ML20217D491

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Rev 0 to B-SP-93-06 Assessment Plan Outline, Program or Area:BNP-1 Startup & Power Ascension Readiness Assessment
ML20217D491
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 07/30/1993
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20217D186 List:
References
FOIA-97-252 B-SP-93-06, B-SP-93-6, NUDOCS 9710030246
Download: ML20217D491 (20)
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wun. wick pient A..... .nt Q o-ASSESSMENT PLAN OUTLINE July 28,1993 l Procram or Area: BNP 1 Stanup and Power Ascension Readiness Assessment Renulatory Commitments: (a) CP&L letter NLS 92-160 dated July 23,1992. Enclosure B. Performance improvement Program (Required Pre-stanup), R. A. Watson to S. D. Ebneter (b) BSEP 92 0046 dated November 30, 1992: Integrated Startup Plan and Schedule submitted to NRC, R. E.

Morgan to S. D. Ebneter htpose of Assessment o Conduct an independent operational readiness assessment of Brunswick Nuclear Plant (BNP) Unit 1 to evaluate the effectiveness of the Integrated Stan Up Plan in ensuring that the People, Processes sud Plant are ready to operate safely and reliably.

e Advise the Executive Vice President, Nuclear Generation Group (NGG), and CP&L Corporate Senior Management of the readiness of BNP Unit 1 to restart.

Note: As a basis for the assessment, the team will use the INPO document Performance Objectives and Criteria for Operating and Near Term Operating License Plants (INPO 90-015 August 1990). -

Iarnet Areas:

Phase I: Phase I will have a two t'er approach, Control Room Operations activities will

  • be covered around-the-clock for one week. - In addition, management oversight, work processes, and equipment readiness to support safe startup will be assessed.

B SP-93-06 Revision 0 1 9710030246--970929 V 4

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F un wick pient A. .. nt ASSESSMENT D PLAN OUTLINE l

  • People l Monitor daily activities in the areas of operations, testing, maintenance, and self j assessment. Determine if plant staff is ready to operate the plant safely. Evaluate the l adequacy of management oversight and involvement in daily activities.

l Procedures and Processes i

Evaluate procedures used for normal operations, transient and alarm responses, system i and component operations and testing, Evaluate the effectiveness of the work management systems as they are used in suppon of plant operation, including inter unit  ;

communicationsc Assess the philosophy and practice of the staff with regard to procedure adherence.

. Plant Systems and comoonents Verify that systems and components required for safe operation are operable and properly aligned, and that the systems are being maintained and operated in accordance with applicable procedures.

Phase II:

Issue followup and resolution of emergent issues.

Monitoring of startup activities. This will consist of 24-hour, round the-clock coverage of plant operations with emphasis on Control Room operations from just prior to initial Unit I rod pull until 100% reactor power is achieved and the plant's power ascension plan objectives have been met, B SP 93-06 Revision 0 2

a' Wunswick Plant Assesspent 7 ASSESSMENT Qb

'p PLAN OUTLINE Mwl Leonaiti Lonin - Team Leader Mike Bradley - Lead Assessor (BNP NAD)

Assessors Assessors Rick Jacobs - (INPO) John Moyer - (llNP NAD)

Wayne Gurganious - (BNP NAD) Don Quick - (BNP NAD)

Eric Harkcom - (BNP NAD) Curtis Schacher - (BNP NAD)

Tom llicks - (Contractor) Ralph Schlichter - (BNP NAD)

Glenn Johnson - (HNP NAD) Roger Stewart - (Corp NAD)

Bruce Leonard -(INPO) John Sullivan - (GPU Nuclear)

Don McCaskill - (BNP NAD) Jim Thompson - (Corp NAD)

Phase II Mike Bradley -lead Assessor (BNP NAD)

Assessors .=.ssessors Cary Briney - (HNP NAD) Don Quick - (BNP NAD)

Eric Harkcom -(BNP NAD) Mike Rogers -(BNP NAD)

Glenn Johnson _- (HNP NAD) Curtis Schach.t- (BNP NAD)

Dick Labelle - (RNP NAD) Ralph Schlichter - (BNP NAD)

Don McCaskill - (BNP NAD) Vic Smith - (RNP NAD)

Jim Thompson - (Corp NAD)

B-SP-93-06 Revision 0 3

i ASSESSMENT h]

w on. icx m ont ......nt PLAN OUTLINE Refertssn (a) Integrated Recovery Methodology (PN 30)

(b) Systems Turnover to Operations and Line Management Staff- Assessment of Readiness for Restart of BNP Unit 1 (c) BNP Unit 1 Stattup Power Ascension Performance Objectives and Management Plan Prepared by: '

Date: 1 f!f8 Approved by:

- D /

Date:

l / f B SP 93-06 Revision 0 4

EPunswick Plant Assessnent Q Q PLAN OUTLINE i

PHASE I August 20,1993 through August 27,1993 l

Operational Readiness

1 i Verification ofIntegrated Startup Plan commitments, as spplicable, have been completed.

l Assess effectiveness of actions in conjunction with the appropriate areas noted below.

