ML20140C092
| ML20140C092 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/28/1997 |
| From: | Mccormickbarge NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 9706090109 | |
| Download: ML20140C092 (19) | |
Text
.o .
~'
May 28, 1997 Mr. S. A. Patulski, Site Vice President Point Beach Nuclear Plant 6610 Nuclear Road .
Two Rivers, Wisconsin 54241
SUBJECT:
POINT BEACH MANAGEMENT MEETING j Dear Mr. Patuiski- I l
This refers to the meeting conducted at the Holiday Inn in Manitowoc, Wisconsin, on May 22,1997. This meeting was to discuss the status of facility performance improvement initiatives and issues to be resolved prior to restarting Unit 2 following completion of the current refueling and steam generator replacement outage.
j in accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures (the agenda and handouts provided by your staff at the meeting) will be placed in the NRC's Public Document Room.
We appreciate your cooperation in this matter. If you have any questions regarding this meeting, please contact me at 630/829-9872.
Sincerely, l /s/ J.lW. McCormick-Barger l J. W. McCormick-Barger, Team Leader l Point Beach Oversight Team Docket No. 50-266 i Docket No. 50-301
! cc: R. R. Grigg, President and Chief
! Operating Officer, WEPCO j A. J. Cayia, Plant Manager Virgil Kanable, Chief, f[
1 l Boiler Section j Cheryl L. Parrino, Chairman
! Wisconsin Public Service Commission i State Liaison Officer /
PUk -01 w/enci
}R.h i Document: P:\2Poin.ltr
{ To receive a copy of this document, indicate in the box "C" = Copy without attach /enci j ' "E" = Copy with attach /enci "N" = No copy j
]
OFFICE Rlil 6. -l 4
NAME McB:dp OnwTy
- v j DATE 05/a197 j OFFICIAL RECORD COPY ;
9706090109 970528 4
PDR ADOCK 05000266 i i
V-
!,h!,h( l
j WEPCO/NRC SENIOR MANAGEMENT MEETING MAY 22,1997 !
HOLIDAY INN - MANITOWOC 12:30 P.M.
l AGENDA _
i
- 1. Outage Completion Plan / Outage Schedule
- Outage Review Committee & System Engineering Review I Board - Summary of Current Results & Future Activities i
. Status of 81 Startup Issues (Focus on Core Reload Action Items) ;
I t
- 2. Oversight / Enforcement of Control Room Standards (Duke, QA, Peer Self-Assessment Results)
- 3. Appendix R Issues (
(Summary ofInterim and Long-Term Actions)
- 4. Containment Post-Accident Sampling System l i
(Summary of Proposed Modification)
Corrective Action Program Improvements !
5.
- 6. NRC Assessment / Inspection Results Summary:
Operations Performance, Refueling Commitment Items Review l
i
- l / PBNP App. R RestartIssues e Reentryin the Cable Spreading Room i e Operation of G01/G02 for App. R e Assoc. Circuit on Yellow Instruments e Diesel Start Circuits for AFP Room
. Shutdown Procedure Revision to Strip DC e IN 92-18 Short on MOVs for CR fire e Supplement Ventilation for Cold Shutdown e Emergency Lighting for Outdoor Areas e CCW Lineup for App. R Safe Shutdown l
P May 22,1997 Restart Commitment Status Scheduled 4 i Awaiting PMT 15 l t Awaiting ther Plant Condition Changes 2 !
In Progress 19 In Closecut Verification Process 3 f
Done 38 ,
i t
P l
l
PBNP UNIT 2 CORE LOAD ISSUES As of May 22,1997 RESTART COMMITMENTS REQUIRING WORK BEFORE CORE LOAD Where discrepancies are identified during conduct of each of these commitments, appropriate corrective and preventive actions will be t core load commensurate with their safety significance.
ID # Description What Must Be Done Work Status Independent Prior to Core Load Verification Status Complete a detailed Unit 2 Containment Materiel Condition Complete the assessment In progress. Draft independent 1 Assessment, addressing housekecping, system walkdowns, materiel for systems and condition, and instrumentation. Extensive work inside Containment was verification supports components needed for core load.
conducted this outage due to the Steam Generator replacement project. core load.
