ML18016A744
| ML18016A744 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/30/1998 |
| From: | Brian Bonser NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Scarola J CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 9812100005 | |
| Download: ML18016A744 (47) | |
Text
November 30, 1998 Carolina Power L Light Company ATTN: Mr. James Scarola Vice President - Harris Plant Shearon Harris Nuclear Power Plant P.O. Box165, Mail Code: Zone 1
New Hill, NC 27562-0165
SUBJECT:
INSPECTION PLAN - SHEARON HARRIS NUCLEAR POWER PLANT
Dear Mr. Scarola:
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 II 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 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 willcontinue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed on Enclosure1, to close open inspection items that are ready to be resolved. We willnotify you at least 3 weeks before the start of these inspections.
The NRC's general policy for reactor inspections is that we willannounce 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. 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 Carolina Power 8 Light. This material willbe placed in the public document room.
98i2i00005 98ii30 PDR ADQCK 05000400 8
CP&L We willinform you of any changes to the enclosed inspection plan. Ifyou have any questions, please contact me at (404) 562-4560.
Sincerely, (Original signed by B.
R. Bonser)
Brian R. Bonser, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No. 50-400 License No. NPF-63
Enclosures:
- 1. NRC Inspection Plan
- 2. Plant Issues Matrix cc w/encls:
D. B. Alexander, Manager Performance Evaluation and Regulatory Affairs CPB 9 Carolina Power &Light Company P. O. Box 1551 Raleigh, NC 27602-1551 J. W. Donahue Director of Site Operations MC: Zone1 Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P. O. Box 165 New Hill, NC 27562-0165 Bo Clark Plant General Manager-Harris Plant Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P. O. Box 165 New Hill, NC 27562-0165 Chris A. VanDenburgh, Manager Regulatory Affairs Carolina Power & Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1
New Hill, NC 27562-0165 cc w/encls continued:
See page 3
CP&L cc w/encls: Continued Johnny H. Eads, Supervisor Licensing/Regulatory Programs Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1
New Hill, NC 27562-0165 William D. Johnson Vice President 8 Senior Counsel Carolina Power & Light Company P. O. Box 1551 Raleigh, NC 27602 Mel Fry, Director Division of Radiation Protection N. C. Department of Environmental Commerce & Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721 Karen E. Long Assistant Attorney General State of North Carolina P. O. Box 629 Raleigh, NC 27602 Public Service Commission State of South Carolina P. O. Box 11649 Columbia, SC 29211 Chairman of the North Carolina Utilities Commission P. O. Box 29510 Raleigh, NC 27626-0510 Robert P. Gruber Executive Director Public Staff NCUC P. O. Box 29520 Raleigh, NC 27626 cc w/encls continued:
See page 4
CPSL cc w/encls: Continued Stewart Adcock, Chairman Board of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602 Margaret Bryant Pollard, Chairman Board of County Commissioners of Chatham County P. O. Box 87 Pittsboro, NC '27312
.1 Distribution w/encls:
L. Ptisco, Rll M. Ernstes, Rll J. Coley, Rll S. Flanders, NRR R. Baldwin, Rll J. Lenahan, Rll D. Jones, Rll D. Thompson, Rll PUBLIC NRC Resident Inspector U. S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hilt, NC 27562-9998 OFFICE SIGNATURE NAME DATE RII:DRP GrnacDonald alt 11/
/98 RII:DRS KBa r 11/
/98 Rll:
R GBoll o
11/
/98 RII:D S F
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11/I
/98 Rll:
K ndis 11/ I
/98 RII:DRS TPoo Io 11/
/98 OFFICIALRECORD COPY Doc T NAME: P:UPLTR1.WPD
~HARRI IN PE I N PLAN INSPECTION PROCEDURE/
TEMPORARY INSTRUCTION IP 50001 IP 81700 IP 71001 IP 84750 IP 86750 TITLDiPROGRAM AREA Engineering Physical Security Operator Requalification Radiation Protection NUMBEROF INSPECTORS 'LANNED INSPECTION DATES 12/7-11/98 2/1-5/99 2/8-12/99 2/22-26/99 TYPE OF INSPECTION-COMMENTS Initiative Inspection - Preparations for Steam Generator Replacement.
Core Inspection Core Inspection Core Inspection IP 82701 Emergency Preparedness 3/1-5/99 Core Inspection IP 84750 IP 86750 Radiation Protection 3/294/2/99 Core Inspection Enclosure 1
Page:
1 of3 Region II HARRIS Date United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Funclional Template Source Area ID Type Codes Item DescripBon Date: 11/?5/1998 ~
Time: 15:10:03 09/26/1998 1998008 Pri: ENG NRC NEG Prk 58 Troubleshooting efforts assodated witha trip of a heater droln pump were Ineffective. The site troubleshooting procedure did not include sufficient guidance for planning and conducting troubleshooting actMties to ensure a systematic ond analytical opproach to troubleshooting was used.
The licensee recognized that inadequacy.
Ter:
09/26/1998 199800841 Pri: ENG Ucensee NCV Prl: 5A A Non-Cited Violationwos Identified for fai'lure to perform Quality Assurance audits of off site activities.
Sec:
Sec:
Ter:
09/26/1998 199800842 Prl: ENG Licenme NCV Pri: 48 A Non-Cited Violationwas Identified for Implementing an Unreviewed Safety Question (USQ) without prior Commission approval. The USQ hvolved a colculated Increase in the dose consequences of a design basis accident for the cycle 6 fuel toad.
Ter.
09/26/1998 199800843 Prl: ENG Sec:
NRC VIQIV Pri: 5A AViolation was Identified for foilure to document an incorrect safety evoluatlon as an adverse condition. This Violationwos an exomple of a larger problem related to enforcement of corporate standards for off-site actMties.
Ter.
09/26/1998 1998008 Pri: MAINT NRC PQS Prl: 2B The licensee does a good Job. during the review and opproval cycle for each work week schedule. of assessing the effects of planned actMties on plant risk. as required by the Maintenance Rule.
Sec:
Ter.
09/26/1998 1998008 Pri: MAINT NRC pQS Prl: 28 The on-line maintenance backlog wos being better managed thon it had been in the previous two years.
Sec:
Sec:
Ter.
09/26/1998 1998008 Pri: MAINT NRC PQS Prl: 3A The Surveillance tests were conducted in accordance with applicable procedures and proved operoMty of the subject equipment.
Sec:
Ter.
09/26/1998 1998008 Prl: MAINT NRC pQS Pri: 3A Maintenance actMtles were performed ln accordance with the work hstructlons. Thorough planning was evident in the process Instrumentation control coblnet power supply replacement work packages In relation to Identmcotlon ofpotential problems.
Ter.
Item Type (Compliance,Foiiowup,other), From 10/01/1997 To 11/13/1999 Enclosure 2
Page:
2of3 Region II HARRIS Date United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area Functional Template Source Area ID Type Codes Ilem Description Date: 11/25/1 998 Time: 15:10:03 09/26/1998 1998008 Prl: OpS Sec:
NRC NEg Prl: IA Pr'ocedures were being opproprlotely followed. The operations procedures for synchronizing to the grid and storting a second feedwater pvmp needed Improvement.
