ML20149E439
| ML20149E439 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/10/1997 |
| From: | Andersen J NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9707180193 | |
| Download: ML20149E439 (126) | |
Text
0,1d
~
y LICENSEE:
Northea ear Energy Compa y NECO) l; FACILITY:
Millstone Nuclear' Power Station Units 1, 2, and 3 F
SUBJECT:
SUMMARY
OF JULY 1, 1997, MEETING WITH NNECO TO DISCUSS PROGRESS OF LICENSEE ACTIVITIES TO SUPPORT RESTART.OF THE THREE MILLSTONE UNITS 2
On July 1, ~1997, the Special Projects Office (SP0) staff-of the Office of Nuclear Reactor Regulation (NRR) participated in a publicly observed meeting with NNECO representatives.
The purpose of the meeting was to discuss NNECO's l
progress in facilitating restart of the three Millstone units. At the start of the meeting, NNECO presented information pertaining to (1) the recent NRC training inspection and NNECO's Oversight training audit and the NNEC0 decision for a training standdown, and (2) the Millstone Unit 3 spent fuel pool heatup event. NNECO then made presentations on Millstone Unit 3 readiness, safety-conscious work _ environment, oversight, self assessment and i
corrective action, Independent Corrective Action Verification Program status for Millstone Units 2 and 3, and unit readiness for Millstone Units 1 and 2.
a l
Due to time constraints, NNEC0 did not present information on the 10 CFR 50.54(f) request response, configuration management overview and status, 1
Nuclear Safety Assessment Board, and security.
i-provides a' list of the principal attendees at the meeting. provides the handout used by NNECO during its presentation.
i provides the background material NNECO provided to the NRC staff during the meeting.
Original signed by:
' James W. Andersen,' Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336, and 50-423~
Enclosures:
As stated (3) cc w/ encl:
See next page HARD COPY E-MAIL Docket: File Sco111ns/FMiraglia (ABJ/JMW1)
PUBLIC RZimmerman (RPZ)
SP0-L Memo WTravers (WDT) l SP0 Reading PMcKee (PFM)
OGC _
JAndersen (JWA)
ACRS LBerry (LGB)
GImbro SReynolds (SARl)
TEaslick DBeaulieu i
9707180193 970710 TCerne e
Dross (e-mail to SLM3)
$m J
WDean (WMD)-
Am 05 25 JDurr, RI DOCUMENT NAME: G:\\ANDERSEN\\MEETSUM.701 To rective e copy of this docwnent,Indcate in the box: 'C' = Copy without ettechment/ enclosure
'E' = Copy with attactwnent/ enclosure
- N* = No copy 0FFICE SP0-L:PM f SP0-L:L4m SP0-/QrW l
l NAME JAnderse W 4 LBerry YF PMcMel/
DATE 07/so /97 07/10 /97 ' ~ \\
07ho /97 07/ /97 07/ /97 0FFICIAL RECORD COPY b!$ $,$flll
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t UNITED S.TATES j
,j NUCLEAR REGtiLA' TORY COMMISSION
's WASHINGTON, D.C. 20666-0001 o
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July 10,1997 LICENSEE:
Northeast Nuclear Energy Company (NNECO)
FACILITY:
Millstone Nuclear Power Station Units 1, 2, and 3 i
SUBJECT:
SUMMARY
OF JULY 1, 1997, MEETING WITH NNECO TO DISCUSS PROGRESS l
OF LICENSEE ACTIVITIES TO SUPPORT RESTART OF THE THREE MILLSTONE UNITS On July 1,1997, the Special Projects Office (SP0) staff of the Office of Nuclear Reactor Regulation (NRR) participated in a publicly observed meeting with NNECO representatives. The purpose of the meeting was to discuss NNEC0's progress in facilitating restart of the three Millstone units. At the start of the meeting, NNECO presented information pertaining to (1) the recent NRC training inspection and NNECO's Oversight training audit and the NNECO decision for a. training standdown, and (2) the Millstone Unit 3 spent fuel pool heatup event.
NNECO then made presentations on Millstone Unit 3 readiness, safety-conscious work environment, oversight, self assessment and corrective action, Independent Corrective Action Verification Program status for Millstone Units 2 and 3, and unit readiness for Millstone Units 1 and 2.
Due to time constraints, NNECO did not present information on the 10 CFR 50.54(f) request response, configuration management overview and status, Nuclear Safety Assessment Board, and security.
j provides a list of the principal attendees at the meeting. provides the handout used by NNECO during its presentation.
4 provides the background material NNEC0 provided to the NRC staff during the meeting.
am s W. Andersen, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336, and 50-423
Enclosures:
As stated (3) cc w/ encl:
See next page
Ie b
Northeast Nuclear Energy Company Millstone Nuclear Power Station Units 1, 2, and 3 cc:
Lillian M. Cuoco, Esquire Mr. Wayne D. Lanning Senior Nuclear Counsel Deputy Director of Inspections Northeast Utilities Service Company Special Projects Office P. O. Box 270 475 Allendale Road Hartford, CT 06141-0270 King of Prussia, PA 19406-1415 Mr. Kevin T. A. McCarthy, Director Mr. F. C. Rothen Monitoring and Radiation Division Vice President - Work Services l
Department of Environmental Northeast Nuclear Energy Company Protection P.O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Charles Brinkman, Manager l
Mr. Allan Johanson, Assistant Washington Nuclear Operations l
Director ABB Combustion Engineering Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 Policy Development and Planning Rockville, MD 20852 Division 450 Capitol Avenue - MS 52ERN Mr. D. M. Goebel P. O. Box 341441 Vice President - Nuclear Oversight Hartford, CT 06134-1441 Northeast Nuclear Energy Company P. O. Box 128 Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. M. L. Bowling, Jr.
King of Prussia, PA 19406 Recovery Officer - Millstone Unit 2 Northeast Nuclear Energy Company First Selectmen P. O. Box 128 Town of Waterford Waterford, CT 06385 Hall of Records 200 Boston Post Road Senior Resident Inspector Waterford, CT 06385 Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission Mr. J. P. McElwain P. O. Box 513 Recovery Officer - Millstone Unit 1 Niantic, CT 06357 Northeast Nuclear Energy Company P. O. Box 128 Mr. J. K. Thayer Waterford, CT 06385 Recovery Officer - Nuclear Engineering and Support Deborah Katz, President Northeast Nuclear Energy Company Citizens Awareness Network P. O. Box 128 P. O. Box 83 Waterford, CT 06385 Shelburne Falls, MA 03170 t
r 1
i
.4 6
l Northeast Nuclear Energy Company Millstone Nuclear Power Station Units 1, 2, and 3 i
cc:
Mr. M. H. Brothers Little Harbor Consultants, Inc.
Vice President'- Millstone Unit 3 Millstone - ITPOP Project Office Northeast Nuclear Energy Company P. O. Box 0630 t
P. O. Box 128 Niantic, Connecticut 06375-0630 Waterford, CT 06385 i
Mr. Evan W. Woollacott Mr. M. R. Scully, Executive Director Co-Chair j
l Connecticut Municipal Electric Nuclear Energy Advisory Council j
Energy Cooperative 128 Terry's Plain Road 30 Stott Avenue Simsbury, Connecticut 06070 l
Norwich, CT 06360 Mr. Daniel L. Curry l
Mr. William D. Meinert Project Director Nuclear Engineer Parsons Power Group, Inc.
Massachusetts Municipal Wholesale 2675 Morgantown Road-Electric Company Reading, Pennsylvania 19607 l
P. O. Box 426 Ludlow, MA 01056' Mr. Don Schopfer Verification Team Manager Ernest C. Hadley, Esq.
Sargent & Lundy 1040 B Main Street 55 E. Monroe Street l
P. O. Box 549 Chicago, Ilinois 60603 West Wareham, MA 02576 Mr. Neil S. Carns Joseph R. Egan, Esq.
Senior Vice President i
Egan & Associates, P.C.
and Chief Nuclear Officer 2300 N Street, NW Northeast Nuclear Energy Company Washington, D.C. 20037 c/o Ms. Patricia A. Loftus Director - Nuclear Licensing Services Citizens Regulatory Commission P. O. Box 128 ATTN: Ms. Susan Perry Luxton Waterford, Connecticut 06385 180 Great Neck Road Waterford, Connecticut 06385 The Honorable Terry Concannon Co-Chair Nuclear Energy Advisory Council Room 4035 Legislative Office Building Capitol Avenue Hartford, Connecticut 06106 l
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LIST OF ATTENDEES I
July 1, 1997 NAME ORGANIZATION Bill Travers NRC Gene Imbro NRC Wayne Lanning NRC Phil McKee NRC Steve Reynolds NRC t
Jacque Durr NRC Ted Easlick NRC Dave Beaulieu NRC Tony Cerne NRC James Andersen NRC Neil S. Carns NNECO David M. Goebel NNECO Pat Loftus NNECO Michael Brothers NNECO Marty Bowling NNEC0 Jack McElwain NNECO Jay Thayer NNECO Frank Rothen NNECO Dick Johannes NNECO Denny Hicks NNECO Pete Richardson NNECO Mike Covell NNECO Ray Necci NNECO Tom White NNECO 1
t b
Northeast Utilities Briefing for the NRC Opening Remarks Restart Assessment Panel Buzz Carns Senior Vice President &
Millstone Station Chief Nuclear Officer-Millstone July 1,1997
- anw=,e=cmadamyr H Agenda Agenda (continued;
- Training Jay Thayer
- MP3 & 2 CMP /ICAVP RayNecci DickJohannes Tom White
- MP3 Spent Fuel Pool Mike Brothers Cooling
- 10CFRSO.54(f) Response Zacn LaPlante Barbara Willkens
- MP3 Readiness Mike Brothers
- NSAB Steve Scace
' Safety Conscious ke N
Work Environment
- Oversight Pefe Richardson
' Unit diness
- Self Assessment and Mike Covell Corrective Action MP1 Jack McElwain
- Awameer=cmareaser H
- ***=.88 *c*ar Ea*vy H Recent Training Events
- NRC Inspection:
- 6/23 6/27 Tra,ining
-41s00 inspecuon, nas.d on NuREa 1220 Dick Johannes
- focus on MP3 technical programs Di e r
- Oversight Audit Nuclear Training Department
- 611 6 6127
- NUREG 1220 format
[merms**faser H
- ann rmem-s,-y, H Page 1 l
i
l e
6 Recent Training Events Recent Training Events (con 6nued)
(continued)
+NRC Inspection Results
- Oversight Audit Results
- evidence that Systems Approach
- Element 5, Program Evaluation -
to Training not being effectively functioninginadequately implemented
- Systems Approach to Training -
- long standing history of inability functinninginadequately to promptly identify and resolve
- apparent violation of 10 CFR 50.120 propiems
- recommendation to STOP Accredited Training Programs -
. ~ ~ s-n +
- m-a.,
Increased Management Current Training Status involvement in Training
+ 8tanddown in effect as of Friday, 6/27/97.all programs
- accredited and non-accredited 1
- Past training delivered NOT in
+
1 question
)m.
n r,
3.es
.---s-.
Current Training Status Training Corrective Action (coa 8 mad >
Plan (CAP)
- Plan to Restart Programs
+R lustion based on recent started W27/97
- Root Causeinvestigation initiated
- As of 6/30/97,48 of 70 activities
- program restart priorttiration
- N orMpoing
+ CAP expansion on going
- program success em
-original: 59 activities developed g
- current: 70 activities mstruction developed g
..-en -e = = - *=,w H
, ===- s.w Page 2 L
-- - - -~
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Major CAP Deliverables Major CAP Deliverables Completed Completed ccontinues)
' Licensed Operator Requalification
- Enhanced NRC Form 396/398 Programs assessed processes
+Self assessment capability of NTD
- Review of past audits and upgraded inspections complete j
- Problem Matrix issued
- Executive Training Council (ETC) established
- CRs generated
+ Assessment of MP3 LOITI LOUT
- Operator Instructor Retention Plan issued lN-***n nce= tawer &
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l
- Assessment of MP1 LOIT / LOUT I
'M programs f.
+ Assessment of MP2 LOIT / LOUT programs
- Records retention / filing practices
=
upgrade
-~.n -,- H
- .-n
-,, v H Major CAP Deliverables in Success Criteria Progress (continues)
- Formallicense candidate selection
' Training restart activities complete process
- CAP ltems complete
- Exam bank process enhancement
- Complete implementation of
' Operations crews ready for restart Training Information Management System (NUTIMS)
- ***** *can sawer H lnana n wc w 1,-,y H Page 3
.~.-
l 9
4 l
Millstone Unit 3 Spent Fuel Pool Cooling Flow Paths Millstone 3 Spent Fuel Pool j i ;_.:.l i
1 Cooling jw + -- * =,
- =
Mike Brothers 1
Vice President-Millstone Unit 3
- ..4*""I
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- u-uw smvH j
Significant items List (SIL) is Now a Challenge For MP3 Millstone Unit 3 Update
- Provided to the NRC for review 58 Mike Brothers Vice President Millstone 3
- Remaining packages 147
- -==.- - *=v F -
a-
,-v H 1
j Significant items List f
License Amendments Continue to be a Challenge at MP3
- * **;$*J*7 Z " " T E 'N
- Total PTSCRs required for start-up 24 7
- PTSCRs remaining as of 6r30 2
/T
- No Significant Hazards j;
Considerat6ons g,-
)
- Schedule Challenges a g
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- Append 6x G curves
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-rnein steem pressure rollef
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bypass vaeves ah',
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- m-n =en-a
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1 License Amendment Requests MP3 Facing Several
" * " * " * ^ ' " _ * '
Challenges For Restart e,
- Safety conscious work environment a
y
' Restart punchlist
' Work off eurves l =.
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a
-LARs, AWOs and modifications l-e MOVs b
' RSS. suction voiding & expansion Jonts e.-
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- Appendix R
- nannussmsnarv &
- nannustmsn,v l
l Millstone 3 Milestones Millstone Unit 3
- CMP / Discovery Complete July 14
- Ready for OSTI Sept. 30 Operational Readiness
- Physically Ready Sept. 30 for Restad G. D. Hicks Unit Director, hillistone 3 1
I
- .-,., - s,
-s,
. t
)
l l
OperatorQualification OperatorQualification
[
+ Units will take the lead in managing IC#"NM additional training activ!!ies
- LoRT training cycles for the
- observation training at operating remainder of 1997 address:
I or start-up plants
- new and significantly revised
)
- reinforcement of operations procedures i
standards, conservative decision-making, NU Nuclear
- onerating experience Safety Standards of Expectations
-annual written and operating tests
-increased use of industry experts to vertfy standards
-start-up task trainir,g l *=naart h sa=vy F--
l as,v r Asamasamer F--
1 Page5 i
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Distractions To Operators Temporary Modifications
=
Meston.3.Jun.1M7 Are Being Reduced Pro., as.,
- Control Board Deficiencies
%-
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' Work Arounds
=
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w~r l herth sf WJtain.ryy %
[ herfA st*4dCAsMIn.tyy %
Control Room and Annunciator Deficienclos Operator Work Arounds mason. 3.Jua. in?
Mmston.3.Jun.in?
Prograss, se.m e
em
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Progress. A sese ee e e e.pa. se f-m
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,,w s,.s.,,1 Open Operability Determinations Preparations Planned For Hot
==ma.3.Jun.in7 Functional Operation
- Discovery of any remaining plant
=
deficiencies I
I
- Enhance operator experience With hot plant
~'
- Extended period to pre-stage s
- i. i.i i.) i. i i..! l. I.i l l l surveillances and post 4nalntenance testing I--
-~ * *'"I
- PORC approval of organizational assessments prior to entry for each mode change j
- n-m sranoce-e sr &
- narn rsucu-un my }
I Page 6
a O
Organization Will Allow Shift Hold Points Have Been Manager To Focus On Established To Allow Plant Safety / Operation Readiness Assessments
- Test lead for restart
- Test engineers
+ Area walkdowns
- On. shift work management
- Surveillance requirements
- Control room mentors / ot, servers
- Post-maintenance testing
- Maintenance response team i
, Mode change assessments'and reviews
- Management presence in thes Control Room na,n uran,emasms F-.
hamun 'a***= smv F--
Hold Points (contin,=t>
- Approximately 30 days prior to mode change Safety-Conscious Work
- Prior to Mode 4,3 and 2 Environment
- At 25-30% power
- At 45-50% power Mike Brothers
- At 70 75% powe; VicePresident niillstone3
- At 90 95% power a a
,=, F
- - naa,*-s-vt We Are Clear About What We Are Doing...
We Are Taking Actior....
- Establishing and maintaining a safety-
- Expectations developed and issued conscious work environmentin wfrich our employees, including contractors,
, Executive Sponsor assigned feel free to raise concerns, both to their
- lssue Manager assigned management and to the NRC-without
- Comprehensive Plan keing fear ofretaliation implemented
- The une organization and ECP have
- Restart Readiness Plan being complementary responsibilities for executed achieving this environment
- a,,,m,,a an,,o,s,,,, l
- :- - ^
- as,ama smv F-~
Page 7
e-t Taking Action...
Taking Action...
ECP Improved Comprehensive Plan implementation Progressing
- Partnership with line management to facilitate the resolution of concerns
,99 of 155 total action items have been completed
- Increased ECP staffing and training
)
33 of 43 ECP-specific action items
- Concerns stay active through have been completed implementation of Corrective Actions
- Employee Concerns oversight Panel
, Plan progress in improving the ECP has been self assessed to monitoreffectiveness i
1 l herwaeostnerenainergv &
l noenneestnewconvinnery &
I Taking Action...
We Are Monitoring Enhanced Employee Training in Our Actions...
Progress
, pp, gu,,,,
- NuclearAcclimatization
- Leadership Survey
- Managing for Nuclear Safety
- Self assessments i
- Forum for Leadership Excellence
- Employee Concems Oversight Panel
- Enlightened Leadership
- Developing a course on Handling of professionaldissent 1
- humeestanoco,ampv &
- m stas, emu e,,,y, p i
ECP Self Assessment ECP Self Assessment Results Indicate Proaress....
Identified...
Needed Imorovement
- Regaining employee trust
- Concem resolution process
- Concem Resolution Process requires furtherimprovement greatlyimproved
- Most concemees are satisfied with
, Case files are deficient in several
+ Additionalformaltraining required to update skills Y
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4 Page 8
s P
i Recovery Plan Progress
- Internal procedures 95% complete
- Staffing near completion Nuclear Oversight
- Rotauon pro 9eam in progress
- Training programs initiated
- Hold-point process reworked and Pete Richardson implemented Director, Performance Evaluation
- Quarterly intemal Self Assessments completed
- Assessment underway by Third Party 3
,-,- r r
Restart Validation Oversight is identifying Significant Problems
- Operational readiness assessment s Audits finding significant issues
- unit specific
-41 audits in 1997,16 complete
- ICAVP readiness
-115+ CRs written,201.evel 1 CRs
- unit speelRc
- Surveillances monitor day to<iay
- Safety conscious work environment activity
- Corrective action and self assessment
-330 surveillances in 1997,174
- Oversight Recovery Plan restart required complete actions
-104+ CRs written,12 Level 1 CRs 3-
, =,- r
, n-
- e-Oversight is identifying Line Response to Significant Problems (continuee Oversight-Identified Problems
- QC toch support identifying issues
- Requesting additional Oversight
- Independent Review Teams reviews
- completed 5 IRTs since 1/1/97
-suWlances in new gogram areas
-IRTs in problematic areas
- ihntW mmmk weaknesses The Goa
' Issuing monthly assessment report To impro@ hib' s and Wity ofLineresponses to Oversightaudit andsurveillance Rndings
- nam.en,annea ne -
- nam =,nnmsmenwrv s Page 9
2
[
Oversight's Challenges Self-Assessment 4
- Engage 4
+1ntegrate
- Train and Develop Corrective Action
- Communicate Mike Covell Director, Corrective Action Program u-,
,v r v s Success Criteria How Are We Doing?
- Self-Assessment
- effective programs and processes are
- Significant number of deficiencies in place documented when discovered
-issues identified by responsible e The backlog of incomplete investigations continues to fide ficationof adverse decrease, while action backlog is condaions increasing
-timely development of action plans
- The quality of the investigations is
-effective resolution improving
-trending to identify recurring issues
- Confirmed by Nuclear Oversight
- Low threshold expectation
,namousnemaan.ev F-
{Nwan.en ncm=*==wv &
Remaining Actions Remaining Actions
+ Perform Self Assessments
- Establish program ownership
- Corrective Action Program
$1mplement HPES program
- Self Assessment Program
- effectiveness of Corrective
, Develop human performance Actions (CR Level 1) indicators
' Corrective Action Program Enhancements
, a-
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. -- n - e-- F-Page 10
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Remaining Actions
- Focus self-assessment on readiness to Ec$tI"a vor.sen GMgmbdanagemeM
.vai i
functionai are.
Restoration / ICAVP
- determine methods of sett Millstone Units 3 & 2 assessment l
- display as indicator windows Ray Necci
- Unit Directors (MRB) review results Director, CMP with functional area managers l~-m. - -vr l.am.u m,,, s i
l 1
j CMP Restoration CMP Completed Activities Success Criteria:
Millstone 3
- 1) When the Licensing and
- Wave 1 systems complete May 27 Design Basis requirements have been documented'
- Program Reviews complete validated, and verified to
- On schedule for July 14 complete reflect unit configuration discovery (Line and Oversight) and operation
- Corrective actions being defined
~
- 2) When this verification is and scheduled confirmed by Oversight
-restart
-postastart l nam *umInner &
l nam.n mucma sw&
s-CMP Completed Activities MP3 Independent Corrective Millstone 3 (continued)
Action veritication is Progressing
- Process changes have been made to replace SSAs
- Sargent & Lundy mobilized
- System Technical Assessments
- NRC identified first 2 systems
-System Assesset > ts
- NU Response Team established
+ System boundaries defined
- Next meetings. July 16-17,1997 l *=m*nwsmv s l no m n m e,w er s Page 11
o 6
MP3 Independent Corrective CMP Completed Activities Action Verification is Millstone 2 Progressing (continue @
, Ready forlCAvP
- System Boundary Meeting defined interfaces
- 15 Group-1 systems complete
- 85 SW interface points (mech.,
e Program reviews complete elec., I&C, oper.)
