ML20196G248
| ML20196G248 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/25/1998 |
| From: | Brian Bonser NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Keenan J CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 9812070293 | |
| Download: ML20196G248 (32) | |
Text
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v.
4 November 25, 1998 Carolina Power and Light Company ATTN: Mr. J. S. Keenan Vice President' Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461
SUBJECT:
INSPECTION PLAN - BRUNSWICK NUCLEAR PLANT
Dear Mr. Keenan:
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 Semi annual Plant Performance Review, which the staff has moved to February 1999, because of the agency's shift to an annual Senior Management Meeting cyc!9.
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 will continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed 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. contains a historical listing of plant issues, called the Plant issues Matrix (PIM).
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The PIM includes only items from inspection reports or other docketed correspondence
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between the NRC and Brunswick Nuclear Plant. This material will be placed in the Public Document Room.
9812070293 981125 PDR ADOCK 05000324 O
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CP&L 2
We willinform you of any changes to the enclosed inspection plan. If you 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 l
Division of Reactor Projects l
L Docket Nos. 50-325,50-324 License Nos. DPR-71, DPR-62
Enclosures:
- 1. Inspection Plan
- 2. Plant issues Matrix cc w/encis: (See page 3) 1 l
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Site Operations Robert P. Gruber Brunswick Steam Electric Plant Executive Director Carolina Power & Light Company Public Staff NCUC So th
, NC 28461 a eigh NC 27626-0520 J. J. Lyash, Plant Manager Public Service Commission Brunswick Steam Electric Plant State of South Carolina Carolina Power & Light Company P. O. Box 11649 P. O. Box 10429 Columbia, SC 29211 i
Southport, NC 28461 Jerry W. Jones, Chairman l
D. B. Alexander, Manager Brunswick County Board of
)
Performance Evaluation and Commissioners i
Regulatory Affairs CPB 9 P. O. Box 249 i
Carolina Power & Light Company Bolivia, NC 28422 P. O. Box 1551 i
Raleigh, NC 27602-1551 Dan E. Summers Emergency Management Coordinator K. R. Jury, Manager New Hanover County Department of Regulatory Affairs Emergency Management Carolina Power & Light Ccmpany P. O. Box 1525 Brunswick Steam Electric Plant Wilmington, NC 28402 P. O. Box 10429 Southport, NC 28461-0429 William H. Crowe, Mayor City of Southport William D. Johnson 201 E. Moore Street Vice President & Senior Counsel Southport, NC 28461 Carolina Power and Light Company P. O. Box 1551 Distribution w/encls: (See page 4)
Raleigh, NC 27602 Mel Fry, Director Division of Radiation Protection N. C. Department of Environment and 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
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i CP&L 4
Distribution w/encis:
L R. Plisco, Ril j
B. R. Bonser, Ril D. C. Trimble, NRR J. L Coley, Rll R. S. Baldwin, Ril J. J. Lenahan, Ril E. D. Testa, Ril D. H. Thompson, Ril G. West, Ril J. L. Kreh, Ril G. R. Wiseman, Ril PUBLIC NRC Resident inspector U. S. Nuclear Regulatory Commission 8470 River Road, SE Southport, NC 28461
- FOR PREVIOUS CONCURRENCE - SEE ATTACHED COPY OFFICE DRP/RIl DRS/Ril DRS/Ril DRS/Ril DRS/Ril SIGNATURE NAME
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- ABelisle DATE 111 /98 11/ /98 til /98 11/ /98 11/ /98 11/ /98 11/ /98 COPY?
YES NO YES NO YES NO YES NO YES NO YE',
NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: 1:VIPB4\\BRUiPPR\\PPRLTR1.WPD l
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Distribution w/encis:
L R. Plisco, Ril B. R. Bonser, Ril D. C. Trimble, NRR J. L. Coley, Ril R. S. Baldwin, Ril J. J. Lenahan, Ril E. D. Testa, Ril D. H. Thompson C. W. Jui,es, W, Ril G. West, Ril J. L. Kreh, Ril G. R. Wiseman, Ril PUBLIC NRC Resident inspector U. S. Nuclear Regulatory Commission 8470 River Road, SE Southport, NC 28461.
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NO YES NO YEs NO OFFICIAL RECORD DOFY DOCUMENT NAME: 1:\\RPB4\\BRUPPRPPRLTRt.WPD
BRUNSWICK INSPECTION PLAN INSPECTION TITLE / PROGRAM NO.OF PLANNED TYPE OF PROCEDURE AREA INSPECTORS INSPECTION INSPECTION -
DATES COMMENTS IP 84750/
Radiation Protection 1
11/16/98-11/20/98 Core inspection IP 86750 IP 82701 Emergency 1
12/7/98-12/11/98 Core inspection Preparedness IP 84750/
Radiation Protection 1
12/7/98 12/11/98 Core inspection IP 86750 IP 83750 Radiation Protection 1
1/4/99 1/8/99 Core inspection IP 40500 Effectiveness of 3
1/4/99-1/8/99 Core inspection Licensee Controls in identifying, Resolving, and Preventing Problems IP 93809 SSEl - Safety System 5
1/11/99-1/15/99, Core inspection Engineering inspection 1/25/99-1/29/99 IP 73753/
Maintenance 1
2/22/99-2/26/99 Regional initiative -
IP 92902 Open item Followup and IGSCC/ internals Coating Inspection IP 81700 Security 1
3/8/99-3/12/99 Core Inspection IP 92904 Fire Protection 1
3/29/99-4/2/99 Regional Initiative -
Open item Followup and Fire Protection improvement Program Review L-
Page: 1 cf 4 Date: 11/2S/1998 Unit d States Nucicar R;gulatory Comm..ission r.meno;52:So.
negion ti PLANT ISSUE MATRIX BRUNSWICK By Primary Functional Areo Functional Template Date Source Areo ID Type Codes item Description 11/09/1998 1998009 Prt ENG NRC POS Prt 58 Improvements were noted in the evoluotion of Inservice Testing Program non-conformances identification of 3,,
root and contributing causes and h @n e ifotion of corrective actions.
Tec 11/09/1998 1998009 44 Prt ENG NRC VIO IV Prt dB Review of a service water volve test foilure revealed on inodequate ondysis justifying nuclear service water P*#
Sec-Sec: 2B P
N*
impacts resutting from this vdve test failure, os weR os for the failure to obtain supervisory opprovd for the Tec operobility determinatiort l
11/09/1998 199800941 Pri: ENG NRC VIO IV Prt 3A Three examples of failures to follow odministrative procedures and thus TS 5.4.1:
E 4
Sec: MAINT Sec: 38
- 1) The inspectors identified a procedure violation during the performance of the Residud Heat Removal Remote Shutdown Ponel System Flow Channe! Cotibration. Technicions did not property flush the transmitter in
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Tec occordance with the procedure. All other ospects of the evolution observed were performed satisfactorily.
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- 2) The inspectors identified a violation for the licensee *s failure to property maintain or retain inservice Testing Deviation Reports, which were o record of pump and volve testing performance problems and corrective T
oClions.
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- 3) The inspectors identified o procedural dotation regarding the failure to perform o procedure revision prior to implementing a procedure acceptance criterio change for on Inservice Testing volve stroke time.
L 09/21/1998 1998009 Prt ENG NRC NEG Prt 2B Both channels of the rodiction monitors for the steam jet air ejectors were dectored inoperable os o result of I
Sec-
- Sec, conflicting terminology and dato produced by severd different procedures Resolution of the conflicting 7
procedures. terminology, and dato by the licensee continued to be poor.