I. Operations

! A. Shift Conduct of Operations

1. Command and control
2. Shift professionalism and communications
3. Control room decorum
4. Shift turnovers, shift briefs, pre job briefs
5. Inter-unit communications i 6. Document Control l 7. Self-checking, attention to detail
8. l.og keeping 1
9. Adherence to procedures
10. Response to plant annunciators
11. Administrative burdens

! 12. Self-assessments B. Control of Systems / Equipment

1. LCO controls
2. Clearances, caution tags j 3. Work control, knowledge of ongoing work activities
4. U-1 and U 2 common systems
5. Verification of system line-ups
6. Independent verification activities
7. Performance of surveillances
9. Supervision of activities outside the Control Room
9. Radwaste operaticns '
10. Fire Protection
11. Switchyard controls B-SP-93-06 Revision 0 5

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. l l a un.. a m.ns 4. ...nt ASSESSMENT 4 PLAN' OUTLINE ,

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1

PHASE I August 20,1993 through August 27,1993 1

i C. Shift Staffing

[ 1. Overtime control 1

2. Pipeline for operators and STAS
3. Compliance with Tech Specs and Admin requirements D. Operator
  • Work Arounds"
1. Annunciators
2. RTGB disabled instruments
3. Jumpers / lifted leads

-4. Equipment ready for startup. Challenges.

5. Other work arounds not identified
6. Technical Specification interpretations E. Operator Requal Training Program
1. Simulator observatioru
2. Amount of requal and attendance
3. Readiness for startup-operating experience
4. Panel awareness and diagnostics F. Operations Interface with other Site Units
1. Impact of plant modifications
2. Planning and scheduling of work activities - POD involvement
3. Operability determinations / safety evaluations
4. Event reporting, root cause, corrective action
5. Control over surveillance testing and maintenance
6. Quality of communication with other units
7. Confidence in Work Management Center and Work Control Center
8. Operations involvement in PMTR process
9. - Teamwork G.- - Adequacy of Operations Procedures / Guidelines Use of standing orders 1.
2. Outstanding procedure change requests -
3. Operator attitude toward procedure quality B-SP-93-06 Revision 0 6

a un..ica pi.nt 4..... nt .c ASEUEE PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 II. General flousekeeping and Material Control

1. Material control
2. Ilousekeeping I
3. Management presence in plant II. Plant Self-Assessment Activities l

4 Corrective Action Program effectiveness (Problem identification, root cause analysis)

Post trip (0122) review (process for unit restart following reactor trip)

III. Facildy Management Organization '

Organization and staffing, including Emergency Plan Activation Site and Corporate interfaces Qualification and training Site management effectiveness Operational readiness self assessment (Integrated Startup Plan commitments PN-31 process) ,

Management oversight activities Management conservatism relating to Pla .'t Operations Management use of performance indica. ors, performance expectations and work practices Management awareness of programs, plant status, procedures, commitments to reuglatory agencies Plant Nuclear Safety Committee activities B-SP-93-06 Revision 0 7

l i

ASSESWEW w un.. ice pi.nt 4..... nt h PLAN OUTLINE Q

PHASE I August 20,1993 through August 27,1993 Procedure Adherence Philosophy Management responsibilities in the CAP IV. Maintenance  ;

Material Condition:

A. Backlog Management

1. Characterization and Status (PN 30)

! 2. Equipment Problem List I B. Equipment Problem Identification

, 1. System Engineer / Operator / Maintenance knowledge of equipment problems,

2. 110w does startup process identify / resolve equipment problems l (PN 30)?

l C. PM/MST/PT

1. Currera backlog
2. Future backlog D. Post Maintenance Testing
1. Backlog which exists (aged)
2. Current tests how captured? how accomplished?

Ability to Maintain / Improve Condition:

A. Work Control

1. Is the new work control process working? Do the procedures reficct the actual process?

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2. Are performance indicators used? Are they effective?

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B SP-93-06 Revision 0 8 l

r B*unswick Plant Asmessment ASSESSMENT O

PLAN OUTLINE PHASE I-August 20,1993 through August 27,1993 B, Conduct of Work

1. Procedures (a) Compliance (b) Quality (change backlog)
2. Skills / Knowledge
3. Professionalism / Practices (a) Work area housekeeping (b) Foreign material exclusion (c) Tool /part control
4. Supervisory oversight V. Startup Activities Evaluate the " Start-up Readiness Assessment Plan" developed by plant management to assure that, as a minimum, the following areas are considered:

A. Start-up organization, staffing, and policy

1. Adequacy of resources
2. Experience of personnel
3. Establishment and communication of appropriate authorities, accountabilities, and expectations.
4. Establishment and communication of appropriate organization interfaces
5. Definition of responsibility for, and scope of involvement ia, identified start-up activities.
6. Appropriate management involvement and support is defined and effectively communicated.
7. Outage / start-up activity documentation and close-out process defined and effectively communicated.

B-SP-93-06 Revision 0 9

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a l ' Brunsdick Plant Assessment -

ASSESSMENT Q ,

PLAN OUTLINE l 1 PHASE I August 20,1993 through August 27,1993 L

4 B. Management direction, suppon, and oversight a

I 1. Defined schedule and scope of management involvement in direction, l

- suppon,-and oversight of start-up activities.

_ 2. Clear definition and communication of policies,- expectations, l - accountabilities, and authority during management suppon and oversight __

j ._ activities.

3. Defined plan for self-assessment of the effectiveness of implementation of start-up _ activities.

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[ 4. Defined process to promote coruistent-conununication of strengths and weaknesses to appropriate levels of management to facilitate timely and-effective action.

5. Defined policies and process for control and timely resolution of emergent issues encountered during stan up activities C. Start-up testing.
1. Plan and schedule, including appropriate hold points, for start-up testing

--/ surveillance.

-2. Effective integration of all special testingc

3. Development of special procedures, as appropriate.

- 4. - Development of stan-up testing organization, including communication of accountabilities, expectations, and authority.