- 61 RSS / QSS interface points
.,-,- H
,,-,- H MP2 CMP Completed MP2 CMP Completed Activities (continued)
Activities (continued)
- Process changes made to improve efficiency:
oWalkdowns forelectrical separation, EEQ, plant
- review process of Pl 7 configuration issues for 15 streamlined systems
- communication of results focused on System Engineering
- Sept. 8 completion of discoveryis challenged
, a-r m e-
- a
, =,.,H Unit 2 independent Assessment Process Activities Performed two independent ICAVP Readiness - MP2
^* *** *=*ats :
Overs /ght's Assessment
- 1. Low Pressure Safety injection
- completed - May 9
- compared to unit graded review
- Dimctor, its d Evaluation
- d"** "P**
Nuclear Oversight
- boundary concem identified
-allissues addressed by the unit
- win.emaa.w H
- m.m,r m,a.,H Page 12
o L
Unit 2 Independent Unit 2 Assessment Activities Assessment Process Activities p,,!ect instruction (P1) Assessment
- 2. Auxiliary Feedwater System
- Examples ofidentified issues
- completed June 23
- Condition Report threshold
- thirteen condition reports
- Position Papers System vs.
- compared to unit-graded review Topical (PI-6)
- allissues addressed by the unit
- lndependent Assessments not implemented (PI-11)
- Allissues addressed by the unit 1
- hta.estme.ardawyr l--
- wrin.est = caw enwyr H 1
1 Unit 2 Assessment Activities Uni! 2 Assessment Activities Enaineerina Procram Reviews Project Graded system Review
]
Closure Activities:
- 17 engineering program packages reviewed
,6 of 15 packages in depth reviews
'No significant issues identified emaining 9 - summapykws
' Multi-discipline review teams
' Unit Project Manager approvals All activities successfully completed I hst *ca-ga-vr I--
- wria,m -so,yI Unit 2 ICAVP Readiness
- m,, -
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b.
Nuclear Oversight concurs that:
h l
lCAVP start E-Unit 2 is ready for t.:-';:=_ - - ':= :=
i_.
- _ -,-v r Page 13
a s
10CFR50.54(f) Submittal Status
- Request for information. Aprl/16,1997 Configuration Management
.initiai r.sponse -may 29,1ss7 10CFR50.54(f) Request for l
information - 4/16/97
-significant items for Restart List
-deferral list (Units 2 and 3)
Zach LaPlante
-selection crheria for other pre-restart Program Manager work items (Units 1,2, and 3)
- Next submittal-July 15,1997
- -~.u -,- s
- -,, -,- r Methodology Significant item
+ tems for mtart Screening Criteria
-significant items:
+ Level 1 CRs and Level A or B ACRs e Maint Rule Group 1and2(safety related orrisk significant)
- Level-2 CRs and Level C or D ACRs
. affected operability or DB function
-selected other items for restart function
' Remaining items will be addressed after restart
..-~.,-,-H
- .-~,-,- r Selected Other Selected Other l
Restart Work items Restart Work items reontinued;
- Screening Criteria
- supports a required Technical
- Scmning CMa Specification change
-prior NRC commitment
- corrects a Licensing Basis or
-required for Maintenance Rule Design Basis deficiency group 1 or 2 system operability e FSAR :orrections
- Management Review e modi 6 cations
- .-~.- -,-,, H
,-,- H Page 14
e Selected Other Restart Work items (continuee; Remaining items
- Originating Documents
- CRs and ACRs
- Provide updates approximately 1
every 45 days
- Engineering Work Requests
- Complete the Significant items for
- Engineering Work Assignments Restart List
- Non-Conformance Reports
- Submit final response
- Automated Work Orders
- Unresolved item Reports from CMP
- -- -,- +-
r Success Criteria Configuration Management
+ Adequate programs and processes Overview and Status have been implemented to maintain configuration control
+ Successful implementation Barbara Willkens Afanager confirmed by Nuclear Oversight Programs & Engineering Standards l **= 8f -,a y l==
l Mwsmest AnecesaEmwpy r Configuration Management.
Configuration Management -
Phased Approach Phased Approach (continued >
- Establishing Configuration Management
- EstablishingConfigurationManagement
~
)t
-restoration of licensing, design and C
rat on rogra operating bases (CMP on each unit)
. programs, processes & procedures
-review of design changes by CMP to have been " linked"10 control ensure LB, DB,08 and plant changes and to maintainlicensing contiguration have not been design andoperating basis compromised
. ownership
-training
-engineering assurance
- ===--,.r
--,, r Page 15
C 4
Configuration Management -
CompletedActivities Phased Approach (continued)
,7,,,,,,,,,,,,,,,yi,,,
- Maintaining Long-Term Configuration
+ Revising and strengthening configuration Management management in programs, processes &
- integrated across functional areas procedures
- Pryms & Eng. Stds. willestablish
-safety evaluations standards
-vendor technical information controls e unit CMgroups willensure
-temporary modifications controls implementation
-non conformance report controls
-implement integrated CM database l narrnoeuwmar annerv V l meneenwherEnerrv H 1
CompletedActivities CompletedActivities
+ Design Control Manual Upgrade
+ internal and Extemal Assessments on
-evolved from a guidance document to a Design and Configuration Control proceduralprocess
-quality assurance audit i
-design / licensing bases considerations
- DCM reflects elements detailedin embedded in design process 10CFR App.B & ANSIN45.2-11(1974)
-requirements for interfacing with other
-MDM Services Corp. strategic overview
- '9'"'*****
-requirements fof formal transmittals to
- DCM benchmarked (Beaver Vaney, Perry.
Nuclear Document Services ViryWa Power, EPR1, NSAC)
-controlof 50.54{f) outputs
- DCM hs mms of M MI programs & existing utilityprograms
, en,v H i-CompletedActivities CompletedActivities
+ Internal and External Assessments
+ initial Assecsment of Existing Data
-engineering self-assessments Bases e calculations, specifications, drawings, equipmentlists, FSAR
- Arnerican Management Systems " quick took" assessment change process, safety evaluations e strengthen configuration control e Millstonein goodposition to implement CMInterface System 4 Engineering A asurance Program Assessments e overv/ data qualityissues
-design change process, safety evaluations, minor mod process
- ,.*- -,- H
- --===, *- H Page 16
a i
Remaining Activities Remaining Activities 1
e implementation of Site Integrated
+ Self-Assessments Configuration Management Policy and
-NCR Process Procedum
-item Equivalency Evaluations e Provide Training on Configuration
-Integrated Design Process Management
+ Development of Performance indicators for Configuration Management Control
- Implementation of Permanent Effectiveness Configuration Management Organizations J
- "FY b**
l Ahrthsest Ah,cds.rens,yy F-NSAB Success Criteria Assessment of Nuclear Oversight Nuclear Safety Assessment
'NSAB confirms that Nuclear Board Ov " 8ht P' d m ' *fctiv' Assessment of Nuclear Oversight s NSAB confirms that unit and I
Steve Scace support organizations address Director, Engineering Programs Nuclear oversight findings in an effective, timely manner i
Ima =,- F-
- a, 4,
p.,,
,, r 9
NSAB Assessment Criteria NSAB Assessment Criteria (cononued)
- Nuclear Oversight audits and reviews are effectively perfM
- Nuclear Oversight is capable of and communicated to the Line integrating observations into effective assessments of Line
- The scope of Oversight activities is performance focused on significant issues and -
mgulatoy mquimunM
- Line organization responses to
- The criteria used to support Nuclear Oversight findings are effective and timely Nuclear Oversight decisions are effective
- a-==.
- - m,,,, g_
Page 17
a a
v NSAB Assessment Criteria The Assessmentincludes (continueef)
- Nuclear Oversight effectively
- An independent Assessment of escalates overdue or ineffective Nuclear Oversight by an expert Line responses to Nuclear extemal team, currently underway Oversight findings (6/19 713)
- Direct NSAB review of selected issues where Nuclear Oversight's and Line's assessments are compared
- aww.urwcnnem,y H
- anomanwen-sevH The Assessment includes NSAB Deliverable and Timing
- Comparison of deficiencies
- Action: NSAB confirms Nuclear identified by the Line, NSAB Oversight's readiness subcommittees, Nuclear Oversight
- Timing: Prior to the start of OSTI and NRC Readiness Assessment
- NSAB confirmation that Nuclear Oversight has effectively
'mplemented its recovery plan
- a=smur =<=,s,y H
- a=womemen-smv H Basis for Violation
- Multiple examples of the failure Security
'*
- a"*' **'*8 "*'d
- Information Notice of Violation & CivilPenaly s y,,,,,,,,,,,,,,,,, q, gg,,,,,
j Frank Rothen control vehicles in the protected Vice President-Nuclear Work Services
- Inadequate Hand-Held Metal Detector search
,smaeursamarms H
- awamurmem=*ms H Page 18
t l
What We Have Done to Date Program Enhancements
- Reduced the number of Safeguard
- 1mplemented Program reposRories Enhancements
- Assigned responsibie custodian for each
- increased Awareness Safeguards repository
+ Increased Management
- Posted signs in vehicles ownership
- Increased Security supervisory oversight
- Security liaisons have been assigned to each unit
- Denial of unescorted access to violators
- -,- H
, - -, _,. r increased Awareness Additional Corrective Action to be Completed
' Posted signs in vehicles
- Vehicle control now part of Plant
- Additional Security Program communications via NU intranet Access Training and pamphlets
- Retraining for Security Officers
- Benchmarking surveys with other
- Sitewide communications of utilities program requirements and
- Security Performance Observation managementexpectations
& Enhancement Program
- --,-, H
+
b Status of Unit 2 Significant items List (SIL)
- ltems on the Unit 2 SIL 48 Millstone Unit 2 Update
- Significant m.ms Not R.guiring Packages 7
p to h NRC fw Rh a
Mady Bowling Unit OfNeer-Mllistone 2
- Rorneining Packages On Schedule 21
, a=*sse -,=vv
- man n.m.,.,, r Page 19
i 6
l l
\\
l l
Significant items List Status of Unit 2 MHistone 2. June 1997 License Amendments
.r....
=c w ew
' Total PTSCRs Required for Start-up 13
~
g
'PTSCRs Submitted to the NRC 6
/
y
- PTSCRs Approved by the NRC 1
' Remaining PTSCRs Submitted by 8/15/97
'No Significant Hazard Considerations
~.~
- a.~.u-e. H
- .-~.- -,,, H 1
License gngen,dment,,Repests Challenges Facing Unit 2
- Operator Training eroer.as..-.
ew
=
s.y.
-common program; implementation l-challenge g*
7 j
/
l'
- Work-Off Curves
\\
I-""
-AWO
.,' ;, ;,' n,,,,,,
-license amendments y., %,,ps
-CMP completion
-modificationimplementation l hath.est-en.,, f
- u-towen-en.,, p Challenges Facing Unit 2 Unit 2 Schedule
' Potential challenges
' Ready for ICAVP June 30,1997
- R.G.1.97
' Physically Ready
- EEQ Documentation.HELB for Restart Nov. 25,1997
'*E*d
' Ready for OSTI Dec.1,1997
- *-,h H
u -,,, H Page 20
l
=
l t
l l
1997 Unit 1 Initiatives l
Millstone Unit 1 Update
- shutdown cooling system Jack McElwain
- diesel system Unit Officer-Millstone 1
- service water system l ""h **=rr H
- m n w s,.,y H 1
1997 Unit 1 Initiatives Unit One Milestones (continued)
' Finalize Outage Schedule
'CMPI Discovery Complete 12m147
' Complete 10CRF50.54(f) Schedule
- Ready for lCAVP 1msme
' Reduce Corrective Action Backlog
' Physically Ready for Restart
- 2sme
' Process Enhancements
- 10 CFR 50.54(f) Submittal vsoms
' Reduce PhysicalWork Backlog
' Ready for OSTI 4m4/es
- ---,- s
- -- -,, r i
Closing Remarks Buzz Carns
- a-==r = 4,-,. H I
Page 21
1 j
indox 1
Key Performance Indicators j
MILLSTONE UNIT 3 KPis l
Paoe Number KPI Title l
A-1...................................
Configuration Management Pian Progress i
A-2...................................
Task Completions Required for Restart j
A-3...................................
Open Condition Reports i
A-4...................................
Condition Report initiation and Evaluation Timeliness A-5...................................
Condition Report Method of Discovery A-6...................................
Open NRC Commitments for Restart 1
A-7...................................
Significant items List A-8......................l............
10CFR50.54(f) Significant items for Restart A-9...................................
Licensee Event Reports l
- - - A-1 0............ T...........~........
License AmendmentRequests--
~
~
{
_A-11.................................
Restart Modifications Awaiting implementation.
A-12.................................
AWOs Required for Restart
)
A-13.................................
A-14.................................
Control Room and Annunciator Deficiencies A-15.................................
Operator Work Arounds 1
A-16.................................
Procedure Revision Backlog i
l MILLSTONE UNIT 2 tTig Pace Number KPl Title A-17.................................
Independent Corrective Action Verification Program Readiness A-18.................................
Configuration Management Plan Progress
}
A-19.................................
Task Completions Required for Restart A-20.................................
Open Condition Reports 3
i A-21.................................
Condition Report Initiation and Evaluation Timeliness i
A-22.................................
Condition Report Method of Discovery i
A-23.................................
Open NRC Commitments for Restart 4
~
A-24.................................
Significant items List i
A-25.................................
10CFR50.54(f) Significant items for Restart A-26.................................
Licensee Event Reports A-27.................................
License Amendment Requests A-28.................................
Restart Modifications Awaiting implementation A-29.................................
AWOs Required for Restart i
A-30.................................
Temporary Modifications A-31.................................
Control Room and Annunciator Deficiacies A-32.................................
Operator Work Arounds A-33.................................
Procedure Revision Backlog i
i t
4 d
Page1
Index
. Key Performance Indicators MILLSTONE UNIT 1 KPis Paae Number KPl Title 3
A-34.................................
Independent Corrective Action Verification Program Readiness A-35.................................
Configuration Management Plan Progress A-36.................................
Task Completions Required for Restart A-37.................................
Open Condition Reports A-38.................................
Condition Report initiation and Evaluation Timeliness A-39.................................
Condition Report Method of Discovery A-40.................................
Open NRC Commitments for Restar+
A-4 1.................... /............ Significant items List
._A-42........................,........
10CFR50.54(f) Significant items for Restsrt (to be developedl A-43.................................
Licensee Event Reports A-44................................. -License Amendment Requests A-45.................................
Restart Modifications Awaiting Implementation A-46.................................
AWOs Required for Restart A-47......-~........................
Temporary Modifications A-48.................................
Control Room and Annunciator Deficiencies A-49.................................
Operator Work Arounds A-50.................................
Procedure Revision Backlog Oversiaht KPls Paae Number KPl Title A-51.................................
Millstone Oversight Recovery Gap Chart A-52.................................
Millstone Oversight AITTS Assignments A-53.................................
Millstone Oversight Recovery Plan Action item Work Off Curve A-54.................................
Status of Oversight Condition Reports, Millstone 1 A-55.................................
Status of Oversight Condition Reports, Millstone 2 A-56.................................
Status of Oversight Condition Reports, Millstone 3 A-57.................................
Millstone Oversight Audit Schedule Adherence A-58.................................
Millstone Oversight Surveillance Schedule Adherence Nuclear Employee Concerns KPls l
l Page Number KPl Title 1
j A-59.................................
Nuclear Employee Concems Program Progress, Millstone A-60.................................
Number of NU and NRC Received Concems, Millstone A-61.................................
Millstone Employee Concems Confidentiality Trend A-62.................................
Millstone Employee Concems Type Trend Page 2
Configuration Menegamant Plan Prograco Millstone 3 - June 1997 Progress:
contiguration Management plan (cup) completion is on track to meet the W13/97 goal.
1 100% -
[
CMP work
{ remainin0 ES of g
i
- 1 l
6/26/97 Good
,. 60% -
f I
40% -
y l Goal: CMP complete 20% -
by - 8/13/97 J
_j...
- o%.
I t
-t t
t I
t l --.
t-
.- I --
t.
k Jan Feb Mar Apr May Jun Jd Aug Sep Oct Nov Dec l
3 CMP Work Romanng f
Raw Dets Jan-97 Feb 97 Mar 97 Apr 97 May-97 Jun 97 Jul-97 Aug-97 Sep-97 Oct 97 Nov 97 Dec-97 CMP work Romanng 0%
78 %
64 %
47%
29%
22%
Work Oft / Goal Definition Definition (cont.)
This indicator measures progress in completing the Note: This KPI was previously Readiness for Configuration Management Plan (CMP). This is the plan by 10CFR50.54(f) Submittal. The NRC revised their which the management of each nuclear plant verifies that 10CFR50.54(f) request for information on 4/16/97. A the design and operation of their plants is consistent wrh specific response with regard to the CMP is no longer what the NRC has approved and all changes and required.
commitments since original licensing are properly reflected in current licensing documents, such as the Final Safety Analysia/ Action Analysis Report (FSAR).
For MP3 this is made up of the:
As of 6/26/97 CMP Punchlist is 82% complete, Group 1 System SSAs/ STAS are 67% complete. This results
Progress towards completion of the work completion (weighted at 75%)
- 2. System Assessments completion (weignted at 25%).
necessary to allow the CMP by 8/13/97 is on track.
These are comprised of System Specifn Assessments (SSAs) for Wave 1 Systems (work Complete) and System Technical Assessments (STAS) for Wave 2 and 3 Systems.
Goal The CMP task comnietion includes CMP Punch Lisi items plus Licensing Commitment Validation, FSAR Change The Unit 3 goalis for the CMP to be complete by Request submittals, Piping & Instrument Diagram Walk B M 7.
Downs, and Design Basis Summary completions.
The STAS orovide: assurance that the CMP identified significant Licensing Basis / Design Bases (LB/DB) issues.
Comments This is accomplished by management technical review of Wave 2 and 3 systems. These systems are the remaining Data through 6/26/97.
Maintenance Rule Group 1 and 2 systems not reviewed for ICAVP.
Data Sourcet G. Closeus x4232l Analysje by G Cloeius x4232lOwnert M H Brothers x4303 Page A 1
Tcck Complctions Raquirod for Rootart Millstone 3 - June 1997 Progress:
This goalis very chattenging; management attention is beIng applied to reduce the Open category and improve the workoff rate of open tasks required for restart.
4000
' Open tasks as of l
3500 6/23/97 l
3000 l
- . -I-
- - ~~
Tasks to be 3 2500 i Good j
completed by j
[
8/13/97
' 2000
'i j
- 5. 1500 Tasks to be Y
completed by
{
9/30/97 1000 s00
=
Ks 0
I Jan Feb Mar Apr May Jun Jul Aug Sep ~~ -Oct.
e Dec I
M 50.54(f) (8/13/97) m Physically Ready /OSTI (9/30/9/)
i
-e-8/13/97 Work Off
-*-9/30/97 Work Off i
Raw Data Jan-97 Feb.97 Mar 97 Apr-97 May-97 Jun 97 Jul-97 Aug-97 Seo-97 Oct 97 Nov.97 Dec 97 50 54(fi (8/11'97) 3059 3076 3489 3753 3650 2972 6/13/97 Work Ott 2547 s49 0
0 0
0 0
Physcally Ready /OSTI (S"Jo/9h 360 9/30/97 Worm Ott 360 360 257 0
0 0
0 Mode Dependent 30 Total Overdue 613 Total Open ( Aestart) 3059 3076 3489 3753 3650 3362 Prer to June all AITTS aasgnments reQured for restart were requred to be corripleted by 8M117 DeRnition AnalyeWAction i
Tha total number of tasks is defined as those requiring closure prior to This indicator includes open items in the Action item e
restart. Automated Work Orders (AWOs) required for restart are not Tracking and Trending System (AITTS), such as NRC included, as they are tracked in a separate indicator. NOTE: the Open Open items, Significant items List issues, and Cond; tion (Undetermined) category are those assignments that are still being Report (CR) corrective actions.
screened to determine whether they are required for restart.
The numbes of taske that must be completed prior to restart continues to decrease. Open assignments in the undetermined category have decreased significantly, the majority of these were not required for startup. Management has developed weekly closure rates for new and existing tasks for each organization.
Increased management attention is being applied to this area. All restart tasks have been designated in AITTS to support one of the following rnilestones:
- 1) 50.54(f) letter-8/13
- 2) Physically Ready for Restart / Ready for OSTI-9/30
- 3) Mode specific issues.
Goel Commente Data through 6/23/97.
These tasks are tracked in Action item Tracking and 3
Trending System (AITTS) and the P2 Schedule.
Automated Work Orders (AWOs) are not included.
Work off curve is based on end of month.
M A Strout x2299l4neve's br M A Strout x2299l Owner-M H Brothers m4303 Date Sourw e a.rrisu m e an eu ew.wieve tst Paoe A-2
. ~..
o Opan Condition Rcporto Millstone 3 - June 1997 Progress: condition Reports requiring corrective action are stillincreasing. Increased Management attention is beIng applied to this area to meet the restart goal.
2750 2500 Open CRs 2250 6/25/97 2000 Good 1750 1500 IOpen CRs >120 Y
2 1250 1000 l
days l
750 500 u
mu o
i I
i i
i i
l l
l i
1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
-tF-CR's Not Closed (Total) M CR's Not Closed (>120 Days)
R ~ w Dets Jan-97 Feb 97 Mar-97 Apr-97 May 97 Jun 97 Jul-97 Aug-97 Sep-97 Oct 97 Nov-97 Dec 97 C"7e Not Closed (Total) 1827 1921 2003 2086 2437 2515 Level 1 141 153 166 176 195 217 Level 2 1686 1768 1837 1910 2242 2298 CR'e Not Closed (>120 Days) 1223 1173 1109 1104 1194 124C Level 1 83 81 74 72 105 127 Level 2 1140 1092 1035 1032 1089 1113 Definition AnalystalAction This indcator depicts the number of condition reports Signrficant attention has been focused on completing the (CRs) which have not had corrective actions implemented evaluation phase of recent and backlogged condition reports.
cs CRs not Closed (Total). The number of these total This has resutted in a large number of corrective actions CRs which are over 120 days old and have not been being identdied and tracked. Efforts are underway to dettred is depicted in the bar graph.
review the identified corrective actions to ensure that they are properfy scheduled and that redundancies are Condition Reports (CRs) are written to document eliminated.
degraded or non-conforming conditions associated with plant systems, structures or components necessary to support the generation of electricity.