Walkdown all accessible Unit 2 and common Maintenance Rule systems Complete the walkdown in progress. Independent 2 for adequate visual material condition. of those systems and verification drafted.
components needed for core load.
Review equipment return to service testing requirements prior to the Complete a Readiness Will be Independent following U2R22 mode change readiness reviews to ensure the required Review prior to core conducted 14 verification drafted.
equipment is operable prior to changing modes: core reload, leaving load. approximately cold shutdown, and the approach to criticality.
7-10 days prior to core load.
Conduct a review of 50.59 evaluations from this outage. Ensure all Complete the review. In progress. Dran independent conditions of the evaluations have been completed. Ensure conditions needed 19 verification supports to support core load are core load.
completed prior to core loading.
20 Review items from existing open item lists (e.g., NUTRK) to identify Complete the review ~
In progress. Independent potentially degraded equipment. prior to core load-verification drafted.
All open operability evaluations for Unit 2 and common equipment will Complete the review for in progress.
22 Independent be reviewed for acceptable closure of the degraded equipment issue. those Condition Reports Disposition outstanding issues in accordance with 10CFR50.59 and verification drafted.
needed to support core Generic Letter 91-18. load.
Page1
.- .., 4 4
RESTART COMMITMENTS READY FOR CORE LOAD . i i
ID # Description What Must Be Done Work Status Independent i
~ Prior to Core Load Verification Status Walkdown all accessible Unit 2 and common systems for Complete walkdowns COMPLETE. FINAL outstanding work order tags, for those systems and 3 Note: The scope was expanded to include all accessible Unit I INDEPENDENT components needed for systems. VERIFICATION core load.
SUPPORTS CORE Complete Work Order 9604151 to perform foreign material LOAD. i Complete prior to core COMPLETE.
exclusion inspections on the Unit 2 4160V safeguards hus 2A-06 and FINAL load- 1 6 breakers. INDEPENDENT VERIFICATION .
SUPPORTS CORE Complete a review of Unit 2 administrative controls impicmenting LOAD.
Complete the review of COMPLETE or referencing Technical Specifications to ensure Technical FINAL :
Refueling Procedures 7 Specification requirements are appropriately reflected in the INDEPENDENT RP-I A and RP-lH, and administrative controls. ~ VERIFICATION Technical Specification SUPPORTS CORE Section 15.3.8.
Review the In Service Testing (IST) acceptance criteria for the LOAD. !
Complete the review COMPLETE.
remaining IST pumps to ensure that the IST acceptance criteria FINAL i for those IST pumps 9 meets the design basis / accident analysis requirements. Make any INDEPENDENT >
needed to support core changes necessary as a result of this review. VERIFICATION !
load.
SUPPORTS CORE l
__] LOAD.
Review the in Service Testing acceptance criteria for all IST vafves ' Complete the review COMPLETE.
to ensure that the IST acceptance criteria meets the design FINAL i for those IST valves 10 basis / accident analysis requirements. Complete necessary INDEPENDENT i needed to support core operabilit3 evaluations, revise procedures, and resolve Unit 2 VERIFICATION -i load.
equipment discrepancies. SUPPORTS CORE <
LOAD. '
i Page 3 ,
i
______ . - _ _ _ _ , _ _ . . _ , . ~ . _ _ . ..,___.___._._ ._ __... -,_ _ _ .._ .
4 PBNP UNIT 2 CORE LOAD ISSUES As of May 22,1997 '
RESTART COMMITMENTS REQUIRING WORK BEFORE CORE LOAD Where discrepancies are identified during conduct of each of these commitments, appropriate corrective and prev core load commensurate with their safety significance.
19 # Description What Must Be Done Work Status Independent Prior to Core Load Complete a detailed Unit 2 Containment Materiel Condition Verification Status Complete the assessment In progress.
1 Assessment, addressing housekeeping, system walkdowns, materiel Draft independent for systems and condition, and instrumentation. Extensive work inside Containment was verification supports components needed for conducted this outage due to the Steam Generator replacement project. core load.
core load.
Walkdown all accessible Unit 2 and common Maintenance Rule systems Complete the walkdown 2 in progress. Independent for adequate visual material condition. of those systems and verification drafted.
components needed for core load.
