ML20149G981

Refers to Mgt Meeting Conducted in Mishicot,Wi,On 970626 to Discuss Status of Facility Performance Improvement Initiatives.Agenda & Handout Encl

ML20149G981
Person / Time
Site:	Point Beach
Issue date:	07/17/1997
From:	Mccormickbarge NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Patulski S WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 9707240156
Download: ML20149G981 (14)

Text

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July 17, 1997 ,

Mr. S. A. Patuiski, Site Vice President Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241

SUBJECT:

POINT BEACH MANAGEMENT MEETING

Dear Mr. Patuiski:

This refers to the management meeting conducted at Fox Hills, Mishicot, Wisconsin, on June 26,1997. This meeting was to discuss the status of facility performance improvement initiatives, 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 handout 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,

/s/J. W. McCormick-Barger, Team Leader 1

J. W. McCormick-Barger, Team Leader  ;

Point Beach Oversight Team l Docket No. 50-266 Docket No. 50-301

Enclosures:

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1. Agenda

2. Startup Commitment List Document: G:\poin\ poi 07167.pdr.

To receive a copy of this document, indicate in the box "C" = Copy without attach /enci '

"E" = Copy with attach /enci "N" = No copy OFFICE Rill ('-

NAME McB:dp hgly a

DATE 07/ fg97 ,

OFFICIAL RECORD COPY (See attached distribution) 9707240156 970717 }{hkk!.!kkk!!kk!!!

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S. A. Patuiski 1 Distribution:

cc w/ encl: R. R. Grigg, President and Chief l Operating Officer, WEPCO I A. J. Cayia, Plant Manager Virgil Kanable, Chief, ]

i Boiler Section  !

Cheryl L. Parrino, Chairman i Wisconsin Public Service I Commission  ;

State Liaison Officer  !

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WE/NRC SENIOR AIANAGEAIENT AIEETING POINT BEACH NUCLEAR PLANT JUNE 26,1997 1:00 P.AI.

FOX IllLLS, MISIIICOT, WI AGENDA 1.- INTRODUCTION Dick Grigg

2. OPERATIONS IMPROVEMENTS Rick Mende

3. MAINTENANCE IMPROVEMENTS Brad Fromm

4. ENGINEERING IMPROVEMENTS Gary Boldt

5. SELF-ASSESSMENT IMPROVEMENTS Norm Hoefert

6. REGULATORY ISSUES

SUMMARY

Doug Johnson

7. PLANT EQt'n MENT STATUS Jim Schweitzer

8. STARTUP ISSUES SUMM ARY Fred Cayia

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SUMMARY

Scott Patuiski CONCLUSION Dick Grigg 10.

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POINT BEACH NUCLEAR PLANT UNIT 2 STARTUP COMMITMENT LIST June 26,1997 Status Update NOTE: The narrative reflects the commitment revisions per our June 13,1997 letter to the NRC.

IDENTIFICATION AND RESOLUTION OF ISSUES PERTINENT TO REACTOR SAFETY e

The following actions will be taken prior to Unit 2 criticality, except as specifically noted. The scope of reviews will be examining the identified 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 corrective and preventive actions will be taken commensurate with their safety significance.

Ccmmitment Description Status ID Number Complete a detailed Unit 2 Containment Materiel Condition Assessment, addressing housekeeping, system Done.

I walkdowns, materiel condition, and instrumentation. Extensive work inside Containment was conducted this outage due to the Steam Generator replacement project.

2 Walkdown all accessible Unit 2 and Common Maintenance Rule portions of systems for adequate visual Done.

material condition.

3 Walkdown all accessible Unit 2 and common systems for outstanding work order tags. Done.

Note: The scope was expanded to include all accessible Unit I systems.

4 Conduct as-built inspections of the electrical and I&C components on the Unit 2 CVCS and CCW systems Done.

(Work Orders 9607322,9611140,9606548, and 9611139).

5 Complete Work Orders 9513222 through 9513225 to conduct inspections of Appendix R alternate power Done.

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 Specifications Done.

