ML20198B198
| ML20198B198 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/09/1998 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Feigenbaum T, Harpster T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| References | |
| NUDOCS 9812180103 | |
| Download: ML20198B198 (22) | |
Text
- _ __ _-
4 December 9,1998
. Mr. T. C. Feigenbaum Executive Vice President and Chief Nuclear Officer Seabrook Station North Atlantic Energy Service Corporation c/o Mr. Terry L. Harpster P. O. Box 300 Seabrook, NH 03874
SUBJECT:
MID-YEAR INSPECTION RESOURCE PLANNING MEETING - SEABROOK STATION
Dear Mr. Feigenbaum:
On November 10,1998, the NRC staff held an inspection resource planning meeting (IRPM). The IRPM p.ovided a coordinated mechanism for Region I to adjust inspection schedules, as needed, prior to the conclusion of the Plant Performance Review cycle in May 1999.
j This letter advises you of our planned inspection effort resulting from the Seabrook Station IRPM review. It is provided to minimize the resource impact on your staff and to allow for i
scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Enclosure 1 details our inspection plan for the next 6 months. Resident inspections are not listed due to their ongoing and continuous nature.
' contains a historical listing of plant issues, referred to as the Plant issues Matrix (PIM), that were considered during this IRPM process to arrive at an integrated view
. of licensee performance trends. The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Seabrook Station. The IRPM may also have considered some predecisional and draft material that does not appear in the' attached PIM, including observations from events and inspections that had occurred since the last NRC inspection report was issued, but had not yet received full review and
=
consideration. This material will be placed in the PDR as part of the normalissuance of NRC inspection reports and other correspondence.
-We willinform you of any changes to the inspection plan. If you have any questions, please contact me at 610-337-5233.
j Sincerely, fI Original Signed By:
\\
i 9912190103 991209 PDR ADOCK 05000443 Curtis J. Cowg.ll, Ill, Chief i
G PDR_
Reactor Projects Branch 5 Division of Reactor Projects Docket No. 50-443 i
.D i
4
Enclosures:
- 1) Inspection Plan-
- 2) Plant issues Matrix M[. bbS O[
. =. _.... - -
Mr. T. Feigenbaum 2
cc w/ encl:
B. D. Kenyon, President - Nuclear Group J. S. Streeter, Recovery Officer - Nuclear Oversight W. A. DiProfio, Station Director - Seabrook Station R. E. Hickok, Nuclear Training Manager - Seabrook Station D. E. Carriere, Director, Production Serv lces
.L. M. Cuoco, Senior Nuclear Counsel
- W. Fogg, Director, New Hampshire Office of Emergency Management D. C. McElhinney, RAC Chairman, FEMA Rl, Boston, Mass.
R. Backus, Esquire, Backus, Meyer and Solomon, New Hampshire D. Brown-Couture, Director, Nuclear Safety, Massachusetts Emergency Management Agency F. W. Getman, Jr., Vice President and General Counsel-Great Bay Power Corporation R. Hallisey, Director, Dept. of Public Health, Commonwealth of Massachusetts Seacoast Anti-Pollution League D. Tefft, Administrator, Bureau of Radiological Health, State of New Hampshire S. Comley, Executive Director, We the People of the United States W. Meinert, Nuclear Engineer i
3 i
l Mr. T. Feigenbaum 3
Distribution w/ encl:
l Region i Docket Room (with concurrences)_
l l
PUBLIC ~
Nuclear Safety Information Center (NSIC) l NRC Resident inspector H. Miller, RA /W. Axelson, DRA DRP Director,' Region i DRP Deputy Director, Region I DRS Director, Region I DRS Deputy Director, Region i DRS Branch Chiefs, Region I C. Cowgill, DRP R. Summers, DRP D. Cullison, DRP C. O'Daniell, DRP T. Moslak, DRS L. Prividy, DRS Distribution w/ enc!s (VIA E-MAIL):
J. Harrison, PD l-3, NRR R. Correia, NRR (RPC)
Inspection Program pranch, NRR (IPAS)
- DOCDESK, DOCUMENT NAME: G:\\ BRANCH 5\\3-SB\\PPR\\SEAIRPM.RJS To receive a copy of this document. Indicate in the box: *C' = Copy wAthout attachment /enciosure
- E' = Copy with attachment / enclosure "N* = No copy
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i OFFICE RI/DRP fj((M Bl/DRP/f(/
l NAME RSummers/piO CCowgill DATE 12/g /98 "
124 /98 l
OFFICIAL RECORD COPY i
I
ENCLOSURE 1 SEABROOK INSPECTION PLAN FOR DECEMBER 1998 THROUGH MAY 1999 Inspection Program Area / Title Planned Dates inspection Type 37550 Engineering 03/08/99 Core 64704 Fire Protection Program 03/15/99 Core Occupational Radiation Exposure 83750 04/05/99 Core (Outage)
Legend:
IP Inspection Procedure Number Tl Temporary Instruction Program / Sequence Number Core -
Minimum NRC Inspection Program (mandatory at all p! ants)
OA Other inspection Activity RI Additional inspection Effort Planned by Region i SI Safety Initiative inspection s
E1-1 L
X IRTA 2M ER S U E 1
S O U 2
LS E
United Statm Nucirr Regulatory Commission E 75"' -
Resion i PLANT ISSUE MATRIX
- Pose: 1 er s SEA 8 ROOK By Primary Functional Aree Functional Templete Date Source Aree go Type Codes item Desenpaon 08/22/1998 05000443/ Pri: OPS NRC POG Pri: 1 A The operators performed routine reactor plant evolutions, includeg the rector startup and an emergency feedwater pump surveillance test well.