Review equipment return to service testing requirements prior to the Complete a Readiness Will be Independent following U2R22 mode change readiness reviews to ensure the required Review prior to core 14 conducted verification drafted.
equipment is operable prior to changing modes: core reload, leaving load. approximately cold shutdown, and the approach to criticality.
7-10 days prior to core load.
Conduct a review of 50.59 evaluations from this outage. Ensure all Complete the review. In progress. Drall independent conditions of the evaluations have been completed. Ensure conditions needed 19 verification supports to support core load are core load.
completed prior to core loading.
20 Review items from existing open item lists (e.g., NUTRK) to identify Complete the review In progress. Independent potentially degraded equipment. prior to core load.
verification drafted.
All open operability evaluations for Unit 2 and common equipment will Complete the review for In progress.
22 Independent be reviewed for acceptable closure of the degraded equipment issue. those Condition Reports Disposition outstanding issues in accordance with 10CFR50.59 and verification dralted.
needed to support core Generic Letter 91-18. load.
PageI
i Complete the review - . Waiting forJ Independent.
Complete an additional Outage Safety Review for the startup phase of .
prior to core load.: closer to core- verification drafted.' >
24 the outage.
load date. ,
Complete the testing of -In closecut : Independent -
! 27 Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11.
Return the electrical systems to normal alignment prior to leaving cold EDGs iaw revised ORT- verification. verification being . j 3 and DCS-3.1.11 prior ' finalized.
shutdown.
to core load.
Complete the upgrade for CL-7B and Cl- Independent 1 Upgrade Unit 2 operations checklists to include requirements for initials, time, and date. During the review, verify that the checklists are checklists CL-7B and 1E have been verification drafted.
34
- CL-1 E. completed.
technically accurate. !
Modification 96-033 - replace control power transformers on Motor Complete the physical Awaiting independent
- work for 67 control P M T.- verification drafted. j Control Centers 2B12 and 2%2. !
power transformers .
38 !
identified in the SER to t be donc during U2R22.
Modification 96-053 - replace an elbow in the west service water Accept prior to core load. In closcout Independent 49 verification.. verification being header. .
finalized. .
Awaiting Work Orders 9613568 and 9613569 - provide bonnet pressure locking Complete prior to core Independent.
load. PMT. verification drafted.
61 relief for the SI-857A and SI-857B valves (interface valves between RilR and liigh llead SI) on Unit 2.
I t
- I Page 2 *
,- 'I i
- ~ - ~ . . . . , . _ . , . . . _ . , . . , . _ , _ . . - .
.._--,,.....__,._--m, .,,m.,,......_-.- --,_.._,..........---..__.--.-u.-.._.._,.~_.
'.__'-...I
RESTART COMMITMENTS READY: FOR CORE LOAD .
ID # Description What Must Be Done . Work Status Independent Prior to Core Load Walkdown all accessible Unit 2 and common systems for Verification Status Complete walkdowns COMPLETE.
outstanding work order tags. FINAL-for those systems and 3 Note: The scope was expanded to include all accessible Unit I INDEPENDENT components needed for systems. VERIFICATION core load.
SUPPORTS CORE Completc Work Order 9604151 to perform foreign material LOAD.
Complete prior to core COMPLETE.
exclusion inspections on the Unit 2 4160V safeguards hus 2A-06 and FINAL load.
6 breakers. INDEPENDENT VERIFICATION SUPPORTS CORE Complete a review of Unit 2 administrative controls implementing LOAD.
Complete the review of COMPLETE or referencing Technical Specifications to ensure Technical Refueling Procedures FINAL 7 Specification requirements are appropriately reficcted in the INDEPENDENT RP-I A and RP-IH, and administrative controls. Technical Specification VERIFICATION SUPPORTS CORE Section 15.3.8.
Review the in Service Testing (IST) acceptance criteria for the LOAD.
Complete the review COMPLETE.
remaining IST pumps to ensure that the IST acceptance criteria FINAL 9
for those IST pumps
' meets the desiRn basis / accident analysis requirements. Make any needed to support core INDEPENDENT changes necessary as a result of this review.
load.
VERIFICATION
- SUPPORTS ' CORE
- Review the in Service Testing acceptance criteria for all IST valves LOAD.
Complete the review to ensure that the IST acceptance criteria meets the design COMPLETE. FINAL for those IST valves l 10 basis / accident analysis requirements. Complete necessary needed to support core INDEPENDENT-l operability evaluations, revise procedures, and resolve Unit 2 load.