5. Defined emergent issue resolution strategy.

-B-SP-93-06 Revision 0 10 4

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EP unswick Plant Assessment ASSESSMENT Q

PLAN OUTLINE PHASE I August 20,1993 through August 27,1993

6. Defined support organization interface and coverage of start-up activities, eg; NED, Technical Support, Maintenance, E&RC, etc.
7. Defined special surveillance of operating systems and equipment, eg; type, frequency, documentation.

D. Control of plant areas and systems.

1. Defined close-out control of outage related maintenance activities, j including responsibility turnover to the start-up organization.
2. Defined special, post maintenance / pre-operational testing requirements for critical components, controls, and instrumentation, eg; blowdown of instrumentation sensing lines and dead-leg piping, control valve stroking, etc.
3. Defined special surveillance during initial operation of equipment.
4. Provision for availability, allowarce, control, and evaluation of minor maintenance activities during pre-operational and start-up testing activities.

E. Integration of industry operating experience

1. Review and incorporate as appropriate, Brunswick, Harris, Robinson, and Industry operating experience feedback.
2. Review in particular, experience of troubled plant recover; from long duration outages, eg; Brunswick Unit 2, Browns Ferry, Fitzpatrick, Pilgrim, etc.

B-SP-93-06 Revision 0 11

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& unsC Ck N ant Assess e nt Q ,

ASSESSMENT PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 4

F.

. Potential detrimental effects of long duration outages on plant components and control systems.

b 1.

Be aware that valve packing deterioration may cause leaks, and ~

that corrective action may necessitate retesting of the component.

2. Be alert for indications ~of system / component internal corrosive or contamination effects due to inadequate long term lay-up, or ineffective cleanliness control during maintenance, eg; rust, 4 sludge, moisture in air / oil.

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3. I Monitor for control system instability, instrument sensing line j- plugging, higher than expected strainer / filter delta pressures, frothing or foreign matter in oil sight-flow indicators, abnormal temperatures / flows / levels / sounds / vibrations, etc.

G. Interface control of Unit 1/ Unit 2 common systems.

1.

' Establish special control.; over conduct of maintenance activities at or near system interface points to prevent any negative effects on

operational portions of common systems, p

t 2. Assure that personnel involved in maintenance or testing activities are aware of the system-interface points, and the effects their activities could have on operational systems or equipment in the area.

3. Establish controls to minimize unnecessary personnel access to 4

common system interface areas, or to other areas of the plant t containing sensitive equipment or controls in an effort to prevent the potential adverse effects of inadvertant actions, i

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. W unswick Plant Assessment Q i

PLAN OUTLINE PHASE I August 20,1993 through August 27,1993

H. Management / Plant Nuclear Safety Committee (PNSC) stan up readiness $

determinations. >

1. Establishment and communication of a defined management philosophy for the decision-making process during stan-up related activities.

, 2. Establishment of pre-defined management decist 4 points at critical stages within the start-up plan and as appropriate, during special j testing activities. ,

i 3. Clearly define the timing and extent of PNSC involvement in the i

1 stan-up readiness determination process, eg; closeout of modifications / work, engineering or maintenance backlogs, post-t maintenance or pre-startup testing results, regulatory commitment review results, people / process improvements, pre-defined stan-up 4

plan decision points.

1 i.

I. Stan-up testing procedures / scheduling.

1. Create an integrated start-up and power ascension schedule that-encompasses all planned routine and special evolutions and testing necessary to take the plant from cold shutdown to 100% power in a safe, reliable, and prudent manner following a long duration outage.
2. Identify all necessary special testing to suppon start-up in accordance with paragraph I.1, above, and develop procedures to suppon satisfactory accomplishment of those evolutions in concen with existing routine stan-up procedures, eg; special post-maintenance or pre-startup flushing or testing, special start-up testing during heat-up and power escalation, etc.

B-SP-93-% Revision 0 13

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ASSESSMENT a un..ic= nient A..... = nt o PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 J. Specialized start-up training for appropriate personnel.

1. Are policy, process, and special procedure training being conducted for all stan up team members.
2. Are detailed pre-test briefings for involved start-up team personnel conducted / planned prior to the performance of testing evolutions.

Determine whether individual organizational units develop, communicate, and implement management plans and policies, commensurate with their level of involvement, that are designed to effectively suppon accomplishment, and assure the success, of the " Start-up Readiness Assessment Plan".

VI. Engineering and Technical Support A. Technical Suppon/NED Organization and Administration

1. Stability of the organization
2. Staffing levels of the organization
3. Training / experience of engineering suppon
4. Corporate initiative and 3-Year Plan initiatives B. Reactor Engineering -
1. Core monitoring function

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2. Reactivity controls
3. Software utilization
4. Operations interface C. Engineering Suppon Activities and Interface
1. Startup suppon (PN-31)

. 2. Operations and Maintenance interface B-SP-93-M Revision 0 14

Wunswick Plant Assessment L

PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 D. Plant Performance Monitoring

1. Review Plant performance weekly trending
2. Review Surveillance Testing / Post Maintenance Testing impact on unit performance E. System Readiness Reviews (EHC, RHR/RHRSW,250 VDC, Condensate /Feedwater. Instmment Air) i
1. Collective impact of open work items
a. Work Requests, Temporary Conditions, Temporary Mods, Operator Work Arounds
b. Walkdown deficiencies, Direct Replacements, Engineering Work Requests
c. Preventive maintenance, periodic tests, vendor recommendations, technical information, operating experience feedback (SOER's, SEN's, etc.)
2. Open Work Item Management (Post PN-30)
3. Co-+iguration Control
a. Modification operability basis
b. Training
c. Design Basis Document program -

d, Drawing control

e. Procedure updates B-SP-93-06 Revision 0 15 8

Grunswlck Plant Assessment Q QJ PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 VII. Environmental tnd Radiological Controls A, Corrective Action Program

1. Interview management and technicians to determine culture for identification of problems,
2. Review E&RC issues / problems that impact startup.
3. Observe work - mechanical and I&C maintenance - which require radiation control coverage. Look for human performance problems.
4. Review E&RC Event Reports and ACRs assigned to E&RC for resolution.