Sec:
Sec:
Ter:
08/22/1998 1998005 Pri: OPS NRC NEG Prl: 5B A minor weakness was noted in that an adverse condation report (ACR) was not initially wirtten to evaluate improperty stored nitrogen bottles. Additionally, the ACR was subsequently approved without fully considenne a!I the potential generic See:
Sec: SC concerns.
Ter:
08/22/1998 1998005 Pri: MAINT NRC MV Pri:
The licensee identified f ailure to property calibrate the power operated relief valve low temperature overpressure protection channels ( LER 98-007) was considered a violatbn of minor significance Sec:
Sec:
Ter:
08/22/1998 1998005 Pri: MAINT NRC NEG Pri: 3A The corrective actions performed in response to an unexpected engineered safeguards feature (LER 98@8) actation during surveillance testing were appropriate Ter: SC t
08/22/1998 1999005 Pri: MAINT NRC POS Pri: 28 Appropriate procedural guide!ines were in place to manage the 12 week work planning process. The newly instit/ed work process was functioning as intended, however, final determination of its effectiveness remains to be determined.
See:
Sec: 1C Ter:
[
08/22/1998 1998005 Pri: MAINT NRC POS Pri: 3A Maintenance technicians performed several activities well druing the period including: installation of a freeze seal and replacement of a safety-related relief valve, installation of new spent fuel racks and testing of a pwoer range nucles:
Sec:
See:
instrument rate circuit.
Ter:
i 08/22/1998 1998005 Pri: MAINT NRC POS Pri: SC Corrective actions taken following the maintenance rule baseline inspection were appropriate See:
See:
6 Ter:
[
i i
r
)
item Typ3 (Compliance. Followup,Other), From 07/01/1998 To 10/30/1998 I'
United St:tes Nuclear Regulatory Commi:sion U:l'*d'S** ~
Resoa i PLANT ISSUE MATRIX P.ge: 2.f a s
' SEABROOK By Primary Functional Area Functional Templete Date Source Afee ID Type Codes item Description 08/08/1998 1998007 Pri: MAINT NRC NEG Pri: 2B The lubrication instruction sin both preventive maintenance and refurbishment procedures were not sufficiently specific to ensure consistent and appropriate breaker lubrication.
Ter:
08/08/1998 1998007 Pri: MAINT NRC NEG Pri. 2B Seabrook had large number of maintenance procedures for low voltage breakers making coordination among procedures cumbersome.
See:
See:
Ter:
08/08/1998 1998007 Pri: MAINT NRC NEG Pri: 58 The licensee's operating experience review (OER) program to review industry events and problems was generally adequate, and their actrions in response to those events were appropriate. However, the licensee's OER reviews fro some information Sec:
See:
notices (IN) were narrowly focused, without considering the generic implication of the ins.
Ter:
08/08/1998 1998007 Pri: MAINT NRC POS Pri: 2A The breakers at Seabrook had performed well during the past five years. The breaker refurbishment program at Seabrook Station was good.
Ter:
08/08/1998 1998007 Pri: MAINT NRC POS Pri: 2A The physical condition of the switchgear was good. The breaker refurbishment room was wellwwpaippped and provided a good environment for performing breaker refurbishment work. The technicians performing breaker refurbishment were Sec:
See: 3A knowledgeable and familiar with the refurbishment procedure.
Ter:
08/08/1998 1998007 Pri: MAINT NRC POS Pri: 2B The licensee's practice of using reduced-control-voltage testing was good. The preventive maintenance and refurbishment procedures for medium-voltage breakers was generally good.
Ter:
08/08/1998 1998007 Prf: MAINT NRC POS Prf: 28 The maintenance procedures for low voltage breakers were clear and detailed. Data sheets for completed maintenance provided a good record of the results of all measurements made and the breaker condition at time of maintenance.
i Ter:
Item Type (Compliance,Folicwup,Other), From 07/01/1998 To 10/30/1998
Dees: 10/21/1998.
Un,ited States Nucl:ar Regulatory Comm.ission Time: is:sO:3.
Region i PLANT ISSUE MATRIX Page:3 of 0 SEARROOK By Pnmary Functional Area Functional Templete Date Source Area ID Type Codee geom W 08/08/1998 1998007 Prl:MAINT NRC POS Pri: 2B The recently-developed circuit breaker tracking system (database) at Seabrook Station provided good information of the curcuit breakers. This initiative was judged to be a program strength Ter:
08/08/1598 1998007 Pri: MAINT NRC POS Pri: SA Work requests and Adverse Condition Reports (ACR) associated with breaker corrective maintenance were well documented.
Corrective actions were appropriate and timely. Root cause and apparent cause evaluations were thorough, of good quality, Sec:
See: 5B and contained appropriate recommendation for corrective actions.