VERIFICATION equipment discrepancies. - - -
SUPPORTS CORE LOAD.
Page 3
Complete the following regarding installed instrumentation used in Complete for IST COMPLETE. FINAL the IST program: program INDEPENDENT instrumentation needed VERIFICATION
. identify the Unit 2 installed irntruments used in the IST to support core load.
program. SUPPORTS CORE 11 . Review the performance of he identified instruments over the LOAD.
last 3 years.
. Review the suitability of the instrumentation for use in the IST program.
Review all IST pump hydraulic data over the past year for adverse trends.
As necessary, make changes as a result of these actions.
Review 20% of the surveillance procedures associated with safety Complete the review COMPLETE.
significant non-pump and valve components (such as heat FINAL for those surveillance INDEPENDENT 12 exchangers and fans) to ensure that the surveillance acceptance procedures needed to criteria satisfy the requirements of the plant design basis / accident VERIFICATION support core load (TS-analysis. Make changes as necessary as a result of this review. SUPPORTS CORE 09 and IIPIP 11.54). LOAD.
Note: This has been expanded to a 100% review.
Review other operating procedures that contain maintenance Complete the review COMPLETE. FINAL activities and revise as necessary to ensure PMT and QC are for those operating 13 properly addressed by those procedures. INDEPENDENT procedures needed to VERIFICATION support core load.
SUPPORTS CORE LOAD.
Review 20% of the work orders performed since January 1,1995 on Complete the review COMPLETE. FINAL Unit 2 or common PSA safety significant systems (AFW, SW, EDG, for those 15 IA,4.16 kv, gas turbine, and CCW) to verify adequate PMT was INDEPENDENT spems/ components performed to ensure systemleomponent safety function. VERIFICATION needed to support core SUPPORTS CORE load.
Review 50.59 screenings conducted in 1996. Upgrade those LOAD.
Complete the review. The four determined to require a 50.59 cvaluation. FINAL Prior to core load, screenings 17 INDEPENDENT upgrade those have been VERIFICATION screenings needed to upgraded. SUPPORTS CORE support core load (4).
LOAD.
Page 4 5 .
Review 20% of the Condition Reports closed since.lanuary 1,1995 Complete the review COMPLETE. FINAL ,
which are associated with PSA safety significant systems for prior to core load. INDEPENDENT 23 - degraded equipment operability issues to ensure that we have VERIFICATION adequately identified and dispositioned operability issues. SUPPORTS CORE Note: This has been expanded to a 100% review of PSA safety LOAD.
significant systems.
Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification Complete the revisions COMPLETE. FINAL 15.4.6.A.2 testing includes dynamic loading of the EDG nith prior to core load. INDEPENDENT 26 sequenced loads. VERIFICATION SUPPORTS CORE LOAD.
Include return to senice testing in the plant schedule, both outage Complete prior to core COM PLETF. FINAL and nonoutage. load. INDEPENDENT 37 VERIFICATION SUPPORTS CORE LOAD.
Modification 90-048 - replace Horic Acid and Reactor Makeup Conditionally accept Conditionally FINAL Water totalizers, replace the CVCS control switch, replace flow prior to core load accepted INDEPENDENT 39 indicators, and refurbish flow controllers. This resolves an (needs PMT after core (needs PMT VERIFICATION Operator workaround issue. load). after core SUPPORTS CORE
_ load). LOAD.
Modification 94-097 - remove six RCS loop drain valves. Complete the Installation FINAL installation prior to complete INDEPENDENT 40 core load (awaiting (awaiting VERIFICATION RCS leak test as PMT). RCS Icak test SUPPORTS CORE as PMT). LOAD.
Modification 92-141 - relocate the RHR flow control valve Accept prior to core ACCEPTED. FINAL controllers on 2C03 for human factoring. Ioad. INDEPENDENT 41 VERIFICATION SUPPORTS CORE LOAD.
Page 5 !
i
._ ._ .._. __ . ___J
Modification 96-073 - scismiccIly upgrade CCW, SI, RllR, and Accept prior to core -ACCEPTED. FINAL RllR/ letdown piping supports and remove an AFW snubber. load. INDEPENDENT VERIFICATION 42 SUPPORTS CORE LOAD.