B. E&RC Organization and Administration

1. Review E&RC goals and status for 1993.
2. Review E&RC organization,
3. Observe E&RC interface with other work groups.

4, Interview E&RC management to determine support for company and project initiatives and effectiveness of " change" management.

5. Observe E&RC management presence in the field.
6. Review effective performance management implementation.
7. Review close-out of regulatory required items.

B-SP-93-06 Revision 0 16

W uns W k Mant Asses e nt ASSESSMENT Q

PLAN ~ OUTLINE PHASE I August 20,1993 through August 27,1993 C. Review E&RC Units' Readiness for Plant Startup

1. Plans for restart of systems from a chemistry perspective (water quality, availability, radwaste processing).
2. Plans for restart of systems from a radiation control perspective (radiological surveys and posting).
3. Integration of industry experience / operating feedback into E&RC activities.
4. Review "E&RC" Startup Plan.

D. Work Control

1. Observe work activities to determine adequacy and effective use of E&RC personnel to support remaining work and startup activities.

Radiation Work Permit system Timeliness and quality of radiation control coverage I -

Contamination control Control of internal / external radiation exposure Radiation control instruments for workers readily available TLDs/SRPDs system effectiveness E. Material Condition

l. Through observation, ensure plant material condition has been upgraded and methods are in place to continue improvements.
2. Review results of plant decontamination program.

B-SP-93-M Revision 0 17

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- k unswick Plant Assessment Q PLAN OUTLINE PHASE I August 20,1993 through August 27,1993 F. Plant Radiation & Effluent Monitors

1. Review status of technical specification required radiation and effluent monitors for operability and reliability. '
2. Review status of other radiation and effluent monitors.

G. Training

1. Review status of training for E&RC to transition from outage to power operation.

II. Chemical Control

1. Tour all areas of the plant to ensure chemicals deleterious to plant systems are controlled to prevent inadvertent entry into plant systems.

I. Radwaste Volume Reduction

1. Observe radwaste volume reduction program implementation.

J. Control of Contaminated Equipment and Material i

1. Observe radiological surveys of potentially contaminated and contaminated tools and equipment.
2. Observe the disposition oflarge amounts of scaffolding materials.
3. Observe the monitoring of waste for disposal at site land fill.
4. Observe the monitoring and shipment of vendor supplied tools and equipment.

B-SP-93-06 Revision 0 18

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w un..lck Plant Assessw nt- O PLAN OUTLINE PHASE II August 28,1993 through 100% Power Operation I. Issue followup II, - Emergent Issue Resolution III, Material walkdown prior to Drywell closeout, See walkdown schedule, IV. Monitoring of Startup activitica on Unit 1 through 100% power operation i

l B-SP-93-06 Revision 0 19

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Attachment 1 4

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Walkdown Schedule TEAM ZONE / SYSTEM DATES Bradley/ Schlichter Drywell below 38' TBD Rx Bldg 80', 98', 117' 250/125 VDC Schacher /Kenworthy - Drywell above 38' TBD Control Bldg /Radwaste EHC Quick'Harkcom Turbine Bldg (cold side) TBD DG Bldg INST, AIR Bradley/Gurganious Rx Bldg -17',20',50' TBD AOG/MWT Bldg RHR/RHRSW Schlichter /McCaskill Turb Bldg (hot side) TBD SW Bldg COND/ FEED B-SP-93-06 Revision 0 20 l

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CP&L Carolina Power & Ught Company Company Correspondence ,

September 10,1993 l SERIAL: BSEP 93 0152 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325/ LICENSE NO. DPR 71 IGSCC INSPECTION RESULTS REFUELING OUTAGE 8 l Gentlemen:

The purpose of this letter is to provide the NRC with a copy of Carolina Power & Light Company's (CP&L) Brunswick Steam Electric Plant, Unit 1, Refueling Outage 8 activities associated with NUREG-0313 Revision 2 inspections of piping susceptible to Intergranular Stress Corrosion Cracking (IGSCC).

TotalIGSCC welds per category inspected during Brunswick Uni'.1 Refueling Outage 8, in accordance with NUREG 0313 and Generic Letter 88 01 are detailed below:

TABLE 1 BNP 1 IGSCC Examination Categories Total A B C D E F Refuel 8 7 0 9 5 6 1' 28 Current 150 10 42 25 11 1 239 Population i

  • Examined during 1992 Structural Outage (Reference NLS-92-306)

The Ultrasonic (UT) examinations of the welds identified in Table 1 were performed by General Electric (GE) UT personnel qualified in accardance with the EPRl/BWROG/NRC requirements, including the latest requalification program.

