B16257, Forwards Unit 2 readiness-for-restart Worklist,Identifying Currently Known Items to Achieve Readiness for Restart.Plan Encl
| ML20135B876 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/26/1997 |
| From: | Bowling M NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135B877 | List: |
| References | |
| B16257, NUDOCS 9703030252 | |
| Download: ML20135B876 (39) | |
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i Nuclear Energy waisu,ne Noaear rower station :
1 Northeast Nudear Enern Cornpany }
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,- Waterford, Cr 06385-0128 1 (860) 447-1791 !
e Fax (860) 444-4277
'Ihe Nortlwant Utilities Systern l- February 26,1997 l Docket No. 50-336
. B16257 i
! U.S. Nuclear Regulatory Commission
- Attention
- Document Control Desk Washington, DC 20555 Millstone I'luclear Power Station, Unit No. 2 l Readiness-for-Restart Worklist j In response to your January 13,1997, letter,M Northeast Nuclear Energy Company
- (NNECO) hereby transmits for Millstone Unit No. 2 the Readiness-for-Restart Worklist
- (worklist) which identifies the currently known items to achieve readiness for restart.
- These are provided in Attachment.51 through 5 and consist of Success Objectives, .
! Activities Necessary to Raise Standards, Design and Configuration Discrepar,cies, i Regulatory Readiness items, and Common Millstone Site issues Applicable to Milstone Unit No. 2.
i l The worklist was developed and reviewed by the individuals accountable for the
! completion of the contained activities and their line management. The worklist will be
- updated and resubmitted periodically. The next update is planned for April 1997. The
!- additions to the worklist will be reviewed and approved by the respective department managers. The removal or deletion of an activity from the worklist will be reviewed by the impacted department managers and approved by the Plant Operations Review Committse and the Unit Director.
The successful accomplishment of the seven success objectives delineated in Attachment 1 are funda ental to raising the standard for the conduct of safe operations at Millstone Unit No.2. The activities necessary to raise standards are provided in Attachment 2 and consist of organizational and management requirements and key performance indicators from the Millstone Unit No. 2 Operational Readiness Plan (6RP). The Millstone Unit No. 2 ORP is currently being revised and will be provided 030005
- W. D. Lanning (NRC) letter to B. D. Kenyon, " Recovery and Restart Plans Meeting of December 17,1996,* dated January 13,1997.
97o3030252 970226 .. i
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' U. S. Nuclear Roguirtory Commission' B16257\ \Page 2 l under separate correspondence when the revision is complete. The Millstone Unit No.
2 ORP Nuclear Oversight Plan provided in Attachment 6 is for information only. t j
We plan on additional communications with your Staff in the near future to review this approach and identify additional details necessary to support the Special Projects Office's informational needs. t The following are NNECO's commitments made within this letter. All other statement's made within this letter are for information only.
B16257-01 The worklist items will be dispositioned prior to the start of '
Millstone Unit No. 2. t B16257-02 The Millstone Unit No. 2 Operational Readiness Plan, i Revision 1 will be submitted by March 31,1997.
if you have any questions, please contact Mr. R. G. Joshi at (860) 440-2080.
Very Truly yours, NORTHEAST NUCLEAR ENERGY COMPANY i
i l Martin L. Bowling, Jr. d j Millstone Unit No. 2 - Recovery Officer )
i Attachments (6) cc: H. J. Miller, Region i Administrator
- D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 l D. P. Beaulieu, Senior Resident Inspector, Millstone Unit No. 2 W. D. Travers, Dr., Director, Special Projects Office i
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Docket No 50-336 B16257 I
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Attachment 1 9 Millstone Nuclear Power Station, Unit No. 2 l Success Objectives i
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- l. . U.S. Nuclear Regulctory Commission B16257\ Attachment 1\Page 1
- Attachment 1
! Millstone Nuclear Power Station, Unit No. 2 Success Objectives 4
Success Objectives
.i The Millstone Unit No. 2 Recovery Organization has identified seven key success objectives to raise operating standards. High operating standards are essential for the safety and reliability of Millstone Unit No. 2 operations. The seven key success objectives also reflect fundamental changes in how the Millstone Unit No. 2 organization will function. The objectives are as follows:
- 1. High Standards and Clear Accountabilities e incorporate best practices from other utilities e Benchmark with other nuclear utilities e Performance indicators show improvement toward excellence e Commitments are met i
- 2. Strong Nuclear Safety Policy
. Careful adherence to high nuclear safety standards l
. Conservative decision making i
- 3. Licensing and Design Bases Restored with Process in Place to Ensure Bases are Maintained.
. ICAVP contractor confirmation that the design and licensing bases have been restored e implement configuration control processes to ensure design and licensing bases are maintained
- 4. An Environment That Supports the identification and Effective Resolution of Employee Concerns e improved Employee Concerns Program actively supported by management e Employee concerns addressed promptly, effectively, and respectfully e independent review of employee safety concerns resolution effectiveness
- 5. Effective Self-assessment Program
. Line management ownership and support
. Significant issues identified by NU rather than the regulator l
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, U. S. Nuclear Regulatory Commission B16257%ttachment 1\Page 2
- 6. Effective Corrective Action Process.
- Corrective actions and commitments are prioritized and resolved in a timely manner e improved regulatory performance demonstrated by a decrease in NRC violations and LERs I
- 7. Commitment to Resolve Long-standing issues and Maintain Safe and Reliable Operations e Resource commitments meet or exceed those of similar well run units e Problems are prioritized and resolved in a timely manner e Commitment to resolve longer term issues is captured by continuous improvement.