Accept prior to core ACCEPTED. FINAL Modification 96-022 -install a new 125 VDC feed to 480V load. INDEPENDENT safeguards bus 2B03.
VERIFICATION 46 SUPPORTS CORE LOAD.
Work Orders 9601506,9602502,9603921,9611267,9611278, and Complete prior to core COMPLETE. F1NAL load- INDEPENDENT 9611755 - replace proximity switches ind targets with an improved '
VERIFICATION 60 design and overhaul the Fuel Transfer Cart to enhance control SUPPORTS CORE system operation. This resolves an Operator workaround issue.
LOAD.
Complete prior to core COMPLETE. FINAL Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow monitoring of door status. load. INDEPENDENT VERIFICATION 65 SUPPORTS CORE LOAD.
Work order 9611052 - replace the 2P-10B switch, the "B" RilR Complete prior to core COMPLETE. FINAL Ioad. INDEPENDENT Pump control switch.
VERIFICATION 66 SUPPORTS CORE LOAD.
Conduct roundtable discussions with all MSS \SS\DTA personnel Complete prior to core COMPLETE. FINAL h,ad. INDEPENDENT regarding conservative decisionmaking, Technical Specification VERIFICATION 76 interpretations, and lessons Icarned from recent regulatory communications and perspectives. Review outlier Technical SUPPORTS CORE LOAD.
Specification interpretations for interim applications.
Page 6 8 1 -p
. _ . _ . _.______m .._________.m_m__ ..__ _ _ _ _ _ _ ____ m_____. _ _ __. .__ _ . _ _. _ . , . _ . _ _ _ . _ _ _ -_ _ _ _ _ _ - _ . - _-__...._,-.m. - - - - - . -
POINT BEACH NUCLEAR PLANT UNIT 2 STARTUP COMMITMENT LIST -
May 22,1997 Status Update
. IDENTIFICATION AND RESOLUTION OF ISSUES PERTINENT TO REACTOR SAFETY The following actions will be taken prior to Unit 2 criticality, except as specifically noted. The scope of reviews will be examining the identiGed documents or items for accuracy and compliance with requirements. Should any reviews identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of those reviews will be expanded. Where discrepancies are identified, appropriate corr and preventive actions will be taken commensurate with their safety significance. :
Description Status Commitment ID Number
~ in progress.
Complete a detailed Unit 2 Containment Materiel Condition Assessment, addressing housekeeping, I system walkdowns, materiel condition, and instrumentation. Extensive work inside Containment was conducted this outage due to the Steam Generator replacement project.
Walkdown all accessible Unit 2 and common Maintenance Rule systems for adequate visual material in progress.
2 condition.
Walkdown all accessible Unit 2 and common systems for outstanding work order tags- Done.
3 Note: The scope was expanded to include all accessible Unit I systems.
Conduct as-built inspections of the electrical and I&C components on the Unit 2 CVCS and CCW Done.
4 systems (Work Orders 9607322,9611140,9606548, and 9611139).
Done.
5 Complete Work Orders 9513222 through 9513225 to conduct inspections of Appendix R alternate power transfer switches.
Complete Work Order 9604151 to perform foreign material exclusion inspections on the Unit 2 4160V Done.
6 safeguards bus 2A-06 and breakers.
Complete a review of Unit 2 administrative controls implementing or referencing Technical Done.
7 Specifications to ensure Technical Specification requirements are appropriately reflected in the '
administrative controls.
Review 20% of the Operations Technical Specification, inservice Test, and Operations Refueling Test Done.
8 related surveillance procedures, with concentration on those involving major equipment. Upgrade as necessary to include appropriate initial conditions, return to service lineups, properly specified independent verification, reviewing acceptance criteria, and Technical Specification implementation.
PageI
f Review the In Service Testing (IST) acceptance criteria for the remaining IST pumps to ensure that the Done.
9 IST acceptance criteria meets the design basis / accident analysis requirements. Make any changes necessary as a result of this review.
Review the In Service Testing acceptance criteria for all IST valves to ensure that the IST acceptance Done.
10 criteria meets the design basis / accident analysis requirements. Complete necessary operability evaluations, revise procedures, and resolve Unit 2 equipment discrepancies.
Complete the following regarding installed instrumentation used in the IST program: Done.