The procedure for synchrontsing to the grid did not olways provide fora smooth tronsfer from the steam dumps to the main turbine. The procedure for starting a Ter.,
second feedwater pump required stable steam generator levels to ploce the feed regulating valves bock In automatic.
This resulted In the opertor's attention being focused primarilyon the feed regulating valves for an excessive period of time.
09/26/1998 1998008 Pri: OPS Sec:
NRC pOS Pri: IA During the period. the conduct of operations was In accordance with applicable procedures.
Operational decision making during the do~ower evolutions wos conservative.
Ter.
09/26/1998 1998008
=
Prl: OPS Sec:
NRC pOS Prl:1C Self~ssmentactMtIeswerebelngproperlyperformedInaccordancewithprocedurolreqvlrements.
Sec: 5A Ter.
09/26/1998 1998008 Pri: pLTSUp NRC pOS Prl: 1C The performance of security and safegvards activities were In accordonce withapplicable procedure and the Sec:
security plan.
Ter.
-09/26/1998 1998008 pri: pLTSUP NRC pOS prl: IC Rre protection equipment was being adequately maintained In accordance with procedures.
Afire brigade drill Sec 38 observed wos adeqvately conducted and evaluated by licensee personnel.
Performance of the fire brigade demonstrated that they were adequately troined to control the fire.
Ter.
09/26/1998 1998008 Pri: PLTSUP NRC Sec:
pOS Prl: 3A The controt of contamination and dose for the site was good and was attributable to good teamwork between ~
the various deportments.
Teamwork was exempli fled by the tank desludglng effort which reduced dose rates In ~
the floordroln tonk area by a factor of opproxlmately 100.
Ter.
Item Type (Compliance,Followup,Other), From 10/01/1997 To 11/13/1999
Page:
3of3 United States Nuclear Regulatory Commission PlANT ISSUE MATRIX By Primary Functional Area gate: 11/$5/1998 Time: 15:10:03 Legend Type Codes:
BU Bulletin CDR Construction DEV Deviation EEI Escalated Enforcement Item IFI Inspector follow-up Item LER Ucensee Event Report LIC Ucenslng Issue MISC Miscelloneous, MV MinorViolation NCV NonCited Violation NEG Negative NOED Notice of Enforcement Discretion NON Notice of Nononformance P21 Port 21 POS Positive SGI Safeguard Event Report STR Strength URI Unresolved Item VIO Violation WK Weakness Template Codes:
IA Normal Operations 1B Operations During Transients lc Programs and Processes 2A Equipment Condition 2B Progroms and Processes 3A Work Performance 3B KSA 3C Work Environment 4A Design 4B Engineering Support 4C Programs and Processes 5A Identificatlon 58 Analysis 5C Resolution IDCodes:
NRC NRC Self Self-Revealed Ucensee Ucensee OPS MAIN ENG PLTSUP OTHER Operations Mohtenance Engineering Rant Support Other Functional Areas:
EEls are opporent violations of NRC Requirements that are being considered for escalated enforcement action In accordance withthe 'General Statement of Policy and Procedure for NRC Enforcement Action'Enforcement Policy). NUREG-1600. However. the NRC hos not reachedits final enforcement declslon on the issues ldentifiedby the EEls and the PIM entries may be modified when the final decisions are mode.
URls are unresolved items about which more Information Is required to determine whether the Issue in question is an acceptable item. a deviation. a nonconformance. or a violation. A URI may also be a potentlol vfolotionthat Is not likelyto be considered for escalated enforcement action. However. the NAC has not reached its fina conclusions on the issues. ond the PIM entries may be modified when the find conclusfons ore made.
item Type (Compliance,Foflowup,OIIMr), From 10/01/1997 To 11/13/1999
I 4
United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 8/15/98 Positive 8/15/98 Positive 7/4/98 NCV 7/4/98 Positive 7/4/98 Positive IOPERATIONS@%WPZygggq'/15/98 Positive IR 98.07 IR 98.07 IR 98-07 NCV 98-06-01 IR 98.06 IR 98-06 NRC Self-assessment activities were identifying issues for improvement.
NRC While completing a semi.annual operability test, non-licensed operator performance was effective and consistent with both procedural requirements and management expectatlons.
NRC Operations perfonnance during the period was In accordance w!th required procedures.
NRC A nonct ted vfohtlon was Identified for approving Technical Specification Interpretafions ITSI)which allowed the TS to be satisfied in ways other than those specified In the TS, without prior Commission approval.
SELF The Plant Nudear Safety Committee meeting met procedural requirements and was appropriately focussed on safety. The Nuclear Safety Review Committee meeting was attended by the Chief Nuclear Officer and was appropriately focussed on safety. Nuclear Assessment Section Audits and a Performance Evaluation Section Assessment were thorough.
SELF Ourfng this period, operator knowledge and perfonnance satfsfied both management expectations and procedural requirements.
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FROM: 10/1/97 TO: 11/16/98 Page1of 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/4/98 Positive 7/4/98 Positive 7/4/98 Positive 7/4/98 Positive 6/18/98 Negative 6/18/98 Positive 7/4/98 Negative IR 98.06 IR 98.06 IR 98-06 IR 98-06 IR 98.06 IR 98-04 IR 98-04 SELF The operations night orders revfewed were determined to be In compliance with applicable procedures.
One night order contained guidance which did not reflect current plant conditions.
NRC While hanging a clearance, operators encountered an inconsistency between current procedural requirements and their recollection of procedural requirements.
In response to the Incident, operations management appropriately emphasized procedural compHance.
SELF During the completion of a quarterly surveillance test, operators followed the applicable procedure, used effective communications, and coordinated test activities weil.
SEI.F Equipment condition, material condition, and housekeeping were acceptable.
SELF Operations performance during the period was generally In accordance with plant procedures and exhibited the appropriate sensitivity to safety.
NRC Pfant Nuclear Safety Committee discussions about one previous NRC violation were not focussed on ensurfng that the licensee reponse addressed the overall root cause.
This shortcoming resulted In an NRC request for an additional response.
NRC Qualltyassurance activities were being conducted as required by procedures.
Identification of adverse condi6ons continued to be a strength.
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C3 QQO FROM: 10/1/97 TO: 11/16/98 Page 2of 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 6/18/98 Positive 6/18/98 VIO 6/18/98 Positive 6/18/98 Positive 5/11/98 Positive 5/11/98 Positive 5/I 1/98 Positive MAINT IR 98-04 VIO 98-04-01 IR 98 04 IR9804 IR 98-03 IR 98-03 IR 98-03 NRC
'" Control Room staffing and overtime usage met the requirements of the Technical Specificatlons. Anew operafions manager was selected who had been a ficensed senior reactor operator at the H. B. Robinson Plant and met the TS requirements.
NRC One violation was identified for fafiing to hang a cleafance tag as required by procedure.
NRC Equipment was being maintained In acceptable condition per plant procedures and housekeeping was effecfive In maintaining plant areas free of unnecessary materials or debris. Equipment defidendes were appropriately identified and were being scheduled and worked in accordance with the licensee's work scheduling system.
NRC In general, the conduct of operafions was professional and safety~nsdous.