Goal Comments The goal is to have all Level I Condition Reports closed Data through &"25,97.
by startup unless they have been reviewed by the Plant Operatons Review Committee (PORC) and approved by a Unit Officer.
De*? Source: AITTS l Analysis by:
S. M Smnh x2277MPl Owner-D. McCracken x0481MP pen. 4 3
....-o....,
Cendition Rcpert initiatian end Evaluntien Timclincoo Millstone 3 - June 1997 Progress: steady Improvement Is being made In meeting goal of completing plant condition report evaluations and identifying appropriate corrective actions within 30 days.
500 450 400 350 Data Through k
250
{
6/25/97 3
3 200 h
h 150 l-f
{_
l_
p 100
-._ 50 g
g g
- . r_ =
_:._ q. __. _ %:.=z:a
.:r. --- :
0 Jan Feb Mar Apr ~ ~ May Jm M
Aug Sep Oct Nov Dec
~
. 5 Total CRs initiated E # Evaluations Completed DCornpleted within 30 days Raw Dets Jan-07 Feb.97 Mar-07 Apr-07 May-07 Jun 97 Jul07 Aug-07 Sep-07 Oct 07 Nov-07 Dec-07 7otal CRs initleted 358 303 284 291 434 190 Level 1 CRs Irvtated 46 24 16 11 23 15 Level 2 and 3 CAs Irvtated 312 273 247 280 411 175 8 Evolustione Completed 337 283 264 282 344 36 Completed within 30 days 79 92 91 155 288 36 Suas Rate 0.22 0.31 0.32 0 53 0 67 NA Definition Analysis / Action This indicator depicts the initiation of Condition Reports (CR) for NOTE: The success rate for May reflects the Unit and the number of evaluations which were not completing 249 of 374 evaluations which are complete (1 within the goal of 30 days.
over 30 days old as of 6/25/97.
The graph shows CR data beginning 1/1/97, and represents the initiation of CRs remains above the 1996 monthly current status /effectrveness of Corrective Action Initiatives.
average. The reason for the decline in early 1997 can be attributed to the completion of major portions of the discovery phases for several recovery projects. Irnprovement has been realized in completing evaluations within 30 days.
Management attention has been focused in this area to enable the unit to complete a goal of having no evaluations over 30 days old by July 5,1997.
Goal Commente Goal is to complete all evaluations and identify appropriate Data through 6/25/97.
corrective actions within 30 days.
Evaluations are considered open if they are either in an open status or a pending review status prior to the approval of the corrective action plan. The latest month's data reflects the status to date.
Dets Source AITTS l Analysis by:
S M Smrlhx2277MPl owner:
D McCracken x0481MP Page A4 B.CRTIME.XLS
Condition Raport Mathod of Diccovory Millstone 3 - June 1997 Progress:
The line organization is continuing to sett-identity issues and the percentage at i
event driven reports is decreasing.
l l
100 i
e0 t Data Through 80 l
Ml 70 0
Oct how Dec Jan Feb Mar Apr May Jun Jul Aug sep
~
isSELF IDENTIFIED WINTERNAL OVERSIGHT DExTERNAL OVERSIGHT DEVENT ROW Date
~
SE' 96_Jg126__,ggG6,,4.gg7 7 yyy Number et CR s e
w q
Unit iden0#ed 103 122 169 297 '4 internal Oversght 22 13 48 30 25
~29 -
27 E xternal Overwant 16 11 3
4 2
0 1
.?.51s' T 0 Event 36 23 20 20 8
1 8
2
-l 1
Total ldertified 177 169 240 357 303 282 290 432 l 191 Dept Sett ID Retlos l
i M mtenance 0 42 0.35 0 33 0 53 0 47 0 45 0 30 0 15 l 0 to Operattoris 0 56 0 68 0 48 0 57 0 60 0 54 0 49 02e l 0 53 worw pianning 0 29 0 as 0 19 0.27 0.36 0 16 0 77 025 l 0 60 Desgn Eng 0 35 0 39 0.30 0 43 0 49 0 15 0.31 0 32 l 0 29 System Eng 0 27 0 38 0.21 0 26 0 42 0.34 0 30 0 44 l 0.17 ucensng o 42 0 40 0 40 N/A 0 00 N/A N/A N/A l 0.09 Dennition AnalysisfAction This indicator represents the percentage of CR's identified by Self identification of issues by Unit 3 as a whole has each of the barriers. CR's are categorized into the following improved during the first part of the year. One factor four areas:
influenong this was the large number of CRs initiated by the discovery phase of the d!fferent recovery plans.
= Event Driven Self-revea!ing, an event occurs.
- External Oversight Identified by NRC. JUMA, INPO, etc.
Increased emphasis on self assessment will help to
- Internal Oversight identified by QAS, PORC, ISEG, increase self-identification ratios within specific NSAB, etc.
departments.
- Self Supervisor observation, document review, Self-checking, independent / dual verification, etc.
The department self identification ratios are a measure of the Individual department's rate of identifying their own issues.
Dept Self 10 ratio =
number of CR's ID'd /assioned to that deoartment number of CR's assigned to that department l
Goal Commente Data through 6/25/97.
Defe Source ArTTS l Analysis byt 5 M SrNth x2277MP l Owner D McCracken x0481MP p., a.:
o er. ria y, e
Opan NRC Commitmonto for Rootart Millstone 3 - June 1997 Progress:
While the total number of open commitments to the NRC remains high, we have reduced the number that are overdue with a goal of closing commitments on their due dates.
35o f Data through 3g l
6G547 l
250 f Good i
I 2*
lY j
)
150 I
i 100 J _
m..
0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec i
M Open items MOverdue items --e-Work Off/ Goat Raw Dets 3
Jan-97 Feb-97 Mar-97 Apr 97 May 97 Jun 97 Jul-97 Au997 Sep 97 Oct 97 Nov.97 Dec.97 Open items 243 237 224 284 316 221 Overdue items 0
3 23 10 1
1 Work Off/ Goal 270 316 147 75 26 6
3 0
0 i
Definition Analysle/ Action An NRC commitment is:
As of 6/25/97,129 items have been closed this month.
However, new commitments requiring closure prior to
- wntten statement that is docketed, restart have been added. There is one overdue NRC
- verbal statement to take a specific action, agreed item.
to by an officer, s
a requirement to take an action imposed by the NRC.
To continue to focus management attention in this area, y
the overdue NRC commitments and a 30 day look The commitments counted here are those that need ahead are included in the Unit 3 daily report.
1 final closure with the NRC prior to restart of the unit.
Goal Comments NRC coinmitments closed on due dates prescribed Data through 6/25/97.
and all closed prior to restart Work Off/Goalis for end of month.
Dels Source:
H. Kross x6656l Analysis by-D Srnsth x5840l owner:
D. Hicks x0326 BARCcou xLr.-
Page A-6 ece
Significant Itamo Liot l
Millstone 3 - June 1997 Progress: closum ofitems on the Significant items List is a challenge for the B/1W97 goal but achievable for the 9M0/97 goal.
200 180 I Data through I 160 1
6/25/97 l
l 140 l
a 12o Good 100 l
l l
Goal: 4 items 80 y
I remaining by 8/13/97 :
60
! ! Goal: allitems !
40 I
i complete by j
20 y
9/30/97
/
~
~
le Mar ~
Jan Apr May Jun Jul Aug Sp Oct Nov Dec 6 Total Remaining -e-Work Oft / Goal.
, o.
n M97* "W "N
apr wi "M
.iuP y r aug yr Opp-y/
Uw w/
NQV W(
UeC WT Total Romaning 59 55 43 189 173 136 Work Ott/ Goat 55 45 191 177 121 74 4
o Definition Analysis! Action items on the Significant items List include those The Significant items list was revised to include the Adverse Condition Reports (ACRs), Notices of items from the NRCs Restart Assessment Plan issued Violation, Unresolved items, Escalated Enforcement on 3/24/97 which is reflected in the sharp increase in items, Licensee Event Reports, and programmatic April. A new work off curve was developed to reflect concerns chosen by the NRC which require closure the completion schedule provided to the NRC on prior to start up.
4/29/97.
The unit is not delivering " designated" closure packages on schedule. To date numerous closure packages have been, or are anticipated to be, rescheduled via OSCRs, thus increasing the workload on the end of the project. A total of 24 packages possible for closure have been targeted by the Project Manager in order to recover and get the program back on track.
Goal Comments Goal: 4 items remaining by 8/13/97 Data through 6/25/97.
Allitems closed by 9/30/97 A total of 205 closure packages have been requested by the NRC to date through revisions of the Readiness Assessment Plan (RAP) issued on 3/24/97.
Dats Source: J. Gionet x55oSMP [Analysie by:
J. Gonet x5505MP l owner: D. Smith x5840MP Page A 7 B_SIL.XLS
10CFR50e54(f) Significent itomo for Roctort Millstone 3 - May 1997 Progress: This is a newIndicator, progress willbe reported in the future.
1400 Data through 1200 5/31/97 1000 800 cr l
sn 400 r..
.m,_=
- =. - - - - - - - - - - - - - - - - -
.=
1 0
1 I
I 1
f I
i
~
l May Jun Jul Aug Sep Oct Nov Dec tytt#PtNtymeweseH=stweemmenemmeesotMrtroegeWfecerefttNitf==uP= Worrorr uoal '
Raw Data May-97 Jun-97 Jul 97 Aug 97 Sep-97 Oct 97 Nov 97 Dec 97 Open Sign #carW hems 686 Closed Signdcant Mems 483 Work off Goal 686 412 137 0
Total Signdcant hems 1169 Deferred Rems
'8052 Defin} tion Analysis / Action Significant items for Restart are those items being reported This is a new indicator, analysis will be provided as data to the NRC in accordance with the 10CFR50.54(f) request accumulates.
of April 16,1997.
Goal Comments All significant stems for restart closed by August 13,1997.
Data through 5/31/96 J. Z. LaPlante x 3269l Analysis by:
J. 2. LaPlanto x 3268l Owner-once socros J. Z. LaPtante x 3269 Peos A-8
l Liconcee Evont Reperto Millstone 3 - June 1997 Progress:
Licensee Event Reports made to the NRC are trending down, reflecting that the discovery effort is concluding.
20 18 16 14 E 12 Good d
i to g
a I8 y
i 6
i Data through l 4 '..
r
._6/23/97
_m 2
x me, Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec CEPfrNCERFHf5f0 ticar =W=fMOUlff7Stindard '
Raw Dets Jan-97 Feb 97 Mar 97 Apr 97 May-97 Jun-97 Jub97 Aug-97 Sep-97 Oct-97 Nov.97 Gec.97 LERs Recent 0
2 1
1 0
0 LERa Hatoncal 3
11 9
3 3
2 LERs-YTD 3
16 26 30 33 35 Industry Standard 1
1 1
1 1
1 1
1 1
1 1
1 Dennition AnalyslWAction Ucensee Event Reports (LERs):
There have been two LER's submitted to date in June.
. are reports made to the NRC pursuant to LER 97 031 'RHR Valve Low Pressure Open 10CFR50.73 Permissive Bistable Setting Set Non-Conservatively'
- are defined as historicalif the event did not occur within the last 12 months LER 97-032 ' Containment Drain Sump Tirners Not
+ are reported in the month of the submittal to the NRC Calibrated Every 18 Months as Required by TS SR 4.4.6.1.b' 0001 Comments Data through 6r23/97.
i Dois Source:
R. Flanagan x5817l Ans/ysis by:
R Flanagan x5317l0wner:
r). Srnith x5840 e_t tm xttmo.weianna Paos A 9 e e.,
s l
s Lic3nso Amandmant Roquasts Millstone 3 - June 1997 Progress:
The June 30 goal for submittal of a!! License Amendment Requests needing approvalprior to restart will not be met.
28 l
l 24 l
20
!LAR submitta: data through 6/25/97 f
gto o
i I"
Goal: All l
l submitted by e
6/30/97 l
l
~
_- -.. = y v---
m 0
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec certece suomettea ammercArtrsoomrtreNwereotr/ coal R*w Data Jan-97 Feb.97 Mar 97 Apr 97 May 97 Jun 97 Jub97 Aug-97 sao.97 Oct-97 Nov-07 Dec 97 LARs to be submmed 19 24 23 17 10 6
LARs submitted 0
0 0
7 6
2 work Off/ Goal 19 24 23 17 8
0 Definition AnalysisfAction License Amendment Requests (LARs) are changes to The resolution of engineering issues is delaying the Technical Specifications or other license changes that submittal of LARs. Daily review meetings are being are required for restart, and that must be submitted to conducted to monitor status of activities and expedite the NRC for approval.
completion of the LARs. Additionalongoing engineering review may identify additional Technical Specifications that require revision.
Also, communications have been ongoing with the NRC staff to insure that the delays in filing the amendment requests do not significant!y threaten the NRCs ability to support our restart schedule.
Goal Comments All LARs requiring NRC review submitted by
- Data through 6f25/97 June 30,1997.
- Two Proposed Amendment Requests are in final review.
RSS Pump Start Times - scope TBD
+ Three are in Engineering review.
- One is in Plant Operations Review Committee (PORC) review.
I Ds1 Source:
G Papanc x2069l Analysis by:
D. smah x5840l owner:
O. Smah x5840 s.uAn m w e Paos A 10
Rcctcrt Modifiestieno Awaiting implomontation Millstone 3 - June 1997 Progress:
completing design modifications required for restart by the 9/30/97 goal requires increased management attention.
180 160 -
140 -
' Restart Mod U0-data through Good 100-l 6/24/97 vf 80 -
Y 60 -
4 f
Goat All
.A modifications
[
- _ do l
- complete 9/30/97 '
i
/
f O
e
.lan Fah Mar Ane uow he h,i 4, m con n,.e m..
rw
~~'
~ EMods Released to Feekt EMods Awaiting engineerk !
Raw Date Jan-97 Fe497 Mar 97 Apr 97 May 97 Jun-97 Jul-97 Aug 97 sep 97 Oct 97 Nov 97 Mods Released to Feld 20 29 20 25 Mods Awading Engineenng 83 81 78 72 TotalMods Aernaining 173 149 103 110 98 97 Work Off/ Goal Definition AnalyelWAction The total number of outstanding modifications As of 6/24/97, the total number of design modifications identified as required prior to restart that have not is 253. Of these,97 are required to be implemented been tumed over to Operations, prior to restart. This month:
- 5 modifications were released to the field
- 4 modifications were completed
- 3 new modifications were added Continued management attention is being applied to the proper screening, design engineering, material procurement, and construction of modifications required / desired for restart to ensure those required for restart are property identr.ied and scheduled for implementation.
Goal Commente All start up related design modifications completed by Data through 6/24/97 9/30/97.
Dets Sourcer W. Crandall x4790 l Analysis by:
S M%t15644l owner:
O Hicks x0326 Paoe A 11
AWOs Rcquired for Rostart Millstone 3 - June 1997
}
PTOgreSS: The generation and completion of corrective maintenance work orders required for restart is lower than expected and currently does not support the restart timeline.
2250 20no -
- C 1;i f
I Work Order 1750 -
data through L
1500 -
2
]
O
[
d
.L 6/23/97 GO0d m
1250 -
w 1000 -
O k 750 -
y 500 -
R M
M
-M M
M - --;
~
}~ - ;---
~-
=-
=-
250 -
O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MRAWO ~ Other AWO -+-MR AWO Goal -e-Total AWO Goal Raw Dets Jan-97 Feb-97 Mar 9'1 Apr 97 May 97 Jun-97 Jul-97 Aug-97 Sep 97 Oct 97 Nov-97 Dec 97 Total AWO Backlog 1637 2123 2170 2069 2006 1950 MR AWO Goal 350 350 350 350 350 350 350 3W 350 350 350 350 Total AWO Goal 500 500 500 500 500 500 500 500 500 500 500 500 MRAWO 12J3 1400 1409 1354 1336 1365 Other AWO 4 34 723 761 715 670 585 DeMn} tion AnalysisfAction
- Automated Work Order (AWO) Backlog is the total The number of AWOs generated and completed have number of corrective maintenance / condition driven (non-been less than expected. Atthough the backlog recurring) AWOs required or desired fcr restart.
decreased, the net reduction this month does not support meeting the goal at start up. Approximately The total does rwiinclude: AviC; awaiting retest,in 300 AWOs will be added to the backlog for work on closure, work planned for futura outages, AWOs that Motor Operated Valves. In order to meet start up support field work already included in bacidog (i.e.
goals, the net reduction in backlog needs to be insulation, staging, etc.) and non-power block AWOs.
approximately 400 AWOs per month.
Safety significant systems are defined as Maintenance Rule risk and/or safety significant systems.
Goel Comments Goal < 500 total AWOs at start up, less than 350 Data through 6/23/97, Maintenance Rule risk and/or safety significant system AWOs at start up, and no AWOs that are required for restart at start up.
Dets Source:
R Rothgeb x5241l Anerysis by-R.Rothgeb x5241l owner: J. R. Beckrnan x5361 e.weno nsawc,*mmune Page A 12 m
Tomparary Modificatione l
Millstone 3 - June 1997 Progress:
Temporary Modifica!!ans are being reduced (goalis less than 15).
J j
60 i
Temp Mod l l
data through !
j
[
6/25/97 I
J40-G 1
D i
l l
l Goal 55l l
1 20-3 j) __
_ R J.
..a O
t i
I I
I I
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec M Temp Mods M Outage Support -e-Work-Off/ Goal Goal <15 I
Row Data i
Jan-97 Feb.97 ' Mar.97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 sep-97 Oct.97 Nov.97 Dec.97 I
Temp Mods 48 45 46 38 34 30 Outage Support 5
6 6
9 8
8 Total installed 53 51 52 47 42 38 i
Work Off/ Goal) 52 52 51 44 35 37 30 25 16 Definition AnalyslWAction A temporary modificoon is a modification to plant The work down curve has been revised to reflect the design that is short term in nature and not part of the latest information conceming plant conditions to allow permanent plant design change process, removal of temp. mods. required to support outage activities and the schedule for implementing design i
Temporary Modifications to permanent plant design are packages to make temp. mods permanent, in addition, categorized here two ways: ' Outage Support' are at this time,13 temp. mods. are scheduled to remain those directly tied to physical work to plant equipment post-startup.
in an outage condrtion, and ' Temp Mods' are all in addition to the temp. mods. requiring design support others.
to remove, other temp mods. require implementation of design modifications already designed. Management has deferred implementing those packages until after design modifications, required to support plant startup, are complete. The workdown curve will need to be reanalyzed to reflect this decision.
4 Eight temporary modifications are required to support outage activities.
Goal Comments
<15 TMs installed at startup Data through 6/25/97 4
None greater than one cycle without Unit Officer cpproval.
Dets Socreet S. Stricker x5409l Analysis by:
S. Stricker x5409l owner:
G. Swider x5381 s.Tumoo n.1 _a=~-
Pan. a.11
Control Room and Annunciator Daficiencloc Millstone 3 - June 1997 Progress:
current work schedule does not support goal of fewer than 10 Items by June 30,1997.
35 IDeficiency data' So through
(
6/22/97 25 I
Good
.i 20 Goal: <10 by l l
J d
June 30,1997 l l
l 15
/
}
10
_ _.- 5
! ~;
~
0
~
~.-
Jan Feb Mar Apr May Jun Jul Aug Sep ^ Oct -- Nov Dec M Total Deficiencies Work Off/ Goal j
Raw Dets Jan-97 Feb-97 Mar 97 Apr 97 May 97 Jun-97 Jr 1.J7 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Total Defcnnetes 21 18 19 23 24 16 Woth Oft / Goal 17 15 14 12 10 10 to 10 10 10 to Definklon Analysis / Action Control room instruments, recorders, indicators, and Of the 16 remaining items,4 are scheduled to work annunciators that function improperly that could affect prior to 6/30/97.
the abihty of the operators to monitor and control plant conditions.
This will not achieve the current goal of less than 10 items by June 30,1997.
1 Goals Comnents Fewer than 10 at startup.
Data through 6/22/97 Projected work off curve is based on less than 10 None greater than 6 months old without Unit Officer items by 6/30/97, approval.
Work that is complete awaiting retest based on plant conditions will not be included in the total.
Date Source: L. Palone x4737 l Analysis by: D Beachy x4980 l owner: J. R. Beckrnan x5361 Page A 14
Oporctor Work Arounds Millstone 3 - June 1997 Progress:
A workoff plan has been developed to support the goalof s 10.
45 l
40 f
hr u h 2/9 0
Good 4 25 y
20 I
15
'0 J
._ - _. ~ - }
=
?M. -
T. _-
= -.
5 0
l l
l l
l l
l l
l l
l l
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec M Operator Work Arounds -e-Work Off/ Goal R~w Dats Jan 97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Seo 97 Oct 97 Nov 97 Dec-97 Operator Work Arounds 21 24 23 21 21 21 Work OftCoal 20 17 15 13 10 10 10 10 i
Definition Analysia/ Action Operator Work Arounds are conditions requiring an operator Of the 12 Work Arounds scheduled to be completed to work with equipment in a manner other than original design prior to plant startup,3 are complete awaiting plant which could:
conditions to support post maintenance testing. These are still reflected in the total count, and are shown on the
- 1. Potentialty impact safe operation during a plant transient, workoff curve to be fully operational by 9/30, but will
- 2. Potentially impose significant burden during normal require NOP/NOT (Normal Operating Pressure / Normal operation, Operating Temperature) to be fully tested.