. Identify the Unit 2 installed instruments used in the IST program.
I1 .
Review the performance of the identified instruments over the last 3 years.
- Review the suitability of the instrumentation for use in the IST program. <
. Review all IST pump hydraulic data over the past year for adverse trends.
As necessary, make changes as a result of these actions.
Review 20% of the surveillance procedures associated with safety significant non-pump and valve Done.
components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria satisfy 12 the requirements of the plant design basis / accident analysis. Make changes as necessary as a result of this review.
Note: This has been expanded to a 100% review.
13 Review other operating procedures that contain maintenance activities and revise as necessary to ensure Done.
PMT and QC are properly addressed by those procedures.
Review equipment return to service testing requirements prior to the following U2R22 mode change Will occur 14 readiness reviews to ensure the required equipment is operable prior to changing modes: core reload, approximately one leaving cold shutdown, and the approach to criticality.
week prior to each of the mode changes.
Review 20% of the work orders performed since January 1,1995 on Unit 2 or common PSA safety Done.
15 significant systems (AFW, SW, FDG, I A,4.16 kv, gas turbine. and CCW) to verify adequate PMT was performed to ensure system / component safety function.
16 Complete all Unit 2 Maintenance Rule related work order post-work, pre-PMT reviews prior to the Done.
approach to criticality.
17 Review 50.59 screenings conducted in 1996. Upgrade those determined to require a 50.59 evaluation.
14 of 21 upgradings completed.
Review outstanding JCO's. Perform operability determinations and 50.59 cvaluations needed to address in progress. One JCO 18 the issues.
remains to resolve.
Page 2 D I
19 Conduct a review of 50.59 evaluations from this outage. Ensure all conditions of the evaluations have in progress.
l been completed.
l 20 Review items from existing open item lists (e.g., NUTRK) to identify potentially degraded equipment.
. In progress.
'l Review open items from the Design Basis Document development program. Done.
All open operability evaluations for Unit 2 and common equipment will be reviewed for acceptable In progress. This will j 22 closure of the degraded equipment issue. Disposition outstanding issues in accordance with 10CFR50.59 continue through tite l and Generie Letter 91-18.
outage.
l Review 20% of the Condition Reports closed since January 1,1995 which are associated with PSA safety Done.
23 significant systems for degraded equipment operability issues to ensure that we have adequately identified
! and dispositioned operability issues.
l Complete an additional Outage Safety Review for the startup phase of the outage. Will occur 24 approximately 7-10 days prior to core l loading date.
I Conduct an integrated review of all outage licensing commitments (50.59's, enforcement conference in progress.
25 items, Technical Specification Change Requests, and Reload Safety Analysis). Ensure all requirements are met.
26 Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.4.6.A.2 testing includes dynamic Done.
loading of the EDG with sequenced loads.
27 Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Return the electrical systems to In closecut verification normal alignment prior to leaving cold shutdown. process.
Resolve the containment penetration commitments, including:
In progress.
28
. CP-32 (Containment penetration for Auxiliary Charging line).
. Penetration thermal reliefissue.
29 Complete a 50.59 evaluation for the existing CCW supply to the RCP seals as a safety function. In progress.
30 Update the diesel generator loading calculation N-91-016 to properly reflect the loading of the in progress.
Containment Fan Coolers.
31 Evaluate the adequacy of coordination on the 120 VAC instrument bus system through a 50.59 or Done.
operability review.
32 Implement interim improvements for the Condition Reporting process, based on a review of assessments Done.
and identified recommendations for improving that process.
Implement interim improvements for the 50.59 process to require that all screenings be either authored or Done.
33 reviewed by a member of the multi-disciplinary review team.
Page 3
y 34 Upgrade Unit 2 operations checklists to include requirements for initials, time, and date. During the In progress.
review, verify that the checklists are technically correct.
Revise applicable IST program documents to prevent equipment from being returned to service (declared Done.
'35 operable) with vibrations in the alert range.
Revise NP 8.1.1, Work Order Processing, and NP 8.1.3, Post-Maintenance Testing to ensure post- In progress.
36 maintenance testing , operability testing, and surveillance test requirements are properly addressed.