Roufine acfivffies were adequately performed. Operations shift crews were appropriately sensiUve to plant equipment condifions and maintained a questionIng attitude InrelaUon to unexpected equipment responses.
NRC Operator performance over the last eight months improved significantly due to the creation of a better operations environment. Administrative distracfions were removed from the control room and an hourly work scheduling system was implemented.
These improvements allowed the operators to focus better on operating the plant, which stgnlficanUy reduced errors.
LICENSEE Control room operators exhibited a quesUonlng atfitude, a dear understanding of Technical Spedficatlons ITS), and a determlnaUon to properly implement TS requirements ln relation to implementation ol TS Interpretafion 89-003. Operator performance during the period was good.
NRC Plant Nudear Safety ComrnINee discussions were appropriately focussed on safety and preventing recurrence of problems.
Identificafion of adverse conditions continued to be a strength.
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HARRIS 16.Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 5/11/98 NCV NCV 98-03-02 LICENSEE The inspectors also IdentiTied a non-cited violation for a failure to maintain equipment cfearances as quality assurance records.
1 234 5/11/98 VIO VIO 98-03-01 NRC Aviolation with two examples was Idenmed by the Inspectors for failures to properly dassify condigon reporls as a significant In accordance with required procedures.
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5/11/98 Positive 5l11/98 Positive 4/20/98 LE R 3/13/98 LER 2/28l98 Negative MAINT IR 98-03 IR 98-03 LER 98.005-00 LER 98-004-00 IR 98-01 NRC Reponse to an electrical ground and containment fire alarms on a non-safety containment air handler was good.
NRC Operations performance during the period was acceptable and in accordance with plant procedures.
LICENSEE Technical Specification verbatim non-compliance.
LICENSEE Design defclency related to Inadequate runout protection for the turbine driven AFW pufnp.
NRC Furlher review of the 'C'team generator blowdown system water hammer event that occurred in December 1997, revealed that failure to enter Technical Speci flcagon 3.7.8 Umtilng Condition for Operation when a btowdown system Isolation valve snubber was removed was an Isolated case and did not result in a TS violation.
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, oaaaa C 0 OOCI 12345 A DDClma B 00000 C 0 000 12345 A HOC3Q 0 B OODDQ C 0 QCICI FROM: 10/I/97 TO: 11/16/98 Page 4 ol 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(8)
SMM CODES 2/2N98 VIO 2/28/98 Negative 2/28/98 Negative 2/28/98 Strength VIO 98-01-01 IR 98.01 IR 98.01 IR 98-01 LICENSEE The licensee identified an additional example of failing to ensure main control room chart recorders wer'e properly marking and timing, which was idenUfied as a vfolaUon. Corrective action for vlolaUon 50400/9749-02 was not effective and additional correcUve acUons had been idenUUed from a root cause InvestlgaUon of the addiUonal occurrence.
The root cause invesUgation found that chart recorder Uming had not been properly checked but itwas not addressed as an lnappropriate act because the invesUgaUon was focused on marking only. This narrow focusing diluted the significance of the overall finding of the root cause invesUgation.
NRC Self.assessment acUvIUes were acceptable, even though the PNSC's discussion associated with a root cause investigation for a missed survellhnce did not identify that a root cause had not been addressed.
y NRC Communications system alarm tesUng was being conducted as comltted to In the FS/N, although documented acceptance criterfa was considered weak.
NRC OperaUons performance durfng the period was acceptable.
Operators appropriately responded to alarms and abnormal conditions.
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1/17/98 Strength 1/17/98 Strength 1/17/98 NegaUve IR 97-13 IR 97-13 URI 97-13 01 NRC Self-assessment activities were good. Site management was aggressive In the pursuit of improvement through the self-assessment and NAS/PES audit programs.
NRC An unresolved Item was opened regarding removal of safety. related snubber 1BDM-169, adjacent to the containment isolaUon valve, without entering a TS action statement; and for review of the root cause and repetitive nature of water hammer events on the SGBD system, Indudfng their continued occurrences.
NRC Mousekeeplng has been good and was considered a strength.
Operator sensiUvlty to long-standing equipment problems has Improved as evidenced by the increase in the number of items identified in the operator work-around log.
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/17/98 Positive 12/6/97 VIO 12/6/97 VIO 12/6/97 Positive 12/6/97
. Positive 12/6/97 Positive 1/17/98 Positive IR 97-13 IR 97-13 VIO97-12-02 VIO 97-12.01 IR 97-12 IR 97-12 IR 97-12 NRC Operations Initial response to the C steam generator blowdown (SGBD) water hammer event and steam leak was determined to be prompt and adequate.
NRC Operations performance during the period was acceptable.
Operators were observed apropdatety using annunciator response procedures.
NRC Aviolation was identified for a Plant Nuclear Safety Committee meeting conducted without the required quorum membership.
NRC The off.site and on.site safety review committees provided effective oversight of plant operations., These committees were selfwrftfcal and focused on safety.
NRC The licensee audit and self.assessment programs were effective in Identifying Issues at the plant and was a strength.
The licensee's identified weaknesses In the cold weather pre paragons were consistent with the Inspectors findings. The licensee's.
assessments identified Improvements inimptementation of the corrective action prognun that were consistent with Inspector Issues.
NRC The operating experience feedback program was fudged to be adequate.
NRC A second violation was identified for not designating the written Plant Nuclear Safety Committee membership appointment as a quality assurance record.
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/6/97 Positive 12/6/97 Negative 12/6/97 Positive 12/6/97, Positive 12/6/97 Positive 10/25/97 VI0 10/25/97 VIO IR 97-12 NRC The Inspector oonduded from a sampling of significant condiUon reports that root cause investigations, Ifperformed. were etfective. Justification of root cause walvers, closure documentation errors, and Implementation of corrective actions resulted In missed opportunities to conduct complete and comprehensive reviews.
These findings were similar to Ucensee audit findings.
IR 97-12 NRC Improper dasslficathn of significance and inconsistent trending of adverse condithns has contributed to the recurrence and longevity of some performance issues.
IR 97-12 NRC The recognitlon/idenfificaUon of problems was IdentiTied as a strength.
IR 97-12 NRC The licensee's approach to preparation for adverse weather was more comprehensive than In the past. The approach was more focussed on addressing the root causa for the heat trace and temperature monitoring problems than In the pasL The lhensee had not adequately forecasted the amount of work hvolved in repairing the heat trace drcults. Not all drcults had beenrepaired prior to the start of cold weather.
Alldrcuits assodated with safety-related equip. were working.
IR 97-12 NRC Operafions performance during the period was good. There were no events caused by operathns performance errors. End~I.shift crifiques were good.
VIO 97-10-01
~ Example 2 NRC of 3 A vloiaUon was Identified for Fafiure to Establish and Implement Operating and Surveillance Procedures.
Three examples were Identified: 2) not pladng a second feedwater pump in senrice a't the required point causing a turbine runback.
VIO 97-10.01
~ Example 3 NRC A violation was idenfified for Failure to Establish and Implement OperaUng and of 3 Surveillance Procedures.
Three examples were idenUfied: 3) falling to establish adequate procedures forwhen to place a second feedwater pump in service and when a turbine runback occurs.