7 to ensure Technical Specification requirements are appropriately reflected in the administrative controls.

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Review 20% of the Operations Technical Specification, Inservice Test, and Operations Refueling Test Done.

related surveillance procedures, with concentration on those involving major equipment. Upgrade as 8 necessary to include appropriate initial conditions, return to service lineups, properly speciHed independent verification, reviewing acceptance criteria, and Technical Specification implementation.

Review the In Service Testing (IST) acceptance criteria for the remaining IST pumps to ensure that the IS f Done.

9 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 lbr all IST valves to ensure that the IST acceptance Done.

10 criteria meets the design basis / accident analysis requirements. Complete necessary operability evaluations, e 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 the requirements of the plant design basis / accident analysis. Make changes as necessary as a result of this 12 review.

Note: This has been expanded to a 160% 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 In progress.

14 readiness reviews to ensure the required equipment is operable prior to changing modes: core reload, leaving cold shutdown, and the approach to criticality.

Review 20% of the work orders performed since January 1,1995 on Unit 2 or common PSA safety Done.

15 significant systems (AFW, SW, EDG, IA,4.16 kv, gas turbine, and CCW) to verify adequate PMT was performed to ensure system / component safety function.

Complete all Unit 2 Maintenance Rule related work order post-work, pre-PMT reviews prior to the Done.

16 approach to criticality.

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l Review 50.59 screenings conducted in 1996. Upgrade those detennined to require a 50.59 evaluation. 15 of 21

17 upgradings

completed.

3 18 Review outstanding JCOs using our operability determination process and/or our 10 CFR 50.59 evaluation in closeout

process. verification.

Conduct a review of 50.59 evaluations from this outage. Ensure all conditions of the evaluations have been In progress.

completed. This will 19 continue through the outage.

20 Review items from existing open item lists (e.g., NUTRK) to identify potentially degraded equipment. Done.

21 Review open items from the Design Basis Document development program. Done.

All open condition reports for Unit 2 and common equipment will be evaluated for their impact on unit In progress.

restart. Any equipment operability concerns will either be corrected or evaluated for operability for This will 22 continud operation in accordance with our operability determination procedure and Generic Letter 91-18. continue 4

Equipment which is operable but either degraded or nonconfonning will be identified and tracked within through the 1 our corrective action program to ensure timely correction of these issues. 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.

Complete an additional Outage Safety Review for the startup phase of the outage. Done.

24 Conduct an integrated review of all outage licensing commitments (50.59's, enforcement conference items, In progress.

Technical Specification Change Requests, and Reload Safety Analysis). Ensure all requirements are met. this will 25 continue through the outage.

Revise ORT-3 and DCS 3.1.11 to ensure Techinu ,dification 15.4.6.A.2 testing includes dynamic Done.

26 loading of the EDG with sequenced loads.

Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Return the electrical systems to normal In closcout 27 alignment prior to leaving cold shutdown. verification.

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Resolve the containment penetmtion commitments, including: Awaiting PMT.

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• CP-32'(Contamment penetration for Auxiliary Charging line).

i e 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 Containment in c!oseout

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Fan Coolers. verification.

31 Evaluate the adequacy of coordination on the 120 VAC instrument bus system through a 50.59 or Done.

operability review. e i Implement interim improvements for the Condition Reporting process, based on a review of assessments Done.

i 32 and identified recommendations for improving that process.

33 Implement interim improvements for the 50.59 process to require that all screenings be either authored or Done.

! reviewed by a member of the multi-disciplinary review team.

34 Upgrade Unit 2 operations checklists to include requirements for initials, time, and date. During the review, in progress.

l verify that the checklists are technically correct.

Revise applicable IST program documents to require the performance of an operability determination and Done.

l 35 NRC notification prior to returning equipment to service in the event that equipment in the Section XI

inservice testing program have vibration levels greater than 0.325 ips.

, 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.