- 3. Create nuisance condition due to recurring equipment deficiency,
- 4. Distract an operator from noticing a recurring condition.
Goal Commente Goal <10 Data through 6/22/97 i
None greater than 6 months olo without Unit Officer Work off curve reflects end of month goal.
approval.
Da7 Source:
L Palone x4737 l Analysis by:
L Palone x4737 l Owner:
B. Pinkowitz x4203 l
l eJMAND XuWaturecomme Pa9e A 15 wwo 1
e Prec3duro Rovicion Bccklog Millstone 3 - June 1997 Progress:
Procedure revision complellon by the 8/13)97 goalis being challenged by the unavailability of Licensed Operator review resources.
d 300 250
! Data through l l
6/25/97 j
200 I
. Good 150 lY p
Goal; coniplete i
100 corrective actions l l
,by 8/13/97 l
O h
h
/u=:_ u =E 0
Jan Feb Mar Apr kby Jun Jul Aug Sep Oct Nov Dec
' M Restart Reg'd. Proc. Rev. M PUP Procedures Restart Reg'd. Work Off/ Goal -*--PUP Work Off/ Goal Taw Data Jan-97 Feb-97 Mar 97 Apr 97 May 97 Jun-97 Jul.07 Aug 97 Sep-97 Oct 97 Nov 97 Dec 97
.i Total Remaining 349 309 288 244 218 164 Restart Reg'd. Proc.
Rev.
251 213 198 162 143 98 PUP Procedures 98 96 90 82 75 66 Restart Req'd. Work Off/ Goal 240
- 08 169 131 tot 70 36 0
PUP Work Off/ Goal 0
S4 78 59 43 27 8
0 l
Definition AnalyslWAction I
Procedure Revision Backlog is the total number of new For non-PUP procedures, individual feedback items will procedures or procedure revisions required or desired for be done as part of the procedure upgrade where restart.
applicable. This will minimize the number of times the Millstone Procedure Upgrade Project (PUP)(Phase Ill).
procedure must be modified, reviewed, and approved.
Upgrade the Technical Procedures at Millstone Station to a Revisions are in progress.
Standardized Writer's Guide and Verification and Validation (V&V) Process. The goal of PUP is to improve Operations is working primarily system operating the technical quality and usability (human factors) of procedures in order to complete PUP. These procedures; this will reduce human errors and enhance procedures include the system operating instructions plant reliability by supporting quality of work, and valve /electricalline ups.
l Comments The biggest barrier to completion of PUP for Data through 6/25/97 Operations is Licensed Operator review support (independent review, validation). An additional Work off curve is based on 100% complete by 8/13/97 resource from the Station Procedure Group is now being used to put the remaining Operations procedures in the upgrade format so that the procedure is ready for Goal operator review. Procedure reviews and the number of procedure revisions started have increased.
A!! open items have been reviewed and proper corrective actions are completed prior to 8/13/97.
Date Source:
Departmenta l Analysis by:
T K@erman x5421l0wner-B. Pinkowitz/J R Beckman Page A.16
Indopandant Correctivo Action Vorification Program Readinoss Millstone 2 - June 1997 Progress:
scA VP willbe ready to start on June 30,1997 4
1 100 %
l i
80%
60*4 Good j Goal: Ready for g
ICAVP 6/30/97 i l
0%
1 l
l l
u I
I I
I I
I Jan Feb Mar Ar,r May Jun Jul Aug Sep Oct Nov Dec MICAVP Remaining --eH Work Off/ Goal :
4 Raw Dats l
Jan-97 Feb-97 Mar 97 Aor-97 May 97 Jun-97 Jul-97 Aug-97 Sep 97 Oct-97 Nov-97 Dec 97 j
ICAVP Remaining 100 %
92*/.
82 %
65%
38 %
0%
Work Ofl' Goat 100 %
90 %
70%
45%
20%
0%
l Definition Analysle/ Action l
This indicator measures progress in completing the The 15 system reviews are complete and the letter has system reviews necessary prior to initiation of been sent to the NRC indicating we are ready for ind: pendent Verification of Corrective Actions Program ICAVP.
(ICAVP). System review involves evaluation of design j
and license basis documents for system and system components for incorporation into procedures.
}
n i
(
l Goel Comments Complete 15 system reviews prior to the ready for Graph reflects data through 6/20/97.
ICAVP date of June 30,1997, including an independent rzview by the Nuclear Oversight Group.
i l
Daw Source: W. Sawatrky x0016 lAnalysk by: W. Sawatrky x0016 l Owner: M. Ahem x5426 Page A 17
Configuration Managament Plan Progress Millstone 2 - June 1997 Progress: CMP output doubled in June and met the " Ready for ICA VP" milestone.
Though challenged, the project expects to meet scheduled completion.
100%
l Data through l-60%
6/20W Good 140%
!1 a
' Goal: CMP I
__j complete byi _.
9/15/97 20%
Y 0%
l i
i t
l l
t l -
l Jan Feb Mar Apr May Jun Jul Aug Sep E CMP completion status Raw Dats Jan-97 Feb.97 Mar 97 Aor 97 May-97 Jun-97 Jul-97 Aug 97 Sep-97 Oct-97 Nov 97 Dec-97 CMP c.eiv@,
status 100%
90%
93%
86%
79%
62%
Definition AnalysisfAction This indicator measures progress in completing the The project started slowly as structure was put into Configuration Management Plan (CMP). This is the plan place and what was really needed underwent more by which the management of each nuclear plant vertfies precise definition, that the design and operation of their plants is consistent Output doubled in June es process improvements took with what the NRC has approved and all changes and hold which allowed the ' Ready for ICAVP' milestone to commitments since original licensing are property be met.
reflected in current licensing documents, such as the Final An additional 50% improvement in output is needed.
Safety Analysis Report (FSAR). CMP complete is While this is a challenge, the project expects to achieve defined as System Review Packages (SRPs) complete the goal as additional process improvements are end approved for all Phase 1 and 2 Systems, along with implemented.
graded reviews completed and documented for all Unit 2 programs.
Note: The title of this indicator was changed from 10CFR50.54(f) Readiness for Submittal due to the revised 10CFR50.54(f) request from the NRC dated April 16,1997.
Gos!
Comments The Unit 2 goalis for CMP discovery to be complete by Data through 6/20/97.
9/15/97.
4 Data Source.*
W. Sawatzky x0016l,4netysis by-W. Sawatzky x0016l Owner:
M Ahem x5426 Page A 18
Tack Complations Required for Startup Millstone 2 - June 1997 progress:
As discovery continues, the tasks required for startup continue to increase.
4000 32 i Data through l
{
~
3000 l
Good 2500
!y 2
I#000 1500 i
. m-
~
500
_,,,u_
0 l
1 1
I I
I I
I I
I I E I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 15 Open (Restart) B Open (Undetermined)
RawData Jan-97 Feb-97 Mar-97 Apr 97 May 97 Jun 97 Jul-97 Aug-97 Sep-97 Oct-97 Nov 97 Dec-97 Open (Restart) 1655 1778 1866 2502 2538 3366 4en (Undeterrnined) 135 165 161 Work-off Goal o
Definition Analysis! Action The total number of tasks is defined as those requiring The increase in tasks required for restart is primarily closure prior to restart. Items in PMMS (AWOs) are not due to the generation of AITTS assignments to track included. Undetermined are those assignments in UlRs.
AITTS that have not been screened as to required for restart.
Management is advised of the increase in outage scope. Action will be taken to improve scope control for restart activities.
i Goal Comments The goal is to have all required tasks complete prior to Data through &20/97
- ntering the applicable mode restraints.
Data source:
G. L. Ahx x2200l Analysis by:
S.V. Heard x5600l Owner:
S.V. Heard x5600 Page A 19
Open Condition Reports Millstone 2 - June 1997 Progress: condition Report Initiations have increased during May and June. The expected number of CRs open >120 days will be approximately 800 by the end of June.
2000 l
1600
! Total Open CRs as of l
Good E
4 l
{ggg i CRs open >120 days j j
3 o
g.._
._2 J_ _as of 6/20/97 3 ----
sm i
0 Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov oec M CRs Open >120 Days - +-Total Open CRs RawDats Jan 97 feb-97 Mar 97 Apr 97 May.97 Jun-97 Jul97 Aug-97 sep 97 Oct 97 Nov 97 oec-97 Total Open C As 1335 1300 1255 1215 1282 1465
{
CRs Open >120 Days 738 787 735 810 722 792 De!)nttion Analysis / Action i
This indicator depicts the total number of open condition The condition report initiation rate has increased from rcports (CRs) and the number of CRs that have been an average of 170' month for the first 4 months of 1997 i
open greater than 120 days.
to >220 Lnitiated in May and almost 300 in June.
{
Condition Reports (CRs) are used to document an The CAD has a population of about 200 CRs that are adverse, discrepant, or other condition that could impact indicated as having all corrective actions complete and ptnt safety and operation, and equipment operability.
require only final review. Therefore, the actual Foitowing characterization of a condition, the Corrective progress is likely to be much better than the indicator is Action Program provides the process to determine the currently indicating. The condition report backlog is r:ason(s) for the condition and to establish appropriate due to a shortage of resources in the CAD.
l corrective actions. From any given CR, a number of corrective action assignments can be generated. The We expect to miss our goal of less than 550 CRs open Corrective Action Program also provides a mechanism greater than 120 days by the end of June. The actual for evaluating adverse conditions and their causes to number will be around 800.
identify and address precursors to problems to minimize occur 7ence of significant problems.
The 120 day criterion was selected based upon industry benchmarks for resolution of open items.
Goni Comments LCss than 550 CRs open greater than 120 days at the Cnd of the second quarter, Dets Source:
G L. Akx x2200 l Analysis by:
- s. V. Heard x5600 l Owner:
S. V. Heard x5600 Paos A 20
e Condition Roport initiction end Evolustion Timalinoss Millstone 2 - June 1997 Progress:
The 11ne departments continue to reduce the number at cas open >30 days, the Corrective Action Department is not keeping pace with the Increasedinput.
200 I
150 i
Data through g 100 4
I f
6/2W97 u
f 2
===*
- - - - ~ -
50 4
g 7
f{
p j
+
t f1 f
i i
li-t Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 5 Total CR:,Indiated ETotal Now Complete OCcmpleted witnin 30 Oays Raw Dets Jan-97 Feb-97 Mar 97 Apr 97 May 97 Jun-97 Jul-97 Aug-97 sep-97 Oct 97 Nov 97 Dec47 Total CRs Indiated 181 162 156 158 197 108 Level 1 CRs indsated 7
7 7
9 9
4 Level 2 CRa inniated 174 155 149 149 188 104 Completed wahin 30 days 31 53 36 25 42 3
Total Now Complete 143 111 71 71 45 3
success Rate 17.1%
32 7%
231%
158%
264%
NA Definition Analyals/ Action This indicator depicts the initiation of Condition Reports NOTE: May data reflect that 45 CRs have been (CRs) for the Unit and the number of evaluations which were completed to date. The following breakdown shows completed within the goal of 30 days. The center bar shows the distribution of CRs in open (investigation phase) the number of CRs for which the investigations have been and P2 (in CAD for review) status:
completed to date.
Jan 3 open / 35 CAD The graph shows CR data beginning 1/1/97, and represents Feb - 10 open / 48 CAD the current status /effectheness of Corrective Action Mar-5 open / 80 CAD initiatives.
Apr-3 open / 96 CAD May-77 open / 75 CAD Jun - 96 open / 9 CAD 1
Most CRs in P2 status have corrective action assignments being tracked in AITTS but require review for administrative completeness.
Goal Comments
. Goal is to complete all evaluations and identify appropriate Evaluations are considered open if they are erther corrective actions within 30 days.
In an open status or a pending review status prior
^
to the approval of the corrective action plan. The latest month's data reflect the status to date.
Dets Source:
G L. AAx x2200l Analysis by:
- s. V. Heard x5600l Owner:
s V. Heard x5600 Page A 21
4 Condition Report Method of Discovery i
Millstone 2 - June 1997 Progress:
Externalidentification of condition reports remains low.
100 Data through 80 6/20/97
/
60 I
g 40 j
gc t
r1, l'1,
~~
~
O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
,5 Self Identified E Intemal Oversight D Extemal Oversight D Event RawDats Jan 97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul 97 Au9-97 Sep-97 Oct-97 Nov-97 Dec 97 i
Self identified 128 122 128 137 174 94 Internal Oversight 22 23 14 20 32 6
External Oversight 7
5 5
0 2
2 Event 16 10 7
7 10 6
173 160 154 164 218 108 Definition AnalysisfAction This indicator represents the percentage of CRs A substantial number of condition reports continue to identified by cach of the barriers. CRs are categorized be self identified with two extemal oversight CRs into the following foiir areas:
identified in June. Event driven CRs remain low.
Event Crtve,'.
Self-revealing, an event occurs.
External Oversight - Identified by NRC, JUMA, INPO, etc.
Internal Oversight Identified by QAS, PORC, ISEG, NSAB, etc.
Self Identified - Supervisor observation, document review, Self-checking, independent / dual verification, etc.
Goni Comments Data Source:
G. L. Alix x2200l Analys/s by:
S. V. Heard x 5600l Owner:
S,V.Haard x5600 Paoe A 22
Opon NRC Commitmanto for Rostart Millstone 2 - June 1997 Progress:
No items have been overdue to the NRC this year. Closure ofitems is
~
on track for completion in September.
150 i
Data through
-..lw.
__lI_I__
n MG'97 1
100 l
M f
75 I
i U 50 l
l
~n n-0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec EOpen items WOverdue items RawDats Jan-97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul-97 Au9-97 Sep-97 Oct 97 Nov.97 Dec-97 Open items 117 103 91 109 109 89 Overdue noms 0
0 0
0 0
0 Definition AnalysisfAction An NRC Commitment is:
These commi'ments consist of: URis, IFis, LERs, Violations, and Docketed correspondence. The
- Any written statement that is docketed.
decrease is due to closure of commitments related to e Any verbal statement to take a specific action, docketed correspondence.
agreed to by an officer.
- Any requirement to take an action imposed by URis
- 12 the NRC.
IFis 5
LERs 31 The commitments counted here are those that need NOVs 6
final closure with the NRC prior to restart of the unit.
Doc corr-35 Total 89 Goal Comments NRC commitments closed on due dates prescribed Data through 6/20/97 tnd all closed prior to restart.
l I
i Data Source: D. W. Perkins x 4604 l Analysis by:
D.W. Perkins x46o4l Owner:
R. Joshi x 2080 Page A-23
e l
Significant items List l
Millstone 2 - June 1997 1
Progress:
closure ofitems on the Significant items List are on track for delivery to the NRC by 8/15/97.
So 40
! Data through l'
l l
6/2047
,, 30
! Good 7
j Y
i.
l Goal: allitems 7h
/
M
- to NRC by f 8/15/97 10
_m m
_a.
y =__
0 I
I i
i I
I I
{
Mar Apr May Jun Jul Aug Sep M Total Remaining Work Off/ Goal Raw Data Mar-97 Apr 97 May-97 Jun-97 Jul 97 Aug 97 Sep-97 Total Remaining 48 45 29 23 Work Off/ Goal 48 45 38 33 27 0
Definition AnalysisfAction items on the Significant items Ust include those items Closure packages for issues related to 20 SILs have (48) chosen by the NRC which require closure prior to been submitted to the NRC for review.
start up. Of the 48 SILs,41 require closure packages to be submitted to the NRC. In May, the NRC determined that 7 SILs did not require closure packages. The work off/goalline in the graph above has been revised as of May to reflect the 41 SILs requiring closure packages.
Goal Comments i
Goal: All closure packages to NRC by 8/15/97.
Data through 6/20/97 r
l i
i Data Source:
J. Rosetar x6411l Analysis by:
J. Rosetar x6411l Owner-R Joshix2080 Page A-24
e 10CFR50e54(f) Significant Itomo for Rostart Millstone 2 - June 1997 Progress:
This is a new Indicator, progress will be reported as data accumulate 1400 1200 1000 l
Good
,a 800 C
400
- a. = -
n.
200 m
0 I
t I
i l
May Jun Jul Aug Sep Oct 3 Open Significant items E Closed Significant items Raw Data May 97 Jun-97 Jul-97 Aug 97 Sep-97 Oct-97 Open Senificant items 601 j
Closed Signifcant items 709 Total Signifcant itoms 1310 Deferred items 346 Definition Analysis! Action Significant items for Restart are those items being This is a new indicator, analysis will be provided as r: ported to the NRC in accordance with the data accumulate, 10CFR50.54(f) request of April 16,1997.
Goal Comments All significant items for restart closed by September 30, Data through 5/31/97 1997.
Deta Source:
J. Z. LAPlanto x 3269l Analysis by:
J. Z. LaPlanto x 3269l owner:
J. Z. LaPlanto x 3269 Page A 25
Liconoco Evont Reports Millstone 2 - June 1997 Progress:
Historical License Event Reports made to the NRC should have peaked l
In May with the completion of Phase 1 & 2 system discovery.
15 i
4
, 10 i
f I
6 t
_a i
1 1
i j
l 5
., ~ __ _
j._. Data through ___t m
- w 6/20/97 (no LERs) '
i f
b
-7
{
f 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ELERs-Recent ELERs-HistoricaT Raw Date Jan 97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul-97 Aug 97 Sep 97 Oct-97 Nov-97 Dec 97 LERs Recent 0
1 0
0 0
0 LERs-Histoncal 0
3 2
3 12 0
LERa-YTD 0
4 6
9 21 21 Definition Analyels/ Action Licensee Event Reports (LERs) are reports made Through June '97, there have been 21 Reportable to the NRC pursuant to 10CFR50.73.
Events. There were no LERs submitted during the month of June. Corrective Action Program LERs are defined as historicalif the event did not improvements currently underway are expected to occur within the last 12 months.
reduce reportable events during the remainder of the year.
LERs are reported in the month of the submittal to the NRC.
1 I
ont Comments Data through 6/20/97 1
Data Source:
R. Joshi x2080l Analysis by:
R. Joshi x2080l Owner:
R. Joshi x2080 Page A-26
a Licanco Amandmant Requests Millstone 2 - June 1997 Progress:
License Amendments are challenged to be completed by 8/15/97.
20 15 Data through 6/20r'97 Good
.E 5'o i
Y k
I Submittal Schedule ;
j 6
-- chai Q --- g _ _._ _ _ g _ i.
i 1
0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec i E LARs To Be Submitted E LARs Submitted !
Raw Dets Jan-97 Feb-97 Mar-97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct 97 Nov-97 Dec-97 LARs Submmed 2
1 1
1 2
0 LARs To Be Submmed 13 12 11 11 9
9 Definition Analysis / Action License Amendment Requests (LARs) are changes to No license amendment requests have been Technical Specifications or other license changes that submitted thus far in June. Delays are a result of are needed for restart that are to be submitted to the additional analysis required by outside support and NRC for approval.
the sharing of intemal resources. The remaining LARs are planned to be submitted to the NRC by 8/15/97.
Gont Comments Receive NRC appmval pnor to restart.
Data through 6/20/97 Data Source:
R. Joshi x2080l AnsIysis by:
R. Joshi x2080l owner:
R. Joshi x2080 Page A 27
Roctort Modifications Awaiting implementation Millstone 2 - June 1997 Progress:
Modifications are being released for work. The completion of these modifications is a chaIIenge.
120 I
100 l
l Data through l i
80 l
gjggjgy 60 i
I 40
~ ~ -
w
- O
~ _.
O I
I I
I I
I I
I I E I I
I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 5 Mods Awaiting Engineering Raw Dets Feb 97 Mar-97 Apr 97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Oct 97 Nov-97 Dec.97 Mods Awamng Engineenna 81 103 91 76 77 j
Work Off/ Goal o
{
Definition AnalysisfAction The total number of outstanding modifications Progress was effected by the addition of severalitems identified as required prior to restart that have not to the required restart modification list. This resulted in been approved for implementation.
an adverse trend with respect to work off.
i 1
i l
l l
T l
Goel Commente
)
All start up related design modifications completed Data through 6/20/97 l
prior to restart.
)
D*ts Source:
M. Amadon x6249l Analysis by:
M. Amadon x6249l owner:
S. Bnnkrnan x5321 Page A 28
AWOc Rcquirod for Rostert Millstone 2 - June 1997 Progress: The generation and completion of corrective maintenance work orders required for restart is high and currently does not support the restart tlineline.
2250 2000-Work Order 1750 -
data through 1500-M7 Gong 1250-E g
y
/
1000 -
o j
l 750 -
y l
500 -
l
=
m m _
m.
m 2M-
\\
Jan Feb Mar Apr May Jun Jul Aug Sep cet Nov Dec MR AWO - Other AWO -+--MR AWO Goal -e-Total AWO Goal
, Raw Dats Jan-97 Feb-97 Mar-97 Apr 97 May-97 Jun 97 Jul-97 Aug 97 Sep 97 Oct 97 Nov 97 Dec-97 Total AWO Backlog 1348 1376 1434 1354 1481 1455 MR AWO Goal 200 200 200 200 200 200 200 200 200 200 200 200 Total AWO Goal 500 500 500 500 500 500 500 500 500 500 500 500 MRAWO 964 976 1031 940 1045 1045 Other AWO 384 400 403 414 416 410 Definition Analysis / Action Automated Work Order (AWO) Backlog is the total The Maintenance Rule (MR) Backlog remained number of corrective maintenance / condition driven essentially constant during the month of June.
(non-recurring) AWOs required or desired for restart.
Approximately 210 new MR AWO's were generated during the month of June. New AWOs continue to be The total does not include: AWOs awaiting retest, generated via the discovery process, and as more in closure, work planned for future outages, AWOs that design modifications are approved for work.
support field work already included in backlog (i.e.