Ter-08/29/1998 1998008 Prt ENG NRC NEG Prk 4C Long standing inspection findings identified between 1996 and 1997 involving potentid discrepancies between
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pl nt s-found conditions and the plant licensing basis resulted in four vioiotions being identified. However. for Se '
Sec-'
each of these violations, the NRC exercised discretion in occordance with the Enforcement Policy and refrained Tec from issuing a citation.
I 08/29/1998 199800841 Prt ENG Licensee NCV Prt 2B The licensee identified a missed Technicd Specifications surveillonce ossociated with the Standby Gos Treatment Sec-Sec*.
System when they identified a deficiency in the aerosol mixing testing. This condition was treated as a Non-Cited Violation.
Tet i
I 07/25/1998 1998008 Prt ENG NRC POS PrtSC The licensee satisfactority implemented the long-term solution for thermd hydroutic instabilities in response to NRC I
Sec-Sec.
Generic letter 9442. Long-term Solutions and Upgrade of Interim Operating Recommendations for
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Thermol-Hydraulic Instabilities in Boiling Water Reactors, Ter:
Item Type (Compliance. Followup.Other), From 05/25/1997 To 02/13/1999 e
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Page: 2 of 4 Unit:d Statss Nuclear R;gulatory Commission Dole: 11/25/1998 - '
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gegion it.
PLANT ISSUE MATRIX BRtJNSWICK By Primary Functional Area Functional Template
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Date Source Area ID.
Type Codes item Description 09/30/1998 1998009 Prt MAINT '
NRC POS Pri:3A Corrective maintenance octMties on the Service Water system were property performed. odequate!y Sec-Sec.
coordinated. and satisfactority supervised.
i Ter 08/19/1998 1998008 Prt MAINT NRC NEG Prt 3A Maintenance actMties were conducted odequately with one exception inoMng the failure to follow procedures S -
Se, fier the identification of sluggish brecker handle response. This condtion did not offect breaker operability and the licensee responded to the concern by inittoting lessons learned fronning and oppropriate corrective i
Tet maintenance. This !ssue was identified as o minor violation.
08/19/1998 1998008 Prt MAINT NRC NEG Prt3A instrumentofion and Control Technicians were generary knowledgeable and experienced in conducting K
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3,c.
electricd breaker preventive maintenance Maintenance ocitivil;es were conducted odequately with one exception invoMng the failure to follow procedures offer the identification of sluggish breaker hande response Tet This condition did not offect breaker operability and the licensee responded to the concern by initioting lessons learned training and oppropriote corrective maintenance. This issue was identified as a minor violation.
08/05/1998 1998008 Pri: MAINT NRC' POS Prt 2B The Maintenance Rule expert panel conducted thorough reviews of system classification changes. The Plant Se -
Sec M Nuclear Sofety Committee choirman provided a good safety focus and knowledge of industry maintenance rule 0
experience.
Ten i
iI/09/1998 1998009 Prt OPS NRC POS Prt 2A increased licensee ottention hos resutted in a reduction in the number of " operator workarounds? However.
opportunities to correct on outoge-related workaround were not token.
3 3,
3 I
Tet 11/09/1998 1998009 Pri: OPS NRC POS Prt 38 The licensee s operator requalification program complied with the requirements and standards of plant See:
Sec: IC procedures os well os the requirements of 10 CFR 55.59 for the areas inspected. The licerceo developed and odministered simulator examinations, in-plant Job Performance Measures (JPMs) and simulator JPMs that
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Ten effectively identified creas in need of improvement.
t 11/09/1998 1998009 Prt OPS NRC POS Prt 3B The feedback program and the remedid training programs were effective tools for improving the overoll I
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Sec K licensed operator requalification program.
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Ter 07/30/1998 1998008 Prt OPS NRC NEG Prt 30 Due to the time constroints involved with the implementation of the Thermd Hydroutic Instability modfication, S
Sec-the licensee did not meet their normd level of operator training expectations.
Ter:
Item Type (Compliance. Followup.Other), From 05/25/1997 To 02/13/1999
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Page: 3 of 4 Dole:11/25/1996 Unit d Stat:s Nucisor Rsgulatory Comm,ission nme:io:s2:so.
- negion n PLANT ISSUE MATRIX BRUNSWICK.
By Primary Functional Area Functianci Temploie Date Source Area ID Type Codes item Description
=
07/30/1998 1998008 Prt OPS NRC POS Prt 38 Ucensed simulator training was adequately performed The operations crew 'esponded satisfactority to oB the occident scenarios.-
- Sec, I
Tec 10/10/1998 1998009 Prt PLTSUP NRC POS Prt 2A. Control of transient combustibles has improved. Two instances of improper storage of combustible materials S
- Sec, were identified by the inspectors. Proper dispositioning of the items was satisfactorily accomplished.
Tec i
08/29/1998 1998008 Pri: PLTSUP NRC NEG Prt 1C A fire brigade orill program weakness was identified for not specificolly demonstrating fire brigade response S
- Sec, through drills in fire creas where devictions from NRC fire protection requirements had been approved.
Tec i
e 08/29/1998 1998008 Pri: PLTSUP NRC POS Prt IC The implementation of procedural requirements for using and storing transient combustibles in safety-related Sec-Se re s w s effective. Controls for combustible gas burk storage and cutting and welding operoflons were being enforced.
Ter r
08/29/1998 1998008 Prt PLTSUP NRC POS Prl-2A The observed level of plant housekeeping reflected good organization and cleontiness proctices on the part of plant workers.
3,,
3 Tec l
08/29/1998 1998008 Prt PLTSUP NRC POS Pd: 2A Corrective maintenance on degraded fire protection systems was accomplished in a timely manner. The Sec:
See: 2B enmce chow CMm o% h goM% gWW feoWs were soMactory Ter:
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08/29/1998 1998008 Pri: PLISUP NRC POS Prt 5A The 1998 Nuclear Assessment Section ossessment of the facility's fire protection program was comprehensive and Sec-See: SC w s eHechWmWng fire potechm pgom gogrWMeWdes to mmagemmt. The M
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identified significant deficiencies in the post change management proctices in the fire protection program.
Tec 1C Planned corrective actions in response to the audit issues were substantial and included the initiation of a Fire Protection Program Upgrade Project.
i 08/29/1998 1998008 Prt PLTSUP NRC POS Prt IB The licensee's preparations for Hurricone Bonnie were timely and comprehensive. Corrective actions for plant t
" P See: OPS Sec:
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Item Type (Compliance, Followup.Other), From 05/25/1997 To 02/13/1999
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Page: ' 4 of 4 Date: 11/25/1996 Unit;d Stat:s Nuci:ar R;gulatory Comm..ission Time:io:s2:so.