37 Include return to service testing in the plant schedule, both outage and nonoutage. Done.
Page 4 5 e
L COMPLETE PHYSICAL WORK WHICil SUPPORTS SAFE STARTUP AND .
Modifications which Point Beach Nuclear Plant has identified as being significant to safety will and scheduled f be in an accepted status.(i.e., the applicable physical work completed, post-maintenance testing complete onent/ system being declared operable) prior to being required to be operable per Technical Specifications. These modifications are Commitment Description ID Number Status 38 Modification 96-033 - replace control power transformers on Motor Control Centers 2B32 and 2B42.
Awaiting PMT.
39 Modification 90-048 - replace Boric Acid and Reactor Makeup Water totalizers, replace the CVCS control switch, replace flow indicators, and refurbish flow controllers. This resolves an Operator workaround Awaiting PMT.
issue.
40 Modification 94-097 - remove six RCS loop drain valves.
41 Awaiting PMT.
42 Modification 92-141 - relocate the RiiR flow control valve controllers on 2CO3 for human factoring.
Done.
Modification 96-073 - seismically upgrade CCW, SI, RilR, and RilR/ letdown piping supports and remove an AFW snubber. Done.
43 Modification 94-066 - install a soll seat in containment isolation valve 2SI-834D, and add a relief valve Done.
and pressure regulator in the nitrogen supply line to the Si accumulators. This resolves an Operator workaround issue.
44 45 Modification 96-065B - seismically upgrade the Refueling Water Storage Tank recirculation line.
in progress.
Modification 96-054 - install pressure gauges in the service water return header from the Emergency Diesel Generator GOl and GO2 glycol coolers, and reset the throttle valves in that line. Scheduled.
46 Modification 96-022 - install a new 125 VDC feed to 480V safeguards bus 2B03.
47 Done.
Modification 94-055 Primary Plant Control Board).
- add seismic supports to the raceway between risers 56 and 62 on C04 (Reactor and Done.
48 Modification valves. 96-068B - eliminate containment heating steam and condensate return containment isolation In progress.
49 Modification 96-053 - replace an elbow in the west service water header.
In closeout verification 50 process.
Modification 95-070 - seismically upgrade the containment cooling fans and tilters.
51 Awaiting PMT.
Modification 96-026 - install, delete, and modify supports for feedwater, main steam, and Si system piping for the 79-14 project. Done.
52 53 Modification 96-058 - move Power Plant Computer System alarms to the exterior of C-20 panels.
Done.
Modification 94-095 - replace 8 Main Steam Condenser steam dump valves with improved design-Awaiting PMT.
Page 5
54 Modification 95-029 - replace SI accumulator level transmitters.
55 Awaiting PMT.
Modification 95-035 - modifv Containment Spray additive tank controller circuit.
56 Done.
Modification 96-063'- replace 345 KV breakers (3-4,4-5, and 142).
57 Awaiting PMT.
Modification 96-069 - rep!a e four breakers (l Y-06-01, I Y-06-03,1 Y-06-05, and I Y-06-11) associated with instrument bus 1 Y-06. Done.
58 Modification 95-058*O - repair Steam Generator intermediate leg supports. This may be resolved through analysis. Awaiting PMT.
59 Modification 96-070 - replace molded case circuit breakers associated with instrument buses 2Y-05 and 2Y-06. Done.
i L
i Page 6
- r ;
- l e e
- _ _ - _ _ _ _ _ _ - . _ _ _ _ _ _ .._ _._.- -_....-.-... ___- _ ___ -,._ .._- -...~. ..- _..-.- .
. _ _ _ - . ~ , - . . _ _ _ - - . . _ . . - - . . . = . _ - _ - - - . -
_ m-- .. - - - _-~_-.~,.--m__ _ _ . _ _ .
= ,
The work and testing associated with these Work Orders will be completed prior to the associated component / system being declared operable. I Emergent Work Orders associated with Maintenance Rule Risk Signilicant Systems which Point Beach Nuclear Plant defines as priority level I to 4 will be completed prior to Unit 2 criticality.
Commitment Description Status ID Number Work Orders 9601506,9602502,9603921,9611267,9611278, and 9611755 - replace proximity switches Done.
60 and targets with an improved design and overhaul the Fuel Transfer Cart to enhance control system operation. This resolves an Operator workaround issue.