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1 COMPLETE PHYSICAL WORK WHICH SUPPORTS SAFE STARTUP AND POWER OPERATIONS Modifications which Point Beach Nuclear Plant has identified as being significant to safety and scheduled for completion in U2R22 will be in an

accepted status (i.e., the applicable physical work completed, post-maintenance testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications. These modifications are

Commitment Description Status ID Number

• Modification 96-033 - complete replacement of 67 of the 90 control power transformers identified in the Awaiting PMT i 38 modification request MR 96-033. Complete remaining post-maintenance testing following reactor startup. (after reactor startup).

39 Modification 90-048 - replace Boric Acid and Reactor Makeup Water totalizers, replace the CVCS control In closcout switch, replace flow indicators, and refurbish flow controllers. This resolves an Operator workaround issue. verification.

40 Modification 94-097 - remove six RCS loop drain valves. Awaiting PMT.

41 Modification 92-141 - relocate the RIIR flow control valve controllers on 2CO3 for human factoring. Done.

42 Modification 96-073 - seismically upgrade CCW, SI, RIIR, and RilR/ letdown piping supports and remove Done.

an AFW snubber.

Modification 94-066 - install a soft seat in containment isolation valve 2SI-834D, and add a relief valve and Done.

43 pressure regulator in the nitrogen supply line to the SI accumulators. This resolves an Operator workaround issue.

44 Modification 96-065B - complete modifications to seismically upgrade the Refueling Water Storage Tank in closcout (RWST) recirculation line and administratively control the manual isolation valves normally closed. verification.

45 Modification 96-054 - install pressure gauges in the service water return header from the Emergency Diesel in closeout Generator GOl and GO2 glycol coolers, and reset the throttle valves in that line. verification.

46 Modification 96-022 - install a new 125 VDC feed to 480V safeguards bus 2B03. Done.

Modification 94-055 - add seismic supports to the raceway between risers 56 and 62. on C04 (Reactor and Done.

47 Primary Plant Control Board).

Modification 96-068B - eliminate containment heating steam and condensate return containment isolation in closeout 48 valves. verification.

49 Modification 96-053 - replace an elbow in the west service water header. In closeout verification.

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Modification 95-070 - scismically upgrade the containment cooling fans and filters. Awaiting PMT 50 (prior to leaving cold shutdown).

51 Modification 96-026 - install, delete, and modify supports for feedwater, main steam, and SI system piping Done.

for the 79-14 project.

52 Modification %-058 - move Power Plant Computer System alarms to the exterior of C-20 panels. Done.

Modification 94-095 - complete the physical work associated with modification request MR 94-095 that Awaiting PMT 53 replaces eight main steam condenser steam dump valves with an improved design. Complete remaining (after reactor post-maintenance testing following reactor startup and completion of fuel conditioning. startup).

54 Modification 95-029 - replace Sl accumulator level transmitters. Awaiting PMT.

55 Modification 95-035 - modify Containment Spray additive tank controller circuit. Done.

Modification %-%3 - complete the physical work associated with modification request MR 96-063 that Awaiting PMT 56 replaces 345 KV breakers 3-4,4-5, and 142. Complete remaining post-maintenance testing following (after reactor reactor startup. startup).

57 Modification 96-069 - replace four breakers (1Y-06-01,1 Y-06-03,1Y-06-05, and lY-06-11) associated Done.

1 with instrument bus 1Y-06.

58 Modification 95-058'O - repair Steam Generator intermediate leg suppons. This may be resolved through Awaiting analysis. PMT.

59 Modification %-070 - replace molded case circuit breakers associated with instrument buses 2Y-05 and 2Y- Done.

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j The work and testing associated with these Work Orders will be completed prior to the associated component / system being declared operable.

! Emergent Work Orders associated with Maintenance Rule Risk Significant Systems which Point Beach Nuclear Plant defines as priority level I to 4

! will be completed prior to Unit 2 criticality.