PLANT ISSUE MATRIX By Primary Functional Areo Legend Type Codes:
Temptote Codes:
Functional Areas:
- Bulletin IA Normal Operations OPS -
Operations CDR Construction IB Operations During Transients MAINT Maintenance DEV Deviction 1C Programs and Processes ENG Engoeering eel Escaloted Enforcement item 2A Equipment Condition PLTSUP Ront Support IFl Inspector follow-up item 2B Programs and Processes
[OTHER Other LER Licensee Event Report 3A Work Performance LIC Licensing issue 3B KSA t
MISC Miscelloneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 4B Engineering Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion SA identification NON Notice of Non-Conformance SB Anotysis P21 Port 21 SC Resolution S Posihve ID Codes:
SGI Sofeguard Event Report NRC NRC S
Strength Self Self-Reveofed URI Unresolved i*em r
Licensee Licensee VIO Violation WK Weakness Eels are apparent violations of NRC Requirements that are being c onsidered for escdoted enforcement action in occordance with the Wneral Statement of Policy and Procedure for NRC Enforcement Action * (Enforcement Policy). NUG EG-1600. However, the NRC hos not reached its find enforcement decision on the issues identified by the Eels and the PIM entries may be modified when the find decisions are inode.
URis are unresotved items about which more information is required to determine whether the issue in question is on occeptoble item, a deviofiort a nonconformance, or a f
violation. A URI may dso be o potential violation that is not likely to be considered for escolated enforcement oction. However, the NRC hos not reached its find conclusions on the bsues. and the PIM entries may be modified when the find conclusions are mode.
I i
i Item Type (Compliance, Followup.Other), From 05/25/1997 To 02/13/1999
/*g United States Nuclear Regulatory Commission
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PLANT ISSUES MATRIX by SALP Functional Area BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES OPERATIONS
'l 7/2/98 Positive IR 98-07 (07.1)
NRC The licensee conducted thorough reviews of improved Technical Specifications 1 23 4 5 irnplementation readiness during several Plant Nuclear Safety Committee meetings.
A00000 s00000 cO 000 6/29/98 URI (R 98-07 (O2.1)
NRC UFSAR discrepancies. Temps. in excess of UFSAR limits identified for the supply 1 23 4 5 to RBCCW and the area around the Reactor Recirculat;on motors. The URI was issued to track the resolution of the elevated temperatures.
AOOOOO B 00000 cO DOG 6/19/98 Strength IR 98-07 (07.2)
NRC The same level of control and risk assessment was applied to a short maintenance 1 234 5 outage as a normal refueling outage.
A00000 B 00000 cO 000 6/6/98 NCV IR 98-06 (08.1)
LICENSEE A Non-Cited Violation was identfieid for missed operator rounds.
1 23 4 5 A G0000 e00000 cO 000 5/21/98 Positive IR 98-06 (O7.1)
NRO The restart affirmation conducted by the Plant Nuclear Safety Committee was a 1 234 5 satisfactory evaluation of the overa!! site organization's readiness to restart Unit 1.
A00000 s00000 cO 000 5/20/98 Positive IR 98-06 (O2.1)
NRC Drywell housekeeping was effective in maintaining areas free of foreign material.
1 234 5 Electrical and mechanical components were secured to support plant restart.
A00000 e00000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 1 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
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t BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 5/9/98 Positive IR 98-06 (O2.2)
NRC The Torus was very clean, with only minor foreign material present; this material was 1 234 5 removed during the licensee's closecut inspection. No deficiencies were identified during the torus suction strainer modification installations, AOOOOO g00000 cO 000 5/7/98 Negative IR 98-06 (O2.5)
NRC The loss of the Supplemental Spent Fuel Cooling System on May 7,1998, resulted 1 234 5 in a 9.5 degree Fahrenheit increase in fuel pool temperature. Eight to nine trips of the system occurred within a 3-week period.
AOOOOO s00000 cO 000 4/30/98 Positive IR 98-06 (01.2)
NRC The core afterations conducted during the Unit 1 Refueling Outage were generally 1 234 5 conducted according to procedure, had adequate communications, and were effectively controlied. However, the inspector noted that one fuel movement AOOOOO occurred without the required communications: this deficiency was promptly corrected by a licensed operator in the Control Room.
B OOOOO cO 000 4/26/98 Negative LER 98 02-00 LICENSEE While in refueling mode, switch not locked in the Refuel position as required by TS 1 234 5 with suppression poolinoperable.
AG0000 s00000 cO 000 4/25/98 Positive IR 98-06 (01.1)
NRC Operator briefings, plant control, and response during the Unit 1 shutdown for the 1 23 4 5 refueling outage were effective.
A00000 sGOOOD cO 000 3/31/98 VIO IR 98-05 (01.1)
NRC Scaffolding erected too close to safety equipment contrary to procedure 1 23 4 5 requirements.
A00000 B 00000 cO 000 3/20/98 Positive IR 98-02 (O4.1)
NRC Licensed operators had a good understanding of the Maintenance Rule, and 1 234 5 understood their responsibilities for implementing the Maintenance Rule.
A00000 s00000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 2 of 22 FOR PUBLIC RELEASE Last updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 3/4/98 Negative IR 98-03 (O2.3)
NRC The diesel generator electricallineups and plant drawings were consistent with the 1 234 5 distnbution panels. Four breakers were incorrectly labeled as compartment heaters instead of spares.
A OOOOO B 00000 cO 000 2/26/98 Negative tR 98 03 (01.2)
NRC Current procedures do not control the use of the Emergency Rod in Notch Override 1 234 5 switch. The licensee was responsive to this issue.
A00000 sG0000 cO 000 2/25/98 Weakness IR 98-03 (01.1)
NRC HPCI system was in standby and the material condition of the system was 1 234 5 satisfactory. A weakness was identified in the licensee configuration contd program for not identifying a valve insta!!ed on the HPCI turbine stop vane operating AOOOOO
- Y""d *
sOOOOO c0 000 2/12/98 Positive IR 98-03 (O5.1)
NRC An exercise scenario and a subsequent critique and training on the plant simulator 1 234 5 which required an operations crew to demonstrate their ability to respond to plant transients and don self-contained breathing apparatus while the control room AOOOOO emergency ventilation system was undergoing modifications was performed in an effective and thorough manner.
8 OOOOO cO 000 1/27/98 Positive IR 97-15 (01.1)
NRC A Recirculation Pump Trip - occurred due to electrical fault on a transmission line.
1 234 5 Operations response to the transient was good.
A 00000 B G0000 cO 000 12/27/97 Weakness IR 97-13 (08.4)
LICENSEE DG Inoperable - Weakness - during bus maintenance tagout for DG did not provide 1 2 34 5 clear instructions.
A O O O O O.
a00000 cO 000 12/27/97 VIO tR 97-13 (O7.2)
NRC Retention of Required QA Records - Clearance sheets not maintaened as O A 1 234 5 records.
A 0000G B 00000 cO 000 FROM: 10/1/97 T0: 11/25/98 Page 3 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-93 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 12/27/97 Positive tR 9713 (01.1)
NRC Cold Weather Preparation - Program satisfactority implemented. Procedures were 1 2 3 4.5 adequate for contingency plans and operation checks for proper operation of the systems.
AOOOOO s00000 cO 000 11/12/97 Positive IR 97-13 (O7.3)
NRC Control of Mid-Cycle Outage - Excellent control - same process as regular refueling 1 234 5 outage.
A 00000 s00000 cO 800 11/12/97 Positive IR 97-13 (O7.1)
NRC Safety Committee Review - Effective review of Unit 1 readiness for restart following 1 234 5 mid-cycle outage.
A 00000 B 00000 cO 000 11/6/97 MISC IR 97-13 (O8.3)
LICENSEE Recirculation Pump Runbacks - Cause determined to be improper functioning of 1 234 5 level contacts in logic circuitry. Unit 2 had modification. Unit I next outage.