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HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/25/97 Positive IR 97-10 SELF Self-assessment acthNes were acceptable.
The root cause Investigation and PNSC discussion related to the TDAFWP forced outage was good.
10/25/97 Positive IR 97-10 SELF Operations performance during the period was acceptable.
I MAINTENAhlCE$$P@ÃMFr >a~
10/25/97 VIO VIO 97-10-01, Example 1
NRC A violation was identified for Failure to Establish and Implement Operating and of 3 Surveifiance Procedures.
Three examples were Idenfified: 1) opening the feed regulating valves prior to opening the associated block valves.
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0 8/15/98 Positive 8/15/98 Positive 8/15/98 Positive 8/15/98 Positive OPS IR 98-07 IR 98-07 IR 9847 IR 98-07 NRC Maintenance on the containment spray check valves has been conducted In accordance viith applicable procedures, and has IdentiTied no adverse conditions associated with those valves.
NRC The surveillance testing was adequately conducted.
The operations and the maintenance personnel exhibited knowledge of the jobs, were professional, and accomplished their job cautiously and with plant safety in mind.
NRC The maintenance acfivlties observed be the inspector were done by well qualified and experienced workmen. The work was satisfactorily completed and was done using approved procedures.
The craftsmen were very knowledgeable and skillful and performed their work In a professional manner.
NRC The periodic assessment performed by the ficensee took into account component performance, condition monitoring, associated goals and preventive maintenance activities and met the requirements delineated In OPAL's procedure ADM-NGGC-0101, Maintenance Rule Program, revision 9. Corrective actions sampled were appropriately implemented.
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FROM: 10/1/97 TO: 11/16/98 Page 8of 28 FOR PUBLIC RELEASE Last Updated:
8/15/98
HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/4/98 VIO 7/4/98 Positive 7/4/98 Positive 7/4/98 Positive 6/18/98 URI 6/18/98 Positive 6/18/98 Positive VIO98-06-02 IR 98.06 IR 98-06 IR 98.06 URI 98-04-03 IR 98-04 IR 98-04 NRC One violation was identified for approving procedures which allowed Technical Specmcatlon Surveillance Requirements that specIHed performance 'during shutdown'o be performed at power without receiving prior Commission approval.
SFLF Conservative decision maMng was observed during the performance of a surveigance.
SELF SurveIHance tests observed were conducted in a thorough and effective manner.
Procedures were fottowed and independent venTcation was performetho Identify potential problems.
SELF Work observed was performed with the work package present and In active use.
Technicians were skHlful, experienced and knowledgeable of their assigned tasks.
Maintenance activities were thorough and effective.
NRC NRC An unresolved item was opened In relation to technical spedHcatfon surveillance requirements tha'I were required to be accomplished at shutdown and were beIng conducted at power. One example was identified in relation to testing of the gross failed fuel detector component cooling water (CCWI isoiatfon valves on low surge tank level. The licensee subsequently idenblied three other examples by the end of the period. as reported In LER 50<00/98-005.
Thirteen surveglances were adequately conducted.
Maintenance and operations personnel performing the surveHlance were skillfuland knowledgeable.
NRC The six maintenance activities observed were beIng conducted with work packages present and In active use. In addibon, the participating technicians were experienced and knowledgeable.
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0 FROM: 10/1/97 TO: 11/1 6/98 Page 9 ol 28 FOR PUBLIC RELEASE Last Updated:
8/15/98
HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 5/11/98 Positive 5/11/98 Positive LER 2/28/98 Positive 2/28/98 Positive
'/28/98 VIO 2/28/98 Strength IR 98-03 IR 98-03 LER 98.006-00 IR 98-01 IR 98-01 VIO98-01-03 IR 98-01 NRC Surveillance activities were adequately conducted.
NRC Maintenance activities were performed adequately.
Minorplanning deficiencies were noted on one of four maintenance activiUes observed.
SELF Englneerlng performed an Inspection of several Agastat relays In the load sequencers and hadequate solder connections were found and the relays were replaced.
NRC Steam generator biowdown system water hammer events were reviewed by the maintenance rule expert panel after the December 1997 water hammer event and determined to have been appropriately evaluated.
The expert panel meeUng on the Issue was thorough and exhibited a proper safety focus. The December event has prompted licensee management to question whether the steam generator blowdown system secondary chemistry performance criteria under the maintenance rule Is sufficfenUy conservative to meet plant goals.
A failure to conduct a shutdown margin calculation as required by TS surveillance requirement 4.1.1.1.1.a when control rods were declared Inoperable on January 29, 1998, was Identified as a vhlation. The failure was due to Inadequate communlcaUon by site management about a decision made in 1997 which clarified the Unk between IIUs surveillance requirement and TS 3.1.3.1.
NRC The surveillance performances observed were adequately conducted.
LICENSEE Failure to perform InspecUon and prevenUve maIntenance on molded case circuit breakers as required by Technical SpecificaUons.
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FROM: 10/1/97 TO: 11/16/98 Page10of 28 FOR PUBLIC RELEASE Last Updated:
8/15/98
HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 2/28/98 VIO 2/28/98 NCV 2/10/98 LER 1/29/98 LE R 1/21/98 LER 1/21/98 LER 1/17/98 Strength OPS OPS OPS OPS VIO 98 01*01 NRC Fafiure to fotlowprocedures, example 2: A violation was identified for inadequate rod control system work Instructions. The inadequate work Instructions were the result of incomplete lnlfiat troubleshooting.
NCV 98.01-02 NRC Maintenance actfvffies observed were generally adequate.
A paper wipe was found in the '8'iesel generator lube oil tank that was apparently left there during the 1997 refuefing outage (RFO7). This was identified as a Non-Cited Violation for failing to establish adequate foreign materhl exclusion controls.
LER 97.021.02 LICENSEE TS survelfiance procedure review proJect Identified deficiencies. This revision is submitted to report an addifional condition idenfified during the on-going TS surv.
procedure review proj. This condition involved the failure to properly test the non-safety related pressurizer pwr oper. relief valve; vlo of TS surv req LER 98-002.01 LICENSEE Sofid state protection system (P-11 Permissive) testing deficiency.
This supplement provkfed additional corrective action.
LER 98.002.00 LICENSEE Sofid state protection system (P-11 Permissive) testing deficiency.
IR 97-13 NRC The plant upgrade coatings program was considered a strength.
LER 98-003-00; VIO 98-UCENSEE Failure to perform shutdown margin calculation required by TS surveillance 01-03 requirements.
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a 08000 8 00000 C 0 000 FROM: 10/1/97 TO: 11/16/98 Page 11 of 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/17/98 Positive 1/17/98 Negative 1/17/98 Positive 1/17/98 Positive 12/6/97 Positive 12/6/97 NCV 12/6/97 Positive ENG ENG IR 97-13 IR 97-13 IR 97<<13 IR 97-13 IR 97-12 NCV 97-12-04 IR 97-12 NRC During weld repairs to the cracked line wMch caused the steam leak, a welder burned through a steam generator sample tubing line while exiting his jobsite.
NRC Maintenance work observed on the C SGB system was well coordinated ind-thorough.
NRC Maintenance activities observed were being properly conducted.
The snubber replacement was adequately inspected by the licensee's QC inspector.