Ter: SC 08/08/1998 1998007 Pri: MAINT NRC POS Pri: 5A The licensee had comoleted a thorough, broad-in-scope self-assessment audit for the medium-voltage and low-voltage breakers, resulting in significant improvement in their breaker vendor interface program. The self-assessment audit report was Sec:
See: 58 of good quality. The self-assessment program was effective.
Ter: SC 08/08/1998 1998007 Pri: MAINT NRC POS Pri: 5A The licensee's vendor interface program improved significantly as a result of licensee's self-assessment audit findings.
Sec:
Sec: SC Ter:
08/22/1998 1998005 Pri: ENG NRC POS Pri: 48 Engineering design and documentation of the SFP rack safety evaluation was adequate. Engineering personnel provided good support during installation of the new SFP racks Sec:
Sec: 4A Ter:
08/08/1998 1998007 Pri: ENG NRC NEG Pd: 2B Commercial-grade dedication at Seabrook for breaker maintenance was limited to breaker lubricant. There was inconsistency of critical characteristics and verification instructions in the breaker lubricant dedication package.
Sec:
Sec: 4C Ter:
08/08/1998 1998007 Pri: ENG NRC POS Pri: 4A The control circuit voltage drop calculations were conservative and were generally thorough and of good quality. The input data arsd assumptions were technically sound.
Ter:
i item Type (Compliana, Followup,Other). From 07/01/1998 To 10/30/1998
Date: 10/21/1998 '
United States Nucle:r Reguttory Commission -
Time:is;.o;3.
nepon i PLANT ISSUE MATRIX Pogo:4 of 6 SEABROOK By Pnmary Funcnonal Aree Funceonel Templete Codes item Description Date Source A'**
ID Type 08/22/1998 1998005 Pri: PLTSUP NRC POS Pri: 1C The licensee was conducting security and safeguards activities in a manner that protected public health and safety in the areas of access authorization, alarm stations, communications, and protected area access control of personnel and packsges Ter:
08/22/1998 1998005 Pd: PLTSUP NRC POS Pd: 1C the level of management support was adequate to ensure effective implementation of the security program and was evidenced by adequate staffing levels and the allocations of resources to support programmatic needs Sec:
Sec:
Ter:
08/22/1998 1998005 Pri: PLTSUP NRC POS Pd: 1C Performance in the radiation protection program was effective.
Sec:
Sec:
Ter:
i 08/22/1998 1998005 Pri: PLTSUP NRC POS Pd: 1C in recognition of the increased source term that may affect future radiological work, the licensee initiated actions to effect better ALARA performance and radiation protection implementation.
Ter: SC The licensee's security facilities and equipment in the areas of protected area assessment aids, protected area detection aids, 08/22/1998 1998005 Pri: PLTSUP NRC POS Pri: 23 and personnel search equipment were determined to be we!! maintained and reliable and were able to meet the licensee's Sec:
Sec:
commitments and NRC requirements.
Ter:
The security force members demonstrated that they had the requisite knowledge necessary to effectively imp! ment the 08/22/1998 1998005 Pri: PLTSUP NRC POS Pd:3A duties and responsibilities associated with their position. Security force personnel were being trained in accordance with the See:
Sec: 3B requirements of the Training and Qualification Plan and training documentation was property maintained and eccurate Ter:3C 08/22/1998 1998005 Pd: PLTSUP NRC POS Fd: 38 The training and qualification process for senior radiological control technicians was well proceduralized, detailed, and implemented.
See:
Sec:
Ter:
V f
i.
Item Type (Compliance. Followup,Other), From 07/01/1998 To 10/30/1998
United States Nuclear Regulatory Commission n9,,,eE""-
nesien i PLANT ISSUE MATRIX Poes: sofa seAssoOK By Pnemy funcuonal Arem -
Funceonel Templete Cedee item Deecrepeon
- Date Source A'**
10 Type 08/22/1998 1998005 Pri: PLTSUP NRC-POS N:3B Selected records for new senior tectvucians were property documented in a detailed and thorough manner.
See:
Sec: IC Ter:
08/22/1998 1998005 Pri: PLTSUP NRC POS N:5B Quality assurance and self-assessment activities, and the rpoblem idnetification process resulted in a thorough and prog ammatic evaluation of the radiation protection (RP) program and were instrumentalin identsfying a need for Sec:
Sec: 5C. improvement in oversight of, and involvement in. RP by management and supennsson from outside of the RP organization.
Ter:
08/22/1998 1998005 N: PLTSUP NRC POS Pri: 5B The security audits wre comprehensive in scope and depth that the audit findogs were reported to the appropriate level of management, and that the program was bein properly administered.
Ter: SA Item Type (Compliance, Followup.Other), From 07FJ1/1998 To 10/30/1998
Detoi 10/2111998 s
United States Nuclear Regulatory Comm.ission Ti,,,e. is:so:3.