A 0000 0 s00000 cO 000 10/29 S 7 Positive IR 97-12 (O2.4)
NRC Good Operation Response to a Transient - Reactor pump control linkage failed 1 234 5 causing slow loss of pump without aiarm, operator caught quickly.
A 00000 8 00000 cO 000 10/24/97 NCV IR 97-12 (O4.2)
LICENSEE Control Rod Movement Error - Operator inserted rods further than allowed.
1 234 5 Weakness in direction provided for reactivity manipulation control.
A 00000 B 00000 cO 000 10/12/97 Positive IR 97-12 (O2.2)
NRC Drywell inspection - Drywell free of foreign material and ready for closeout.
1 234 5 A 00000 s00000 cO 000 FROM.10/1/97 TO: 11/25/98 Page 4 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC. SFA SOURCE (s)
!D'd ISSUE (s)
SMM CODES 10/11/97 Strength IR 97.12 (07.2)
NRC Outage Planning and Control-Planned outage work completed without difficulty.
1 234 5 Planning and control continues to be a strength. 35 day outage work completed in 32-33 days.
AOOOOO aD0000 c0 000 10/11/97 Positive IR 97-12 (O7.1)
NRC Restart Aff!rmation by Plant Nurclear Safety Committee - Evaluation was thorough 1 234 5 and effective.
A00000 s00000 cO 000 10/11/97 Negative IR 97-12 (O4.4)
LICENSEE DG Autostart Defeated - URI - During mair:tenance on an electrical bus a DG 1 234 5 autostart was defeated as part of the clearance without Ops recognition. URf closed 12/27/97.
A OOOOO e00000 cO 000 10/10/97 Negative IR 97-12 (O4.1)
LICENSEE inadvertent DG Start-Operator error while restoring system lineup. Lack of 1 234 5 understanding and procedure step not clear.
A 00000 s00000 cO 000 MAINTENANCE
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'l 8/11/98 VIO IR 98-07 (M4.1)
NRC Dunng the Spring 1998 Unit 1 outage an increase in errors was noted in 1 234 5 maintenance and test activities. Several examples of multiple barrier breakdowns, such as independent verification, were identified as a violation of plant procedures.
A OOOOO The licensee initiated a human performance improvement inibative to address the declining trend. See 6/6/98 PIM entry.
B OOOOO cO 000 6/6/98 URI 1R 98-06 (M4.1)
NRC The cross-connection of multiple phases of a breaker compartment resulted in a 1 234 5 brief " fireball". No adjacent personnel or equipment were damaged and reactor make-up and control was maintained at all times. An Unresolved item was identified A OOOOO fo urther review of this item and other related maintenance and test configuration OOOOO c0 000 FROM: 10/1/97 TO: 11/25/98 Page 5 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Wou-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 5/B/98 Strength IR 9846 (M7.1)
NRC The effectiveness of licensee controls over their ISI vendor and in ident:fying.
1 234 5 resolving, and preventing problems were determined to be excellent. This was demonstrated by integrity of the vendor oversight observed; the conduct of a A OOOOO thorough assessment (B-OM-98-01) to determine the effectivenss of preoutage preparations in support of the outage; and the effective investigation documented in B OOOOO CR 98-0424 of discrepancies in inspection coverage and defect length sizing on Unit 1 & 2 core shroud welds.
C O OOO 5/8/98 Strength IR 98-06 (M2.2)
NRC The material condition of the Unit 1 torus was very good U1 that, even below the 1 234 5 water line, the paint was in excellent condition. Sma!! isolated areas of discrepant paint identified by the inspector which needed attention were found to have already AOOOOO been identified by the licensee in the paint analysis for the torus. The completed weld repairs observed and the applicable documentation was found to be in B OOOOO accordance with procedures and specifications.
O OOO 5/8S8 Strength IR 98-06 (M2.1)
NRC Inservice inspection activities observmi were conducted in an excellent manner by 1 234 5 examiners and analysts who were very knowledgable and skillfut in their use of the examination methods. Enhanced inspection techniques were found to be very AOOOOO effective in thoroughly examining and evaluahng the quality of welds.
g cO 000 4/28/98 Weakness IR 98-06 (M2.3)
NRC For the most part, Foreign Material Exclusion controls were implemented 1 234 5 satisfactorily. However, a lack of control of material in the fuel poolled to a thermocouple wire being inadvertently placed on top of the reactor vessel core.
AOOOOO Also, spent fuel pool inventory and contro! was considered a weakness.
OOO cO 000 4/16/98 NCV IR98-06 (M8.4); LER 98-LICENSEE Reactor Building Roof Vent. Noble Gas Activity Monitor set at a value above 1 2 3 4 5 01-00 ariowed by TS. Procedure deficiency identified by ficensee.
A00000 s00000 cO 000 3/31/98 VIO IR 98-05 (M3.1)
NRC Ouality Control (OC) procedure step signed by non-qualified OC inspector. There 1 23 4 5 were inconsistent requirements in a mechanical maintenance surveillance for Diesel Generator inspections. Nuclear Assessment had not reviewed a procedure revision AOOOOO that deleted OC steps.
s00000 c0 000 3/31/98 Positive IR 98-05 (Mt.1)
NRC Observed Maintenance activities conducted by the Fix It Now Team were conducted 1 234 5 satisfactory and met the licensee's procedural requirements.
A 00000 s00000 cO 000 FROM.10/1/97 TO: 11/25/98 Page 6 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-93 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 3/26/28 VIO PLT SUP IR 98-05 (M3 2)
NRC During the performance of the Transformer Deluge System Functional Test 1 234 5 procedure steps were performed out of sequence.
A 00000 a00000 cO 000 3/26/98 NCV 1R 98-04 (M t.1, M1.2)
NRC Non-Cited Violation for failure to perform response time testing by TS and 1 234 5 inadequate 50.59 review deleting requirements. Four apparent violations changed to one NCV.
A OOOOO s00000 cO 000 3/20/98 Strength IR 98-02 (M7.1)
NRC Self-assessments of the Maintenance Rule were considered to be excellent and 1 234 5 successfullymonitored the effective implementation of the Maintenance Rule. The team considered the assessments performed to be a program strength.
AOOOOO B 00000 cO 000 3/20/98 Strength IR 98-02 (M2.1)
NRC
!n general, plant material condition and housekeeping observed during walkdowns 1 234 5 was excellent. However, the team did identify some minor discrepancies. Overa!!,
the excellent material condition and housekeeping was considered a strength.
A OOOOO s00000 c0 000 3/20/98 Positive IR 98-02 (M1.7)
NRC in general, for (a)(2; SSCs. detailed performance criteria had been property 1 2 3 4 5 established; appropriate trending had been performed; corrective actions were taken when SSCs failed to meet performance criteria or experienced failures; industry-wide A OOOOO operating experience had been considered, where practical; and operating data had been property captu ed.
B OOOOO cO 000 3/20/98 Weakness IR 98-02 (M1.6, M1.7)
NRC A weakness in the Maintenance Rule process implementation was identified relative 1 234 5 to: 1) proper alignment of system and component functions with performance monitoring groups (PMG),2) omission of a corrective action p'an for a PMG,3) use AOOOOO of incorrect equipment type codes in reviews for repetitive fu'ctional failures that could lead to not identifying repetitive functional fai5ures across system boundaries, B OOOOO and 4) incorrect computer calculations of unavailability times when editorial changes O
OOO were made to unavailability start and stop times.