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. Document Control Desk BSEP 93 0150 i Page 2 As indicated in Table 1, twenty eight (28) welds out of the current population of 239 lGSCC susceptible welds were examined during the current Brunswick Unit 1 outage consistent with CP&L's approved Generic Letter 88 01 IGSCC Inspection Program, except as noted in Table 1. During the examination of the welds in the scope of the inspections, no apparent growth to existing indications and no new indications were noted.

Enclosure 1 to this letter provides CP&L's updated GL 88 01 classifications and inspection schedule. Changes to the schedule reflect rescheduling 3 Category D Feedwater (inconel) welds from refuel 8 to refuel 9 in accordance with GL 88 01. These welds were examined in refuel 7 and are not required to be examined again until refuel 9 (to be examined every two (2) refueling cycles per GL 88 01). The original scheduling of refuel 8 reflected a better distribution of the Category D weld population every other outage. To reduce radiation exposure and expenditures, within the requirements of GL 88 01, these three (3) welds were rescheduled from refuel 8 to refuel 9. However, these 3 welds and nine (9) of the remaining Category D welds, are scheduled to be removed during refuel 9. The new welds would not require IGSCC examinations in accordance with GL 88-01 and NUREG-0313 requirements. Once the new welds are implemented, the classifications and inspection schedule will be revised to reflect the deletion of 12 Category D welds. The new welds will be inspected in accordance with ASME Section IX requirements.

Please refer any questions regarding this submittal to Mr. K. A. Harris at (919) 457-3312.

Very truly yours, W. Levis Manager Regulatory Affairs Section SHC/she (igsecro8.ul)

Enclosure cc: Mr. S. D. Ebneter Mr. P. D. Milano Mr. R. L. Prevatte

3-

! ENCLOSURE 1 i

l BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1

. NRC DOCKET NO. 50 325 1-- - OPERATING LICENSE NO, DPR 71

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LDL t025 V 3180/did3 an30 X i L3EL L029 V did3/3180 5630 V 3180/did3 an30 X LDL LOEI LDL L029 V did3/3180 3830 e

6E LZ?50'MS3 03513NV13S d33S33A133 !NSd33110N 03 N36 6314

8 fWCLOSURE 1 Po9e 3 of 8 B$f P t*lf 1

  • ICSCC th5*EC110N CLAttlFitATM ICSCC JOIW1 WELD NUMBER Sf5 SCHEDutt0 IWSPECfl0NS CAftCORY CONFIC.

RF07 RF06 RF09 RF010 RF011 1C31 1029 A PIPE /EL80 pc x 1C31 987 A PIPt/ffE RWCU 1C31 986 A TEt/VALV RWCU iC31 988 A TEf/ PIPE RWCU iC31 989 A PIPE /ttto RWCU x iC31 990 A tito/ PIPE RWCU 1C31 991 A PIPE /Etto RWCU 1C31 992 A Et80/ PIPE RWCU iC31 993 A PlPE/Elto RWCU iC31 995 A tit 0/ PIPE RWCU 1C31 996 A PIPE /FtWC RWCU 1C31 997 A FtWC/P!PE RWCU 1C31*980 A PIPt/ttt0 RWCU 1C31 981 A ttt0/Etto RWCU 1C31 983 A Ftto/tteo RWCU 1C31 984 A ttt0/ PIPE RWCU 1C31 985 A PIPE /fxCH RWCV 1RWCU 90A A EXCN/Ett0 RC 1RWCU 145 A ELB0/ PIPE RWCU 1RWCU 150 A PIPf/ftto RWCU x 1RWCU 96A A Ett0/ExCN RWCU 1C31 1032 A EL50/PIPF RWCU 1C31 1033 A PIPE /ftto RWCU X 1C31 1034 A tito/Etto RWCU 1C31 1035 A ELB0/ PIPE RWCU 1C31 1036 A PIPF/Etto RWCU 1C31 1037 A ELB0/Etto RWCU N 1C31 1038 A Etto/ PIPE RWCU 1C31 1040 A P!Pf/Etto RWCU 1C31 1041 A Etto/P!PE RWCU 1C31 1042 A PIPE /Etto RWCC X 1C31 1043 A Etto/ PIPE RWCU 1C31 1044 A PIPE /FtWC RWCU 1C31 1055 A FLWC/ PIPE RWCU 93 12450.Msc

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

t 3M310Sne3 4 400# ? 01 9 eS]4 0481 L 83533 14S4131102 J1V55ljiJV11045 13533 f0141 n310 NAMtla $1$ SJN300130 14543361045 3V13308A 3ONAIS' 5104 4409 5406 51010 uJOLL 63EL 6059 V 4143/3180 an3R X L3[t*L054V V 3140/d143 anan 43E t = L 052 V d143/3180 anan X 4316 6054 V 3180/d843 tnan L3EL L09L W did3 /3180 an30 X 63EL 6092 V 3180/4143 5630 X 63Et*L09E V 41d3/1140 8630 L DE L

  • L 097 V 3180/d143 anan 63EL*t095 V l 4143/3180 anan 63E1 6099 V 3180/d143 4630 X 43Et*L094 V 4843/3140 4630 63EL*t099 V 3180/did3 anan 43Et*t096 V Jld3/3180 anan 63EtaL040 V 3100/did3 8630 t UE L
  • L OLE V 4I43/3180 en3n 63EL*t04E V 3180/did3 an30 63EL L041 V d143/3180 463n 43EL 6045 V 3180/d143 5630 LSEL 4049 V 41d3/3180 8630 431L 6044 4 3100/did3 anan X LSEL 173 V did3/AvlA an30 43530 9458 V 3X3H/31tO 8n30 L3ELAd*L?ainhn3 nets V AV1A/did3 8630 X t3ELJJ 47 dnan3natS v eld 3/AvlA an30 X X 4335 .