61 Work Orders 9613568 and 9613569 - provide bonnet pressure locking relief for the SI-857A and SI-857B Awaiting PMT.
valves (interface valves between RIIR and fligh Ilead SI) on Unit 2.
62 Work Order 9611757 - correct the leakage which leads to boric acid buildup in the cylinder blocks of"B" Awaiting PMT.
Charging Pump.
63 Work Order 9603532 - repair the handswitch for 2P-2A, the "A" Charging Pump. Awaiting PMT.
64 Work Orders 9611624 through 9611626 - replace existing pneumatic turbine generator circuitry time Scheduled.
delay relays with plug-in, electronic time delay relays.
65 Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow monitoring Done.
of door status.
66 Work Order 9611052 - replace the 2P-10B switch, the "B" RIIR Pump control switch. Done.
67 Work Orders 9611198 and 9611199 - repair the body-to-bonnet boric acid leak on CV-307 B (lowside tap Awaiting PMT.
, for "B" RCP #1 seal d/p) and CV-308B (lap seal d/p fbr "B" RCP).
i Page 7
The following actions will be completed to correct Operator workarounds prior to Unit 2 criticality except as specifically noted:
1 Commitment Description Status ID Number 68 Repair valve AR-3511 per Work Order 9513340. The Unit 2 priming air ejector is blank flanged due to Awaiting PMT.
air in-leakage through the condenser air removal isolation valve, AR-3511.
Repair the drain valve for the heating steam moisture separator per Work Order 9613451. The Unit 2 Work is scheduled.
69 heating steam moisture separator level has been difficult to maintain during normal operations, and frequent alarms were received due to low level. This will be tested following Unit 2 startup.
~
Install a new level control system for the brine tank (T-118) per Modification 92-008*Q. The tank Done.
70 overflows because the installed automatic level control system is not effective, and there is no high level alarm for the tank.
71 Repair MS-249, the Unit 2 steam line sample valve, per Work Order 9603128. The valve had a packing Awaiting PMT.
leak which required steam headcr sampling to be shifted to the B steam header.
72 Repair alarm switch 2LS-2511 per Work Order 9605711. The Unit 2 D MSR level was being maintained Awaiting PMT.
low in the band due to level oscillations and a steam leak from the alarm switch.
73 Repair 2P116, the Unit 2 Boric Acid Recirculation Pump, per Work Order 9603130. It has a significant Work is schedule 1.
seal leak.
Page 8 W
- I PERSONNEL AND LICENSING READINESS The following actions will be completed prior to Unit 2 criticality:
Commitment Description Status ID Number 74 Each operating crew will receive simulator training to gain proficiency in casualty response, the expected Done.
response of the newly installed steam generators and reactor core, and placing the turbine on-line.
Revise the initial and requalitication operator training plans to include a review of the administrative Done.
75 procedures identified as significant to daily operation of the plant during each two year operations training plan.
Conduct roundtable discussions with all MSSiSS\DTA personnel regarding conservative decisionmaking, Done.
76 Technical Specification interpretations, and lessons !cerned from recent regulatory communications and perspectives. Review outlier Technical Specification interpretations for interim applications.
77 Complete the procedure changes and training associated with the new Technical Specification on ECCS In progress.
regarding the new Containment Integrity Analysis.
78 Communicate specific expectations regarding Al W and liDG status control to Operators. In closcout verification process.
79 Restore a proceduralized capability to operate the Containment Spray Pumps in the recirculation mode of in progress.
the ECCS.
Obtain amendments requested by Change Requests 188 and 189 related to Steam Generator replacement; in progress.
80 192 related to Service Water operability; and 194 related to 1 ow Temperature Overpressurization limits.
This will include resolution ofissues related to Control Room and offsite dose evaluations for the analyzed events.
Submit the following requests for license amendments resulting from the review of existing Technical in progress.
Specification interpretations:
81 . Revise the maximum acceptable power level when crossover steam dumps are inoperable (TS 15.3.4.E).
. Revise requirements for offsite power lines availability to address adequacy (TS 15.3.7.A.I.a).
. Remove allowances in TS 15.3.1.A.I.a for single reactor coolant pump operation.
. Appropriately modify the minimum required boron concentration in the Refueling Water Storage Tanks.
Page 9
_____m __-__m___._-_m ._ _ - __ , ~-