3/20/98 Positive IR 98-02 (M1.6)
NRC in general, operating experience was being property captured, and industry-wide 1 234 5 operating experience was considered, as approriate.
A00000 s00000 t
cO 000 FROM: 10/1/97 TO: 11/25/98 Page 7 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Noe-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 3/20/98 Positave IR 98-02 (M1.6)
NRC Corrective actions, goals, and monitoring were comprehensive and were generally 1 234 5 appropriate for the (a)(1) SSCs reviewed.
A00000 B 00000 cO 000 3/20/98 Positive IR 98-02 (M t.6)
NRC The licensee considered safety in establishment of goals and monitoring for the 1 234 5 (a)(1) system and components reviewed.
A 00000 B 00000 cO 000 3/20/98 Positive IR 98-02 (M1.4)
NRC The approach to balancing rehability and unavailability was reasonable. The detailed 1 234 5 evaluation of balancing in the (a)(3) periodic assessment was considered good.
A00000 s00000 cO 000 3/20/98 Positive IR 98-02 (M t.3)
NRC The (a)(3) periodic assessment was considered an excellent evaluation of the 1 234 5 licensee's compliance with their program and the program's ccxpliance with NUMARC 9341 and paragraph (a)(3) of 10 CFR 50.65. The asressment met the AOOOOO requirements of paragraph (a)(3) of 10 CFR 50.65 and was considered to be a strength.
B DGOOO c0 000 3/20/98 Positive IR 98-02 (Mt.1)
NRC Required structures, systems, and components (SSCs) were included within the 1 234 5 scope of the Maintenance Rule.
A C0000 B 08000 cO 000 3/20/98 Strength IR 98-02 (Exec. Sum.)
NRC Overall, the inspection team concluded that the licensee had a comprehensive 1 234 5 Maintenenace Rule program thet met the requirements of 10 CFR 50.65, and the program was being effectively imp!emented. The overall program was detailed, well AOOOOO documented, and was considered to be a strength.
OOO cO 000 3/4/98 Positive IR 98-03 (M1.1, M1.4)
NRC Maintenance activities observed were conducted in an effective and thorough 1 234 5 manner by knowtedgeable and skilled technicians. Procedures and drawings used had been verified as current. Satisfactory supervisory oversight was present.
A OOOOO B 00000 cO 000 FROM.10/1/97 TO: 11/25/98 Page 8 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 2/12/98 Negative PLT SUP IR 98-05 (M7.1)
LICENSEE There was a long standing history of fire door hardware deficiences. Various 1 2 34 5 licensee assessments identified these deficiencies and these represented missed opportunities to correct the adverse conditions.
AOOOOO s00000 cO 000 2/12/98 VIO PLT SUP IR 98-05 (M4.2)
NRC Failure to report a condition outside the 10 CFR 50 Appendix R design basis 1 23 4 5 conceming unreviewed modifications to fire doors between reduntant safety equipment, (7/1/98 Licensee Contested)
AOOOOO e00000 cO 000 2/12/98 VIO PLT SUP IR 98-05 (M4.1), IR 97-15 LICENSEE Unreviewed modifications were made to 28 Diese! Generator Building fire doors 1 234 5 (F4.1) which introduced a common mode fai!ure. The modification degraded the three hour fire barrier separating redundant safety equip.nent. (7/1/93 Licensee Contested)
A OOOOO e00000 cO 000 2/5/98 Negative IR 98-03 (Mt.5)
NRC The programs goveming control of component leakage and the maintenance 1 234 5 backlog were ineffective in the timely resolution of a degrading secondary containment penetration link seat. The failure to promptty correct this situation has AOOOOO resulted in a spread of contamination into clean areas and the establishment of long-term contaminated areas.
B OOOOO cO 000 2/3/98 Negative IR 98-03 (M t.7)
NRC Red-line changes made to vendor procedures were consistent with the requirements 1 2 3 4 5 of licensee procedures and Technical Specifications. Improvements were needed in monitoring training certification of contractor qualification.
A OOOOO e00000 cO 0DO 1/12/98 Positive IR 97-15 (M1.1)
NRC Routine Maintenance Activities - Licensee continuing to upgrade the materia' 1 234 5 condition of plant equipment and equipment spaces.
A 00000 sD0000 c0 000 1/9/98 NCV IR 97-15 (M2.2)
LICENSEE Control of Special Processes -Inadequate control of shroud weld examination.
1 23 4 5 Comparison UT data indicate H6B weld crack - data inconsistent.
A00000 s00000 cO 000 FROM: ? 0/1/97 TO: 11/25/98 Page 9 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE' TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 1/7/9Q Weakness IR 97-15 (M2.1)
NRC Surveitlance Test - Tests performed satisfactonly but weakness is foreign material 1 234 5 exclusion for test equiptrent.
A 0000 0 e00000 cO 000 1/4/98 VIO IR 97-15 (M4.1)
NRC Corrective Action Violation - Process computer failures not documented on CR 1 234 5 needed for Maint. Rule input Data.
A 00000 B 00000 cO 000 12/11/97 VIO IR 97-13 (M1.3)
NRC EO Maintenance - PM procedure did not indicate inspection requirements of seals 1 234 5 in Motor Control Centers.
A 00000 B 00000 cO 000 12/11/97 Positive IR 97-13 (M1.3)
NRC EQ Maintenance - EO maintenance cf electrical equipment was conducted in a 1 234 5 thorough and effective manner.
A 00000 s00000 cO 000 12/2/97 VIO IR 97-13 (M3.1)
NRC Abnormal Values not Detected in Daily Surveillance Log - Abnormal values for 1 234 5 Steam Jet Air Ejector radiation monitor not redi:ircled on logs.
A00000 s00000 c0 000 12/2/97 Positive IR 97-13 (Mt.1)
NRC Fuel Shipping Cask Movement - Cask moved in accordance with approved 1 234 5 methodology with good supervisory oversight.
A00000 eD0000 cO 000 11/5/97 Positive IR 97-12 (Mt.3)
LICENSEE Surveillance Testing - Testing stopped once a discrepancy was identified. Action 1 234 5 taken to correct procedure and drawing.
A 00000 B 00000 c0 000 FROM: 10/1/97 TO: 11/25/98 Page 10 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 10/11/97 Posit ve IR 97-12 (MS.1)
NRC Measuring and Test Equipment - M&TE found property labeled and calibrated.
1 234 5 i
A00000 e00000 cO 000 10/3/97 LER LER 2-97-04 LICENSEE Safety Relief Valves Exceeded TS Setpoint Umits - Five of 11 SRVs found to lift at 1 234 5 pressures outside TS limits. Power Uprate change tolerance from + or - 1 to + or -
- 3. Only one SRV was -3.2.
A OOOOO s00000 cO 000 10/3/97 LER LER 1-97-13 LICENSEE RCIC Sury. Procedure Not Adequate - Found during GL 96-01 review. Test did not 1 234 5 verify ability of RCIC exhaust diaphragm high pressure channellogic.
A 00000 e00000 cO 000 10/2/97 Negative IR 97-12 (M2.3)
LICENSEE Shroud Crack Inspections - Examinations showed little crack growth, however weld 1 234 5 HGB gave conflicting information, depth less than perviously measured. EPRI to assist. (See NCV 1/9/98)
A OOOOO s00000 cO 000 10/2/97 Positive IR 97-12 (M2 2)
NRC In-vessel Inspections - Inspections performed by skilled technicians and 1 23 4 5 examinations good.