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Docket No. 50-336 B16257 Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Activities Necessary to Raise Standards February 1997 1
ACTIVITIES NECESSARY FOR RAISING STANDARDS Affirm that Maintenance Rule risk significant systems are ready for restart.
Communicate standards and expectations to employees in accordance with the MP2 Communications Plan.
Complete actions to ensure compliance with 10CFR50, Appendix R for Thermo-Lag.
Complete development of Unit Performance Indicator for ORP.
Complete employee familiarization with Employee Concerns Program.
Complete independent (external) assessment of conduct of Operations.
Complete independent review of ORP.
Complete management training on expectations and standards for resolving employee concerns, as well as, the Employee Concerns Program.
Complete required design change modifications.
Complete response for SOER 96-01.
Complete self-assessment of work flow process.
Complete work flow process changes.
Conduct independent Organizational Readiness Assessment (use INPO and NRC 0350 criteria).
Conduct operational readiness self-assessment prior to each mode change and significant plant configuration change.
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Conduct periodic self-assessments for adherence to Surveillance Testing schedule and requirements.
Conduct periodic self-assessments for conduct of operations.
Conduct periodic self-assessments for Configuration Management.
Conduct periodic self-assessments for Corrective Actions.
Conduct periodic self-assessments for PORC etTectiveness.
Conduct periodic self-assessments for technical procedures adequacy.
Conduct periodic self-assessments of Safety Evaluations (10CFR50.59) Program and Process.
Conduct self-assessment to ensure MP2 Nuclear Safety Policy expectations are embraced by MP2 organization.
Coordinate 10CFR50.59 training schedule for all applicable MP2 staff.
Develop and implement an operational readiness self-assessment process (pre-INPO/ pre-IPAP methodology).
Develop and implement lluman Performance Enhancement Program.
Develop and implement MP2 Nuclear Safety Policy.
Develop and plan for efTective use of Nuclear Oversight for periodic assessment of daily activities, processes and programs.
Develop and rollout Operations Department standard for reactivity management.
Develop CMP Plan and Schedule.
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Develop plan for effective self-assessment of relevant industry operating experience.
Develop schedule and agenda for lluman Performance Standdowns.
Develop schedule and methodology for benchmarking trips.
Develop schedule for Improved Standard Technical Specifications.
Develop set of Operations Standards.
Establish a Level 1 Management Accountability System.
Establish appropriate linkage between operability determinations and bypassjumpers with the 50.59 process.
Establish Engineering Assurance Program.
Establish goals and trends for corrective actions.
Establish housekeeping standards and program.
Establish indicators and goals for deterniining effectiveness or the Corrective Action Program.
Establish ownership for systcm design and t chnical prog ams.
Establish ownership of corrective action program within line organization through revision of Corrective Action Program procedure.
Establish plan to review technical procedures.
Establish schedule for facilitated working sessions to introduce and reinforce behavioral characteristics for first line and above supervisors.
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i Establish Single Technical Procedures Group.
Establish WIN team. 4 I
Identify actions necessary to ensure full compliance with 10CFR50 Appendix B for Oversight Audits.
implement Observation Training.
Implement required actions to ensure timely response to NRC violations. Develop schedule to achieve timely ;
comphance. j Implement Station Qualified Review (SQR) Program, applicable for Millstone Unit 2.
Open Bypass Jumpers, Operability Determinations, and NCRs not resolved prior to startup are screened against 10CFR50.59. ;
Open safety related AWOs not addressed prior to restart have been assessed by an Operations SRO and PORC.
Open unresolved items (URIs) and LER commitments have been addressed prior to restart. f Perform benchmarking assessment at well-perfomiing plants Perform independent assessment of restart readiness.
Perform periodic independent technical review of CMP.
Perform self-assessment of AITTS effectiveness.
Prepare Startup and Power Ascension Plan.
Provide plans for Engineering Drawing Backlog.
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Provide self-assessment training to applicable personnel. ,
Provide / set standards and expectations for self-assessment.
Publish and review on a monthly frequency UPIs for ORP. l Request independent (external) restart readmess assessment. t Review a sample of previously closed ACRs for adequacy.
Review and revise Operating procedures to ensure water hammer events are precluded.
Review Tech Spec Surveillance Procedures to ensure compliance with Tech Specs. ;
Set and communicate expectations and standards for resolution ofemployee concerns.
I Specific departmental operational readiness assessments will be performed prior to mode changes.
Train department coaches.
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Millatona Unit No. 2 Restart Readiness Indicators Corrective Actions Restart List NCR Backlog ARTS Assignments Required for Startup Restart Related NRC Commitments Open/ Overdue Licensee Event Reports Open/ Overdue Notices of Violations License Amendments Required for Restart ARTS Assignments in NOTIFY Status grdue Assignments by Department At.signments Against ACRs Open >l20 Days by Dept.