NRC Each of the 8ve surveillance tests observed ware conducted in a thorough and effective manner.
Procedures were followed, maintenance and operations personnel performed peer checking to Identify potential problems before they impacted plant operations.
The inspectors also noted engineers who supported the on-going maintenance activities were very capable and knowledgeable.
NRC One maintenance activity was found delident in that the craft failed to correctly implement the WR/JO work Instructions resulting In a non<ted violation.
NRC Post maintenance testing of the Emergency Safeguards Sequencer was thorough and professional.
NRC Survelllances were adequately conducted.
Maintenance and operations personnel performing the surveNances were shllful and knowledgeable.
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8/15/98
HARRIS 16-Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
SMM CODES 12/6/97 Strength 12/6/97 Positive 11/18/97 LER 10/25$ 7 VIO 10/25/97 NCV 10/25/97 NCV 10/25/97 Positive PLT SUP IR 97-12 NRC Radiagon monitoring was a strength in maintenance activities.
IR 97-12 NRC Maintenance activities'were generally completed fn a thorough and professional manner.
Maintenance personnel were knowledgeable of the assigned tasks.
Maintenance procedures were detailed and actively used on the Iob.
LER 97-024-00 D
LICENSEE Solid state protecgon system (P-10 6 P-14 Permfsslves) testing defidency. This condition was caused by an Inadequate testing scheme provided by the SSPS vendor that resulted in not properly testing all Inputs for the P-10 and P-14 functions.
VIO 97-10-01, Example 4 NRC
~
A fourth example of the Failure to Establish and Implement Operating and Surveillance Procedure vlotatlon was Identi6ed for deadheading the TDAFWP.
NCV 97-10.02, Example
~ LICENSEE Anondted vhtation was Identttted for Failure to Establish and Implement TDAFWP 1of2 Maintenance Procedures.
Two examples were Identified: 1) failure to followa maintenance procedure for Installation of the TDAFWP coupling.
IR 97-10 NRC Maintenance and surveillance activities observed were being properly conducted.
Maintenance and Operations personnel performing the survelllances were approprhtely sensitive to potential problems and appropriately performed peer checking to identify potential problems before they impacted plant operations.
NCV 97-10-02, Example LICENSEE A nond ted violation was identified for Failure to Establish and Implement TDAFWP 2of2 Maintenance Procedures, Two examples were IdentiTied: 2) failure to establish an adequate procedure for gasket cutting and assembly of the TDAFWP.
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i ENGINEERING~z.. ~p:~g~i,<r FROM: 10/1$ 7 TO: 11/16/98 Page13of 28 FOR PUBLIC RELEASE Last Updated:
8/15/98
HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/4/98 Positive 7/4/98 Posltiv8 7/4/98 Weakness 7I4I98 Positive 7/4/98 VIO 7/4/98 URI 8/15/98 Positive IR 98.07 IR 98-06 IR 98-06 IR 98.06 IR 98-06 VIO98-06-03 UAI9846-04 NRC Five subject Engineering Service Requests IESRs) were rejected for valid technical and/or administrative reasons.
No significant Issues were dropped when these ESRs were rejected.
SELF The Nuclear Assessment Section assessments and the self-assessments performed by engfneerlng section personnel were effective in Identifying engineering performance deficiencies. and were useful ln providing Insights to management.
Corrective actions in response to the findings were generally acceptable.
This was a positive obseNation.
NRC The licensee's planning and project management for the steam generator replacement proJect appeared to be comprehensive and well organized.
NRC The licensee's training for qualification of engineering personnel on 10 CFR 50.59 requirements was effective and complied with NRC requirements.
NRC Avhlation was identified for failing to followthe approved corrective acbon program innot Inlthtfng a condition report durfng the 1997 refueling outage for a deviation from the approved design In relation to brackets ce the containment sump suction pipes. The root cause investigation for the containment sump bracket Issue was thorough.
NRC For 15 of 16 unrevfew'ed safely questke determinations reviewed, the licensee's determfnagon that the corresponding changes dldnot Involve anunreviewed safety question were ccesldered correct. An unresolved item was opened with respect to unrevlewed safety questke determinations as described in the safety evaluation for the cycle 6 r8load.
NRC Aweakness was kfentified for the increase In the backlog of work In the Engheering section since 1996. However, at the present time, safety has not been Impacted by the increase In work backlog.
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I IQOQ CO QE 1 234 A CIQOO 8 OQBO c 0 OCI 1 234 A ClC300 8 OOOCI c 0 CIO 1 234 Cl 5
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8/15/98
HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/4/98 URI 7/4/98 POSTIive 7/4/98 Positive 5/11/98 Positive 5/11/98 Positive 5/11/98 Positive 6/18/98 Negative URI 9846.04 IR 98-06 IR 98-06 IR 98-04 IR 98-03 IR 98.03 IR 98.03 SELF Engineerhg Service Request (ESR) 98.00134, Reactor Coohnt Pump Long Term Operability with Reduced Compartment Cooling, Rev. 0, was prepared in
'ccordance with applicable procedures.
The ESR describes a valid analysis that concluded that operation of reactor coolant pump 'C's a'cceptable until the next refueling outage.
NRC An operability evaluation for reactor head vent valve 1RC-905'was conducted In accordance with required procedures.
However, itwas not performed until approximately 8 months after the condition occurred due to management willingness to live with the cutoff-service condition. This condition constituted an unecessary operational burden on plant operators.
NRC Nudear Assessment Section audits in Engineering were good.
NRC A 10 CFR 21 report on the turblne4rfven auxiliary feedwater water pump governor valve stem was being adequately addressed.
NRC
~
In general, engtneedng activities were being conducted adequately and in accordance with required procedures.
NRC For 19 safety evaluation forms reviewed, the licensee's determinations that an unrevlewed safety question determfnation was not required wire considered correct, although the bases for those determinations were typicallyweak. Similarly, the bases for unrevlewed safety question determinations were weak ln some cases.
The inspector's findings In this regard were consistent with the findings descdbedin a recent Nudear Assessment Section assessment of this program.
SELF The licensee's program for complying with 10 CFR 50.59 was consistent with that rule, and withTechnical Spedfication 6.5.2.6. The licensee had established suitable programmatic guidance to ensure that the regulatory requirements of 10 CFR 50.59 would be met, and the Information necessary for preparing adequate safety evaluations was availabte to licensee personnel.
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OB0 12345 A 00000 B OOOBO Co 000 12345 A 00000 B OQOBO Co 000 12345 A OOBOB 8 00000 Co 000 12345 A'0000 0 B OQOBQ C 0 000 12345 A QOBBO B 00000 Co 000 FROM: 10/I/97 TO: 11/16/98 Page 15 of 28 FOR PUBLIC RELEASE Last Updated:
8/15/98
HARRIS 16.Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES Negative 2/28/98 Negative 2/28/98 Positive 2/28/98 Weakness 2/28/98 Pos! tive 2/28/98 Positive TS amendment IR 98-01 IR 98-01 IR 98-01 IR 98-01 IR 98 01 LICENSEE NRC NRC NRC NRC NRC Slow licensee response to a staff RAI on TS amendment entitled 'defection of shutdown requirements from selected surveillances.'he staff requested, on several occasions since Suly 1997, for a response to the RAI. however, a response was not received untff April 13, 1998, after the licensee Identified an urgent need for the amendment.