PLANT ISSUE MATRIX Page & G By Primary Functional Ares Legend Type Codes:
Templete Codes:
Functional Aroes:
BU Bulletin IA Normal Operations GPS Operations CDR Construction 1B Operations Dunng Transients MAINT Maintenance CEV Deviation 1C Programs and Processes ENG Engineering eel Escalated Enforcement item 2A Equipment Condition PLTSUP Plant Support IFl inspector follow-up item 2B Programs and Processes LER Licensee Event Report 3A Work Performance UC Licensing issue 3B KSA MISC Miscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 48 Engineenns Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion 10 Codes:
NON Notice of Non-Conformance NRC NRC P21 Part 21 Self Self-Revated S
Po d ve Licensee Licensee SGI Safeguard Event Report Eels are apparant 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 en the issues identified by the Eels and the PIM entries may be modified when the final decisions are made.
URis are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation. A URI may also be a potential violation that is not likely to be considered for escalated enforcement action. However, the NRC lus not reached its final conclusens on the issues, and the PIM entries may be modified when the final conclusions are made.
! tem Type (Compliance. Followup.Other). From 07/01/1998 To 10/30/1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 7/30/98 Negative IR 98-04 N
1-OPS 1C The SORC review of an operability determination for a degraded compressor lubricating oil 405 SB system pressure condition could have been more complete since it did not consider all available technicalinformation.
7/30/98 Positive IR 98-04 N
1-OPS 1C The licensee implemented severalinitiatives to improve the effectiveness of the Nuclear Safety 395 SA and Audit Review Committee.
SB 7/30/98 Positive IR 98-04 N
1-OPS 1A Safety-related systems and component material conditions were adequate.
394 2A 7/30/98 Negative IR 98-04 LP 1-OPS 1A The operators did not control a planned pressurizer levelincrease well which resulted in 393 58 exceeding the allowable pressurizer cooldown limits. A subsequent evaluation indicated that the pressurizer integrity was not compromised by this event.
7/30/98 Positive IR 98-04 N
1-OPS 1A Routine operations were performed well and operators wee knowledgeable of plant and 392 1B equipment status. The piant shutdown and cooldown were performed well.
5/4/98 Violation IR 98-02 N
1-OPS SB Several performance deficiencies were noted during review of the steam 5ne pressure channel 381 2A calibrations. This issue remains unresolved pending resolution of the calibration methodology questions being investigated by the Ecensee. (Violation issued in IR 98-04).
5/16/98 Positive IR 98-02 N
1-OPS 1A The field walkdown program continued to be e'iective at identifying minor equipmerit issues as 380 1C highlighted by the large number of equipment da.iciencies tags generated.
2A 5/16/98 Positive IR 98-02 N
1-OPS 1A Routine operations were performed in accordance with station procedures and plant evolutions 379 were completed in a deliberate manner with clear communications and effective oversight by shift supervision.
10/4/97 Negative IR 97-06 N
1-OPS During a surveillance test of the "A" SI pump, the inspector observed beric acid accumulation at 298 the pump's mechanical seal,in the seal basin, and the seal basin drain. Operator awareness and usage of the process to identify and clean boric acid leakage from the "A" safety injection pump mechanical seal was ineffective since boric acid was not being cleaned from the pump on a regular interval. The system engineer adequately assessed the pump's mechanical seal leakage, however, the inspector noted that the possible failure mode ofincreased leakage without drainage was not evaluated.
FROM:10/1/97 TO:7/30/98 Page 1 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 10/4/97 Positive IR 97-06 L
1-OPS The control room operators noted oscillation of the "A' main feed pump govemor contro! valve 297 position and the steam flow indications to the MFP. Operators maintained control and stabilized the plant throughout the entire event. Operations management determined that neither the reactor nor the secondary plant was in jeopardy at any time and therefore did not initiate a plant trip.
10/4/97 Positive IR 97-06 L
1-OPS The conduct of operations was professional and focused on safety principles.
296 7/30/98 Positive IR 98-04 N
2-2B 1C The forced outage was performed safely.The mode change controls implemented prior to start-401 MAINT up were appropriate.
7/30/98 Negative IR 98-04 N
2-3B The corrective actions for the RC-V-89 pipe leak involving prevention of wetting to insulation had 400 MAINT SC not been completed as scheduled.
7/30/98 Positive IR 98-04 N
2-3A The licensee performed freeze seal activities well. Minor procedural weaknesses were noted 399 MAINT 3B regarding precautions for installing freeze seals near welded joints.
7/30/98 Positive IR 98-04 N
2-2A The Ecensee promptfy identified and investigated an abnormal noise in the emergency feedwater 398 MAINT 4B pump room.The engineering evaluation and follow-up of this condition was sound.The decision i
to repair the leaking valves during the forced outage was appropriate, and the repair achvities were effective.
7/30/98 Positive IR 98-04 N
2-SA The Ecensee's investigation into lead / lag card methodology issues was thorough.
397 MAINT 2B 7/30/98 Violation IR 98-04 N
2-SA The Ecensee did not promptly initiate action to confirm the operability of the steam pressure 396 MAINT SC protection channels on the A and D steam generators (NOV 98-04-01).
2A 5/16/98 Positive IR 98-02 N
2-3A The Ecensee promptly initiated an investigation for a failed pressurizer sample valve position 385 MAINT 2A indication, and implemented appropriate corrective actions.
5/16/98 Positive IR 98-02 N
2-3A The electricians performed well during refurbishment of a safety battery breaker.