ACR Aging / Overdue Report Open/ Overdue Assignments - Audits /Surveillances Configuration Management Program Unresolved items Report Drawing Update Backlog Restart Modification implementation Status Configuration Management Plan - System Assessments Configuration Management Plan - Program Assessments Physical Plant Maintenance Rule AWO Backlog Maintenance Rule (ah l) Systems Status MEPL Systems Validated Open Operability Determinations Operator Burden Reduction Control Room Panel Deficiencies Temporary Modifications Liquid Radwaste Release Data Gaseous Radwaste Release Data Organizational Performance and Safety Restart Required Technical Pmeedure Revisions Reportable Events Ratio of Cited /Non-Cited Notices of Violations Work Planning / Scheduling Effectiveness Industrial Safety Accident Rate Personnel Contamination Events Collective Radiation Exposure MEPL Systems Validated
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! Docket No. 50-336 B16257 1
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l Attachment 3 i Millstone Nuclear Power Station, Unit No. 2 l
Design and Configuration Discrepancies l
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4 U.S. Nucle:r Regulitory Commission
, B16257%ttachment 3\Page 1 i
Desion and Confiouration Discrepancies As required by NRC letter dated May 21,1996,
- attached is an initial list of Millstone
- Unit No. 2 design and configuration discrepancies based on a review of the Adverse Condition Reports (ACRs). In addition, this list includes other discrepancies identified i during routine operation, maintenance, and design activities. As stated in the cover 1
letter, this worklist will be updated in April 1997. ;
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- W.T. Russell letter to R.E. Busch, "MP1, 2, and 3 - 10CFR50.54 (f) Letter in Regards to the Operation of All Three (3) Millstone Units", dated May 21,1996.
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Mill;t :na Nucl=r P;wer Stati::n, Unit 2 Design and Configuration Deficiencies ,
Number Description 00503 RCS LOW FLOW TRIP MAY NOT SATISFY BOUNDS ASSUMED IN MP2 SAFETY ANALYSIS 01991 VITAL DC POWER FAILURE (201 A/B) PREVENTS POST-LOCA FLOWPATH ALIGNMENT FOR HYDROGEN MONITOR SYSTEM 02797 AUX FEED REG VALVE WILL NOT FULLY SHUT WITH FLOW THROUGH THE VALVE (2-FW-438) 03531 SERVICE WATER STRAINER MOTOR OPERATION NOT DESCRIBED IN APPENDIX R OF FLOOD DOCUMENTS 04071 REED SWITCHES PROVIDED ERRONEOUS POSITION INDICATION FOR CEA 1-28 DURING SURV TESTING 05595 REACTOR CORE POWER EXCEEDED 2700 MW-THERMAL FOR 11 HOURS (BLOWDOWN CURVE ERRORS) 05857 EBFS IS DRAWING LESS VACUUM THAN EXPECTED WHEN RUNNING ON ENCLOSURE BUILDING WITH AC 1 & 3 SHUT 06351 MP1 DESIGN CHANGE (ROLL-UP DOOR) MAY AFFECT MP2 TURBINE BUILDING OVER PRESSURIZATION 06372 RCS HEATUP RATE EXCEEDED TECH SPEC LIMIT OF 50 DEGREES PER HOUR 06668 TRIAL INSTALLATION OF SERVICE WATER PUMP FLOOD CAN ON "A" MOTOR WAS UNSUCCESSFUL; LER INITIATED 07506 PASS IS OUTSIDE DESIGN BASIS - SLOW POST-LOCA CTMT PRESSURE REDUCTION PREVENTS TIMELY PASS AIR SAMPLE 07896 50542. DISCREPANCIES FOUND IN TECH SPECS 34.1.3,3.4.3,3.4.7,3.4.9.1,3.4.9.2&3.4.9.3 1 of 7
Number Description -
07910 2-RB-13.1 A/B ACCUMULATOR MAY BE SIZED INCORRECTLY BASED ON WRONG TIME FROM EVENT TO SRAS .
07916 50542.EBFS HUMIDITY MAY NOT MEET DESIGN BASIS DUE TO DESIGNED FLOW INCREASE WITHOUT RESIZING HEATER 07924 HYDROGEN ONITOR!NG SYSTEM MAY NOT MEET SINGLE FAILURE CRITERIA 07958 50542: Di N BASIS FOR MCC ENCLOSURES IS NOT EASILY RETRIEVABLE OR UNDERSTOOD 08038 SERVICE WATER STRAINER BACKWASH LINES MAY FREEZE IF VENTILATION HEATERS LOST FOR PROLONGED PERIODS 08331 HYDROGEN ANALYZER SAMPLE PUMP DEADHEADS AT 25#, IT WILL NOT DISCHARGE INTO CTMT IN ALL CONDITIONS 08391 H2 ANALYZER PRESSURE REGULATOR DESIGN MAY PREVENT H2 SAMPLING WHEN CTMT IS AT ATMOSPHERIC PRESSURE 08395 SIEMENS REPORTED A SIGNIFICANT LARGE BREAK LOCA ANALYSIS ERROR; PCT REMAINS BELOW 2200 DEGREES 08490 CONTAINMENT SUMP SCREEN ENCLOSURE HAS OPENINGS LARGER THAN DESIGN (MESH SIZE ALONG END & 3 HOLES) 09563 AUX FEED REG VALVE BACKUP AIR BOTTLE PRESSURE MAY BE TOO LOW TO ISOLATE S/G IN STEAM LINE BREAK 09590 50542:NUREG 0612 EVALUATION OMITS TURBINE BLDG CRANE'S IMPACT ON SAFETY-RELATED SWITCHGEAR ROOM 09600 50542: CIRC PUMP LOSS OF LUBE WATER AUTOMATIC TRIP LISTED IN THE FSAR DOES NOT ACTUALLY EXIST 09612 50542: DIESEL GENTERATOR START TIME REQUIREMENTS DIFFER IN TECH SPECS (<15 SEC) & FSAR (<12 SEC) 2 of 7
Number Description .