LSEZJJV LZ JM401 V did3/SZ 43EZJJt LZ*JM402 V 4143/53 3335 e did3/S3 3335 .

ttEZJJ3 LZ JA40E V tsEZJJ0*t/.JA407 V did3/53 daaS ttEZJJ3 LZ-JM405 V dle3/03 3335 4143/S3 8335 e L8EZJJJ LZ JA409 V X 4143/53 8335 .

ttE2JJ3 LZ JM402 V did3/S3 43a5 e ttEZJJH LZ*dm409 V did3/S3 aaaS .

ttEZJJr LZ JM406 V did3/S3 3335 e ttEZJJ3*tZ-dn4LO V 6E LZ?50*MSD e 13313NV13$ da3533At33 !NSd33110N 34 M3n n310

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

l t l l

1 J

[W.ELQ$VRf.1 Pete 's of 8 BSEP UWIT i ICSCC IktpfC110W CtkS; 'ICATIOWS IC$tt JOINT WELD kWSER $1$ SCHEDULED INSPEC110N',

CATLC& Y CONFIG.

RF07 RF08 RF00 RF010 RF011 iB11W2A*RPV FWABA A SE/WO22LE RCRS tX) iB11W28*RPV*FWABA A SE!N022LE RCRS * (K) l iB11W2C RPVaFWABA A SE/WO22LE RCRS *

(X) iB11N?D*RPV FWABA A SE/WO22LE RCRS . (K) 1811W2E RPV FWABA A St/WO22LE RCRS (X) 1811W2F RPV FWABA A SE/WO22LE RCRS (X) 1911N20 RPV FWABA

  • A SE/WO22LE RCRS (X) 1911N?N.RPV.FWABA A SE/WO22LE RCRS (K) 1811N2J RPV*FWABA A SE/WO22LE RCRS (K) 1811W2K*RPV.FWABA A SE/WO22LE RCRS (K) 1811W5A.RPV FWRNA 16A
  • A SE/W322LE CS (X) 1811W58*RPV FWRNB 16A A SE/WO22LE Cr *

(r) 1E21FF.4 FW1C2180 A TRAWS/SE CS * (X) 1E21FF 8 FW1E2183

  • A TRANS/SE CS (X)

,1332FFA 12 FWRh310A B SWpt/ PIPE RCRS

  • 1932FFB 12 FWRRB11A e SWPL/FIPE RCR$
  • 4.

1832FFC+12 FWRRB12A B SWPL/ PIPE RCRS * (X) iB32FFD*12 FWRRB13A B SWpt/ PIPE RLRS *

(X)

SkPL/P!PE

  • 1832FFE 12 FURRB14A B kCRS IB32FFF 12 FWRRA10A B SWPL/ PIPE RCRS '
  • RCRS
  • _1832FFG 12 FWRRA11A B SWPL/ PIPE SWPL/ PIPE
  • 1932FFM.12.FWRRA12A B RCRS
  • (X) 1B't2FFl-12 FWRRA134 d 8 SWPL_/ PIPE RCES 1832FFK 12 FWRRA14A B SWPL/ PIPE RCR$

4 1832RECIRC-2842(INSI) C PIPE /SE RCRS X 1832REclRC 28A3(IMSI) C PIPE /ELB0 RCRS X 1832RECIRC 28A5(INSI) C PIPE / TEE RCRS X 1832RECIPC 28A6(thSi) C TEE / PIPE RCR$ X i 1832RECIRC 28A9(lHSI) C VALV/P!PE PCRS X

  • DESIGNATES PRESERVICE INSPECTION OF NEW WELO (X) DESIGNATES SECTION XI INSPECTION OF WELD THAT WIL'. ALSO MEET THE 93 12450 MSC REQUIREMENTS OF NUREG 0313, REY 2.

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

n EWCLOSURE 1 Pope 6 of 8 M 'If 1 ICSCC IkSPEC110H CLAttlFitAfl0NS IG5CC J0lHT .

WELD WUMBER STS SCHEDULED !WSPECTIOus CATEGORY CONFIG.

RF07 RF08 RF09 RF010 RF011 1332RECIRC 2&A10(INSI) C PIPE /Etto RCRs X 1832REclRC 26A11(IHS1) C Etto/ PUMP PCRs X iB32RECIRC 26A12(INSI) C PUMP /PlPE RCR$ 1 it32RECIRC 2&A13(INSI) C PIPE / /ALV RCRt ,,

X 183?tECIRC 28A16(IHSI) C PIPE / TEE RCR$ X 1832eECIRC 28A17(IHsi) C TEE / Cross RCRs X 1832REclRC 2&A18(INSI) C CROSS / RED RCR$ X

< iBl?RD282 64 FW833(INSI) C TEE / vat VE RCR$ X iB32REclRC 288?(IN$1) C PIPE /SE RCR$

4 in32RECIRC 2h83(INSI) C PIPE /ft80 RCRS iB32RECIRC 2885(INSI) C PIPE / PIPE RCRs X X 183?RECIRC 28p0(INSI) C VAtV/ PIPE RCR$

it32RECIRC 28810(INSI) C PIPE /ELB0 RCRS X it32RECIRC 28811(INSI) C EttO/ PUMP RCRS X 1832REclRC 28812(INSI) C PUMP / PIPE RCR$ X

