functional Areas: ID Code:
1A ' OPERATION PERFORMANCE - Normal Operations LICENSEE LICENSEE IB OPERATION PERFORMANCE - Operations During Transients ENG ENGINEERING NRC NRC 1C iOPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SELF lSELF-REVEALED 2A {MATERI AL CONDITION - Equipment Co@2on OPS , OPERATIONS 2B MATERIAL CONDITION - Programs and i'rocesses PLT SU PLANT SUPPORT 3A ; HUMAN PERFORMANCE - Work Performarice SAQV
- SAFETY ASSESSMENT & OV 3B jHUMAN PERFORMANCE - KSA 3C ' HUMAN PERFORMANCE- Work Environment 4A ENGtNEERING/ DESIGN - Design 48 ENG!NEERING/ DESIGN - Engineering Support 4C ENGINEERING / DESIGN - Programs and Processes 5A PROBLEM IDENTIFICATION 8 SOLUTION - Identification 58 PROBLEM IDENTIFICATION & SOL'JTION - Analysis SC iPROBLEM IDENTIFICATION & SOLUTION - Resolution Eels are apparent violations of NRC requirements that are being considered for escalated enforcement action in accordance with the " General Statement of Policy end Procedure for NRC Enforcemer t 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 e predecisional enforcement conference.
URis are unresolved items about which more information is required to determine whether the issue in questi3n is an acceptable item, a deviatica, a nonconformance, or a violaton.
However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
FROM: 10/1/97 TO: 8/31/98 Page 22 of 22 FOR PUBLIC RELEASE Last Updated: 9/5/98 j