09623 DUAL FUNCTION VALVES MAY NOT BE SET UP PROPERLY - PAST CORRECTIVE ACTIONS NOT TIMELY OR -
EFFECTIVE 09643 50542: RBCCW HEADER DRAINAGE PATH MAY RESULT FROM AN LNP COINCIDENT WITH A LOCA OR SEISMIC EVENT 10107 ELECTRICAL SEPARATION VIOLATIONS & INADEQUACIES FOUND IN MAIN CONTROL BOARDS 11104 50542: POST-LOCA INITIATION OF SPENT FUEL POOL COOLING PER FSAR 9.4.3.2 MAY NOT BE PROCEDURALIZED 11116 DESIGN CALC'S SHOW RBCCW MOTOR AMBIENT TEMPERATURE MAY EXCEED RATED TEMPERATURE BY 20 DEGREES C 13527 50542: APPLICABILITY OF RCS PRESSURE / TEMPERATURE LIMITS IS 12 EFPY IN FSAR & 20 EFPY IN TECH SPEC 13530 50542: TS LCO 3.4.9.1 HU/CD LIMITS BASED ON TAVG, SHOULD BE TC OR VESSEL INLET TEMPERATURE 13531 50542: INSUFFICIENT ANALYSIS DONE AFTER THERMAL SHIELD REMOVAL, 13532 50542, SG PRIMARY MANWAY HU/CD LIMITS NOT UPDATED IN FSAR AFTER SG'S REPLACED 13534 50542;VCT OUTLET HEADER RELIEF SETPOINT IS NOT CONSISTENT WITH ASSOCIATED HIGH PRESSURE ALARM M2-96-0017 LTOP PRESSURE ANALYSES MAY BE NON-CONSERVATIVE; PORV ACTUATION LOOP UNCERTAINTY NOT USED (50542)
M2-96-0018 50542: CONTROL ROOM INDICATION Eh LOR EXCEEDS P-T CURVE'S RCS COLD LEG TEMPERATURE ERROR ASSUMPTION M2-96-0019 50542: CONTROL ROOM INDICATOR LOOP ERROR EXCEEDS P-T CURVE'S PRESSURIZER PRESSURE ERROR ASSUMPTION 3 of 7
Number Description 50542: QUESTION ABOUT TC SHADOWING FACTOR IN POWER RANGE NEUTRON FLUX SAFETY CHANNEL LOOP M2-96-0241 CALC M2-96-0242 50542: QUESTION ABOUT NEUTRON DETECTOR LINEARITY ASSUMPTIONS IN LOOP UNCERTAINTY CALCULATION M2-96-0252 50542:PAST SIEMENS ANALYSIS DOES NOT JUSTIFY PAST REMOVAL OF STARTUP RATE (SUR) TRIP.
M2-96-0261 BORATING DURING COOLDOWN MAY CONFLICT WITH SOME DESIGN BASIS DOCUMENTS.
M2-96-0267 50542: WIDE RANGE NI HIGH VOLTAGE POWER SUPPLY CAN PRODUCE 2000V - OUTPUT CABLE IS RATED FOR 1000V.
M2-96-0283 50542: ELECTRICAL SEPARATION DISCREPANCIES IN CONTROL BOARD CO6 M2-96-0284 50542: ELECTRICAL SEPARATION DISCREPANCIES IN CONTROL BOARD CO7 M2-96-0289 50542: SPENT FUEL POOL RADMONITORS' INSTRUMENT UNCERTAINTY ALLOWANCES QUESTIONED M2-96-0296 MSIV CHECK VALVE NON-RETURN FEATURE COULD Fall CAUSING STEAM GENERATOR BLOWDOWN INTO CONTAINMENT M2-96-0318 50542: ELECTRICAL SEPARATION DISCREPANCIES IN CONTROL BOARDS C06 AND C07 M2-96-0322 50542: CONTAINMENT RAD MONITOR CALCULATIONS DO NOT ADDRESS INSTRUMENT UNCERTAINTY ALLOWANCES M2-96-0323 50542: RPS POWER SUPPLY MAY NOT MEET DESIGN REQUIREMENTS M2-96-0325 50542: MP2 RAD MONITOR MANUAL DOES NOT INCLUDE INSTRUMENT UNCERTAINTY IN SETPOINT CALCULATIONS M2-96-0329 50542: ESAS ACTUATION MODULE CONFIGURATION DOES NOT MATCH DRAWINGS 5 of 7
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Number Description M2-96 0?"1 50542: WR NI OUTPUT TO Ni CHART RECORDER NOT PROPERLY ISOLATED FROM POTENTIAL RECORDER FAULT ~
M2-96-0352 50542: SOME WEIDMULLER TERMINAL BLOCKS DO NOT HAVE A LOCKING WIRE INSTALLED M2-96-0379 50542: MP2 DOES NOT CONFORM TO LICENSING BASIS FOR BORON DILUTION EVENT M2-96-0412 50542: POWER SUPPLIES MAY NOT MEET RPS LICENSING & DESIGN BASIS REQUIREMENTS M2-96-0433 50542: ESAS UNDERVOL FAGE SETPOINT PROCEDURE MAY NOT P E ' TECH SPEC SETPOINT CRITERIA M2-96-0437 Single MSIV c-osure event puts SG's outside design basis per ASME.