^

1832REclRC 28813(INSI) C PIPE /VAtV RCRs X 1832REclRC 28814(INSI) C VAtV/Ett0 RCRS X

, 1832RECIRC 28815(IMSI) C EttO/ PIPE RCRS X 1832RECIRC 28816(INSI) C PIPE / TEE RCRS X 1832REClRC 28817(INSI) C TEE / CROSS RCR$ X iB32REclRC 28R18(lHST) C CRDSS/ RED RCRS X 1832RD2A2 87 FWA33(INSI) C TEE /VALV RCR$ X X 1B32REclRC 22AM1(INSI) C VALV/ PIPE RCR$ X 1832RECI R C-22AM2(INSI ) C PIPE /VAlv RCRS X 4

1812REclRC 22Ax4(INSI) C PIPE /CRSS R CRS 1832RECIRC 22AM5(IHSI) C CRSS/ PIPE RCRS X 1832REclRC 22AM6(IMSI) C PIPE / CAP RCRS X 1832REclRC 228M1(INSI) C CAP / PIPE RCRS 1832REclRC-228M2(IMSI) C PIPE /CRSS RCRS X 18?)RECIRC-228M3(IHSI) C CRSS/ PIPE RCRS X 1832RECIRC 229M5(INSI) C PIPE /VALV RCRS X 1932RS282 10 Fs930(INSI) C TEE / PIPE RCRS X 1E1110 1 10 Fk2HRC1(lHSI) C PIPE /VALV RHR X 1832REClRC 28A1(MSIP) C WC22tE/SE RCRS X X 93 12450.MSC

4 4

ENCtOSURE i Pope 7 of 8 SSEP Uwlf 1 - ICSCC InSPict t0W CL AS$1FICAT10NS ICSCC JolWT WELD WUMBER STS SCWEDULED INSPECTIONS CATEGORT CONFIC.

RF07 RF08 RF09 RFD10 RF011 183?tECIRC 2881(MSIP) C WOZZLE/SE RCR$ X 1811W8A RPV SWAR(MSIP) S WO22LE/SE JPl X iB11W88 RPV SWAB (MSIP) C WO22LE/SE JPI X X l

1B32RECIRC+2&A7(IMSI) D PIPE /Etto RCRS X X X 1832RECIRC 2886(INSI) D PIPE / TEE RCR$ X X X 1832RECIRC 2887(IMSI) D PIPE /ELSO RCRS X X X 183?RECIRC 28A9sC1 0 Wot/ PIPE RCRS X X X it32RECIRC 28A12BC D WOL/ PIPE ('CR S X X X 1832RECIRC 28A15BC1 0 WOL/ PIPE RCRS X X l l

_132RECIRC 2889st D WOL/ PIPE RCRS y X X i

_ l32RECIRC 28812SC D WOL/ PIPE RCRS X X X l it32RECIRC 288158C D WOL/ PIPE RCRS X X X 1E1110 1 10 SWA D PIPE /WOL RNR X X X 1C31PCl*1.FWRWCUC1A D WOL/ PIPE WWCU X X X ic3115 1 15 FWRWCUB2A D VALV/ PIPE RWCU X X 12B11N8A JPl*FWR122=1 D SE/PWSEAL JPI X X 12B11W88 JP! FWR122 2 D SE/PWSEAL JPl X X X 1821W4A 2 FWW4A45 3 0 EXT /SE FW X X X 1821W4A 2 SV1 2 0 SE/SE. EXT FW X X 1821W44 2 SV2 3 D TRAWS/ EXT FW X X 1821W48 3 FWW48135 3 D EXT /SE FW X X X 1821W48 3 SV1 2 0 SE/SE. EXT FW X X X 1R21W45-3 SV2 3 D TRAWS/ EXT FW X X X il21W4C 6 FWW4C225 3 F EXT /SE FW X X X 1821W4C 6-SW1 2 D SE/SE. EXT FW X X X 1821W4C 6 SV2-3 D TRAWS/ EXT FW X X X 1821W40 5 FWW40315 3 D EXT /SE FW X X X 1821N40 5-SW2 3 D TRANS/ EXT FW X X 1832tECIRC 2844(08 TAT) E ELB0/ PIPE RCRS X X X 1832RECIRC 28A14(O' LAY) l E VALV/ELB0 RCRS X X 93 12450.MSC m..

9 thetesuet i Pope 8 cf 8 BSEP UWlf i ICSCC IkSPEC1f 0N Ct AttlFICAtl0N$

IGSCC J0lWT WELD WUMBER SYS SCHEDutED INSPECTIDNS CAftGotf CONFIC.

RF07 RF08 RFD9 RF010 RF011 iB3?tECitC*?SA15(O'tAY) E Etto/ PIPE RCat X X X it32tttttt 2884(O'tAY) E Etto/ PIPE Acts X X X 1832tEcitt 2888(O'tAY) E Ett0/VALV RCes X X 1832tECISC 22AK3(O'tAY) E VALV/ PIPE RCPS X X 1832RECIRC 4A1(O'tAY) E WOL/ PIPE R CES X X X 1832tECInt 4A10(O'tAY) E PIPE /Wot DCRs X X 1832RECIRC 481(08tAY) E WOL/ PIPE ACa$ X X X 1832REttac 4810(O't AY) E PIPE /Wot RCes X X is32tECitC 2&A8(INSI) E Ett0/VAtV RCR$ X X 1821N40 5 SW12 F SE/St. EXT FW X X X X X l

93 12450.MSC

p A

BNP UNIT 1 STARTUP COMMITMENT VERIFICATION ASSESSMENT DEBRIEF NOTES Report No.: B-SP-95-10 -

- An assessment of the status of regulatory commitment completion related to Brunswick Nuclear Plant (BNP) Unit I startup was performed on August 30 through September 3,' 1993, and was debriefed on September 8,1993.