A00000 e00000 cO 000 10/2/97 VIO IR 97-12 (M1.3)
LICENSEE Clearance Errors - incorrect breaker racked out, cooling water to recire. pump seals 1 23 4 5 isolated while plant in hot standby caused temp. limit of seal to be exceeded.
A 00000 s00000 cO 000 ENGINEERING ~
l 6/30/98 Negative IR 98-07 (E3,1)
NRC The inspector found that the licensee had maintained Special Nuclear Material 1 234 5 (SNM) accountability for a Local Power Range Monitor (LPRM)in question, The inspector found that the licensee's warehouse inventory had an error in the number A OOOOO of LPRM units on hand due to not having well defined procedura! guidance on SNM in their material control procedures, sOOOOO c0 000 FROM: 10/1/97 TO: 11/25/98 Page 11 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
=
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 6/24/98 VIO IR98-07 (E2.1)
NRC The inspector identified a corrective action violation in the identification and untimely 1 234 5 initiation of corrective actions regarding an adverse condition involving the Run Control Relay and Jet Assist Time Relay DG air bettows tirne delay relays.
A OOOOO s00000 cO 000 6/24/98 MISC IR 98-07 (M2.1)
LICENSEE The licensee identified a 63-inch crack in a fuel rod from the Unit 1 core. Debris was 1 234 5 determined to be the initiator of the failure.
AOOOOG B 00000 cO 000 6/11/98 Negative IR 98-07 (E7.1)
NRC The licensee acknowledged that design control activites warranted additional 1 234 5 attention. These activities were accuracy of Equipment Database System, staffing of design control organization, and UFSAR updates-AOOOOO B 00000 cO 000 6/6/98 Strength IR 98-06 (E2.3)
NRC The inspector concluded that the same excellent planning and decision-making 1 234 5 which was implemented during the Unit 2 Emergency Core Cooling System (ECCS) strainer modifications led to the successful completion of the Unit 1 ECCS straine' A OOOOO modification.
B 00000 cO 000 5/22/98 Positive IR 98-06 (E2.2)
NRC The licensee's operability evaluation of bolted connections for RPV pipe support was 1 234 5 completed in accordance with the guidance specified in Generic Letter 91-18.
A 0000 0 s00000 cO 000 5/22/98 Positive IR 98-06 (E2.1)
NRC The licensee's actions to repair the pinhole leaks in the Unit 1 SLC flexible piping 1 234 5 were performed in accordance with good engineering practices and NRC requirements.
A OOOOO e00000 c0 000 5/22/98 Negative IR 98-06 (E1.3)
NRC The licensee was making adequate prog'ess in resolving and closing CRs identified 1 234 5 by the EO group. However, engineering failed to recognize that a repair should be rnade to the Okonite T95 tape splices on the drain wires for two Containment A OOOOO Atmosphere RTDs to prevent multiple grounds in the circuit. This was considered a weakness.
B DDDOO cO 000 FROM: 10/1/97 TO: 11/25/98 Page 12 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Geov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 5/21/98 V10 IR 98-06 (E4.1)
NRC A change to the Diesel Generator load test was made which aftered the test loading 1 234 5 profile. The use of a temporary change to after the intent of the test load procedure was identified by the inspector as a violation.
A OOOOO B 00000 cO 000 5/19/98 Negative LER 98-03-00 LICENSEE Safety Retief Valves Exceeded TS Setpoint Limits - modification to fix did not work -
1 23 4 5 suppl. LER expected A00000 o00000 cO 000 4/11/98 Positive iR 98-05 (E2.1)
NRC The heensee provided effective oversight for the design and installation of the 1 234 5 Control Building Air-Conditioning upgrade modification.
A00000 B 00000 c0 000 376/98 Negative IR 98-05 (E3.1)
SELF Due to the inability of the Standby Liquid Control system piping heat trace to 1 23 4 5 maintain adequate temperatures to maintain the chemicals in solution during cold temperatures the licensee implernented more Irmiting administrative limits than AOOOOO existed in Technical Specifications. A modification was planned for the summer of 1998.
B 0000O cO 000 3/20/98 Strength IR 98-02 (E4,1)
NRC System engineers were very knowledgeable of their systems, were proactive in 1 2 3 4 5 corrective actions, and had a good understanding of Maintenance Rule requirements and how to apply the Rule to their system.
A OOOOO s00000 cO 000 370/98 Positive IR 98-02 (M1.5)
NRC The use of the equipment out-of-service (EOOS) computer program to evaluate 1 2 34 5 plant configurations was also good, as was the process for ensuring that critical safety functions were available during planned outages.
A OOOOO e00000 c3 000 3/20/98 Positive IR 98-02 (M1.5)
NRC The overall approach, under paragraph (a)(3) of the Maintenance Rule, to assessing 1 234 5 the risk-impact of maintenance activities was good.
A 00000 g00000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 13 of 22 FOR PUBLIC RELEA$E Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 3/20/98 Positrve IR 98-02 (M1.2)
NRC Bosed on the review of the sample SSCs, the licensee's approach to risk-ranking for 1 234 5 the Maintenance Rufe was good.
A00000 s00000 cO 000 3r20/98 Strength IR 98-02 (M1.2)
NRC The expert panel committee meeting discussions on covered topics were excellent.
1 234 5 The expert panel meeting minutes were well documented, and were considered a strength.
A OOOOO s00000 cO 000 3/20/98 Positive IR 98-02 (M1.2)
NRC The current method of assuring the assumptions for reliability and availability in the 1 234 5 PSA are conserved was good.
A00000 s00000 c0 000 3*20/98 Positive IR 98-02 (M12)
NRC The overall quantitative approach used to perform risk ranking for SSCs in the scope 1 234 5 of the Maintenance Rule was good. Performance criteria were established with substantial p! ant safety analysis (PSA). Documentation of PSA input was good.
A OOOOO s00000 cO 000 3/14/98 NCV 1R 98-03 (E8.3)
LICENSEE A non-cited violation was identified for failing to perform a 10 CFR 50.59 review 1 234 5 when downgrading the quality classification of the Control Duilding air-conditioning units.
A OOOOO B 00000 cO 000 3/12/98 ViO IR 98-04 (E8.3)
NRC Violation for using non-design verified engineering evaluation to change plant design 1 234 5 documents.
A 00000 s00000 cO 00O 3/6/98 Positive IR 98-03 (E1.1)
NRC Based on completed and planned licensee actions, the inspectors concluded that 1 234 5 the licensee had made adequate progress on the implementation of the program and had met the intent of GL 89-10, Motor-Operated Valve program.
AOOOOO aD0000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 14 of 22 FOR PUBLIC RELEASE Last updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 2/17/E8 Negative IR 98-03 (E2.1)
NRC Operator training for the oncoming crew on the compensatory rneasures during 1 234 5 upgrades of the Control Building Ventilation System was not timely.
A00000 sD0000 cO 000 1/4/98 Negative IR 97-15 (E2.1)
NRC Improved Standard TS Implementation - Inspector review of ITS implemention 1 234 5 instructions and changes indicated additional clarification and licensee review were needed.
A OOOOO s00000 cO 000 12/12/97 Positive IR97-13 (E1.2)
NRC EO Program Reconstitutation Progress - Progress being made in closure of JCOs 1 234 5 and CRs Training rneets NRC requirements. Inst. setpoint cales. adequate.