384 MAINT 2A 5/16/98 Positive IR 98-02 N
2-3A The Ecensee implemented an aggressive inspection criteria for detecting sparking emergency 383 MAINT 2A diesel generator brushes. Upon identification of minor sparking, the Ecensee promptly evaluated the condition, determined that operability of the EDG was not affected, and conservatively decided to replace the affected brushes.
FROM:10/1/97 TO:7/30/98 Page 2 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 5/16/98 Positive IR 98-02 N
2-3A The troubleshooting of the personnel access hatch hydraulic control valves and replacement of 382 MAINT 2A the mechanicalinterlock cable were performed well. Excellent briefings were observed, and the mechanics were weil prepared to perform the planned evolutions.
3/28/98 NCV IR 98-01 L
2-2B The licensee reported several examples of fa ure to develop adequate surveillance test n
369 NCV 98-01-01 MAINT 48 procedures. The Ecensee subsequently revised the test procedures and properly tested each SA component.This Ecensee identified violation of failure to develop adequate test procedures is being treated as a non-cited violation.
3/28/98 Positive IR 98-01 N
2-3A Safety-related degraded voltage bus testing was perfomied well, and the test results satisfied 368 MAINT 2B technical specification requirements.
2A 3/28/98 Positive IR 98-01 N
2-2B The Ecensee performed the planned freeze seal activities well. The work package, and 367 MAINT associated on-Ene maintenance and freeze seal evaluations and management oversight were effective.
3/28/98 Positive IR 98-01 N
2-SA An electrician demonstrated excellent attention to detail and a questioning attitude, to detect and 366 MAINT 3A identify the incorrect installation of two operating mechanism springs on a safety-related 2B breaker.
1/21/98 VIO IR 97-09 N
2-2B Measuring and testing devices were not properly controlled to maintain accuracy within 362 VIO 97-09-02 MAINT necessary Emits. This was a violation of 10CFR 50, Appendix B, Criterion Xil.
1/21/98 VIO IR 97-09 N
2-2B On March 13,1997 the Ecensee changed procedures as described in the UFSAR and failed to 361 VIO 97-09-01 MAINT perform a written safety evaluation to determine that the change did not involve an unreviewed safety question (USQ).This was a violation of 50.59.
1/21/98 Positive IR 97-09 N
2-3A The instrumentation and control (l&C) technician's use of procedure and equipment to perform 360 MAINT 1C caHbrations of M&TE is acceptable. Also, the M&TE moming meetings are useful for discussing current and future M&TE issues.
1/31/98 URI 1R 97-08 N
2-3A The apparent cause evaluation report for six loose service water valve flange nuts did not 351 URI 97-08 MAINT SB document an apparent root cause. The failure to properly document apparent cause findings could affectthe identification and correction of the underlying causes for deficiencies. This issue will remain unresolved.
1/31/98 Positive IR 97-08 N
2-3A The emergency feedwater (EFW) surveillance activities were performed well.
350 MAINT FROM:10/1/97 TO:7/30/98 Page 3 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code Item Description 1/31/98 Negative IR 97-08 N
2-3A Foreign material exclusion controls during the control building air conditioning (CBA) system 349 MAINT SC modifications were poor, and the actions taken to improve performance in this area were not fully effective.
1/31/93 Positive IR 97-08 N
2-3A The residual heat removal (RHR) system pipe replacement activities were performed well 348 MAINT 12 S/97 LER 1R 98-01 L
2-28 North Atlantic Energy Service Corporation (North Atlantic) determined that the current SoEd 344 LER 97-17-00 MAINT State Protection System (SSPS) surveillance testing did not adequately test certain logic circuits.
12/6/97 Negative IR 97-07 L
2-2B A Ecensee review of the Reactor Coolant System (RCS) wide range pressure channel caEbration 343 LER LER 97-14-00 MAINT procedures concluded that the Residual Heat Removal System (RHR) Low Pressure Interlocks (LPI) reset on increasing pressure such that the RHR isolation valves can be opened with an RCS pressure above the TS Emit.
12/6/97 Negative IR 97-07 N
2-3A Minor weaknesses were noted in the program guidance for evaluating fluctuating gage 329 MAINT 2B indications, and scheduEng EDG preventive maintenance activities. The Ecensee identified appropriate measures to address these concerns.
12/6/97 Positive IR 97-07 N
2-2A The emergency feedwater (EFW) and emergency diesel generator (EDG) survei!!ance activities 328 MAINT 2B were performed well. Troubleshooting activities to carrect an adverse EDG start time trend were 3A effective.
12/6/97 Positive IR 97-07 N
2-2A The repair of a failed hot leg temperature instrument was well contro!!ed and prompt. A good 327 MAINT 2B initiative was identified to enhance instrument and technician procedural guidance.
3A 10/4/97 VIO
!R 97-06 N
2-2A Several performance problems occurred during the troubleshooting and repair activities for the A 319 VIO 97-06-05 MAINT 3A Main Feedwater Pump (MFP) that collectively resulted in the A MFP failing to trip during the post-maintenance trip test. A lack of self-check and questioning attitude on the part of supervision and technicians resulted in the use of an inadequate procedure, poor configuration control (failure to document Efting electrical leads) during corrective maintenance, and adherence to procedures. This was a violation of Technical Specification 6.8.1 for failure to fo!!ow procedure.