M2-96-0448 50542: SHOR7 CIRCUlT FAULT MAY CAUSE SUSTAINED UNDER VOLTAGE CONDITION ON VITAL 120VAC M2-96-0449 50542: PASS TESTING & TRAINING DOES NOT MEET PAST COMMITMENTS M2-96-0450 50542: AN RBCCW HEAT CALCULATION WAS NOT PUT INTO RECORDS M2-96-0455 50542: REACTOR CCOLANT VENT SYSTEM MAY NOT BE OPERABLE DURING PLANT OPERATION M2-96-0460 50542: NUMEROUS DI3CREPANCIES FOUND ON SHUTDOWN PANELS C21, C09 C10, C70A, C70B M2-96-0486 50542: SEISMIC IMPACT NOT EVALUATED WHEN COMPONENTS REMOVED FROM MCC'S M2-96-0507 Aux Steam Unit Heaters 132 & 133 do not match design M2-96-0542 50542: TECH SPEC REACTOR POWER LIMITS FOR INOP MSSVS ARE NON-CONSERVATIVE M2-96-0642 Closure times for CTMT Purge valves in FSAR not same as Tech Specs.
M2-96-0658 TS LCO 3.9.8.2 non-conservative: Second SDC train not required if any (1) of (4) stated conditions satisfied.
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Number Description M2-96-0662 Changes to relief valve setpoints resulted in two ACR's which failed to identify the Root Cause.
M2-96-0663 Metal blocks used for vibration monitoring were installed without deign documentation or 50.59 evaluation.
M2-96-0670 TSAS 3.9.7, Crane travel- SFP Bldg, & Surveillance Requirement 4.9.7 are not compatible.
M2-56-0761 issue of Wide Range NI's becoming a Mode 6 hold should have been submitted in a more timely manner.
M2-96 ')777 Apparent problem with OP2209A
- Refueling Operations" and directions provided on filling the refuel pool as it pertains to applying the Tech Specs.
M2-96-0844 The Spent Fuel Pool Monorail Crane does not have interlocks or surveillance requirements to ensure compliance with Tech Specs M2-96-0860 CRAC supply damper 2-HV-210 is not single failure proof and could prevent the performance of the safety related function.
M2-96-456 BAST volumes differ from procedure to design basis documents M2-97-0024 SFP decay heat calculation concems. The current SFP decay heat load calculation for establishing the max heat load utilized nonbounding assumr,tions.
M2-97-0083 Containment Spray Pumps RBCCW seal cooler flow of 2gpm dose does not appear adequate. Seal flow may not be adequate to preserve pump performance during post LOCA containment sump recirc.
M2-97-0089 FSAR and TS are in conflict with respect to when AES is required during fuel movement.
MP2-96-0583 Electrical Separation Criteria not consistent between Electrical Specifications, the FSAR, and other regulatory documents.
MP2-96-0613 LTMT Purge Valve testing may not be adequate enough to satisfy Tech Specs 7 of 7
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4 Attachment 4 a Millstone Nuclear Power Station, Unit No. 2 i
l Regulatory Readiness items '
NRC Open items ;
i - Required License Amendments '
4 - Required Relief Requests
- Required Applicable Exemptions I
I February 1997
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- . U. S. Nuclear Regulitory Commission 1
B16257\ Attachment 4\Page 1 i
i Attachment 4 Millstone Unit No. 2
- Regulatory Readiness items i
, Renulatory Readiness items i 1. NRC Open items The NRC Open items shown on the attached are required to be resolved prior to
! restart of Millstone Unit No. 2 (i.e., prior to entering Mode 4). These items I
include:
Escalated Enforcement items Inspection Open items Licensee Event Report (LER) Commitments Notice of Violation Response Commitments l
Other NRC docketed correspondence (e.g., commitments made in
- response to the generic letters and bulletins and other Licensing i submittals.
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i 2. Reauired License Amendments i These include the technical specilication changes that are required prior to the i startup of Millstone Unit No. 2.
- 3. Reauired Relief Reauests At present, there are no known relief requests that require NRC review and approval.
- 4. Reouired Applicable Exemotions At present, there are no known exemptions that require NRC review and approval.