A00000 s00000 cO 000 12/12/97 Weakness IR9713 (E1.1)
NRC EO Procedure Reference Wrong - Reference to a drawirig for accident temperature 1 234 5 data was not avaitable for use and inconsistencies in procedure.
A 00000 s00000 cO 000 12/12/97 VIO IR 97-13 (E1.1 & E1.4)
NRC Inadequate EO Maintenance Procedure - Difference greases for EO electric motor 1 234 5 specified in procedure had not been evaluated by EQ program.
A 00000 e00000 i
cO 000 10/31/97 ED IR 97-12 (E8.1)
LICENSEE Failure to Perform 50.59 Review for Spent Fuel Shipping Cask EA 97-521 -
1 234 5 Enforcement Discretion granted 12/10/97.
A 00000 g00000 cO 000 10/31/97 Negative IR 97-12 (E7.1)
LICENSEE NAS Audit of Engineering - NAS audit adequate but showed corrective actions have 1 234 5 been ineffective.
A 00000 g00000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 15 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 85h98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 10/31/97 Positive IR 9712 (E12)
NRC Modi $ cations for USl A Mods. adequately implemented in accordance with 1 234 5 design requirements.
A 00000 s00000 c0 000 10/31/97 VIO IR 97-12 (E1.1)
NRC EO Program Lack of Progress - 2 VIOs - Failure to take corrective action to correct 1 234 5 EO problem and failure to document operability of equipment.
A 00000 s00000 cO 000 10/13/97 VIO IR 97-12 (E3.1)
LICENSEE Errors in Database for Minimum Critical Power Ratio Safety Limit Calculation -
1 234 5 Licensee failed to correct database after a problem in April occurred. Another error found September 1997.
AOOOOO a00000 cO 000 10/13/97 Licensing IR 9712 (E2.3) LER 1 NRC Torus Bypass Flow - Enf. conf. 12/19/97. No violation, licensee reported before 1 234 5 11 Pad 21 issued.
A00000 g00000 cO 000 10/11/97 Strength IR 97-12 (E2.1)
NRC Torus Suction Strainers Modificatron - Significant strengths in project management.
1 234 5 Excellent planning and decision making led to the successful completion of a major plant modification.
A OOOOO s00000 c0 000 PLANT SUPPORT l
7/27/98 Positive IR 98 07 (F7.1)
LICENSEE The triennial fire protection audit was determined to be a thorough review of the 1 234 5 program. Audit findings reflected extensive auditor knowledge of fire protection and the associated requirements. Additional assessments were schedufed to AOOOOO independently review corrective actions for the fire protection program.
OOO cO 000 7/17/98 Positive IR 98-07 (Rt.1)
NRC The heensee's radiation control practices for radiological posting and labeting.
1 234 5 personnel dosimetry, radiological surveys, RCA ingress and egress control, and whole body counting were consistent with the licensee's Radiation Control and A OOOOO Protection Manual and relevant sections of 10 CFR 20.
OOO cO 000 FROM: 10/1/97 TO: 11/25/98 Page 16 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 5/29/98 VIO IR 98-00 (Rt.3)
NRC The licensee failed to take prompt action when a continuous air monitor and an 1 23 4 5 additional sample indicated abnormal airbome activity. As a result, five workers were present in an area of airbome radioactivity levels greater than 0.25 DAC A OOOOO (Derived Air Concentration), without appropriate radiation work permits. A violation was issued for the failure to property implement and establish procedures that B OOOOO outlined those actions to be taken in the event of survey resuits indicating abnormal airbome activity.
O OOO 5/22/98 VIO IR 98-06 (RI.1)
NRC An unresolved item was identified to further evntuate the adequacy of detection 1 23 4 5 methods for detecting Fe-55 concentrations or quantities on material free released from the site.
A OOOOO B 00000 cO 000 5/22/98 URI 1R 98-06 (RI.1)
NRC A violation was identified for faiture to perform nine procedura!!y required routine 1 234 5 radiation surveys.
A 00000 8 00000 cO 000 5/22/98 Strength IR 98-06 (R1.1)
NRC Contamination controls were effective in containing high levels of contamination to 1 234 5 appropriate areas.
A 00000 B 00000 cO 000 5/14/98 Positrve IR 98-06 (S1.2)
NRC The inspector determined. through Ac. cess Authorization procedures and records 1 2 34 5 review, that the licensee had established adequate procedures as required by 10 CFR 73.56 for the review of a denial or revocation by the licensee of unescorted A OOOOO secess authorization, at the request of an affected employee.
cO 900 4/25/98 Positive IR 98-05 (R8.1)
NRC The root cause analysis for a cited violation conceming chemical control was 1 23 4 5 excellent. Subsequent se!f-assessments were self-critical and effective in the identification of issues.
A OOOOO B 00000 cO 000 4/22/98 Strength IR 98-06 (R1.1)
NRC Radioactive material was labeled in accordance with icquirements and appropriately 1 234 5 stored. Radiation and high radiation areas were property posted and controlled.
A 00000 8 00000 cO 000 FROM; 10/1/97 TO: 11/25/98 Page 17 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25 Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 4/20/98 VIO IR 98-06 (F3.1)
NRC The procedures for maintaining minimum staffing for Altemate Safe Shutdown 1 234 5 (ASSD) during a fire were determined to be inconsistent with 10 CFR 50 Appendix R.10 CFR 50 Appendix R requires that all personnel needcd for ASSD be onsite at A OOOOO all times. However, the procedures for ASSD staffing a!Iowed less than minimum staffing for 14 days. A violation was issued for the failure to properly establish fire aOOOOO protection procedures in accordance with 10 CFR 50.
O OOO 4/20/98 VIO 1R 98-06 (F1.1)
NRC Staffing for attemative safe shutdown procedures was not implemented in 1 23 4 5 accordance with procedures. The failure to maintain adequate Attemate Safe Shutdown staffing was identified as a violation. A violation was also identified for AOOOOO the failure to retain OA documents requested during this inspection.
OOO cO 000 4/3/98 Positive IR 98-05 (S1.1)
NRC Security activitives during observation in the CAS and SAS were satisfactory.
1 234 5 Lighting inside the protected area was acceptable with one exception that was corrected.
A OOOOO e00000 cO 000 3/14/98 Positive IR 98-03 (Rt.3)
NRC The licensee effectively implemented training and qualification for Radiation 1 234 5 Protection and Cherrustry Technicians in accordance with the training program procedural requirements.
A OOOOO eD0000 cO 000 3/14/98 Positive IR 98-03 (R1.2)
NRC The licensee was generally effective at identifying and correcting radiological control 1 234 5 related deficienies in accordance with the corrective action management program.
A00000 s00000 c0 000 3/14/98 Positive IR 98-03 (RI.1)
NRC Radiation control practices for Radiation Control Area ingress and egress control.
1 234 5 personnel dosimetry, radiological surveys and postings, and container labeling were consistent with the licensee's Radiation Control and Protection Manual and relevant AOOOOO sections of 10 CFR 20.
OOOOO cO 000 3/12/98 Positive IR 98-201 ( Cover Ltr)
NRC Very positive ORSE team inspection. Significant involvement by Operations.
1 234 5 protective strategy effective and demonstrated excellent capabilities against threat.
Effective measures for safeguards measures.