Purpose:

The Nuclear Assessment Department (NAD) performed an independent verification that regulatory. commitments applicable to BNP Unit I startup have been satisfactorily completed or are being tracked to completion.

Overall Atweement Summary:

Ibe conclusion of this team is that, to the best of our knowledge and belief, all doc ===ned explicit eamml*===ts made to the Nuclear Regulatory Cammtenina. (NRC) that pertain to the ristart of BNP Unit I have been adequately satisfied, or are currently being tracked to completion.

Results:

As a result of the team's assessment, overall commitment identification, tracking and documentation were considered satisfactory to support of BNP Unit I restart. Some minor deficiencies were noted which were similar to those noted in the BNP Unit 2 Startup Commitment Verification Assessment (B-SP-93-04). No STRENGTHS, ISSUES, or new '

WEAKNESSES were identified as a result of this assessment, self-Ae=ur.mt.

' As a result of previously identified missed commitments, site management had recognized weaknesses in the commitment tracking system. This had resulted in revision to BNP Three-Year Plan Initi:tive TY309, Improve Management of Regulatory Commitments, with a refocus to commitment tracking and accelerating implementation in 1993. Additional steps were taken to upgrade the quality of commitment information contained in the current FACTS system.

During the previous commitment verification assessment in April 1993, Regulatory Compliance was in the process of conducting a review of regulatory correspondence initiated over the past three years to ensure that all commitments were properly identified. At the time of this B-SP-93 1

1 k

assessment, this effort had been partially completed.

BNP.Three-Year Plan:

'Ihe status of Initiative TY 309, Improve Management of Regulatory Commitments, was _

reviewed. This Initiative, previously titled Site Work Tracking System (SWTS), had been revised on August 11,1993, to focus on commitment tracking and to accelerate this Initiative for completion by September 30,1993. W final task to implement a Sitewide Commitment Management procedure was on target.

Previous ISSUES and WEAKNESSES Ameettad

'Ihr m;n identified minor deficiencies related to the one WEAKNESS identified during the BNP Unit 2 Startup Commitment Verification Assessment (B-SP-93-04). 'Ihat WEAKNESS is restated herein with examples noted during this assessment.

l All site ea==h==nts should be identitled, evaluated, and tracked in a manner that ensuris i

that appropriate actions are completed in a timely manner.

'Ibe current process does not provide sufficient confidence that all site cammknwnee are identifled and adequately completed, as indicated by the following examples:

1. Commitments were made and not captured by an existing tracking system.

One example of a commitment not being capttdd was noted. This was selfidentified during a review of commitments in May 1993. No FACTS was generated to track an IER 92-42 commitment to replace all cracked 4KV switchgear current transformers (the item has since been completed).- Measures taken to improve capturing of commitments as a result of Three-Year Plan Initiative TY309 have resulted in improvement in the short period since corrective action was taken as a result of the last assessment.

2. Startup commitments identified and tracked across organizational lines by dittaent systems sometimes were not consistent.

- Startup tracking lists used by three organizations did not include all items identified on the Regulatory Compliance list for completion this outage. The Technical Support list

- contained (nly two of twelve items, and the Project Maintenance Section list contained 22 of 24 iten s. 'Ihe Nuclear Engineering Department list contained several discrepancies

.and was under review with a September 12, 1993, target to ensure that all required startup items are captured.

3. Adequacy of corrective actions sometimes could not be readily determined based on B-SP-93-10 2
f' .
7 closure documentation, i- FACTS 93B9106 Corrective action to IER 93-12 committed to stem replacement on a valve. The valve was repaired without a stem replacement; i however, the NRC has not been informed of the clange in
l. commitment.

i

FACTS 92B477A 'Ihe Root Cause Analysis only addressed why a damaged nuclear service water pipe went unreported and did not address how the

, pipe was damaged. As a result, improper work practices were not i

! addressed in the analysis or corrective action.

i l FACTS 92B477E This item had been closed out on March 23,1993 with the action

listed not taken (track actions resulting from FACTS 92B477D).

FACTS 92B477D was closed on Augtst 20,1993.

l l FACTS 93B9090 Several FACTS associated with a Notice of Violation had been j transferred to this FACTS item. The item had been later voided j - with no reason or documentation on file.

l FACTS 93B137B There was no documented justification for deletion of an action L (replacement of a shroud head bolt) when actions were transferred from FACTS 93B137A.

! FACTS 92B9A31, These items had either no or incomplete closue. documentation.

92B9B28, 92B9B32, two of the six had been closed since June 1993.

! 92B9B36, 92B9B58, l 92B9034 i

4. 'Ihe following FACTS files could not be located during the course of this assessment.

L l Some additional examples were noted.

l Although the same types of examples were noted on this assessment, some improvement had ,

l' - been noted by most team members who participated in the previous commitment verification i j assessment. This WEAKNESS was not ready for closure because insufficient time has elapsed

. to either correct all the items p::viously noted or to verify effectiveness of corrective action

! (e. g., issuance of PLP-26). Continued attention is required to upgrade documentation to i achieve world-class standards.

i i

! B.SP-93-10 3 A

- ., - . , - - - - - - . - - - ,. _- , .__ - - - , - . _.,r-, .- --- ---.-

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