Millstone Nuclear Power Station, Unit 2 Regulatory Readiness items Description A/R Number Source Document NRC Open items Escalated Enforcement items Failure to prevent the use of potentially non-conforming materialin safety related applications 96031368 NRC IR 96-201 due to lack of adequate MEPL dispositions (eel 96-201-43)
Dvnamic testing of steam admission valve (eel 96-05-09) 96005104 NRC IR 96-05 Failure to prepare a safety evaluation for borating RCS during cooldown to Cold S/D (eel 96- 9700198515 NRC IR 96-06 06-05)
Failure to identify the cause and to take corrective actions for the incorrect RBCCW flow rates 9700198508 NRC IR 96-04 used in the CTMT accident analysis (EEI 96-04-10)
Failure to properly implement the requirements of the Technical Specifications during the 9700198502 NRC IR 95-44 formation of an ice plug in the SW Strainer backwash line (eel 95-44-05)
Failure to promptly resokve deficiencies in the analysis and design of MCC enclosures (eel 96- 9700198533 NRC IR 96-201 201-20)
Failure to[dentify and implement corrective actions conceming CTMT Sump Screen 9700198517 NRC IR 96-06 discrepancies (eel 96-06-11)
Full review and assessment of the function of the PASS, H2 Monitor and CTMT Radmonitors 9700198506 NRC IR 96-01 (eel 96-01-05)
Failure to maintain the plant configuration within the Licensing Bases for the CTMT Gaseous 9700198545 NRC IR 96-201 and Particulate RMs. H2 Monitoring system and PASS (eel 96-201-41) f
De~cripti* n A/R Number Sourc, Document Failure to adequately evaluate the installation of electncal jumpers for a malfunction of a 9700198523 NRC IR 96-201 -
different type as required by 10 CFR 50.59 (eel 96-201-03)
Failure to update the[S hk which states that the H2 monitoring system is manually initiated in 96033790 NRC IR 96-08 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> versus the 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> previously docketed in a letter addressing NUREG 0737 response (eel 96-08-13)
Failure to provide up-to-date data or reflect results of dynamic tests in GL 89-10 Closure 9700198512 NRC IR 96-05 Report (eel 96-05-11)
Identifies the condition where both H2 monitors were inoperable due to insufficient air flow and 96033783 NRC IR 96-08 not taking a representative sample (EEt 96-08-11)
Failure to adequately control the installat on of a temporary modificati$n to the RBCCW Surge 9700198526 NRC IR 96-201 Tank (eel 96-201-11)
Failure to adequately control standards resulted in inappropriate downgrade of OA Cat 1 96031361 NRC IR 96-201 equipment to a Non-QA status (eel 96-201-42)
Inadequate corrective actions conceming a seismic design deficiency for a Vital Switchgear 9700198544 NRC IR 96-201 room cooler (eel 96-201-36)
Failure tolmplement timely Aorrective action for identified significant bnditions adverse to 9700198539 NRC IR 96-201 quality (eel 96-201-30)
Failure to address the SBO issues identified in the VECTRA assessment (hkl 96-201-28) 96004632 NRC IR 96-201 Failure to effectively track and implement corrective actions conceming "bual function" 9700198535 NRC IR 96-201 isolation valves (eel 96-201-25)
Corrective actions for Turbine Bldg crane usage as a heavy load did not adequately prevent 97001985 NRC IR 96-08 the Unit 1 crane from carrying loads over Vital Swgr. (eel 96-08-10) 2
De'cripti* n A/R Number Sourca Document Inadequate corrective action in LER 96-024 (eel 96-08-08) 97001985 NRC IR 96-08 bhange made to OP2305 was inadequate in that it failed to iock open the valves. This was 97001985 NRC IR 96-08 corrective action for the seismic issues associated with the refueling drain line. (eel 96-08-06)
Inaaequate design verification for RBCCW Surge Tank seismic restraint modification (eel 96- 9700198542 NRC IR 96-201 201-31)
Failure to take appropriate corrective actions for audit issues involving trending and 9700198537 NRC IR 96-201 prioritization of NCR's (eel 96-201-29)
Failure to establish and maintain measures and design controls to rnaintain design basis for 9700198529 NRC IR 96-201 the WR N1 Channels (eel 96-201-12)
Adequate design control measures not established for verifying the accuracy of the DBDP's 9700198524 NRC IR 96-201 (eel 96-201-09)
Failure to establish adequate design controls when CTMT response analysis was changed 96033772 NRC 1R 96-08 during the SGRP (EEI 96-08-12)
Failuhe to adequately establish the qualification of connectors for seven solei.oid valves (eel 9700198520 NRC IR 96-06 96-06-12)
Inspection Open items Deficiencies in establishing tagging boundaries (IFl 95-201-06) 97004014 NRC 1R 95-201 Failure to comply with RG 1.97 Commitments (IFI 94-201-06) 97003982 NRC IR 94-201 3ailure to follow NEO Procedures 3.03 and 5.11 (IFl 94-201-02) 97003987 NRC IR 94-201 Lack of NCRs and verifying ACR database (URI 95-81-01) 97004029 NRC IR 95-81 3
De7cription A/R Number Sourco Document The site MCP was terminated with no replacement identified. Open items resulting from the 97004112 NRC IR 96-08 -
previous program are not tracked (IFl 96-08-21)
Leakage through letdown isolation valves (IFl 93-20-05) 97003985 NRC IR 93-20 Containment sump screen mesh size (URI 96-06-10) 97004025 NRC IR 96-06
. Shutdown Cooling system water hammer investigation (URI 96-06-08) 96030559 NRC IR 96-06 Complete HELB analysis of Turbine Bldg as well as analysis of CST pipe trench (URI 93 96232872 NRC IR 93-19 02)