The unit continues to work down the backlog. Each insulation, staging, etc.) and non-power block AWOs.
department on the unit continues to work hard to achieve a net decrease in the backlog. This task Safety significant systems are defined as becomes increasingly more difficult, as "new work,' is Maintenance Rule risk and/or safety significant created and the number of working hours decreases.
systems.
Changes to improve efficiencies in the work process, and increase staffing needs ' critical to restart
- are being pursued. These efforts will also help to expedite work completion, and supports restart goals.
Goal Comments Less than 500 AWOs and trending down prior to Data through 6/20/97 readiness for restart, with none required for restart.
Data Source:
R. Lally x4426l Analys/s by:
R.W. Poole x5338l owner:
S.J. Jordan x4292 Page A 29
e Tomporary Modifiestione Millstone 2 - June 1997 Progress:
Temporary Modifications are not being reduced. Additional management attention will be required to make the goal.
60
- Data through,
_. liI_.l_I_lIA
/
M 97 I
i 40-Good f
T e
20-i m
I
.O I
I I
I I
I I
I I
i 1
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 5 Temp Mods BOutage Support Raw Data Jan 97 Feb-97 Mar.97 Apr 97 May-97 Jun-97 Juk97 Aug-97 Sep-97 Oct-97 Nov 97 Dec-97 Ternp Mods 29 29 30 31 31 31 Outage Support 21 21 19 18 18 20 Totalinstallad 50 50 49 49 49 51 Definition AnalysisfAction A temporary modification is a modification to plant There are 51 Temp Mods installed on the plant. A review of design that is short-term in nature and not part of the the MP2 Manager Restart Worklist compared with the Temp permanent plant design change process.
Mod list showed a dramatic reduction in the number to be installed by start-up. While future developments may require Temporary Modifications to permanent plant design are changes, cunent gectauons can for fewer than ten Ternp categorized here two ways: " Outage Support' are Mods to remain installed at start-up. The to-be-implemented procedure WC 10, Rev.1, " Temporary Modifications,' states those directly tied to physical work to plant equipment that all Temporary Modifications installed greater than six (6) in an outage condition, and " Temp Mods' are all months shall have an FSAR change request submitted. This others.
process will eliminate thirty-three (33) Temporary Modifications when the change requests n..; been made to the FSAR.
Goal Comments The industry benchmark and Unit 2 goal of less than 5 Data through 6/20/97 installed temporary modifications will not be reached until post Restart.
With the plant shutdown there are temp mods required to support shutdown work. There are currently twenty temp mods for this purpose.
Data Source:
W. Woolery x0698l Analysis by:
W. Woolery x0698l owner:
M. J. Wdson x2081 Pace A 30
e Control Room and Annunciator Daficiencios Millstone 2 - June 1997 i
Progress:
Most deficiencies tracked in PMMS are scheduled to be worked and released prior to start-up. Some are Mode dependent and will be removed post Restart.
so So i
l __.l...
- ~~
'N
- - =-
Deficiency data j J
through 6/20/97 j
l-ee 2
g 20 Y
0 i
t i
I i
i 1
I
'I t
l l
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec i E Total Deficiencies '
Raw Dets Jan-97 FetF97 Mar-97 Apr-97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov 97 Dec-97 Tot:1 Deficionews 41 39 45 52 49 51 Work Off! Goal 52 48 41 39 37 30 25 20 11 Definition Analysis / Action Control room instruments, recorders, indicators, and Since April 21,1997, the number of corrected tnnunciators that function improperly that could affect deficiencies has been greater than the number of TRs the ability of the operators to monitor and control plant submitted. During the most recent week (ending 6/23),
conditions.
the number of TRs submitted exceeded the number of deficiencies corrected. Many deficiencies are mode dependent and will remain on the list until mode changes occur and the work and/or retests can be performed.
So far through 6/20,2 deficiencies closed and 5 deficiencies opened for a total of 51.
Goals Comments Operations has a goal of less than 10 CRP Deficiencies Deficiency data through 6/20/97.
during Mode 1. Presently, there are 9 deficiencies that are being tracked by EWRs and may not be finished prior to Restart. The 41 other deficiencies are being worked on and tracked by PMMS or Minor Maintenance.
Den Source:
W. Woolery x0698l Analysis by:
W. Woolery x0633l Owner:
M. J. Wilson x2081 Page A-31
Oparator Work Arounds 4
Millstone 2 - June 1997 Progress:
Operator Burdens are not being reduced. Additional management attention willbe required to make the goal.
45 40 i
Data through j
6/20/97 i
. Good 30
- 25 Y
20 15 g
4 10 5
]
O I
I I
l l
I I
l i
l l
I Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec E Operator Work Arounds,
R Tw Data Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug 97 sep-97 Oct 97 Nov-97 Dec-97 Optrator Work Arounds 43 39 41 42 41 41 2
Definition AnalysisfAction Operator Work Arounds are conditions requiring an operator The number of Operator Burdans has remained to work with equipment in a manner other than original design relatively constant over the past six (6) months due to j
which could:
the plant priority of working on Restart items. Presently, 16 Operator Burdens are on the Restart list and will be
- 1. Potentially irnpact safe operation during a plant tr Ansient resolved prior to Restart. The other 25 Operator
- 2. Potentially impose significant burden durir; r.r.nal Burdens have plans (DCNs/EWRs) associated with operation them to be completed post Restart. Management is
)
i
- 3. Create nuisance condition due to recurring equipment aware of the necessity to reduce the number of burdens i
deficiency on operators but is Working on restarting the unit.
- 4. Distract an operator from noticing a recurring condition 1
Gon!
Comments Goal is a 10 burdens remaining. This goal will not be Data through 6/20/97 achieved until after Restart. The Operations Review Board (ORB) has accepted the task of prioritising the existing Operator Burdens and establishing criteria for. future issues.
Ed Seacor, the ORB Chairman,la implementing a plan that J
incorporates the best elements from several plants' programs j
t.s they apply to MP2.
Da7 Source:
W. Woolery x0698l Analys/s by:
W. Woolery x0698l owner:
M.J. Wilson x2081 4
Page A 32
Praccduro Rovicion Backlog Millstone 2 - June 1997 Progress:
Procedure revisions are a challenge to be completed prior to restart.
Additional resources and management attention is being appIled.
300 250 i Data through l l
l 6/20/97 j
i 20 I Good Goal: complete 1
150 corrective actions l. Y l
by restart 4
r _-
yl--wr=:rm s
R h
9 E
e 50
_m
_ 0 35431 35462 35490 35521 35551 35582 35612 35643 35674 35704 35735 35765 Restart Req'd Proc. Rev. M PUP --G-Restart Reg'd Work OWGoal --*-PUP Work Off/ Goal Raw Osta Jan-97 Fet>97 Mar 97 Apr 97 May 97 Jun-97 Jul 97 Aug-97 sep-97 Oct 97 Nov-97 Dec 97 Total Remaining 268 270 269 257 243 220 Restart Req'd Proc.
nov 88 102 116 108 102 92 pup 180 168 153 149 141 128 Restart Req'd Work Off/ Goal 94 106 115 105 93 92 86 76 54 25 25 pup Work Off/ Goal 210 100 150 120 100 70 50 35 10 0
Definition AnalyslWAction Procedure Revision Backlog is the total number of new One hundred fifty-nine deficier t procedures have been procedures or procedure revisions required or desired for identified to date. The majority are EOP revisions and restart.
AOP development and upgrades. The remaining are Millstone Procedure Upgrade Project (PUP)(Phase lil).
actual deficiencies which are identified as needed for Upgrade the Technical Procedures at Millstone Station to restart. This performance indicator is expected to a Standardized Wnter's Guide and Verification and have constant input of newly identified procedure Validation (V&V) Process. The goal of PUP is to improve deficiencies, still with the goal of completion before the technical quality and usability (human factors) of restart.
procedures; this will reduce human errors and enhance plant reliability by supporting quality of work.
PUP is 90% complete. The Centralized Procedure Group (CPG) is continuing to work down the number of Coments procedures not yet upgraded.
Data through 6/20/97 Gos!
All restart required procedure revisions and PUP requirements have been reviewed and proper corrective actions have been taken prior to restart.
Dets source: W J. Charent 16416 l Analysis by:
W R. Watson x6245l owner:
H L. Meer x0474 Page A 33
Indspondant Corrcctivo Action Vorification Program Roadiness Millstone 1 - June 1997 Progress: The work remaining is on schedule for this period.
100%
8o%
l l ICAVP Work
- I remaining as of a
,, I, N i j, en l
6/27/97 j
f
/
j Good 4a
. Goal: Ready for ! ;
I l ICAVP 11/8/97 i j h
Y
[
_7 i
i Jan Fe par
' Apr uay'
' Jun au Aug sep oct w
o.c MICAVP Remaining --G-Work Off/ Goal Raw Oste Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ICAVP Remairung 100%
95%
67%
45%
42%
33%
Work Off/ Goal 4 2*/.
37%
31%
26 %
18%
7%
o%
Definition Analysis / Action This indicator measures progress in readiness for Independent Good progress in regard to target is ongoing.
Corrective Action Venfication Program (ICAVP). For MP1, this No new action is required.
consists of the following systems:
TBSCCW Core Spray Service Water Emerg Diesel Generator RBCCW Gas Turbine Generator ESW 4160 Volt Electrical EDG Am Vent /Cookng 480 Voit Electrical RWCU 125 Volt DC Electrical Condensate Vital AC Nuclear instrumentation instrument AC Standby Liquid Control
- Original 17 Systems The displayed % value is a weighted average for progress within the 17 systems hsted in the PI-6, PI-7, and PI-8 arenas.
Goni Comments The Unit 1 goal is to be ready for ICAVP / Scheduled 11/8/97 June data is through 6/27/97 Data prior to 4/23 is estmated.
Dora source:
GE ScorecarclAnerysis by:
C. Weeden x6ao3l owner:
E Patelr5729 Page A.34
Ocnfigurction Menegamant Plan Progroso Millstone 1 - June 1997 Progress:
contiguration unnagement pian (cup) comptation is on schedute to meet the snaise goat.
l inog.
CMP work t
remairung as of I
6/27/97 1 eo%-
' Good i. 60% -
j Goal: CMP I
B 4og.
' complete by-g l
3/30/98 20% -
m,_
uw l
I I
I l~
I "" l -
l ~
l l
l "M
- I i
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar ig CMP Woe Romanng - G-Wo* Off/ Goal
~
l RawDnte Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul-97 Auo.97 Sep 97 Oct-97 Nov-97 Dec 97 Jan-98 Feb-98 Mar-98 CMP Wo* Aemanng e5%
75%
73%
68%
63%
wo* Oft / Goal 69%
63%
57%
So%
43%
36 %
29%
22%
15%
7%
o%
DeMnition AnalysisfAction This indicator measures progress in completing the Progress is on target.
Configuration management Plan (CMP). This is the plan by which management of each nuclear plant venfies that j
the design and operation of their plants is consistent with wtti the NRC has approved, and all changes and commitments since originallicensing are property rifteted in current licensing documents, such as the Final Safety Analysis Report (FSAR).
For Unit 1,an analysis to set up this KPl was used as the data source and was performed as follows:
A weight was applied to each of the Project instructions Es well as the ICAVP and OSil. The computation of that dita provided the % shown.
Note: This KPl was previously Readiness for Goel 10CFR50.54(f) Submittal. The NRC revised their The Unit 1 goalis for the CMP to be complete by 3/30/97.
10CFR50.54(f) request for information on 4/16/97. A specific response with regard to the CMP is no longer required.
Comments Data is through 6/27/97 To date, approximately 912 UIRs have been written; 112 CRs initiated.
i Data Source
- UPM Ananysesl Analysis by:
E. Patei r5729l Owner:
E. Patel x5729 Page A 35
Tcok Complationo Rcquired for Roctart 1
Millstone 1 - June 1997 Progress: work ott curves witt be developedin conjunction with e revised startup schedule.
i 2500 2
I *.
- - ~~
-i -
Open tasks as ofl a
6/24/97 2o00 E..
Good
.n 1500 Y
1000 f.
.s00
- - - =
. __. f. _
Jan Feb Mar Apr May o
M Aug Sep Oct Nov Dec i E Open (Flestart) E Open (Undetermined) Work Off/Goali l
Raw Date Jarw07 Feb-97 Mar-97 Apr-97 May 97 Jur>07 M 97 Aug-07 Sep-97 Oct 07 Nov-07 Dec-97
]
Open (Restart) 1489 1687 2094 2113 2245 Open (undetermined:
325 413 197 189 247
)
Work Ortrool l
DefinMon Analysis! Action The total number of tasks is defined as those requiring The number of tasks required for restart is increasing closure prior to restart. Automated Work Orders (AWOs) primarily due to the approval and assignment of required for restart are not included, as they are tracked corrective actions. Work-off curves are not available at in a separate indicator. NOTE: the Open this time.
(Undetermined) category are those assignments that are still being screened to determine Whether they are required for restart.
All data retrieved from AITTS.
Goal Comments Goal is all complete pnor to restart.
ArrislAm4sk by:
G Winters x5491l Owner:
G Wnrders r5491 Dets source Page A-36
o Opon Condition R0porto Millstone 1 - June 1997 Progress: condition Reports requiring corrective action are stitt increasing. Increased Management attention is being appIled to this ares to meet the restart goal.
240c 2200 h
Open CRs 2W 6/24/97 1800 Good 1800 i
1400 i
g Open CRs >120 Y
1000 4
days l
600 u --
J 4.~
^Z. - ~. -
T,_
O I
I I
I l -
1 I
I l
l l
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l-e-CR's Not Closed (Tota!) M CR's Not Closed (> t 20 Days) !
Raw Dets Jan-97 Feb-97 Mar 97 Apr 97 May-97 Jun 97 Jul-97 Aug 97 Sep 97 Oct 97 Nov-97 Dec 97 cR's Not Closed (Total) 1680 1740 1778 2010 2235 2341 Level 1 96 122 130 159 c06 197 Level 2 1584 1818 1648 1851 2029 2144 1
CR's Not Closed (3120 Days) 1275 1455 1487
.1515 Level 1 51 82 103 131 I
Level 2 1224 1373 1384 1384 Definition AnalyslWAction This indcator depicts the number of condition reports The work scheduled for RFO 15 will reduce the number of I
(CRs) which have not had corrective actions implemented Open CRs. At this point, the aggregate of Open CRs has not ts CRs not Closed (Total). The number of these total been assessed to determine which CRs are constrained by CRs which are over 120 days old and have not been plant conditions. Therefore this graph represents all CRs that deferred is depicted in the bar graph, are not closed.
I Condition Reports (CRs) are written to uocument
{
degraded or non-conforming conditions associated with plant systems, structures or components necessary to support the generation of electricity.
l 1
)
Gont Comenents The goal is to have all Level I Condition Reports closed Data through 6/24/97.
by startup unless they have been reviewed by the Plant Operations Review Committee (PORC) and approved by l
a Unit Officer.
Dets Soures:
AITTS! Analysis by:
G. Winters x5491l owner:
G Winters x5491 Psoe A 37
O e
C ndition Report initiation cnd Evolustion Timalinoss Millstone 1 - June 1997 Progress: A step linprovement was realized with both cs Timeliness and cn Evaluations Completed this reporting period.
400 350 300 250 Data Through 200 l
I4. hl 1
I 150 l
4 4
i 100
?
. _. 5o 4
g.
=
= = m=a
=. -
Jan Feb
~ Mar Apr - - May Jun Jd Aug Sep Oct teov Dec ~
~~
- 5 Total CRs initiated B # Evaluations Cornpieted DCompleted within 30 days '
Row Dets Jan47 Feb 97 Mar 97 Aor 97 May-97 Jun-97 Jul47 Aug-07 Sep-97 Oct-97 t?ov-97 Dec-97 Total CRe tnitteled 249 191 194 296 387 241 Level 1 CRs Inmated 59 30 8
29 33 20 Level 2 and 3 CAs Irvtiated 190 tot 186 267 354 211
- Eveaustione completed 217 153 175 200 331 78 Completed witNn 30 days 34 23 34 03 124 63 Success Rate l 014 012 0.25 0.33 o 56 Dehnition AnalystalAction This indicator depicts the inrtiation of Condition Reports (CR) for The Unit I leadership placed high priority on the Unit and the nurnber of evaluations which were not completing corrective action plans within 30 days.
cornpleted within the goal of 30 days.
As a result of this effort the success rate, as well as the total number of evaluations completed have The graph shows CR data beginning 1/1/97, and represents the shown a step improvement.
current status / effectiveness of Corrective Action initiatives.
NOTE : The success rate for May is calculated Evaluations are considered open if they are either in an open based on the number of CRs that are 30 days old as status or a pending review status prior to the approval of the of 6/28/97 without Corrective Action Plans approved.
corrective action plan. The latest month's data reflects the The success rate does not include the Level 3 CRs.
status to date.
Goal Comments Goal is to complete all evaluations and identify appropriate Data through 6/28/97.
corrective actions within 30 days.
Deze soures:
Arrrs Analysie by:
G wlnters x5401l owner:
G Whers us491 Page A 38
3 Cenditien Rspcrt Msthcd cf Discovary Millstone 1 - June 1997 Progress:
The line continues to identity a high percentage or cas.
100 e0 Data Through j 70 6/24/97 8,
j so g so
- 40 30 20 10 0
Jan Feb Mar
. Apr May Jun Jul Aug Sep Oct Nov Dec
- 5 SELF IDENTIFIED WINTE ANAL OVERSIGHT DEXTERNAL oVh,(*gT DEVENT.
New Deh
~
'07 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Sep-07 Oct 97 Nov-97 Dec-97 Number of CR's Unit idensted 218 171 160 277 361 158 Internal Overaght 17 7
24 11 21 8
External overscht 1
2
-1 3
3 3
Event 13 5
o 5
2 3
Total ldent:16eo 249 191 194 296 387 172 l
Dept sew 10 Ratku i
Man 1tenance TBD Operations T80 Wotit Plannsng TBD Demon Eng TBD Tectvscal S@ port TBD Ucansing TBD DeMnition Analysis! Action This indicator represents the percentage of CR's identified by The line continues to identify a high percentage of total each of the barriers. CR's are categorized into the following CRs. An element of MRT CR Review now includes four areas:
challenging the une to recognise that an Oversight CR indicates a missed opportunity by the line to self-identify.
- Event Drtven Self-revealing, an event occurs.
- Extemal Oversight identified by NRC, JUMA, INPO, etc.
Events:
- Intemal Oversight Identified by QAS, PORC,ISEG.
M1971372 - Leak found on Hypochlorite Tank piping.
NSAB, etc.
M197-1375 - Crane parked within 20 feet of Vital Area.
- Self Supervisor observation, document review, Self-M197-1454 - Operator sustained back injury during checking, independent / dual verification, etc.
training evolution.
Extemal Oversight:
The department self identification ratios are a measure of the M1-971309 Familiarisation training for NGP 2.25, indtvidual department's rate of identifying their own issues.
Rev.10 not received by all personnel.
M1971312 Failure to perform trend reports as Dept Self 10 ratio =
specified in RP-4.
M1-97-1313 Failure to meet TS requirement 4.7.A.3.E number of CR's ID'd lastlaned to that rianartment (LER 96-012-00).
number of CR's assigned to that department Goal Commenin The line identihed percentage and the department self Data through 6/24/97.
identification ratjos should be rising as the self-assessment culture matures.
Data Souros AITTSl Arnalyses by:
O Wmters x5401l Owner-G wmters x5491 Paos A 39
\\
4 Opan NRC Commitmanta for Rectert I,
Millstone 1 - June 1997 Progress:
While the total number of open commitments to the NRC remains hign, we are reducing the number that are overdue with a goal of closing commitments on their due dates, and none open at restart.
450 400 350 Data Through 300 6/24/97 250 T
200 150
__ _ _,,R.
~
m..--_.
-=
50 0
5 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'EOpen Hems MOverdue items,
Raw Dets Jan 97 Feb-97 Mar 97 i Apt 97 May-97 Jun 97 Jul-97 Aug.97 Sep-97 Oct-97 Nov 97 Dec 97 Open items 156 177 233 218 241 216 Overdue iteme 26 17 0
2 2
2 Work Off/ Goal TBD TBD TBD TBD TBD TBD TBD Definition Analysis / Action An NRC commitment is:
The work off curve will be developed.
- Written statement that is docketed.
+ verbal statement to take a specific action, agreed to by an officer.
- requirement to take an action imposed by the NRC.
(
The commitments counted here are those that need final closure with the NRC prior to restart of the unit.
Goet comments NRC commitments closed on due dates prescribed Data through 6/24/97, and all closed prior to restart Work Off/Goalis for end of month.
Commitments that need to be changed can be evaluated under NGP 4.06. This date reflects AITTS changes through 6/24/97.
Data Source:
! '2 Muder x0508l Anstysis by-Liz Mueller x0500l Owner:
A Wetmie x2191 Paos A 40
s 4
Significant Itamo Liot Millstone 1 - May 1997 Progress: SIL due dates are currently under evaluation.
I 120 Ill
'Datathmugh l
100 05/28/97 Good 80 l
Y 60 i
i 40 Goal: Allitems I
, complete by 03/01/98 -
2o j
-_ _D Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb I N Total Remaining E Work Oft / Goal.
Lw Dets Mar 97 Apr 97 May 97 Jun 97 Juk97 Aug-97 Sep-97 Oct 97 Nov 97 Dec 97 Jan-98 Feb 98 l
Total Romanng 108 108 108 Work Oft / Goal N/A PFA N/A Definition Analyele/ Action Items on the Significant items List include those items Due to the decision to scale back work and minimize (108) chosen by the NRC which require closure prior resource expenditures on Millstone Unit 1, the existing to start up.
SIL due dates provided to the NRC on 04/18/97 are under evaluation. A work off curve will be developed to reflect the revised completion schedule which will be provided to the NRC by 06/30/97.
i 1
Goel Comments Goal; All items complete by 03/01/98-Data through 05/28/97.