10/4/97 Positive IR 97-06 N
2-2B The installation of the makeup totaEzer modification was well coordinated. Good inter-318 MAINT 2A departmental cooperation was demonstrated. Station and operations management demonstrated a conservative approach to conducting the on-Ene maintenance by estabEshing contingency plans for addressing a rapid power reduction scenario.
FROM:10/1/97 TO:7/30/98 Page 4 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 10/4/97 VIO IR 97-06 N
2-2A Several performance problems occurred during the troubleshooting and repair activities for the A 301 VIO 97-06-??
MAINT 3A MFP that collectively resulted in the A MFP failing to trip during the post-rnaintenance trip test. A lack of self-check and questioning attitude on the part of supervision and technicians resulted in the use of an inadequate procedure, the lack of configuration control during corrective maintenance, and adherence to procedures.
7/30/98 Positive IR 98-04 N
3-ENG 2A The Ecensee's actions to improve the reHability of the controi building air conditioning system 404 4A were extensive.
4B 7/30/98 Positive IR 98-04 N
3-ENG 2A The Ecensee responded well to investigate the temporary loss of the normal reactor coolant 403 4B pump seal cooling flow. The identified causes and corrective actions for this event were adequate.
7/30/98 Positive IR 98-04 N
3-ENG 4B The evaluation of an evaporator coil over pressurization event was good. A weakness was 402 5B noted involving the initial estimate of the maximum coil pressure.
5/16/98 Positive IR 98-02 N
3-ENG 4B The licensee performed well by identifying and investigating questions pertaining to their 389 2A previous lead / lag card caEbration methodology. This issue will remain unresolved pending review of the impact of the initial method on the channel operabiEty.
5/16/98 Positive IR 98-02 N
3-ENG 4B The system engineer provided good support and analysis of a degraded charging pump drive 388 3A pin / bushing. The Ecensee's actions to replace the components and continue with the inspection program were appropriate.
5/16/98 Negative IR 98-02 N
3-ENG 48 The inspector noted some weaknesses in the Ecensee's method to evaluate the long term 387 4C reliability of the EDG exhaust piping.
2A 5/16/98 Positive IR 98-02 N
3-ENG SB The licensee promptly and adequately evaluated the inspector's concems, and determined that 386 2A no immediate concem regarding degradation of the EDG exhaust piping existed.
FROM:10/1/97 TO:7/30/98 Page 5 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 1/15/98 VIO L-ill IR 97-08 L
3-ENG 2A The control room air conditioning system had inherent design deficiencies and performance 378 EA 98-073-4A problems dating back to initial plant startup and testing. Past actions taken to correct the system 02013 4B performance were primarily focused on the component level to address symptoms associated with the inherent design. These changes were made without a complete understanding of the full effect on the integrated system. A design change to improve the system performance had been developed, however, it was not implemented in a timely manner. Additionally, the corrective action program did not result in the prompt correction of the design deficiencies that were significant conditions adverse to quality. This resulted in a severity level til violation (no civil penalty) for failure to promptly correct a degraded condition.
3/28/98 Positive IR 98-01 N
3-ENG 2A The licensee determined that incorrect!y installed coupling hubs caused a degraded EFW motor 374 4B outboard bearing condition.The pump remained operable in this condition and the Ecensee implemented appropriate corrective actions to address this deficiency.
3/28/98 Positive IR 98-01 N
3-ENG 1A Operations personnel performed well by identifying the safety injection accumulator nitrogen 373 5A leaks. The Ecensee promptly investigated the leakage and implemented appropriate repairs to 4B reduce the leakage. Engineering property assessed the impact of this minor leakage en the accumulator operability.
3/28/98 Negative IR 98-01 N
3-ENG SB The inspector noted that the Ecensee's response to a previous condition involving four minor 372 pipe leaks did notinclude identification of the other plant areas potentially susceptible to periodic wetting. The Ecensee implemented appropriate actions to address this concem.
3/28!98 Positive IR 98-01 N
3-ENG 1A The Ecenses promptly reviewed and evaluated the identification of boric acid accumulation on a 371 4B RHR drain Ene.The identification of this condition reflected positively on the licensee's now system walkdown program.
3/28/98 VIO IR 98-01 N
3-ENG 4B The Ecensee failed to implement adequate design contrc!s to ensure that the safety-related 370 VIO 98-01-02 3A components within the residual heat removal system pump room would remain within their required temperature Emits prior to modifying the room ventilation system. A subsequent Ecensee analysis, performed after the NRC identified this deficiency, indicated that the modification reduced the room ventilation flow by about 50% hewever, the room temperature Emits would not have been exceeded.
1/31/98 URI IR 97-08 N
3-ENG 4C Several performance weaknesses were identified regarding the implementation of the oil 356 URI 97-08-05 analysis program. Incorrect information was provided to the shift manager which formed the basis for the decision to delay sampling the 2B charging pump motor bearing oil. The motor oil was subsequently samp!ed and found not to adversely affect the pump operability, and the oil sampling frequency was increased to better monitor the oil condition.