ERT item resolution - Complete the commitments and recommendations identified in the ERT 96002502 NRC IR 95-42 report (URI 95-42-03)
EDG fuel oil supply questions (IFl 94-201-90) 97004028 NRC IR 94-201 Review of Cycle 13 Reload Safety Analysis Report (URI 95-27-01) 97003995 NCR IR 95-27 Appropriateness of the SUR Trip removal in 1978 (URI 96-08-14) 96035513 NRC IR 96-08 Loss of DC Bus Event (URI 96-01-04) 97004015 NRC IR 96-01 Core thermal power exceeded (URI 96-06-09) 97003996 NRC IR 96-06 Weakness in procedure classification system (IFl 95-201-03) 97004010 NRC IR 95-201 Numerous GL 89-10 MOV items to be resolved (URI 95-001-01) 97004004 NRC 1R 95-01 Use of locked rotor current in degraded voltage calculations ((URI 96-05-10) 96029543 NRC IR 96-05 4
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Det cription A/R Number S*ure, Document Refueling Pool drain line seismic issues (URI 96-06-07) 97003989 NRC IR 96-06 -
Resolution of adequacy of the as-left RBCCW flow rates (URI 96-04-11) 97002641 NRC IR 96-04 Licensee Event Report (LER) Commitment Corrective Actions Recommended by Heatup ERT - 96005424 LER 96-007-00 LER 95-Ob-02: Perform Analysis 97002778 LER 95-019-02 LER 96-012-00-SOV Operability (Mode 4) 96005447 LER 96-012-00 LER 95-019-02: Evaluate 79-02 & 79-14 Reviews 97002778 LER 95-019-02 LER 95-019-03: Return RWST Piping to full design compliance 97002778 LER 95-019-03 LER 96-019-00, SOV Circuit Full Review (Mode 2) 96005591 LER 96-019-00 LkR 96-019 b0 SOV Circuits Configu[akion Reviews (Mode 4) 96005591 LER 96-019-00 LER 96-019-00, EEQ SOV Circuits in Containment (Mode 4) 96005591 LER 96-019-00 LER 96-019-00 SOV Circuit Modifications (Mode 4) 96005591 LER 96-019-00 UER 96-020-00 DGN. Chng. for t$s of RBCCW (LER 96-020-01) (N) (M4) 96005922 LER 96-020-00 LER 96-019-00. SOV Circuit SFR Review (Mode 2) 96005591 LER 96-019-00 LER 96-022-00-Dgn Chg. to Correct sgl. Fail. Susp.- EBFS HTRs(SU) 96007508 LER 96-022-00 5
D?scription AIR Number S rurc, Document LER 96-016-00 CWP Trip Function - Cond. Pit Level Switches 96004898 LER 96-016-00 Supplement LER 96-031-00. re-analysis of single MSIV Closure 96032859 LER 96-031-00 Submit Supplement to LER 96-003-00 -(heat up and cool down report) 96002914 LER 96-003-00 Submit Supplement LER 032 96033653 LER 96-032-00 LER 96-041-Ob Develo[ Procedure for Fuel Transfer Tube Flange 97001426 LER 96-041-00 LER 96-029 SUR Trip Analysis 96030253 LER 96-029-00 t ER 96-007-00 Heatup/Cooldown Corrective Actions (N) 96003852 LER 96-007-00 LER 96 018-Ob Gaps in Enclosure Doodeals 96030988 LER 96-018-00 LER 96-030-00 Verify and Correct Bases and Surveillances 96031106 LER 96-030 LER 96-009-00 Complete Prior to Startup (N) 96003567 LER 96-009-00 LER 96-009-00 Post LOCA CTMT Press & Temp Curve Review (S/U)(N) 96003567 LER 96-009-00 Operating Guidance and Operator Burdens From ERT Heat Up 96005424 LER 96-007-00 LER 96-028-00 SW Strainer Backwash Solenoid Install. (Mode 4) 96027503 LER 96-028-00 LER 96-012 TS ESFAS Response Time (N) 96005447 LER 96-012-00 Lhk96 029-00 Prepare Suppl. LER-SUR Trip Analy. (Mode 4) 96030253 LER 96-029-00 6
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De 7criptiv n AIR Number Sourc7 Document LER 96-018-00 MCC B51/B61 Enclosure Door Seals 96030988 LER 96-018-00 -
LER 96-007-00 Heatup/cooldown Rate Proc. Changes & Train. (Mode 4) 96003852 LER 96-007-00 LER 97-001-00. Replace Homcock Fire Seal Material 97002940 LER 97-001-00 LER 96-043-00 Review of Design Cal bration Calculations 97002697 LER 96-043-00 Re-analysis of single MSIV closure event, LER 96-031-00 96032859 LER 96-031-00 Notice of Violation Response Commitment ATWS system testing (VIO 96-01-06) 96008733 NRC IR 96-01 InadeqEat[correctibact5cn (VIO 9b11-01) 95025539 NRC IR 95-11 inadequate retest of solenoid valves (VIO 96-04-08) 96027036 NRC IR 96-04 Operation of Service Water and RBCCW coohng systems outside of their design basis during 96032418 NRC IR 94-17 condenser backwashing (VIO 94-17-10)
Failure to address the leaking of check valve 2-CS-15A and to take action to assess the 97004029 NRC IR 95-08 impact of water being present on the sump side of 2-CS-16.1 A (95-08-01)
Potential violation of Y c. .<hich requires two separate and independent ECCS subsystems 97004026 NRC 1R 95-08 due to inadequate pressure locking / thermal binding susceptibility evaluation (95-08-02)
EOP Procedure Upgrade NOV 94-17-10 96032418 NRC IR-94-17 Failure to document review of Vendor QA design services IAW NU Procedures (95-08-04) 97004024 NRC IR 95-08 7
De =cripti~n A/R Number Sourc7 Document intake structure ventilation system deficiencies (VIO 95-42-04) 97003992 NRC IR 95-42 -
Failure to adequately evaluate information on pressure locking and thermal binding LAW PIR 97004030 NRC IR 95-08 procedure (95-08-03)
Other NRC Docketed Correspondence Complete review required by Generic Letter 96-01 9603?301 GL 96-01 Complete 110X/Y MODS For Instrumentation Loop Class 1E Power 95026372 B15100 Mode 2 - Review Tech Spec Surveillance Procedures 96037089 B16076 10CFR 50.54(F) for MP2 96003732 A12753 Self-assessment of ESAS related issues and deficiencies - B15283 95027429 815283 Develop Altemate means of Appendix R compliance 96036400 816065