Data Source:
M Janus x3181MPl Analysis by:
P. Mner x2085MPl Owner:
P. uner x2085MP Page A-41
~
s 10CFR50s54(f) Significent Itama for Roctert Millstone 1 - May 1997 Progress: Indicator to be developed 1400 1200 1000 Good Indicator to be developed l
e
['
Y 400
-. m. r_
-.e.
-=
.__g 0
~
I May Jun Jul Aug Sep Oct Nov Dec M Open Significant items MCicsed Significant items -e-Work off Goal,
Raw Dets May-97 Jun-97 Jul-97 Aug 97 Sep-97 Oct 97 Nov 97 Dec-97 Open SonNeard Rams Closed Sgnicant noms Work off Goal Total SignNcant items ceterred noms j
DefinMon Anetysbe/ Action Significant items for Restart are those items being reported This is a new indicator, analysis win be provided as data l
to the NRC in accordance with the 10CFR50.54(f) request accumulates, of April 16,1997.
Goal Comments M significant items for restart closed by.
Data through Dnie Sowee:
lAnalyok by:
l Owner:
Paoe A-42
s Licancee Evant Roporto Millstone 1 - May 1997 Progress:
License Event Reports made to the NRC are trending down to the Industry standard.
16 1
14 12 5
Good 10 a
l 8
1
[
6 Data through
?
6/19/97 y
f a
E h
s/_
^
M M
M 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec LERs-Recent MLERs-Historical -+-industry Standard l
Raw Data Jan-97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul 97 Aug-97 Sep-97 Oct 97 Nov 97 Dec-97 LERs-Recent 2
1 3
2 1
0 LERs-Historcal 2
4 10 2
6 1
LERs-YTD 4
9 22 26 33 34 industry Standard 1
1 1
1 1
1 1
1 1
1 1
1 Definition AnalysisfAction Ucensee Event Reports (LERs):
One LER has been submitted in June. This LER involves a historicalissue related to the scope of a
+ are reports made to the NRC pursuant to Technical Specification surveillance procedure.
+ are defined as historical if the event did not occur within the last 12 months
+ are reported in the month of the submittal to the NRC 0001 Comments Data through 6/19/97.
j
~ 1.
Data Source:
T. L Hooper x0677l Ans/ys/s by-T. L. Hooper x0677l0wner:
A Wapole x2191 Page A-43
Liconco Amondmont Roquacto Millstone 1 - May 1997 Progress:
unit 1 is on schedute for submittat ot ticense amendment requests to support reload and restart 10 8
6 b
j i
li LAR submittal data l
g4 through 6/24/97 I
l i
~
-. _._. 2
=--
u-+.=,- -
=-~
\\
g Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec LARs to be Submitted BM LARs Submitted --G-Work-Off/ Goal 1
Raw Dets l
Jan-97 Feb.97 Mar-97 Apr 97 May 97 Jun-97 Jul-97 Aug-97 Sep 97 Oct-97 Nov-97 Dec-9'7 LARs to be Submmed 4
3 2
2 1
0 1
LARs Submmed 2
1 1
0 1
0 Work Off/ Goal 4
3 2
2 1
1 o I Definition Analysis / Action License Amendment Requests (LARs) are changes to There are two License Amendments required for Technical Specifications or other license changes that reload, both are submitted.
are required for restart, and tr at must be submitted to
- 1. Response Time Testing, submitted on the NRC for approval 2/7/97
- 2. Allowed Outsge Time (AOT), submitted on 3/6/97, approved on May 28,1997.
NRC verbally requested additional information IRAI) regarding Response Time Testing sent 4/3.
There are four license amendments required for start-up, three are submitted.
- 1. SBGT Vent and Purge
- 2. SRV Electric Lift
- 3. Neutron Monitoring Comments For the SBGT Vent and Purge amendment, the NRC Data through 6'24/97.
Issued RAI which has questioned the approach for the PTSCR. Engineering is conducting a review of other utilities to determine an alternate approach for venting and purging containment.
Gost The fourth issue is GL 87 09. This will be submitted All LARs requiring NRC review submitted by Oct 21, by 7/31/97 1997.
Data source:
R Walpole X2191l Analysis by:
R. Walpole X2191l owner:
R Walpole X2191 Page A 44
s Rootort Modificationc Awciting implomantation Millstone 1 - June 1997 Progress: ou* to a reduction in <*sourc*s. proer*ss on modifications was !!mit*d to partis! r*!*s**s for Restorstion MODS,10:97-0055 EEQ Program Walkdowns, 96-0020 Intake Structure Materist Condition for SWand CW, and completion of work on MOV LP168.
50
/ datathrough Restart Mod 45-40 6/20/97 30 -
Good
~
25-l l 20 <
Y 15-10 -
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov M Mods Released to Field
- Mods Awalting Engineenng -e-Work Oft / Goal Ra w Dets Jan-97 Fet>.97 Mar-97 Apr 97 May-97 Jun 97 Jul 97 Aug-97 sep-97 Oct 97 Nov 97 Mods Released to Field 4
10 18 27 30 30 Mods Awaiting Engineenng 45 39 31 22 19 19 Total Mods Remaining 49 49 49 42 39 39 Work Off/ Goal 49 49 46 42 39 39 36 33 32 31 Definition AnalyslWAction The total number of outstanding modifications identified 61% of the 49 restart modifications are released as required prior to restart that have not been tumed to the field for construction.
over to Operations.
- 20*4 of the 49 restart modifications are Installation Completed and retumed to operations.
Gos!
Comments
[
All start up related design modifications completed Data through 6/20/97 prior to restart.
Dets Source: W. Crandall l Analysis by: S. Doubet l0wner: E. Harkness Page A-45
s AWOc Rcquirod for Rostart Millstone 1 - June 1997 Progress: shutdown cooling has been Restored 400o 3500 -
1000 -
< l l datathrough j
!]
I 6/23/97 2500 -
GOOD 2000 -
h 1500 -
Y
.m,_
=y _
--y
=
=
O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M MR AWO Mother AWO -+-MR AWO G0a! -e-Total AWO Goal:
Raw Dats
~*
Jan-97 Feb-97 Mar-97 Aor97 May-97 Jun-97 Jul-97 Aug-97 Seo-97 Oct-97 Nov-97 Dec97 Total AWO Backlog 2636 3041 3290 3112 3604 MR AWO Goal 350 350 350 350 350 350 350 350 350 350 350 350 Total AWO Goal 500 500 500 500 500 500 500 500 500 500 500 500 MRAWO 2281 2581 2798 2629 2602 Other AWO 355 460 492 483 1002 Definitlen AnalyslWAction Automated Work Order (AWO) Backlog is the total Restoration of Service Water and Diesel Generator to number of corrective maintenance / condition driven (non-retum to Green Shut Down Risk Status are the focus
{
recuning) AWOs required or desired for restart.
Items for the Unit. Shut Down Cooling has been restored to an available status.
The total does not inciude: AWOs awaiting retest,in closure, work planned for future outages, AWOs that support field work dready included in bacidog (i.e.
Insulation, staging, etc.) and non-power block AWOs.
Safety significant systems are defined as Maintenance Rule risk and/or safety significant systems.
Goel Comments Goal < 500 total AWOs at start-up, < 350 Maintenance Data through 6/23/97.
Rule risk and/or safety significant system AWOs at start up, and no AWOs that are required for restart at start up.
Dets Source E. Anrmo x0492lAnstysis by-J. Law x4373l owner:
J. Law x4373 Page A-46
i Tomporary Modifications Millstone 1 - June 1997 Progress:
Due to recent changes in manpower and work scheduling, the goalis set at the current level until a revised schedule is developed.
\\
l 70-l 60-l j Temp Mod I
M' i data through,
l 40-Y 30 j
20-10--
i
- ~ - -.
w- _
0 l
I I
I I
I I
I i
I i
Jan Feb Mar Apr Ma, Jun Jul Aug sep Oct Nov Dec mTemp Mods - Outage Support -S-Work-Off/ Goal Raw Osts Jan-97 Feb-97 Mar 97 Apr-97 May 97 Jun-97 Jul-97 Aug 97 sep-97 Oct 97 Nov-97 Dec.97 j
Temp Mods 69 69 67 66 66 65 Outage supfud Totalinstalled 69 69 67 66 66 65 Work Off/ Goal 69 69 67 66 66 65 65 65 65 65 65 65 Definition AnalysisfAction A temporary modification is a modification to plant design that is short-term in nature and not part of the 2
permanent plant design change process.
Temporary Modifications to permanent plant design are categorized here two ways: ' Outage Support' are those directly tied to physical work to plant equipment in an outage condition, and " Temp Mods' are all others.
Gos!
Commente The goal is set at the current level of 65 until a revised Data through &25/97 schedule is developed, at which time a better estimate of the work off rate will be established.
Data Source:
C. Ackley x0771l Analysis by:
W. Noll X5742 l owner:
P. Hinnenkamp X0466 Page A-47
Control Room and Annunciator Doficiancloc 3
Millstone 1 - June 1997 Progress:
Due to recent changes in manpower and work scheduling, the goalis set at the current level until a revised schedule is developed.
35 I
i 8
4 25 l Good 2o j
15 j
1 lDefconey data l
g10 through 6/25/97
{
y l
j
__5
~
= - - - ~
~-- T
!-~
t=
o
~~ -
Jan Feb Mar Apr May Jun Jul Aug Sep" Oct--
Nov Dec l
! M Total Deficiencies -G-Work Oft / Goal.
1 Raw Dets JardQ7 Feb-97 Mar 97 Apr 97 May 97 Jun 97 Jul-97 Aug-97 Sep-97 Oct 97 Nov-97 Dec 97 70tal Defoenc,es 24 24 21 16 16 18 Work Ofi/ Goal 24 24 21 16 16 18 18 18 18 18 18 I8 Definition Analysis! Action Control room instruments, recorders, indicators, and The total deficiencies count displayed is the sum of the annunciators that function improperly that could affect old/previously identified Control Room Panel (CRP) the ability of the operators to rnonitor and control plant items and the new items. The total count reflects CRP conditions.
deficiencies on operable and shutdown risk significant equipment.
l Goele Comments The expectation is that new deficiencies will be evaluated when systems are turned over for Operability. The goal is set at the current level of 18 until a revised schedule is developed, at which time a better estimate of the work off rate will be established.
Data Source:
C Ackley mo771l Analysis by-W. Non x5742l owner:
P. Hannenkamp x0468 Page A-48
i Op3rator Work Aroundo Millstone 1 - June 1997 Progress:
Due to recent changes in manpower and work scheduling, the goalis set at the current level until a revised schedule is developed.
15 l
10 l
E Work Around data i
through 6/25/97 l
Y 1
_J
__i o
I i
i i
i l
i i
i i
i l
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec
{
Operator Work Arounds -e-Work Off/ Goal !
RTwDatn Jan-97 Feb 97 Mar 97 Apr 97 May-97 Jun 97 Jut 97 Aug-97 sep-97 Oct 97 Nov.97 oec-97 OperatorWork Arounds 12 12 11 11 11 Work Off/ Goal 12 12 11 11 11 11 11 11 11 11 11 Definition AnalysisfAction Operator Work Arounds are conditions requiring an operator to work with equipment in a manner other than original design which could:
- 1. Pctentially impact safe operation during a plant transient,
- 2. Potentially impose significant burden during normal operation,
- 3. Create nuisance condition due to recurring equipment tieficiency,
- 4. Distract an operator from noticing a recurring condition.
Goal i Commente The goalis set at the current level of 11 until a revised No new Operator workarounds will be logged until schedule is developed, at which time a better, estimate of systems are retumed to Operable status. Operations the work off rate will be established.
Manual chapter being revised to reflect this, Data through 6/25/97 De7 Source:
C. Ackley x0771lAristysis by:
W NoliX5742l owner:
P. Hinnenkamp X0486 Page A49
Prscaduro Rovicion Backleg Millstone 1 - June 1997 Prcgress:
not app 11 cable, first report.
450 400 350 I
Data through l Good 300 6/26/97 j
j 250 i
200 i
Y Goal: complete l
procedure revisions 150
/
___m..
m
_ _.by 3/1/98 ; _ - _ _
r_
_=.
100 50
~
^
0
~
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May
! M Other Procedures - PUP Procedures -*--PUP Work Oft / Goal -G-Other Work Off/ Goal Raw Data Jun 97 Jub97 Aug-97 Sep-97 Oct-97 Nov-97 Dec 97 Jan-98 Feb.98 Mar-98 l! Apr 98 May-98
~
Total Rernanng 536 Other Procedures 441 PUP Procedures 95 PUP Work Oft / Goal 95 85 75 65 55 45 35 25 15 0
Other Work Off/ Goal 441 400 350 300 250 200 150 100 50 0
Definition AnalyslWAction Procedure Revision Backlog is the total number of new The biggest barrier to completion of Operations 4
procedures or procedure revisions required or desired for procedure revisions is a shortage of SOR qualified rIstart.
Procedure Screeners. Individuals are in the process Millstone Procedure Upgrade Project (PUP) (Phase Ill)-
of obtaining this qualification to remedy this shortage Upgrades Procedures at Millstone Station to a Standard Writ:r's Guide, Verification and Validation (V&V) process.
The goal of PUP is to improve the technical quality and usability (human factors) of procedures; this will reduce human errors and enhance plant reliability by supporting Comments quality of work Work off curve is based on 100% complete by 3/1/98.
This provides 3 months from the scheduled completion Goal of 50.54f discovery phase to complete 50.54f l
All procedure revisions required for restart completed prior resolution and procedure i
to 3/1/98 revision /aoproval/ training / implementation.
For non PUP procedures,149 deficient l&C items,128 deficient Maintenance items, and 164 Ops items have been identified to date.
OsM Source Ops, Maint.. l&C Analysis by-Pete Schilke x0421 owner:
PaJI Hinnenkarro x0466 Page A-50
Milletona Ovaraight Rccovory Gsp Chcrt Juna 1997 J
l Progress:
Progress is being made In all areas. Management attention is being focused on problem areas.
l Data Through 6/30/97 l 100%
90%
80%
70%
60 %
^
I 50 %
40%
i
^
)
20%
d
-=
=
i 0%
Stathng Procedures Recovery Audits Survs Self AFTTS j
Plan Assess-ments l
u Actual aGoal j
l Raw Date l
Apr-97 May 97 Jun 97 Jul-97 Aug-97 Sep-07 Oct-97 Nov 97 Dec-97 Jan-98 Feb 98 Mar 98 Stathng Actual 121 118 118 I
Staffing Goal 134 134 134 Procedures Actual 23 25 25 Proc-dures - Goal 31 30 30 Recovery Plan-Actual 88 88 101 Ricovery Plan Goal" 119 99 132 Audits - Actual 2
5 4
Audits -Goal 2
5 4
5 4
5 7
5 0
Surveillances - Actual 18 33 25 Surveillances - Goal 34 45 43 Se# Assessments Actual
- NA NA 6
NA NA NA NA j
Self Assessments - Goal
- NA NA 9
NA NA 8
NA NA 6
AITTS Cunent Actual 159 140 166 AITTS Current - Goa:
206 202 236 Definition AnalyelWAction This indicator measures progress in Millstone Oversight Six of nine self assessments were completed during the
- Recovery, second quarter. The remaining three have been started The two bars measure actual percentage vs. the goal.
and will be completed in July.
Data Through 6/30/97.
- Self Assessment goals set by the quarter.
Goel Comments
- On 5/27 the total number of action items was increased by 34 and the schedule due dates were revised to provide more realistic goals.
Dets Source M. Baldini x4456l Anstyels by V. Papadopoll x5245l owner:
D Goebelx4300 Page A-51
Milletsno Ovarcight AITTS Aesignmsnta Juno 1997 i
Progress:
outstanding items are being addressed by all organizations. Work off
\\
curves are being utilized to track Individual group efforts.
25o I I (lDataThrough' 6/27/97 15o Good 100 Y
m l
l E
I I
I I
t i
I t
I i
i j
.Feb
. Mar Apr May Jm Jtd Aug Sep Oct Nov Dec Jan l E Overdue MCurrent l Raw Dets Feb-97 Ma -97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct 97 Nov-97 Dec 97 Jan-98 i
Overdue 41 58 47 62 70 l
Current 130 155 159 14o 166 l
Total 171 213 206 2o2 236 j
NRC Commrrments 4
17 4
3 4
Und Restart items 105 114 119 126 125 Definition Analysis! Action Displayed are the number of NR assignments for the Nuclear Breakdown of June data by Department:
Oversight Organizabon at Mitistone in the Action item Traciong Overdue / Total and Trending System (AITTS). Both overdue and total yp g
assignments are shown.
Assignments made to Oversight groups that are designated as PE 38/140 commrtments to the NRC (assignment type:CATC in AITTS) are ECP O/3 led in the table, as well as assignments made to Oversight A&P 13/36 groups that the Millstone units have designated as necessary to A&E 19/54 be completed for their urut restart.
Data is based on all Millstone Oversight alert groups.
h@MM Goel Comments Goal: No overdue items. Any items determined to require item due dates are being screened to deterrane any which resoluton prior to key events (ICAVP, OSTI or mode changes) require resolubon pnor to key events, such as ICAVP, OSTI, or are completed in a bmcq manner.
mode changes.
Defe Source M. Baksni x4456l AnstysJe by:
V. Papadopoll x5245l Owner:
D. Goebel x4300 Page A 52
Milletena Ovarcight Rocovery Picn Action Itom Work Off Curvo June 1997 Progress: Oversight is behind schedule in completing Recovery Plan items.
Corrective measures am being taken to reduce overdue items.
140 -
120 -
i i! 100 ~
Data through ~
6/21/97 f oo.
jeo
.0 m
=~
c~~~~~~~~~~~~~
=
==
~ ~
I s = $ $'
Rs$$ ass $
i
$ 'i f al m$ ssS a
sa s
e
}
-G-Sche &ded Work Off Curve
+ Actual Acton noms Remaining 1
Raw Dets Remainmg items 2/15/97 2/22/97 3/1/97 3/8/97 3/15/97 3/22/97 3/29/97 4/5/97 5/8/97 5/23/97 5/31/97 6/21/97 Actual 99 99 97 96 96 90 77 60 52 52 85 72 Current Schedule 92 92 77 77 70 68 67 25 21 15 74 41 Schedu!s Vanance 0
0 0
0 0
0 0
0 35 37 11 31 Definition Analysis / Action This chart displays the work off curve for the action items in Weekly VP/ Director meetings are conducted to review plan the Nuclear Oversight Recovery Plan. Depicted are the status and to implement corrective action. Management current schedule.
believes of plan schedule will be recovered and that Nuclea: G ersight will not impact unit readiness for restart.
The majority of Oversight intemal process improvements were scheduled to be complete by 3/31/97. Four such initiatives slipped beyond that date, which account for most of the overdue action items. Corrective action underwayis expected to bring three of these issues to closure by 4/18/97. Due to the significant scope of the license commitment review, this activity is rescheduled to be complete by 6/30/97.
On 5/27 the total number of action items was increased by 34 and the schedule due dates were revised to provide more realistic goals.
Action items duc after 10/4 relate mainly to Unit 2 and Unit 1 " readiness for restart" reviews.
Goal Comments The goal is to close out the Recovery Plan items in accordance with the approved schedule, s
T. Houanton no27ol Ans/ysis by; V. P=W x5245lOwrier:
ones source D. Goebel x4300 Pa9e A 53
Stctuo of Ovaraight Condition Poporto Millstena 1 - June 1997 Progress: Improvements are noted in nit areas. Totat open items have been reduced as wellas allitems open greater than 30 days.
i l
l 150 v
f 7p Data through '
,on
- g..
l y
.i l
r.
So l
fl
- S
'{
l 9
MA L
))
v_
m
~
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr E Level 1 Open E Level 2 Open DLevel 3 Open RawDets Feb-97 Mar 97 l Apr-97 May 97 Jun-97 Juk97 Aug-97 Sep. 47 Oct 97 Nov 97 Dec 97 Jan-98 Total CRs 164 181 205 232 214 Open 125 135 133 150 98 L1/>30 days 11/1o 11/10 10/9 8/7 5/5 L21>30 days 114/102 120/113 118/96 138/118 90/69 L3/>30 days o/0 4/o 5/4 4/4 3/2 ResoNed 39 46 72 82 116 Definition Analysis! Action This graph displays the status of Condition Reports (CRs)
Data through 6/26/97, initiated by Nuclear Oversight for adverse, discrepant, or other conditions needing improvement.
Open Condition has been identified. The evaluation for reportabihty and operability, failure mode and/or root cause has not been performed, or, has been performed, but not yet approved.
Resolved Condition has an accepted solution, a clear owner, a commitment for completion and a corrective action date and plan. The corrective action has not been completed by the unit.
Overall evaluation of the unit based on this KPl is as follows:
SAT (Green) No Level 1 or Level 2 CRs open > 30 days without an approved corrective action plan.
UNSAT (Red) Any Level 1 CR open > 30 days without an approved corrective action plan.
MARGINAL (YeDow) No Level 1 CR open > 30 days but a Level 2 CR open >30 days without an approved corrective cebon plan.
Goal Comments No Level 1 or 2 CRs open > 30 days.
Dods Source M. Baksni x4456l Ans/ysle by:
V. Papadopoll x524Sl Owner:
D. Goebel x4300 Page A 54
Statua cf Ovaraight Condition Rcporto i
Mill: ten 2 2 - Juna 1997 Progress: Backlobs continue to increase. Many items remain open with the majority over30 days old.
i 15o 100 Data through 6/26/97 Good 50 l _
. -L
- ?
V O
^
. ~ ~-
a_,
-u--<
m Feb --Mar - Apr -May Jun --Jul Aug Sep Oct Nov Dec Jan Feb - Mar Apr -
-~~
j ELevel t Open E Level 2 Open DLevel 3 Open j i
Raw Dets Feb 97 Mar 97 Apr97 May 97 Jun 97 Jul 97 Aug-97 Sep-97 Oct 97 Nov 97 Dec 97 Jan 98 Total CRs 87 95 107 1o8 124 Open 60 65 76 70 70 L1/>3o days 2/1 2/2 2/2 3/2 4/3 L2/>30 days 58/51 63/58 68/59 63/52 60/41 L3/>3o days C/o 0/o 6/1 4/3 6/5 Resolved 27 3o 31 38 54 Dennition An elalAction This graph displays the status of Condition Reports (CRs)
Data through 6/26/97.