The late response created the need for additional staff effort to.
ensure that the amendment was issued In an expedited manner. The need to review and approve the amendment in an expedited manner was to preclude a potential plant shutdown.
Condition report trending had not revealed a trend related to the blowdown events, which had resulted in a tack of management attention prior to the event. NRC IR 50-400/97-12 reviewed trending and concluded that inconsistent trending had contributed to the significance and longevity of some performance issues.
The steam generator btowdown water hammer event was an example consistent with those conduslons.
Management, Including the Plant Nuclear Safety Committee, was appropriately focussed on determining the root cause of the December 1997 'C'team generator blowdown system water hammer event and ensuring corrective actions provide a permaneht solution. The root cause investigation was appropriately rejected by the PNSC due to a lack of adequate detail related to why prior actions failed to resolve the problem.
A trend in corporate procedure Inadequacies was IdentiTied. Trending of corporate related adverse conditions was diluted because the condition reports were spread over the site corrective action data bases of three sites, rather than one data base.
The licensee had Identified that trending program guidance in general was weak and was determining a course of action to fmprove it.
The short term operability determination for containment recirculation sump brackets
'as adequate.
II concluded that foreign material exclusion cover brackets tnstalled during construction could remain in the sump and the sump would still perform its Intended function. The conclusion was based on tack welds having been strength-tested during the outage (RFO7), on ca!cutatfons which showed that ifthe brackets came loose they wouldn't be transferred into the sump, and that grout fnstalled during RFO7 would hold the brackets in place.
The engineering operability evaluation for a paper wipe found in the diesel generator lube ofi suction tank was thorough.
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5 A QGGClG B CIOOHCl c 0 QClG 12345 A GGOCl0 B OQC300 C 0 CIOB FROM: 10/1/97 TO: 11/16/98 Page16ol 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/17/98 Negative IR 97-13 NRC The feedwater preheater bypas valve actuators system was not described in the FSAR.
2 3
4 5
1/17/98 Negative 1/17/98 Positive 1/17/98 VIO 1/9/98 LER 12/6/97 Positive 1/17/98 Negative-URI 97-13-03 NRC The licensee imp!emented corrective actions for deficiencies Involving inadequate dose out and turnover of modified systems which do not provide for recurrence control. An unresolved item was opened because an extent of condition review had not been completed to Identify the scope of the problem.
IR 97-13 NRC The licensee's field evaluafion of the 'O'GBD problems was thorough. Good support was obtained by personnel called in offholiday leave and the repair activities were well coordinated.
This water hammer event was the most significant water hammer event In the SGBD system since May 1997.
VIO97-13.02 NRC A correcfive acfion vfoiafion was identified because the ficensee had not adequately addressed a design deficfency assodated with the feedwater preheater bypass containment Isolation valves. The deficfency involved a slow loss of air pressure that could cause the actuator to be Incapable of operating, resulting in the valve not dosing when called on by an automatic closure signal.
IR 97-13; VIO 50-400/97-NRC 12-05 The licensee did not 5mely implement corrective actions for a conditIon adverse to quality Involving devfafions between as constructed plant configuration and design output documents contained in EQDPs. This item was Identified ln violation 50-400/97-1245.
LER 98-001-00 LICENSEE Potential condltke outside design basis related to instrument air system leak causing the S/G pre-heater bypass isolation valves to be inoperable.
IR 97-12 NRC The AFW assessment was performed in accordance with commitments to NRC and deficiencies were documented In the Corrective Action Program for tracking and disposifion.
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a OOOOB B OOOOO C Q OBQ FROM: 10/1/97 TO: 11/16/98 Page 17 of 28 FOR PUBLIC RELEASE Last Updated; 8/15/98
HARRIS 16.Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/6/97 Strength 12/6/97 Positive 12/6/97 Weakness 12/6/97 Weakness 12/6/97 Negative 12/6/9?
VIO 12/6/97 VIO IR 97-12 IR 97-12 NRC The assessment of Operafions and Engineering support programs was being adequately performed by the PES unit.
IR 97-12 IR 97-12 NRC NRC Troubleshooting had Improved and was at the appropriate level for 3 of the 4 examples observed.
The synchronization to the grid toubleshooting did not have suifident irialmangement aNenfion to ensure success equivalent to the other 3.
This was mainly due to inadequate communication of expectations down the management chain. The communication aspect was Identified as an additional example of the engineering communlcafion weakness from NRC IR 50400/97-10.
Aprocurement engineering weakness was Identified in review of the materials evaluation for a replacement motor starter.
IR 97-12 NRC The licensee's Nudear Assessment Secfion evaluallon of the Environmental Quaiificafion (EQ) Program Induding the line response to the assessment were adequate, however, the assessment did not address the hadequate EQ Program procedures.
VIO 9?-12-05, example 2 NRC Two addtthna1 10 CFR 50 Appendix B Criterion Vvlolafion examples were Identified for fafiure to estab!ish and Implement engineering procedures.
The second additional example was for fafiure to establish a dear time requirement for updafing environmental qualification documentation packages to ensure that the packages are malntahed current and auditable for installed ptant equipment.
VIO 97-12-05, example 2 NRC Two additional 10 CFR 50 Appendix B Criterion V violation examples were identified for faHure to estabfish and Implement engineering procedures.
The first additional example was for faHure to update EDBS fogowhg Instagatlon of replacement motor starters In the post acddent hydrogen analyzer.
NRC The use of industry assessors (peers) on the PES assessment team was considered astrength.
=
1 2
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/6/97 VIO 10/25/97 Negative 10/25/97 NCV l,PLrANTrSUPPORT1W%$ 4%4M'c VIO97-12-05, example 1
NRC IR 97-10 NCV 97-10-03 This was Identified as a violation of 10 CFR 50 Appendix 8 Criterion V, failure to.
establish and imptement engineering procedures.
The licensee's procedural controls for computer software development activities tailed to ensure that the development activities could not affect quality related software and associated data files installed In the phnt.
SELF Communications wINn engineering management related to the TDAFWP needed ImprovemenL NRC In general, Engineering acthNes were being adequately conducted in accordance with required procedures.
A noncfted violation was identified for the unapproved extension of a temporary modification due date.
1 234 A CICIQO B OCIOO CO OB 1 234 A 0000 B 0000 CQ OB 1 234 A OOBO s CIQOB CO 00 5
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0 8/15/98 Positive 8/15/98 Positive 7/4/98 Positive 8/15/98 Positive IR 98-07 IR 98 07 IR 98-07 IR 98-06 NRC Fire Protection activities were being adequately conducted in accordance with procedures.
NRC The performance of Security and Safeguards activltlels was In accordance with applicabte procedures.
NRC The control of contamination and dose for the site was good and was attributable to good teamwork between the various departments.
SELF Fire protection activities were being adequately conducted.