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Effectiveness of Corrective Actions Program - A12863 96008778 A12863 Reference TRM in the FSAR Chapter 12 (N)- B15702 96007779 B15702 Thermo-lag Resolution - Fire Rating Evaluations - B15558 96005888 B15558 Provide Training Regarding GL 96-01 96035429 GL 96-01 Reevaluation & Modification of SG Hydraulic Snubbers - B16019 % 034250 816019 Submit the Revised LBLOCA Analysis to the NRC 96036408 A13114 6
Description A/R Number Sourco Document Review design processes and take appropriate actions - B16019 96034250 B16019 -
Ensure implementation of the ICAVP 96032302 A12884 Thermo-Lag Resolutions - Appendix R" Re-analysis 96005888 B15558 GL 96-06 Actions to Eliminate Thermally Induced Overpressure 97002555 GL 96-06 Owners Groups' RPV Integnty Program Results - A12931 96027793 A12931 Complete Resolution of Seismic Outliers Priar to Startup - GL 87-02 97001885 GL87-02 Modify RM 8123A/B & RM-8262 A/B instrumes- 97001960 B16159 Generic Letter 96-06 RBCCW balct$lations 97002555 GL 96-06 Revise Procedures to Ensure Continued Compliance with GL 96-01 96035429 GL 96-01 Generic Letter 96-06 Actions to mitigate RBCCW Waterhammer 97002555 GL 96-06 Operation of Thermolag Cables not Meeting Design Ampacity Requirement 96036400 B16065 Mode 1 - Review Tech Spec Surveillance Procedure 96037089 B16076 Mode 6 - Review Tech Spec Surveillance Procedure 96037089 B16076 Mode 5 - Review Tech Spec Surveillance Procedures 96037089 B16076 Mode 4 - Review Tech Spec Surveillance Procedures 96037089 B16076 9
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De?cription A/R Number Sourc, Document Mode 3 - Review Tech Spec Surveillance Procedure 96037089 B16076 -
Thermo-Lag Resolutions - Appendix "R Fu I Comphance 96005888 B15558 Thermo-Lag Resolutions - Select Product Upgrades 96005888 B15558 Request for Additional inform. Related to 50.54(f) Letter 96007039 A12852 Steam Generator Wide Range Level Incorpor into EOP 96005888 B15100 Resolution of 59 design issues (ACR 8761) 96001273 ACR 8761 10
De cripti~n A/R Number Sourc7 Document
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Required License Amendments Revise SG Safety valve setpoints in Table 3.7-1 - -
Section 6 0. Organization Structures / Titles - -
Steam Generator Blowdown Monitor Action statement changes - Section 3.3.3.9 - -
MET Tower Instrument Accurracies - Section 3.3 3.4 - -
-- - . . - _ . _ _ _ _ _ - . . _ _ . ~ - _ _ - _ - - - - . . . _ _ _ -
Ultimate Heat Sink Temperature measurement location changes - Section 3.7.11 - -
Enclosure Building Integnty and application of Specification 3.0.3 - Sections 3.6.5.1 and - -
3.6.5.2 Fuel oil capacity (7 day requirement) for Emergency Diesel Generator - 3.8.1 - -
Revise Pressure / Temperature in Specification 3.4.9.1 - -
Control Room Emergency Ventilation System - Surveillance Requirements - Section 3.7.6.1 - -
Spent fuel storage area ventilation system - Section 3.9.14 - -
Containment integrity / Containment isolation Valves - Section 3.6.3 - -
Reinstate a note to Tech Spec related DNB LCO - Section 3.2.6 - -
LTOP condition (specification 3.4 - 9.3), Reinstate the applicability of specification 3.0.4 - -
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Description A/R Number Sourca Document Addition of 2 second time delay to 4.16 kv under voltage Level 1, Table 3-3-4 - -
RCS - Mode 4 and 5. Action statement changes - Section 3.4.1.3 - -
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Description A1R Number Sourc7 Document
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Required Relief Requests None identi ied at this time - -
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Description A/R Number Sourco Document
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Reauired Applicable Exemptions i
None identified at this time - -
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Docket No 50-336 B16257 i i
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f Attachment 5 ,
l Millstone Nuclear Power Station, Unit No. 2 Common Millstone Site lasues Applicable to l Millstone Unit No. 2 l
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February 1997
. . ' U.S. Nuclear Regulatory Commission B16257%ttachment 5\Page 1 Attachment 5 Millstone Nuclear Power Station, Unit No. 2 Common Millstone Site issues Applicable to Millstone Unit No. 2 The following list includes Common Millstone Site issues that are applicable to Millstone Unit No. 2:
. Employee Concerns Program
. HELB/EEQ
. Dual Function Valve Control and Testing i
e Review of NUREG-0737 Action items
! . Control of Safeguard information
! . Procedural Adherence l . Procedure Upgrade Program ,
l . Communication Between Units l . MEPL Program Evaluation' l
. Operator Training
. Formality of Non-Routine Security Activities e Control and Use of Vendor information ,
! . Work Planning and Controls, Engineering and Maintenance Backlogs l l
. Work Planning and Controls, Automated Work Order Process
. Oversight Effectiveness of Each Group
. Emergency Preparedness Effectiveness l Each of the above issues will be addressed by one or more specific actions and each issue will be dispositioned prior to restart of Millstone Unit No. 2.
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I Dtvig No. 50-336 B16257 1
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Attachment 6 j l Millstone Nuclear Power Station, Unit No. 2 )
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- Operational Readiness Plan - Nuclear Oversight Plan l
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5 February 1997 i
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