FROM: 10/1/97 TO:7/30/98 Page 6 of10 21 October 1998
SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code Itern Description 1/31/98 VIO L-ill IR 97-08 L
3-ENG 4B The licensee did not promptly investigate potential pressure boundary leakage from RHR pipe 354 EA 97-073-3A located below the RC-V-89 relief valve. This resulted in a severity level til violation (no civil 01013 SA penalty) for failure to take prompt corrective action.
1/31/98 Positive IR 97-08 N
3-ENG SB The inspector did not identify any factors that would provide a basis for disagreeing with the 353 4B event team finding that the RHR pipe leaks were a result of stress corrosion cracking initiated from the outside of the pipe from chlorides leached on to the pipe from the heat insulating material.
1/31/98 Positive IR 97-07 L
3-ENG 4A Westinghouse informed North Atlantic Energy Service Corporation that a developmental fuel rod 342 LER LER 4B performance model could calculate reduced fuel rod intemal pressure margins when compared 97-015-00 to the previously licensed computer code. Westinghouse has determined that in very limiting cases for high power, high bumup Integral Fuel Bumable Absorber fuel rods, calculated pressures are in excess of the fuel rod design criterion that the fuel rod pe!!et to clad gap shall not reopen.
12/6/97 Positive IR 97-07 N
3-ENG 4A The licensee was taking appropriate actions to improve the content of the Seabrook design 340 48 basis. The EFW system was instal!ed and operational consistent with the design requirements 4C as described in the UFSAR.
12/6/97 Negative IR 97-07 N
3-ENG 4B Weaknesses were noted in the control of temporary equipmentin that some nonpermanent 333 4C components were connected to or located near plant systems without a formal evaluation.
There were no immediate operabiHty concems with the temporary equipment, and noted that the licensee initiated an ACR to review the program.
12/6/97 Positive IR 97-07 N
3-ENG 4B The Ecensee took appropriate steps to evaluate and correct plant problems regarding the l
332 Potential for high primary component cooling water temperatures during post-accident conditions and high vibrations in the steam piping for the steam generator feed pump turbines.
12/6/97 Positive IR 97-07 N
3-ENG 4A The licensee was taking appropriate actions to improve the content of the Seabrook design 330 4B basis. The EFW system was installed and operational consistent with the design requirements 4C as described in the UFSAR.
10/4/97 VIO IR 97-06 N
3-ENG 4B A weakness existed in the maintenance / procurement engineering (PE) interface, such that a 321 VIO 97-06-05 3A barrier to ensuring the use of the correct replacement component broke down. Personnel performing the work identified the wrong component in the field, but that information was never related to PE contrary to the guidance in MA 3.0. This resulted in a severity level lV violation for failure to adhere to procedures.
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O I SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 10/4/97 Positive IR 97-06 N
3-ENG 4B Overall, Seabrook performed the fuelinspection activities well. The inspector observed 320 3A adequate reactor engineering supervisory and vendor oversight on the job. Further, there was excellent HP coverage and radiation controls, good FME program implementation, adequate operations support, and adequate self-assessment by the QA department.
7/30/98 Positive IR 98-04 N
4-PS 3A Security activities were performed well. The licensee implemented a detailed r..M to ensure 409 1C proper vital area access controls were maintained during a planned demonstration.
7/30/98 Negative IR 98-04 N
4-PS 5B The licensee did not implement interim corrective actions to enhance the control of cleaning 408 SC boron from remotely operated vatves following an event vthere a valve was unexpectedly positioned during a cleaning activity.
7/30/98 Negative IR 98-04 N
4-PS 3A The inspector identified a poor practice involving a health physics technician who performed an 407 38 activity on a potentially contaminated system without wearing protective gloves. The licensee's corrective actions for this event were adequate.
7/30/98 Positive IR 98-04 N
4-PS 3A The radiological control technicians at the radiological controlled area (RCA) check point and in 406 1C the liefd were generally attentive, knowledgeable, and provided high quality assistance to ensure proper radiological work practices. The RCA access tumstile installation as a good initiative to ensure that radiation worke : comply with RCA access control requirements.
5/16/98 Positive IR 98-02 N
4-PS 3A The inspectors observed good security force performance during inspection activities. Protected 391 area access controls were found to be properly implemented during random observations.
Proper escort control of visitors was observed. Security officers were alert and attentive to their duties.
5/16/98 Positive IR 98-02 N
4-PS 3A The radiological controls technicians were observed to be attentive and provided high quality 390 assistance to plant workers. Plant workers were observed to be following proper radiological work practices including use of dosimetry and protective equipment. Personnel briefings prior to containment entries were thorough and informative.
3/28/98 VIO 1R 98-01 N
4-PS 1C The inspector that identified four workers were performing maintenance on the *B' containment 375 VIO 98-01-03 3A spray pump in a posted contaminated area without wearing any protective clothing as required by the radiation work permit and posted instructions.
1/31/98 Positive IR 97-08 N
4-PS 3A The inspector concluded that the licensee's actions in response to a positive test result were 359 SB consistent with the fitness for duty program.