Initiated by Nuclear Oversight for adverse, discrepent, or other conditions needing improvement.
Open Condition has been identified. The evaluation for reportability and operability, failure mode and/or root cause has not been performed, or, has been performed, but not yet approved.
Resolved Condition has an accepted solution, a clear owner, a commitment for completion and a corrective action date and plan. The corrective action has not been completed by the unit.
Overall evaluation of the unit based on this KPI is as follows:
SAT (Green) No Level 1 or Level 2 CRs open > 30 days without an approved corrective action plan.
UNSAT (Red) Any Level 1 CR open > 30 days without an approved corrective action plan.
MARGINAL (Yellow) No Level 1 CR open > 30 days but a Level 2 CR open >30 days without an approveo corrective action plan.
0001 Commente No Level t or 2 CRs open > 30 days.
Oses sowoe M. Bandinis4456lAnsfyeJs by:
V. Papadopoli r5245l Owner:
D. Goebel x4300 Page A 55
Stctuo cf Ovarcight Ccndition Rcporto Mill:t::na 3 - Juns 1997 Progress: Progress is evident in reducing overali numbers ofissues.
i 150 k
100 Data through 6/26/97
+ Good 50
.l.
j j
'~
[;
k h(;
i m
m _ o I
0 I
4
^-
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar ~
r W Level 1 Open ELevel 2 Open DLevel 3 Open l RawDets Feb 97 Mar 97 Apr-97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov 97 Dec 97 Jan-98 Total CRs 152 179 2ou 213 247 Open 96 to9 99 78 73 L1/>3o days 11/5 15/11 11/1o to/8 9/4 L2/>30 days 85/63 93/85 86/6o 63/So 6T32 L3/>30 days o/o 1/o 2/1 5/3 1/1 Resolved
$6 70 101 135 174 Definition Analysle' Action This graph displays the status of Condition Reports (CRs)
Data through 6/26/97, initiated by Nuclear Oversight for adverse, discrepant, or other conditions needing improvement.
Open Condition has been identifed. The evaluation for reportability and operability, failure mode and/or root cause has not been performed, or, has been performed, but not yet approved.
Resolved. Condition has an accepted solution, a clear owner, a comrNtment for completion and a corrective action date and plan. The corrective action has not been completed by the unit.
Overa# evaluation of the unit based on this KPI is as follows:
SAT (Green) No Level 1 or Level 2 CRs open > 30 days without an approved corrective action plan.
UNSAT (Red) Any Level 1 CR open > 30 days without an approved corrective action plan.
MARGINAL (Yellow) No Level 1 CR open > 30 days but a Level 2 CR open >30 days without an approved corrective action plan.
Goal Cornenents No Level 1 or 2 CRs open > 30 days.
Dets Source M. Baldini x4456l Analysis by:
V. Papa & poli x5245l Owner:
D. Goebel x43co Page A-56
Millotona Ovarcight Audit Schadula Adharanca l
Jun31997 Progress: Audits are on track and schedule adherence has been exceIIent.
10 9
e, Data Through '
6/27/97 6
5 4
s 2 t
._ _ R m
01 I
I I
I I
I I
I I
I t
i Jan
~Feb
' Mar Apr May Jun JLJ Aug Sep Oct Nov Dec
, M Audits Performed Audits Scheduled RawDets Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep 97 Oct-97 Nov 97 Dec-97 Audits Scheduled 2
4 4
2 5
4 5
4 5
7 5
0 Audtts Penormed 2
4 4
2 5
4 DeRnition AnalysisfAction This charts depicts the schedule adherence of Oversight our audds exned Nune:
Audits at Millstone Station. The, audit schedule for the Rad Protection year was approved in January,1997. The audit is considered perforrned when the exit occurred.
e s Training Data Through 6/27/97, Goal Comments Goat Perform all audits as scheduled.
B. Kaufman x2246lAnesysis by:
B. Kautman x2246l Owner.
T. Whee x4463 Dets source l
Paos A 57
Millatena Ovarcight Survaillcnco Schcdulo Adharanco Juna 1997 Progress:
schedule adhenence has declined in June.
j 50 40 Data Through 30 20 j
ll 10
_ [,.
,w.
.4 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Mar Apr f MScheduled Surveillances Performed M Unscheduled Performed
-e-Surveillances Scheduled f RawDate i
Jan.97 Feb 97 Mar-97 Apr 97 May-97 Jun-97 Juk97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Surv Scheduled 22 16 19 34 45 43 Surv Performed (sched) 9 9
12 18 33 25 P*rformed (unscheduled) 14 12 11 17 7
8 Performed / Scheduled by Unrt:
Und1 5/6 2/7 7/8 6/11
&7 7/8 Unit 2 2/12 3/4 2/4 7/17 17/26 13/27 Unit 3 2/4 4/5 3/7 5/6 10/12 5/8 Definition AnalyelalAction This chart depicts the Oversight surveillance scheduled and the As of June 30, there was a decline in productivity due to over number of them performed. The table shows the breakdown of the commitment in our rolling schedule (Unit 2).
scheduled surveillances performed vs. those scheduled by unit. It Clso shows the total number of unscheduled survesances Data Through 6/30/97.
performed.
Goal Commenen Pr' im;rmry goalis 100% schedule adherence. As of May 1,1997 June data:
J surveillances will be performed within 2 days.
(Perforrned)
Scheduled Unscheduled Unn 1 7
0 UnH2 13 0
Unn3 5
8 osas source:
L Borek x3086lAns& sis by:
L Bozek x3086l Owner:
P. Achardson x4302 Paos A 58
Nucicar Employco Concarna Program Progroes Millstone - June 1997 -
Progress:
The drop in usy 1997 new concerns has mitowed ecP to focus resources to keep the number of unresolved concerns from Increasing e5 60 NOTE: No 55 Resolved / Overdue During Dec, Jan, l Data Through 50 6/20/97 45 Feb. Mar 40 30 25 N
n m
i j
Dec Jan Feb Mar Apr May Jun Jul Aug Sect,-.Qst Nov Dec Rec'd Resolved (This Month) l C 3 Total Resolved /Pending Closure M Resolved / Overdue
-*-Total Unresolved Row Dats 1996 1997 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Now Recerved 6
8 12 12 27 8
10 Rate / Year 72 96 144 144 324 96 120 R' solved 11 23 13 10 21 12 9
UnresoNed < 45 Days 11 4
12 14 15 12 13 Unresolved 45-60 Days 5
3 2
5 12 8
8 UnresoNed 290 Days 20 14 6
3 1
4 5
Total Unresolved 36 21 20 22 28 24 24 ResoNed/Pending Closure 22 31 37 49 57 60 j
R
- solved / Overdue l
0 0
0 1
2 2
l NOTE: Data listed through 6/20/97.
Definition Analysis / Action The ECP recetves, and attempts to resolve, concoms which are both As of 6/20/97,24 concerns are unresolved at Millstone.
drectly sasety rented and non-safety related The data refiects both types Based upon the current filings, ECP can expect to of e neems.
receive well over 100 concerns during 1997, Beginning January 1,1997 the Ernployee Covems Program htroduced
' Resolved
- as a category of concem st*a ineet this conditon a concem must have an accepted solute sar owner, a material commitment for completson and a correctwo acten completon date and plan. The data h his table reflects this new dersvtion.
Begrvung web January data. ECP is plottng the number of ResoNed/Pendng Closure concems as well as any concems which have been ident&ed as resoked, but whose correctNo acten completion is overdue for completion.
Goal Comments The ECP Goal is to have no unresolved concem older than one year by in the report, the statistes esplayng 'ResoNed/Pending Closurs' 2/13/97, no unresolved concem older than 3 rnonths by 5/13/97, and no have been modified to reflect trendng issues vs. case Ides to make unresoNed concem older than 45 days by 7/13/97 this nformaton consistent with other categones.
The long term goal established in the ECP Ccmprehenske Plan calls for concem resolutaon withe 45 days of banal fling.
Does souros: C. Mbako x4541 l AneHe by: C. Mhako x454 t l owner:
E. Morgan x4335 Paos A 59
Numbar of NU cnd NRC Roccivad Conecrno Millstena - Juno 1997 Progress:
May results continues the overait improving trend of NRC vs NU concerns received.
80
{
70 i
60 50 40 Data Through 30 6/20S 7 1
E ALumLam /
2:
v
=
_1994 1995 1996.-..Jan
.._Feb Mar.
Apr - - - May ---.-Jun.------Jul
- -Aug Sep -
97 97 97 97 97 97 97 97 97 j
W NU Rec'd M NRC Rec'd i
Raw Dets
)
1997 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec i
NU Recetved 8
12 12 27 8
10 NRC Received 17 9
11 4
8 5
NU Rec'd YTD 20 32 59 67 77 NRC Rec'd YTD 17 26 37 41 49 6
NOTE Data hated through 6/20/97.
i Definition Analysia/ Action ECP concerns include:
Year to-date, the NU ECP received more concems than were received by the NRC. A continued decline in the number of
- 1) Nuclear safety concems, which are nuclear or radiological concems filed with the NRC, combined with an increased svents or observations believed to violate regulatory requirements number raised with the NU ECP, is evidence of increased or NU policy or procedure employee confidence in our intemal resolution process.
- 2) Other safety concems Data through 6/20/97 3
- 3) Other Employee concems which are not directly safety related l
NRC allegations include concems received from licensee employees, contractors, the general public and concems self-generated by NRC staff based upon observations and/or media reports.
s i
1 Data Source: C. Mt ako x4541 l Analysis by: C. Mhako x4541 lOwnen E. Morgan x4335 Page A-60
' Millateno Empisyco Concarno Confidantielity Trand Juna1997 Progress:
Higherlevels of confidentiality waivers Indicate employee confidence in the ECPprocess.
so%
I No one requested 70 %
confidentialityin ! f 60%
June,1997 l Data Through sn 6/20/97 l
30 %
2o%
'O
==
__- ~= ---X c,-JT=
.2
_a i
0%
I i
l I
i l
l l
l t
1 -
l Jan - Feb Mar Apr ~-~ May Jun Jul Aug Sep Oct Nov Dec
~
EAnonymous EConfidentialtiy DNo Confidentiality D3rd Party l
)
Raw Dets 1997 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Anonymous 4
1 5
7 1
4 Confidentiahty 1
2 1
4 2
0 No Confidentiahty 3
9 6
16 4
6 f
3rd Party 0
0 0
0 0
0 i
Tetal 8
12 12 27 7
10 Definition Analysia/ Action For each concern filed by an identifed concerned individual, The percentage of individuals warving confidentiality he/she determines whether to request or waive confident-lality, continues to exceed anonymous concemees and those Anonymous concerns have no confidentiality contsraints.
requesting confidentiality.
Third party concems are those received through an ECP Peer R:presentative or similar person where the concern has an Data "i htough 6/20/97.
identifiable origin, but the identity of the concerneo is not known.
This trend report tracks the selections made by identifed concemees and any anonymous or thrid party concerns r;ceived.
Goal Comments Dets source: C. A Mhako x4541 l Analysis by: C. A. Mhako x4541 l Owner:
E Morgan x4335 Page A41
Milleteno Empicyco Cencarno Typo Trond JunD1997 Progress:
The relative number of Non techinal, Non-Nuclear Safety issues dominate.
100 %
00 %
Note: No nuclear safety concerns received in May,1997 70 %
1 i
en I Data Through
~
6/20S7 So%
40 %
30 %
20%
.,gg 0%
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec I
W Nuclear Safety E Personnel Safety DOther Raw Dets 1997 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Nuclear Safety 4
,4 4
11 o
5 Prrsonnel Safety 0
2 1
2 1
1 Otner 4
6 7
15 11 5
To*l 8
12 12 28 12 11 Definition AnalyelalAction ECP currently trends three types of concems: Nuclear Safety, Concems continue the multi-month trend where non.
Personnel Safety and Other, nuclear safety issues far outnumber nuclear safety related issues.
Nuclear Safety Concems are concerns which in a broad interpretation could have an impact on plant or public safety or Data Through 6/20/97.
the quality of plant operations. These would include concems about sytems, components, nuclear procedures, engineering, ctc.
Personnel Safety covers concems related to industrial safety cnd similar issues.
Other covers management issues, compensation, work place conditions, fraud waste and abuse, etc.
Goal Commente Dets Soures: C. A Mhako x4541 l Analysis by: C. A. Mhako x4541 l Owner:
E. Morgan x4335 Page A 62
l t
l i
Millateno Point Managomont Obaarvations of Training June 1997 1
l l
80 -
70 -
i
>s j 60 -
/,..,
1 50 -
% '? + '
'e g 40 -
^;s
<; a ;
'- w.,
l n
L+ g:
o 3o -
2
l 3
- ss, 5
< A,:'s
- ~ 20
, ;; o J
o t
d'
+
10 -
' is O
0 I*
+3
" ' + ' '
Jan-97 Feb-97 Mar 97 Apr-97 May-97 Jun-97 Date
- Data Jan-97 Feb-97 Mar-97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Totals 6
0 10 17 80 60
' Definition '
^
Observatons for whch an evaluabon report was submitted.
i industry Benchmark / Nt.1 Goel -
l-
< Co.Timts Unit Trainmg Advisory Councils are developmg expectabons for Data as of 06/24/97 managementobervabons of training.
Unit 1 and Unit 3 are goals have been established as of 06/06/97.
'Anatysis/ Actions
=l Data sourest observabon Evaluabon Reports l Analysis by: A. Gtverson lOw er: Directors l
l
s i
Nuclear Training Dopartment CAP Progress June 1997 Progress:. On Schedule r
70 60 Good l
Data
'O '
Through y
I
'-- T
. _i 6GOS7 E 4'
/
E
/
Goal: 99%
h 30
/
l Complete p
9/20/97 l 20 -
\\
. _.. = -
-1 Fe&97 Mar-97 Apr 97 May-97 Jun 97 Jul97 Aug-97 Sep 97 I
Open
--+--Work Off Goal Raw Data Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov 97 Open 70 67 66 46 22 Work-Off Goal 70 67 66 51 22 15 7
1 Definition Analysis / Action Corrective Action Plan includes 70 items.
No action required. CAP is on schedule, One item is not due until January 1998 and is not included in the graph.
j 4
Goal Comments Complete Corrective Action Plan on schedule with no Data as of 06/24/97, late items.
Overall on schedule.
2 items have been re-opened.
]
Data Source: CAP Matrix & AITTS l Analysis by: A. Giverson l Owner: M. Ross i
7/1/97 RAPFILE1.XLS
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NRC Plan Dated 3724/97. MP3 Status Dated W3W97 Sch sfuled_Date.
Estimated.
N-t Besponikle ACB_Beastyjar_
pate fo_r NB.C BtMew.
i Zone / Document No.
Ogscription of NRC_!!ent NRQ EP_Bevie NRC Review Statug Campi te t
1.1 ACR 10773 RSS and OSS P6 ping Temperature May Be Higher Than NRR 07/23/97 08/12/97 Analyzed (NRR Review Engineering Analysis. DRS Inspect DRS Installation)
ACR 10773. eel 96-06-13. LER 96-007-01. LER 96-Od7-02 a
_......................................................................L.....................................
1.2 eel 96-06-13 RSS and OSS Piping Temperature May Be Higher Than NRR 06/30/97 07/21/97 Analyzed (NRR Rewew Engmeering Analysis. DRS Inspect DRS Installation) j ACR 10773. eel 96-06-13. LER 96-007-01. LER 96-007-02
.......-..........-.-....--....m..................-
,...m......~..........-~..~........-
1.3 LER 96-007-01 RSS and OSS Piping Temperature May Be Higher Than NRR 07/28/97 08/13/97 Analyzed (NRR Rewew Engineenng Analysis. DRS Inspect DRS Installation)
ACR 10773. eel 96-06-13. LER 96-007-01. LER 96-007-02
.........m.......m.......................~......m.............m.......................................~
1A LER 96-007-02 RSS and OSS Piping Temperature May Be Higher Than NRR 07/28/97 08/13/97 Analyzed (NRR Review Engineenng Analysis. DRS Inspect DRS Installation)
ACR 10773. eel 96-0G-13. LER 96-007-01. LER 96-007-02
.............................-.--..............-.-.....m............-..<
................~..-mm..-......mm......m...-..
1.5 LER 96-007-00 RSS and OSS Piping Temperature May Be Higher Than NRR 07/28/97 08/13/97 Analyzed (NRR Review Engmeenng Analysis. DRS Inspect Insta!!ation)
ACR 10773. eel 96-06-13. LER 96 007-01. LER 96-007-02
........~...~.m...............-...-m-.............~m...m.--..-..~......m.....mm.....~..................m......m..m.
10.1 ACR 11322 Closure of PtR Without Addressing Design Feature of DRP 02/03/97 02/21/97 Closed Closed Affected Components l
..............................-.~.mm m m... ~. ~.. ~... m - -....
.... ~..... m m m.............. m m............... -........-....
11.1 ACR 10774 Turbine Driven Auxillary Feedwater Design Concems SPO(!)
05/21/97 06/12/97 To the NRC ACR 10780. ACR 10774. NU Letter B15397. URI 96 201-40 for Review on eel 96-201-04. eel 96-201-05 6/12/97
....................--m.--~~.mma.mmm-.---...-~~~..-~.m.~...-~..-~-~.m..........-~~........m.m.........-~..............'.-
t 11.2 ACR 10780 Turbine Driven Auxiliary Feedwater Design Concems SPO(t) 07/22/97 08/12/97 ACR 10780. ACR 10774. NU Letter 815397. URI 96-201-40, i
eel 96-201-04. eel 96-201-05 I
..........................m.--.m...-.............~.m...............................................
TBD = No Action Required Frorn NU. NRC To Detemune When Review To Be Completed.
f i
i
~~
I
$@911giggl D Estimated.
NRC Besponsittle AC!LR9JKivfor Date fot.
IIEC-O"!'*-
Z9ne/ Document No.
Description of MRC teem ERQ EP Review -
NRC Review Status Compi !t t
11.3 eel 96-201-04 Tur*Jine Driven Aux 8ary Feedwater Design Concems SPO(t) 07/16/97 08/05/97 ACR 10780. ACR 10774. NU Letter B15397. URI 96-201-40 j
eel 96-201-04. EEI 96 201-05
....m.............m..m......-........
11.4 eel ' 96-201-05 Turbine Driven AuxBary Feedwater Design Concems SPO(1) 07/16/97 08/05/97 ACR 10780. ACR 10774. NU Letter B15397. URI 96-201-40 eel 96-201-04. eel 96-201-05
......m
~.m.
..m..................m.
11.5 URI 96-201-40 Turbine Detven AuxiRary Feedwater Design Concems SPO(f) 05/29/97 06/18/97 To The NRC ACR 10780. ACR 10774. NU Letter B15397. URI 96-201-40 eel 96-201-04. eel 96-201-05 For Review On 5/30/97
...m.................................m...m...................,...m...................m....
- 1.6 Letter B15397 Turbine Driven Auxinary Feedwater Design Concerns SPO(t) 07/23/97 08/12/97 ACR 10780, ACR 10774. NU Letter B15397. URI 96-201-40 EE! 96-201-04. eel 96-201-05
.omm.......om.-~.---.---.o......~........--...........m 12.1 ACR 06323 Contamrnent Foundation Erosion NRR 07/24/97 08/13/97
........m....
ACR 06323. URI 9644-13. URI 96-04-14. URI 96-04-15. IFl 94-11-09 M3-97-0317. INF Notice 97-11
..m.........--
......m...........m.....-.......................-
12.2 ACR M3-97-0317 Containrnent Foundation Erosion NRR 07/10/97 07/31/97 ACR 06323. URI 96-04-13. URI 96-04-14. URI 96-04 15. IF1 94-11-09. M3-97-0317. INF Notice 97-11
.......m.............--..-....-.o-o.......~...-m.......m.....m...
12.3 URI 96-04-13 Containment Foundation Erosion NRR 05/24/97 8 06/16/97 To The NRC ACR 06323. URI 96-04-13. URI 96-04-14. URI 96-04-15. IFl 94-11-09. M3 97-0317. INF Notice 97-11 For Review On 6/6/97
..m...................-.m-.-.....m.o..-..m..m..~.....................
12.4 URI 96-04-14 Containtnent Foundation Erosion NRR 05/24/97 '
06/16/97 To The NRC ACR 06323. URI 96-04 13. URI 96-04-14. URI 96-04-15. IFl For Review On 94-1109. M3-97-0317. INF Notice 97-11 6/6/97
..................--.-o..~..--.~..m.-m.m....~-.o....-...~..............
12.5 URI 96-04-15 Contamment Foundation Erosion NRR 06/16/97 To The NRC ACR 06323. URI 96-04-13. URI 96-04-14. URI 96-04-15. IFl 05/24/97 l' 9411-09, M3-97-0317. INF Notice 97-11 For Review On 6/6/97
........................m.......................m...I 12.6 IFl 94-11-09 Containment Foundation Erosion NRR 07/24/97 08/13/97 ACR 06323. URI 96-04-13. URI 96-04-14. URI 96-04-15. IFl 94-11-09. M3-97-0317. INF Notice 97-11
......mo.............
.........m.
.m.mm........
.....m......
f F
r i
i TBD = No Action Required From NU. NRC To Detemune When Review To Be Completed.
i 2
i 5
i
_~
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NR_Q.
Btsponsitple ACBEeMir.ftr Date for NRC BRYifw_
Zone /Da...ut No-Description of NRC ltem flRQ EP_Reykw NRC Review Status C9!npfgig 13.1 ACR M3-96-0326 CCP System Operation Above Design Temperature: 3 SPO(t) 07/24/97 08/13S 7 RHS*HCV 606/607 Failing Open ano Other Failure Modes ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00. LER 96-040-00, M3-96-0887 13.2 ACR 13427 CCP System Operation Above Design Temperature: 3 SPO(!)