1 2
3 4
5 a 00000 B OCIOOQ C B 000 12345 A OQQOCI B OOQCI0 C B CIQO 12345 A 00000 B 00000 C B 000 12345 a OOOOO B 00000 C B 000 FROM: 10/1/97 TO: 11/1 6/98 Page 19 of 28 FOR PUBLIC RELEASE Last Updated:
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1'
HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/4/98 Positive 7/4/98 Positive 6/18/98 Positive 5/11/98 Positive 5/11/98 Positive 5/11/98 Positive 6/18/98 Positive IR 98-06 IR 98-06 IR 98-04 IR 98.04 IR 98.03 IR 98.03 IR 98.03 NRC The protected area barrier was observed to be In good condition. Isotations zones were of suNcient size and were free of objects.
SELF Participant performance ln the July 9, 1998, drilldemonstrated an acceptable ability to respond to emergencies.
NRC The licensee's program for testing of continuous air monitors satisfied the speciffcagons set forth In the Final Safety Analysis ReporL NRC The Inspectors found radiological controls to be in accordance'with required procedures.
The general approach to the control of contamlnagon and dose for the site was effective. Teamwork between the vadous departments continued to be a major contributor to the good control of dose.
NRC The perlormance of security and safeguards activities was good.
NRC Fire protection activities were being adequately conducted.
NRC The control of contamination and dose for the site was good and was attributable to good teamwork between the various departments.
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FROM: 10/1/97 TO: 11/16/98 Page 20of 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
IDid ISSUE(s)
SMM CODES 2/28/98 Strength 2/28/98 Strength 2/28/98
~
Positive 2/28/98 Positive 2/28/98 Weakness 2/28/98 VIO 2/28/98 Strength IR 98-01 IR 98-01 IR 98-01 IR 98.01 IR 98.01 VIO 98-01-04 IR 98-01 NRC The ficensee's 1998 Nuclear Assessment Sec5on assessment of the facility's fire protection program was of good quafity and effective in Idenfifying fire protection program performance to management.
Correcfive acfions in response to the ldenfified assessment Issues were being tmplemented and completion was anficfpated kt 1998.
SELF The fire barrier penetrafion seal installer was appropriately trained to accomplish fire banler penetra5on seal installation work and QC inspectors were qualified to perform the appropriate verifica5on for installation and repairs made to the fire barrier penetration seals.
SELF The lire brfgade demonstrated good response and fire fighting performance during a simulated fire brigade drificonducted during tMs inspection period.
NRC The surveillance Inspection procedure for the fire barrier penetrafion seals was adequate.
The three most recent inspections had been satisfactorfiy Implemented.
However, a large number of fire protection surveifiance procedures continued to be Implemented wltMn the procedure grace period. An Improvement over the results from previous inspecfions was noted, but continued management attenfion Is needed to achieve the corrective action goal of timely surveifiance performance.
NRC The ficensee did not perform engineering evaluafions that followed the guidance of NRC GL 86-10 for deviations from lire barrier configurafions qua!ified by tests. This was considered an engineering program weakness.
SELF The performance of security and safeguards acfivitles were good. Security staff responded appropriately to the discovery of a gun during processing of employee belongings In the access area X-ray macMne.
NRC Avhtafion was identified for failure to adequately implement and maintain the applicable fire protecfion program design control documentafion requirements that demonstrated that the as-bull t configurations ol fire barrier penetration seats P 3008, P 447A, and E 156 were bounded by the vendor's design and test documentafion.
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
'MMCODES 1/29/98 LER 1/17/98 NCV 1/l7/98 NCV 1/17/98 Positive 1/17/98 Positive 1/17/98 Positive 2/28/98 Strength IR 98-01 LER 98-S01-00 NCV 97-13.05 NCV 97-13-04 IR 97-13 IR 97-13 IR 97-13 SELF The control of contamlnafion and dose for the site was good and was attributable to good teamwork between the various departments.
LICENSEE Unescorted access granted to contract outage worker due to falsified Personal History QuesUonnalre (PHQ).
LICENSEE Design deficfency of Appendix R, III,G, fire protecfion of safe shutdown capability.
LICENSEE Breach of Appendix R, III,G, fire protection of safe shutdown capability.
NRC Fire protection acfivlUes were being adequately conducted.
NRC The performance of security and safeguards activlUes were good.
NRC The surveillance requirements for demonstrafing operability of the meteorological monitoring Instrumentafion were met.
12345 A 00800 8 00000 C 0 000 1
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A 00800 B 00000 CB 000 12345 A 00080 s 00000 C 0 00'0 12345 A 00080 B 00000 C 0 000 12345 A 00800 B 00000 C 8 000 1
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 1/17/98 Positive 1/17/98 Positive IR 97-13 IR 97-13 NRC The licensee had effectfvely Implemented the radiological environmental monitoring program. The sampfing, analyfical and reporting pr'ogram requirements were met and the sampling equipment was being well maintained.
NRC The licensee was maintaining radioactive effiuent monitors in an operable condition and performing the required surveillances to demonstrate their operability.
1234 a OHHQ B GOGO CO 00 1 234 5
0 0
0 1/17/98 Positive 1/17/98 Positive 12/12/97 Positive 12/12/97 Positive 12/12/97 Positive IR 97-13 IR 97-13 IR 98-02 IR 9842 IR 98-02 NRC The licensee had maintained an effective program for the control of liquid and gaseous ratfioactfve emuents from the plant. There was an overall decreasing trend in the amoun6 of activity released from the plant in fiquld and gaseous effiuents and the radiafion does resulting from those releases were a small percent of regulatory limits.
NRC The licensee was closely monitoring annual and outage collective dose and was generally very successful inmeeting established ALARAgoals. Maxlum individual radlaiton exposures were controlled to levels which were well within the licensee's administrative limitand the regulatory limits for occupational dose specified In 10 CFR 20.1201 (a).
SELF The review and verification of commitments of selected security and administrative procedures did not identify any Inconsistencies or noncompliance.
SELF The IntrusIon detecfion systems and assessment aids were functional, well maintained, and effective for both covert and overt penetrafion attempts, and met the licensee's commitments.
SELF The inspector concluded through observation and Interviews of security force personnel that the security force could adequately cope with the design-basis threat described In 10 CFR 73.1(a) and that the security force met the requirements of the PSP and T8 Q Plan. The security training program was a major strength ln the security program.
a 0800 B CIHOO C 0 CICI 1 234 o ~
a 00000 B 00000 C 8 OOCI 1
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a OOOO 0 B ClOOCI 0 CH 000 12345 a ClGOO 0 B 00000 C 8 OCIO 12345 a 00000 B 00000 CH 000 12345 a OOGQO B OQCIOO CH 000 FROM: 10/1/97 TO: 11/1 6/98 Page 23 of 28 FOR PUBLIC RELEASE Last Updated:
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HRRRIS 16-Nov.98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/12/97 Positive 12/12/97 EEI 12/12/97 Positive 12/12/97 Positive 12/6/97 Positive 12/6/97 Positive 12/6/97 Positive IR 98-02 EEI 98.02-01; LER 97-S01-00; LER 97-S01-01 IR 98-02 IR 98-02 IR 97-12 IR 97-12 IR 97-12 SELF The licensee was comtylng with the criteria of the Physical Security Plan (PSPI and Security Plan Implementing Procedures for alarm staflons and communications.