Ccamitment Description Status i ID Number

{ Work Orders 9601506,9602502, %03921,9611267,9611278, and 9611755 - replace proximity svatenes 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 %13568 and %13569 - provide bonnet pressure locking relief for the SI-857A and SI-857B Awaiting 4

valves (interface valves between RllR and High Head SI) on Unit 2. PMT.

Work Order %11757 - correct the leakage which leads to boric acid buildup in the cylinder blocks of"B" Awaiting PMT 62 Charging Pump. (when RCS >

140 degrees F).

Work Order %03532 - repair the handswitch for 2P-2A, the "A" Charging Pump. Awaiting PMT 63 (prior to fill and vent).  :

i Complete the physical work associated with Work Orders 9611979,9611981, and 9611982 that replace Awaiting PMT 64 existing pneumatic turbine generator circuitry time delay relays with plug-in, electronic time delay relays. (after reactor Complete remaining post-maintenance testing following reactor startup. startup).

Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow monitoring of Done.

65 door status.

i 66 Work Order %11052 - replace the 2P-10B switch, the "B" RHR Pump control switch.- Done.

67 Work Orders %11198 and 9611199 - repair the body-to-bonnet boric acid leak on CV-307 B (lowside tap Awaiting 4

for "B" RCP #1 seal d/p) and CV-308B (lap seal d/p for "B" RCP). PMT.

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i The following actions will be completed to correct Operator workarounds prior to Unit 2 criticality, except as specifically noted:

Ccmmitment Description Status ID Number Complete the physical work on the repair of valve AR-3511 per Work Order 95-13340. The Unit 2 priming Awaiting PMT 68 air ejector is blank flanged due to air in-leakage through the condenser air removal isolation valve, AR- (after reactor 3511. Complete remaining post-maintenance testing following reactor startup. startup).

I Complete the physical work to repair the drain valve for the heating steam moisture separator per Work In closeout 69 Order 9607489. The Unit 2 heating steam moisture separator level has been difficult to maintain during verification.

normal operations, and frequent alarms were received due to low level.

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.

Complete the physical work to repair MS-249, the Unit 2 steam line sample valve, per Work Order Awaiting PMT 71 9603128. The valve had a packing leak that required steam header sampling to be shifted to the "B" steam (after reactor header. Complete remaining post-maintenance testing following reactor startup. startup).

Complete the physical work to repair alarm switch 2LS-2511 per Work Order 9605711. The Unit 2 D MSR Awaiting PMT 72 level was being maintained low in the band due to level oscillations and a steam leak from the alarm switch. (after reactor Complete remaining post-maintenance testing following reactor startup. startup).

73 Replace the seals on 2P-116, the Unit 2 Boric Acid Recirculation Pump. In progress.

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PERSONNEL AND LICENSING READINESS I

l The following actions will be completed prior to Unit 2 criticality:

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i Commitment Description Status j ID Number j 74 Each operating crew will receive simulator training to gain proficiency in casualty response, the expected ' Done.

4 response of the newly installed steam generators and reactor core, and placing the turbine on-line.

Revise the initial and requalification operator training plans to include a review of the administrative Done.

j 75 procedures identified as significant to daily operation of the plant during each two year operations training

! plan.

! Conduct roundtable discussions with all MSS \SS\DTA personnel regarding conservative decisionmaking, Done.

76 Technical Specification interpretations, and lessons learned from recent regulatory communications and i 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. t regarding the new Containment Integrity Analysis. l 78 Communicate specific expectations regarding AFW and EDG status control to Operators. In progress.

3 79 Restore a proceduralized capability to operate the Containment Spray Pumps in the recirculation mode of In progress.

I the ECCS.

Obtain amendments requested by Change Requests 188 and 189 related to Steam Generator replacement; In progress.

l 192 related to Service Water operability; and 194 related to Low Temperature Overpressurization limits..

l 80 This will include resolution ofissues' related to Control Room and offsite dose evaluations for the analyzed j events.

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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).

e 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. i Revise DCS 3.1.20 to restrict operation of a unit with one line supporting that unit to 50% power.

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