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SEABROOK PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 1/31/98 Positive IR 97-08 N
4-PS 3A The radiological controls technicians at the Radiological Contro! Area (RCA) check point and in 358 1C the field provided high quaEty assistance to ensure proper radiological work practices. A!!
personnel observed were properly wearing dosimetry and protective clothing as reouired. The Ecensee began to report the daily work group exposures at the station management meeting to heighten personnel exposure awareness.
12/6/97 Positive IR 97-07 N
4-PS 1C The Ecensee maintained an effective security program. Management support was evident 338 3A based on the implementation of the security program as documented in this report. Audits were thorough and in-depth, alarm station operators were knovriedgeable of their duties and responsibiEties, communications requirements were being performed in accordance with the NRC-approved physical security plan (the Plan) and assessment aids had adequate picture quaEty. Security equipment was being tested and maintained in accordance with the Plan and security training was being performed in accordance with the training and quaEfication plan. The Ecensee's provisions for land vehicle control measures satisfied regulatory requirements and Ecensee commitments.
12/6/97 Negative IR 97-07 N
4-PS 1C Chapter 11, Radioactive Waste Management, of the Updated Final Safety Analysis Report 337 (UFSAR) does not accurately reflect the current status of plant equipment and of methods used for radioactive waste processing.
12/6/97 Negative IR 97-07 N
4-PS 1C Weak attributes were noted in the scope of the Process Control Program document, in the 336 documentation of the technical rationale for changes to the PCP, and in the procedure for updating scaEng factors for radioactive waste streams.
12/6/97 Positive IR 97-07 N
4-PS 1C The management of solid radioactive waste and of transportation of radioactive materials was 335 3A generally effect:ye. The volume oflow level radioactive dry active waste which was being generated continued to be low as the result of effective management in this area.
10/4/97 Positive IR 97-06 N
4-PS 4A The fire suppression system configuration in the main control room meets the requirements of 323 the station's fire protection program. Seaterook Station's fire suppression systems meet General Design Criterion 3 with respect to inadvertent operation of fire suppression systems.
10/4/97 Positive IR 97-06 N
4-PS 3A Security personnel properly responded to alarms caused by card readers inaccurately reading 322 security access cards. The security staff adequately demonstrated that the security system appropriately alarmed and identified errors in access control.
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t ABBREVIATIONS USEDIN PIM TABLE CBA Control Building Air Conditioning System EDG.
Emergency Diesel Generator EFW Emergency Feedwater MFP Main Feedwater Pump t
t NRC Nuclear Regulatory Conmssion RCA Radiological Control Area f
[
RHR ResidualHeat Removal SI Safety injection SSPS Solid State Protection System UFSAR Updated Final Safety Analysis Report t
I i
i i
t l
I t
I t
FROM:10/1/97 TO:7/30/98 Page 10 of10 21 October 1998 l
l
-a
..- u4-w.
GENERAL DESCRIPTION OF PIM TABLE COLUMNS The actual date of an event or significant issue for those items that have a clear date of occu,rence (mainly LERs), the date the source of the information
- l was issued (such as for EALs), or the last date of the inspection period (for irs).
Type The categorization of the item or finding - see the Type / Findings Type Code table, below.
Source The document that describes the findings: LER for Ucensee Event Reports, EAL for Enforcement Action Letters, or IR for NRC Inspection Reports.
ID Identification of who discovered issue: N for NRC; L for Ucensee; or S for Self identifying (events).
SFA SALP Functional Arsa Codes: OPS for Operations; MAINT for Maintenance; ENG for Engineering; and PS for Plant Support.
Code Template Code - see tab!e below.
Details of NRC findings on LERs that have safety significance (as stated in irs), findings described in IR Executive Summaries, and amplifying information Item Descripffon contained in EALs.
e TYPE / FINDINGS CODES TEMPLATE CODES ED Enforcement Discretion - No Civil Penalty 1
Operational Performance: A - Normal Operations; B - Operations During Transients; l
and C-Programs and Processes Strength Oveiall Strong Ucensee Performance Weakness Overall Weak Ucensee Performance 2
Material Condition: A - Equipment Condition or 8 - Programs and Processes eel
- Escalated Enforcement Item -Waiting Final NRC Action 3
Human Performance: A -Work Performance; B - Knowledge, Skills, and Abilities /
- " 9; ~
VIO Violation Level I,11,111, or IV 4
Engineering / Design: A - Design; 8 - Engineering Support; C - Programs and Processes NCV Non-Cited Violation DEV Deviation from Licensee Commitment to NRC 5
Problem identification and Resolution: A - Identification; B - Analysis; and C -
Reso>; tion Positive Individual Good Inspection Finding Negative Individual Poor inspection Finding NOTES:
Eels are apparent violations of NRC requirements that are being considered for LER Licensee Event Report to the NRC escalated enforcement action in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action' (Enforcement Policy), NUREG-1600.
URI" Unresolved item from inspection Report However, the NRC has not reached its final enforcement decision on the issues Ucensing Licensing issue from NRR identified by the Eels and the PIM entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided MISC Miscellaneous - Emergency Preparedness Finding (EP),
with an opportunity to either (1) respond to the apparent violation or (2) request a Declared Emergency, Nonconformance Issue, etc. The predecisional enforcement conference.
type of a;l MISC findings are to be put in the item Description column.
URis are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation. However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
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