A OOOOO s00000 l
c0 00O FROM: 10/1/97 TO: 11/25/98 Page 18 of 22 FOR PUBLIC RELEASE Last Updated: B/11/98
l l
l BRUNSWICK 25-Nov-98 l
l DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 3/10/98 Negative IR 98-05 (R4.1)
SELF Work activities on the refuel bridge grapple that resulted in skin contarrunations were 1 234 5 covered by the radiological work permit and work instructions. However, work practices to prevent the spread of contamination were not effective.
AOOOOO s00000 cO 000 3/8/98 VIO IR 98-05 (F3.1)
NRC The engine diven fire pump flow test procedure did not demonstrate 'nat the pump 1 234 5 was operable until the procedure was revised and acceptance crit 6a changed. This was similar to an event in June 1997 where a dual unit shutdr%n was commenced A OOOOO as a result of erreneous data from an inadequate test procedure. NRC concem noted over the proper establishment and implementation of the fire protection sOOOOO program.
O OOO 1/29/98 MISC IR 98-01 (P4.2)
NRC Except for the exercise weakness, command and control of the Emergency 1 23 4 5 Operatons Facility (EOF) and timeliness of off-site notifications were good. Off-site dose projections were completed satisfactorily, although a software inconsistency A OOOOO was detected but not fully evaluated during the exercise, Restnctions on food consumption were not effectively communicated to all EOF staff. Status boards sOOOOO were well maintained, but position logs were not. The State of North Carolina was O
OOO effectively integrated into the EOF organization.
1/29/98 Negative IR 98-01 (P4.2)
LICENSEE The Emergency Operations Facility failed to fulfill a primary facility responsibility by 1 234 5 not providing off-site agencies with off-site Protective Action Recommendations in a timely manner. This failure was identified as an exercise weakness.
A OOOOO s00000 cO 000 1/29/98 Positive IR 98-01 (P4.2)
NRC Command and control of Technical Support Center operations by the Site 1 23 4 5 Emergency Coordinator were judged to be exemplary. Emergency declarations were made timely, and accident mitigation activities were well coordinated with the A OOOOO Operational Support Center.
OOOOO cO 000 1/29/98 Positive IR 98-01 (P4.2)
NRC The Shift Superintendent / Site Emergency Coordinator and the Control Room 1 234 5 Simulator staff were very effective in performing initial emergency responsibilities.
A 00000 B 00000 cO 000 1/29/98 Positive IR 98-01 (P4.1)
NRC The scenario developed for this exercise was effective for testing the integrated 1 2 34 5 emergency response capabihtty, and exercise preparations were organized.
A 00000 s00000 cO 000 FROM: 10/1/97 TO: 11/25/98 Page 19 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK 25-Nov-98 DATE TYPE (s)
SEC.SFA SOURCE (s)
ID*d ISSUE (s)
SMM CODES 1/2/98 Negative IR 97-15 (R4.1)
NRC Health Physrcs Tecivwcian Waikthrough - Procedure lacked guidance to ensure 1 234 5 continuityof walkthroughs.
A00000 sD0000 c0 000 12/27/97 Negative IR 97-13 (RI.2)
NRC Pow Radiological Work Practices - Inspector found several poor work practices in a 1 234 5 radioactive material storage area.
A 00000 B 00000 cO 000 12/12/97 Positive IR 97-13 (F7.1)
NRC NAS Assessments of Fire Protection - Effective in identifying issues. Aud:ts were 1 234 5 substantial.
A 0000 0 e00000 cO 000 12/12/97 Positive IR 97-13 (F6.1)
NRC Fire Brigade Organization - Licensee got rid of Loss Prevention Unit and re-1 234 5 assigned fire protection to Operations. This change met NRC requirements.
A00000 B 00000 cO 000 1E/12/97 Positive IR 97-13 (F5.1)
NRC Fire Brigade Organization - Org. and Training met site procedures. Equipment 1 234 5 property maintained.
A 00000 e00000 cO 000 12/12/97 URI 1R 97-13 (F2.2) (F3.1)
NRC UFSAR Discrepancy - Documentation of Fire Door and Frame Evaluations not in 1 234 5 Fire Hazard Analysis section UFSAR.
A00000 a00000 cO 000 12/12/97 Negative IR 97-13 (F2.1)
NRC Fire Seal Testing hntation - Design adequate but records not available.
1 23 4 5 A00000 e00000 cO 000 FROM: 10/1/97 TO.11/25/98 page 20 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98
BRUNSWICK N4ov-98 E
TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
SMM CODES 12/12/97 VIO IR 9714 (RI.1)
NRC Failure to write a conditen mport - Licensee did not write a condsten report upon 1 234 5 identrf'rying a Locked High Radiation Area as riot controlled.
A 00000 g00000 cO 000 12/12/97 VIO in 97-14 (R 1.1)
NRC Control of Locked High Radiation Area - Failure to control a locked high radiaten 1 234 5 area.
A00000 B 00000 cO 000 12/12/97 Positive tR 9714 (R1.1)
NRC HP Inspection - Radiaticn Control Program effectivety implemented with good 1 23 4 5 occupationa! exposure controls observed during normal plant operations.
A00000 sD0000 cO 000 12/11/97 Positive tR 97-13 (F1.1' NRC Fire Protection System Corrective Maintenance - Maintenance was timely and 1 23 4 5 material conditions satisfacPJy.
A 00000 B 00000 cO 000 10/13'97 Positwe IR 97-12 (R1.1)
NRC Radiation Control Pradices During Outage - traproved supervisory overs:gtit was 1 23 4 5 observed on refuet floor, drywett, and torus.
A 00000 a00000 cO 000 10/3'97 VIO tR 97-12 (S4.1)
NRC Inadequate Security Procedure Procedure did not direct actions to lock turnstile 1 234 5 for unauthorized entry. Licensee denied but NRC concluded still VIO.
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6 BRUNSWICK 25Wov-98 I
DATE TYPE (s)
SEC.SFA SOURCE (s)
ID'd ISSUE (s)
' SMM CODES SMM Template Codes:
SALP Functional Areas:
ID Code:
{ OPERATION PERFORMANCE - Normal Operations j ~NGtNEERING
1A dCENSE'E' l LICENSEE ~
10 : OPERATION PERFORMANCE - Operations During Transients ENG jE NRC jNRC 1C. OPERATION PERFORMANCE - Programs and Processes MAINT ; MAINTENANCE SELF iSELF-REVEALED 2A. MATERIAL CONDITION - Equipment Conditon OPS jOPERAT10NS 28 ;MATERtAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A l HUMAN PERFORMANCE - Work Performance SAQV, SAFETY ASSESSMENT & QV 3B : HUMAN PERFORMANCE - KSA 3C l HUMAN PERFORMANCE-Work Environment 4A ;ENGlNEER!NG/ DESIGN - Design 4B l ENGINEERING / DESIGN - Engineering Support l ENGINEERING' DESIGN - Programs and Processes 4C 5A l PROBLEM IDENTIFICATION & SOLUTION -Identification SB, PROBLEM IDENTIFICATION & SOLUTION - Analysis SC PROBLEM IDENTIFICATION & SOLUTION - Resolution Eels are apparent violations of HRC requirements that are being considered for escalated enforcement action in accordance with the
- General S NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues iden entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with a the apparent violation or (2) request a predecisional enforcement conference.
URls are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonc 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: 11/25G8 Page 22 of 22 FOR PUBLIC RELEASE Last Updated: 8/11/98 w
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