NRC Two viotaflons weie Idenflfled invoMng Individuals responsible for implementing the Access Authorfzaflon Program who, on18 separate occashns, fafled to.process personnel property for unescorted access to the site's protected and vital areas.
This resulted In contractors who were not authorized having been granted unescorted access to the protected and vital areas.
This ls apparent vfolation EEI 9%00/984241.
SELF Through obsenrathns, discussions with security force personriel, and document review, Itwas determined that the licensee used compensatory measures which ensured the rellalityof security-related equipment and devices. Asignificant reduction In compensatory hours was the result of effective maintenance support, NRC Fire Protectke acUvffles were being adequately conducted.
NRC The performance of Security and Safeguards acflviUes was good.
NRC The licensee's ALARAprogramwas effectively implemented and adequately controlled collective dose.
SELF The evaluaflon of the Protected Area (PA) access controls for packages, personnel, and vehicles revealed that the criteria of the Physical Security Plan were being met in an excellent manner.
12345 A OClCl00 8 00000 C8 000 12345 A CICI800 B 00000 C 8 CIClCI 12345 A 00000 B 00000 C 8 000 1
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4 5
a 0000 0 B 00000 C8 000 12345 a 008DCI g ODOQO C 8 Cl00 1 234 5
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A 00800 8 00000 C 8 QOCI FROM: 10/1/97 TO: 11/1 6/98 Page 24 of 28 FOR PUBLIC RELEASE Last Updated:
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o
HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/6/97 Negative 12/6/97 Positive 12/6/97 Positive 12/6/97 Positive 10/25/97 Positive 10/25/97 Positive 10/25/97 Positive IR 97-12 IR 97-12 IR 97-12 IR 97-12 IR 97-10 IR 97-10 IR 97-10 NRC Some radla6on workers interviewed had a minimallysufficient knowledge of RWP requirements and working condi6ons.
Prior to the end of the fnspection the affected workers had increased in their RWP knowledge. Inadequate training.
NRC Specific radiation controls were effectively implemented with good occupational exposure controls demonstrated during routine power operations.
NRC Self assessment ac6vNes were Identified as a strength of the licensee's radiation control program.
NRC
'he Hcensee's ratLt6on control program in the areas of radiation surveys, Radiation Work Procedure controls, and pre-Iob planning and ALARAbriefings were Implemented effectively and in accordance with procedures.
SELF Fire Protection activities were being adequately conducted.
SEI.F The performance of Security and Safeguards activities were good.
SELF Emergency Preparedness activities, fn general, were adequatety conducted.
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A OOClOQ g OCIBCICI C B QCICI 12345 A QQBQQ g 00000 CB 000 12345 A OClQQB g QOOOB C 0 OCIB 1
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A OOBOCI g 0OQ CI CI C B CICICI 1
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A OQBOO B QCIOCIO C 0 OCIQ 1
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A OOBOQ g OCICIOQ C 0 000 12345 A 00000 8 OCIQCI0 CB 000 FROM: 10/I/97 TO: 11/I 6/98 Page 25 of 28 FOR PUBLIC RELEASE Last Updated:
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HARRIS 16 Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SINM CODES 10/25/97 Positive 10/10/97 Positive 10/10/97 Negative 10/10/97 Positive 10/10/97 Positive 10/10/97 Positive 10/10/97 Positive IR 97-10 IR 97-11 IR 97-11 IR 97-11 IR 97-11 IR 97-11 IR 97-11 SELF The control of contamination and dose for the site was good and was attributable to good teamwork between the various departments.
NRC The controller/evaluator organization conducted an excellent critique process.
NRC An exercise weakness was Identi6ed concerning timely protective measures for the TSC.
NRC The licensee demonstrated the ability to Implement protective'measures for onsite personnel and to make the required protective ac6on recommendations (PARs) for the protection of the p'ublic.
NRC ERFs were organized, equipped, and maintained in a manner that provided for the emergency response.
NRC Provisions existed for the prompt communications among principal response organizations to emergency personnel, and they were effectively used during the exercise to provide timely information and coordinate emergency response.
NRC The JIC and its staff were activated and functioned In a manner that provided for the dissemination of coordinated and accurate information to the public via the news media.
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C 1 234 00 80 0000 8
00 1 234 A 0000 B 0000 C8 00 1 234 A 0080 B 0000 CO 00 1 234 A
B C
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00 1 234 A 0800 B 0000 C8 00 1234 A
B C
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00
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FROM: 10/1/97 TO: 11/16/98 Page26of 28 FOR PUBLIC RELEASE Last Updated:
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r
~
HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/10/97 Positive 10/10/97 Positive 10/10/97 Positive 10/10/97 Positive IR 97-11 IR 97-11 IR 97-11 IR 97-11 NRC The licensee demonstrated the abflityto make timely and concise initial and follow-up nottflcatfons to the States and counties.
NRC The licensee had a standard system for emergency dassiflcations and used it to effectivel classify the off-normal events promptly and correctly.
NRC Onsite Emergency Organization-Predesignated personnel with well defined responstbilifles promptly staffed the Emertency Response Facilities (ERFs).
NRC The scenario developed for this exercise was effective for testing the integrated emergency response capability and exercise preparations were well organized.
1 234 A OCIHO B OOOO CH 00 1 234 A QOHO B l3000 CH 00 1 234 A 0000 B 0000 CH 00 1 234 A 0000 B 0000 CH 00 5
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HARRIS 16-Nov-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES SMM 1A 1B 1C 2A 2B 3A 3B 3C 4A 4B 4C 5A 5B 5C Template Codes:
OPERATION PERFORMANCE - Normal Operations OPERATION PERFORMANCE - Operations During Transients OPERATION PERFORMANCE - Programs and Processes MATERIALCONDITION ~ Equipment Condition MATERIALCONDITION-Programs and Processes HUMANPERFORMANCE - Work Performance HUMANPERFORMANCE - KSA HUMANPERFORMANCE-Work Environment ENGINEERING/DESIGN - Design ENGINEERING/DESIGN - Engineering Support ENGINEERING/DESIGN -
Programs and Processes PROBLEM IDENTIFICATION6 SOLUTION - IdentiTication PROBLEM IDENTIFICATION6 SOLUTION - Analysis PROBLEM IDENTIFICATION& SOLUTION - Resolution SALP Functional Areas:
ENG ENGINEERING MAINT MAINTENANCE OPS OPERATIONS PLT SU PLANTSUPPORT SAQV SAFETYASSESSMENT6 QV ID Code:
UCENSEE LICENSEE NRC NRC SELF
SELF-REVEALED EEIs are apparent violations of NRC requirements. that are being considered for escalated enforcement action in accordance with the 'General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached Its final enforcement decision on the Issues Identified by the EEIs and the PIM entries may be modified when the final decisions are made.
Before the NRC makes Its enforcement decision, the licensee willbe provided with an opportunity to either (1) respond to the apparent violation or (2) request a predeclslonal enforcement conference.
URls are unresolved Items about which more Information ls required to determine whether the Issue ln question Is an acceptable item, a deviation, a nonconformance, or a violation.
However, the NRC has not reached Its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
FROM: 10/1/97 TO: 11/16/98 Page 28of 28 FOR PUBLIC RELEASE Last Updated:
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