07/25/97 08/13/97 RHS*HCV 606/607 Failing Open and Other Failure Modes ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00. LER 96-040-00. M3-96-0887
..m...............m...................................m 13.3 URI 96-08-20 CCP System Operation Above Design Temperature: 3 SPO(l) 09/09/97
- 09/09/97 RHS*HCV 606/607 Failing Open and O:her Failure Modes ACR 13427. URt 96-08-20. IR 96-201 M3-96-0326. LER 96-
~
028-00. LER 96-040-00. M3-96 0887
....m.............m................................................................
13.4 LER 96-028-00 CCP System Operation Above Design Temperature: 3 SPO(I) 07/24/97 08/13/97 RHS*HCV 606/607 Failing Open and Other Faiture Modes l
ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00. LER 96440-00. M3-96-0887 l
..m
.4.
....m........
13.5 LER 96-028-01 CCP System Operation Above Design Temperature: 3 SPO(t) 07/25/97 1
08/13/97 RHS'HCV 606/607 Failing Open and Other Failure Modes ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00.LER 96-040 LOO M3-96-0887 l
........m........m.....-.~.m-..-..............<.....m.............
.....m..
13.6 LER 96-040-00 CCP System Operation Above Design Temperature: 3 SPO(t) 07/01/97 l 07/22/97 RHS*HCV 606/607 Failing Open and Other Failure Modes i
ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00. LER 96-040-00. M3-96-0887
.................~...m.....m......m...m.m........m..............
13.7 ACR M3-96-0887 CCP System Operation Above Design Tempera *ure: 3 SPO(1) l RHS*HCV 606/607 Failing Open and Other Failure Modes ACR 13427. URI 96-08-20. IR 96-201. M3-96-0326. LER 96-028-00. LER 96-040-00. M3-96-0887
............................--.......~...m..-~..........%...................-m........m.........
14.1 ACR 07745 Catety Grade Cold Shutdown Operational Configuration
$PO(l) 06/12/97 h 07/03/97 To The NRC Control ACR 07745. URI 96-01-07 i
For Review On 6/24/97
....m........m.............-..........~..~...~.~.-...~~.m............~..m 14.2 URI 96-01-07 Safety Grade Cold Shutdown Operational Configuration SPO(1) 04/19/97 l
05/09/97 To The NRC Control ACR 07745. URI 96-01-07 '
For Review On 5/8/97
...........-m.....mm....-o..............'o.......................................
e l'
l TBD = No Action Required From NO. NRC To Determine When Review To Be Completed.
l 3
1 s
i I
.a Scheduled Datt Entimattd_
NEE-Bejpppn11ttle ACB.Beadylor D#te for NRC_
Berket Zone / Document NE Description of NRC ttefn
.NRg EP Beykw NRC Review Status Compiele 15.1 ACR M3-96-0159 Letdown Heat Exchanger Leakage and Design Discrepancies SPO(l) 05/10/97 I 05/31/97 To The NRC ACR M3-96-0159, eel 96-06-15 I
For Review On 5/28/97 m.......m......--.......m.m.m...m.................m.....m..................
15.2 eel 96-06-15 Letdown Heat Exchanger Leakage and Design Discrepancies SPO(t) 05/29/97 f 06/19/97 To The NRC g
ACR M3 96-0159. eel 96-06-15 i
For Review On 6/18/97
.......m...............--m............m..........m.............m-.............
16.1 ACR 019'85 (U2)
Dual Function Valve Control and Testing -
SPO 02/07/97 -
02/26/97 To The NRC Updaled in IR 97-02 NRR
- h For Review On 2/21/97 r
.-....m..................--.-m..................-...............m........m..m..........mm..........m...........m...m..
17.1 ACR 07266 RCP Seal Housing Leakage and Bolt Corrosion DRS 09/23/97 N 09/30/97
.m.......mo..m...........om......................--mmm................sm t.........
...m 18.1 ACR 10562 Control and Use of Vendor Information DRS 06/07/97,8 {
06/27/97 To The NRC eel 96-201-15. eel 96-201-18. eel 96-201-19s URI 96-201-For Review On
- 17. G 2 1
6/20/97 U
......-m.--m.m.......o-....m-......--....--.....a...m.mm.-...m.m.m..do..=m...-...............---.....
06/21/97 f 18.2 eel 96-201-15 Control and Use of Vendor Information DRS 07/12/97 eel 96-201-15. eel 96-201 18. eel 96-201-19. URI 96-201-
- 17. G.2 i
....m.......m.....m..-.......m.m~~.....m..-.....-.................~.m......~...l........m...m......m.............
18.3 eel 96-201-18 Control and Use of Vendor Information DRS 07/01/97 -
07/22/97 eel 96-201-15. eel 96-201 18. eel 96-201-19. URI 96-201-l
- 17. G.2 l
~..................................................-.m...................................................................................
18.4 EEI 96-201-19 Control and Use of Vendor Information DRS 04/26/97 '
05/16/97 To The NRC eel 96-201-15. eel 96-201-18. eel 96-201-19. URI 96 201-For Review On
- 17. G.2 j
l 5/16/97
__.........._........._.._....._____...m...._..._....._.__........_......................._......................_..............._.._
18.5 URI 96-201-17 Control and Use of Vendor information DRS 10/97 0909/97 To The NRC Closed in IR 97-02 eel 96-201-15. eel 96-201-18. eel 96-201-19. URI 96-201-For Review On Dated 6/24/97
- 17. G2 4/14/97
.....m.....mmm..m...-...........m......-....mo.......1..............mm........m..................
19.1 URI 96-201-16 Resolution of AFW Valves HELB Concem SPO(l) 06/24/97 07/16/97
.........................om-.-.--..................
.....m...........m................m 2.1 CEI 96-201-01 UFSAR not updated to reflect actual plant conditions (50.71 SPO(L) 07/16/97 08/05/97 violation) j Degree the FSAR Needs to be Updated Before Restart
+
ACRs: 10780.12868.12215.10525.13778. M3-96-0930 l
't L
...--....m.....m...--........m...-.....mm.....m.................-~~..---.....-..........m...m.....
i TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
4 l
1 p
h
(
.= +
Schedhi Date.
Estimated.
Responsiten ACR needy for Date for NRC R**W i
ZonefDocument No.
Description of NRC ltem NRC EP Redan NRC Review Status Comolm I
3 20.1 VIO 96-59-13 Review Oulput from Hannon's Employee Concems Report SPO(L) 07/02/97 07/23/97 VIO 96-59-13 l
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--.m
-~
t 21.1 None Associated Fatigue Cycle Open items l'P 37750 DRS N/A j Complete Closed IR 96-Closed IR 96-01 (Unit 2 issue) 01
.............................................................m.........~........................~......~
22.1 None - Associated Part 70 Storage and inventory IP 84750 DRS N/A !
Complete Closed IR 96-Closed IR 96-05 (Unit 1 Issue) 05-
..--.m..mmm.....mm--.-...--....--.......-...--..-......---....~.---...
s 23.1 None Associated Formenty of Non-Routine Securtly Activities and New Fuel DRS N/A Complete Closed IR 961 Closed IR 96-05 i
x Secunty IP 81064 05
..m==.-m....--..--..............-..~..mm..mmm..(...m.............-....'
f 24.1 URI 9641-08 Ovedap Tesung of RPS/ESF SPO(I) 05/31/97 06/21/97 To The NRC LER 97-017-00, URI 96-01-08 For Review On f
I 6/12/97
......................--.m..--.--........I mm....--...m.........-
24.2 LER 97-01740 Ovedep Testing of RPS/ESF SPO(l) 07/26/97 08/13/97 LER 97-017-00, URI 96-01-08
........--.-m.m.-m.m.-~~....--~.......mb..m.......~..........
t 25.1 ACR M3-96-0912 Material Equipment and Par".s List (MEPL) Program NRR 02/20/97 i 03/08/97 To The NRC Evalua90n DRS I
For Review On i
URI 95-07-10. eel 96-201-43 ACR M3-96-0912 3/7/97
.........-.--.m.--....-....---.-~m.-..........m........-...~.m.............-
k 25.2 URI 95-07-10 Material Equipment and Parts List (MEPL) Program DRS 06/$6/97 07/07/97 Evaluallon NRR URI 95-0710. eel 96-201-43, ACR M3-96-0912 I'
....m==m.m..mo
..-~
.. ~
...-.m...m
- l.m.
~...
m.m.....m.mm....
i 25.3 eel 96-201-43 Material Equipment and Parts List (MEPL) Program NRR 06/19/97 07/10/97 I
Evaluation DRS URI 95-07-10. eel 96-201-43, ACR M3-96-0912
?
..............m....---.--
m.--
-..-mm.
s mmm....
m
-~~......mm 26.1 ACR M3-96-0277 Motor Operated Valve Program GL 89-10 DRS 08/04/97, 08/13/97 ACR M3-96-0277 ACR M3-96-0278, M3-96-0627,12862 t
LER 96-019-00, LER 96-020-00, LER 96-035-00, URI 95-17
- 09. IFl 95-01-01. IFI 95-17-01. IFl 95-17-02, IFl 95-17-03, IFl
)
{
95-17-04, IFl 95-17-05, Info Notice 97-07 i
26.10 E'l 95 17-01 Motor Operated Valve Program GL 89-10 DRS 07/02/97
'l7/23/97 ACR M3-96-0277 ACR M3-96-0278, M3-96-0627.12862 LER 96-019-00, LER 96-020-00 LER 96-035-00, URI 95 09, IFl 95-01-01. iFi 95-17-01, IFl 95-17-02. IFI 93-17-03 IFI
.l
-4 95-17-04, IFl 95-17-05. Info Notice C7-07 l
....m.--...mmm.........mm...m....................m.,...........mm.......................
i TBD = No Action Required From NO. NRC To Determme When Review To Be Completed <
i 5
i rl t
f
f SchedwiesLDLitm_
Estimatest MC_
Besponalble ACR Ready for Date for NEG.
OIM Zone / Document N9.
Description of NRC ltem J4RC EP Revient NRC Rev%
Stahls MM 26.11 IFl 95-17-02 Molor Operated Valve Program GL 89-10 DRS 07/02/97 '
07/23/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627,12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 09, IFI 95-01-01. IFl 95-17-01, fF195-17-02. IFl 95-17-03. IFl f
95-17-04. lFl 95-17-05. Info Notice 97-07 l
................................-..................-...m.m.m........-...-.......--.............-...-...............................~.
26.12 IFl 95-17-03 Motor Operated Valve Program GL 89-10 DRS 07/02/97!
07/23/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 09. IFl 95-01-01. IFl 95-17-01. IFl 95 17-02. IFl 95-17-03. IFI 95-17-04. IFl 95-17-05. Info Notice 97-07 l
-.......-...o-~~....-m.u,.m.......---.~.m~.--~..----~~~.=~~~~~~~~~.~'.-~....-~~.-~~a..-.a===*~.-~~~.~~~~~~~~
26.13 IFl 95-17-04 Motor Operated Valve Program GL 89-10 DRS 07/02/97:
07/23/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862, i
LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 '
- 09. IFl 95-01 01. IFl 95-17-01. IFl 95-17-02. IFI 95-17-03, IFl
/
95-17-04. IFI 95-17-05, into Notice 97-07 i
.-.~.m............~.....-.......-~.........~.-.............--................
26.14 IFl 95-17-05 Motor Operated Valve Program GL 89-10 DRS 07/02/97 07/23/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862 l
LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 L
- 09. IFI 95-01-01. IFl 95-17-01, IFI 95-17-02. IFl 95-17-03. IFI j
95-17-04. IFl 95-17-05. Info Notice 97-07 3 I m m...............~........-
.......=== = =.
.......-~ ~......
.m
.o= =..-=i
.m m i
26.15 LER 96-019-01 Motor Operatec Valve Program GL 89-10 DRS 06/02/97 06/21/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627,12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95,
- 09. IFl 95-01-01. IFI 95-17-01. IFl 95-17-02. IFl 95-17-03. IFl 95-17-04. IFI 95-17-05 I
m.- -..-o..
no.......
..-...............- -.--......y.1...............m...........................-
26.2 ACR M3-96-0278 Motor Operated Valve Program GL 89-10 DRS 08/01/97 l 08/13/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862 I
LER 96-019-00. LER 96-020-00. LER 96-035-00, URI 95 f
- 09. IFI 95-01-01, IFl 95-17-01. IFI 95-17-02. IFl 95-17-03. IFl n
95-17-04. IFl 95-17-05. Info Notice 97-07
.-.....................--.~..~.-~~~~~..-~~~~~~~~~~~~~.--.--an=====~----~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-~~
26.3 ACR M3-96-0627 Motor Operated Valve Program GL 89-10 DRS 07/25/97 :,
08/13/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862 LER 96-019-00. LER 96-020-00. LER 96-035 00. URI 95 -
- 09. IFI 95-01-01. IFl 95-17-01, IFl 95-17-02. IFl 95-17-03. IFl t
95-17 04. IFl 95-17-05. Info Notice 97-07
...-..-........~......~.......a.=~....--.....-----.~.-~~.=~~.--~~.--.m.a..........{)a{..~......u==..~........-....--.......--..-.
L TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
3 6
i k.
.a.
. ~. --.
.s <
kheduled_Dato.
Estimated NEC_
Reznons_He ACfLBeadrJ9t Done tot NRC.
Revim.
R ZonelDocument No.
Denniption of NRC flem NRC EP_Bevhwj PIRC Reyim Status GCfD1dt!t
-26.4 ACR 12862 Motor Operated Valve Program GL 89-10 DRS 08/0857 08/13/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627,12862 O
LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95-17
- 09. IFl 95-01-01. IFl 95-17-01. IFI 95-17-02. IFl 95-17-03. IFl 9517-04. IFl 95-17-05, Info Notice 97-07
' 26.5 LER 96-019-00 Motor Operated Valve Program GL 89-10 DRS 08/05/97 08/13/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627,12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 09. IFl 95-01-01. IFl 95-17-01. IR 95-17-02, IFl 95-17-03. IFl s
t j
95-17-04. IFl 95-17-05. Info Not: e 97-07
...~......
mom.m...
26.6 LER 96-020-00 Motor Operated Valve Program GL 89-10 DRS 68/01/97 08/13/97 ACR M3-96-0277, ACR M3-96-0278. M3-96-0627.12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 y
- 09. IFl 95-01-01. IFl 95-17-01, IFl 95-17-02. IR 95-17-03. IFl 95-17-04. IFl 9517-C5. Info Notice 97-07
..........m...--...........a.-o......m.........................<
26.7 LER 96-035-00 Motor Operated Valve Program GL 89-10 DRS 09/06/97 09/27/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627,12862 LER 95-019-00. LER 96-020-00. LER 96-035-00. URI 95.
- 09. IFl 95-01-01. IFl 95-17-01. IFl 95-17-02. IFI 95-17-03, iFi t
95-17-04. IFl 95-17-05. Info Notice 97-07
....om.m......--............m.--.ao.....mo...ono.mm.o...m..~.--...mmm.......mm..........mm...m....
26.8 URI 95-17-09 Motor Operated Valve Program GL 89-10 DRS 06/16/97 07/08/97 ACR M3-96-0277. ACR M3-96-0278. M3-96-0627.12862 LER 96-019-00. LER 96-020-00. LER 96-035-00. URI 95 L
- 09. IFl 95-0101. IFl 95-17-01, IFl 95-17-02. IFI 95-17-03. IFI 95-17 04. IFI 95-17-05. Info Notice 97-07
....................................................om.m............._....................~.m......................l..................._..........._.....................
26.9 IFl 95-01-01 Motor Operated Valve Program GL 89-10 DRS 07/07/97
~
07/26/97 ACR M3-96-0277. ACR M3-96-0273. M3-96-0627.12862 LER 96-019-00. LER 96-020-00. LER 96 035-00. URt 95 i g
- 09. IFl 95-0101. IFl 95-17-01. IFl 95-17-02. IFl 95-17-03. IFl
[
95-17-04. IFl 95-17-05, Info Notice 97-07 m.............................~...--...-~......-~~...mm..mm.o.............~.mm...m....m..~.......mm.............P.....
27.1 PPR G.1.C. G.2 Resident Emphasis: Missed Surveillances/ Test Control SPO(l)
N/A Complete Closed IR 96-Closed IR 96-08 k
...................m.......
m a.
a===..o m o...oon
...=*..
=......a m...o.m...
.~.m....
08
.--.m.o.
mm
..m-l 26.1 PPR G.1.C Resident Emphasis Diluton Events SPO(f)
N/A Complete Closed IR 96-Closed IR 96-08
}
-.....mm.mm..mm..............--.m.................m........~....I...'...mo.......08 L
.......................m.....
29.1 PPR G.1.C Resident Emphasis: Feedwater Hammer DRS N/A Complete Closed IR 96-Closed IR 96-01 m...
............~.m m.
-mn
.~
.m m
.m.
...........01 r
[
l TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
[
7 i
m m m
+,
t I
Sch ouhd3atit.
Estiinated E C-t E'X f*-
I Responsibig ACR Ready for Dets_for EMC_
Zone /Decument No.
Description of NRC ftem
.NRQ EP Rttew :
NRC Review Status C9ERIC19 l
i 3.1 ACR 05715 Reactor Power increase When Unborated Cation Demin DRP 06/19/97 07/11/97 Placed into Service 3CHS-DEMfN2
................................m.,.......................m..................a(......................................
30.1 ACR, M3-96-0855 Resident Emphasis:AFW Check Valve Leakage DRS 02/22/97 03/11/97 To The NRC Closed in IR 97-02 ACR M3-96-0855. G.1.C. IR 95-31 For Review On Dated 6/24/97 3/11/97
_........................................................................l..........................................
30.2 IR 95-31 Resident EmphasisAFW Check Valve Leakage DRS 06/17/97 07/09/97 IR 95-31. G.1.C i
......mm.........mo.............m................................j..............m........................................
31.1 PPR G.1.C. G.2 Resident Emphasis: Work-Arounds and Abuse of Use-As Is SPO(f) 07/25/97 08/09/97 Deficiencies
...................m........m...m..............m.................... m.................................................
32.1 NOV 94-16-05 Resident Emphasis:AWO Quality and Backlog Control G 2 DRS 05/24/97 06/14/97 To The NRC L
NOV 94-16-05 For Rew" n On 6/13W
~
.........-............m..mm.......um.m............'...........m.o.............................m.......................................
33.1 IFI 97-01-07 Seismic II/I DRS 07/0I/97 !
i 07/22/97 i
IR 96-201. G.2. IFl 97-01-07. LER 96-003-00. ACR M3,
0563. CR M3-97-0850
..................mm...~.........-..........m~.......~..m........m........m.<.............~.........m......................................
33.2 LER 96-003-00 Seismic II/l DRS 05/06/97 05/27/97 To The NRC IR 96-201. G.2. IFl 97-01-xx LER 96-003-00. ACR M3 96-For Review On I
0563. CR M3-97-0850 S/22/97
.......................................m.mm.............~.............~......l...................................................~.
I 33.3 ACR M3-96-0563 Seismic II/I DRS 06/03/97 06/23/97 IR 96-201 G.2. IFI 97-01-xx. LER 96-003-00. ACR M3 0563. CR M3-97-0850 6
............m....m..........mo..m.--.....m..........m.......mmo............~.Jm.....................mm..mmm...........................
33.4 ACR M3-97-0850 Seismic It/I DRS 06/24/97 07/15/97 IR 96-201. G2. IFl 97-01-xx. LER 96-003-00. ACR M3 0563. CR M3-97-0850
........m.......-.m.o..m....moa.......om.~oo...........m....-~.=~.~.......~..m......................................m.m....................
34.1 NOV 96-09-18 Effluent / Environmental Samphng and Analytical ProGeiency DRS 06/03/97 l 06/23/97 To The NRC NOV 96-09-18. NRC Inspection Moduel 84750. IFl 96-13-01 j
For Review On (U1) 6/21/97
_.......................................................mm.......m......m.....~...............a.........................................................
34 2 IFI 96-13-01 (U1)
Effluent /Ermronmental Sampling and Analytical Proficiency DRS f
NOV 96-09-18. NRC Inspection Moduel 84750. IFI 96-13-01 (U1)
..............................................~..~...om....~............m..........................................................................
1 TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
i 4
8 i
i l
l Schedvied Dste_
Estim_atti NRC Responsitte ACR Ready fnt Date for NRC BintM.
l Zone / Document N.
Description of NRC flem fiRG EP_Revied NRC Reslew
$_tatus C9mp_I te 9
t a
35.1 None Associated Radwaste Systems /Controts DRS N/A 06/21/97 NRC Inspection Module 86750 Ready For Inspection
'36.1 None' Associated Heat Exchanger Performance (GL 89-13)
DRS 06/10/97 07/01/97
.................................................................-........--.................p-................................................
37 1 EEI 96-201-13 Review Licensee Corrective Action Progrems for SPO(f) 05/30/97l 06/19/97 To The NRC Effectiveness to include ACRs and NCRs i
For Review On EEI 96-201-13. EEI 96-201 21. eel 96-201-22. eel 96-201-5 6/19/97
- 24. eel 96-201-26. eel 96-201-27, eel 96-201-28. eel 96-t 201-29. IR 96-04
.................--................-...............-.....-...............-~~an.........~..........[...........................--..............................
I 37.2 eel 96-201-21 Review Licensee Corrective Action Programs for SPO(t) 06/03/97*
06/23/97 To The NRC Effectiveness to include ACRs and NCRs For Review On eel 96-201-13. eel 96-201-21. eel 96-201-22. eel 96-201-24, eel 96-201-26. eel 96-201-27. eel 96-201-28. eel 96-l 6/12/97 201-29. IR 96-04
.....................................................-...-o........................'..............................................................
37.3 eel 96-201-22 Review Licensee Corrective Action Prog.'ams for SPO(!)
07/21/97 I
08/11/97 Effectiveness to include ACRs and NCRs l
eel 96-201 13. eel 96-201-21. eel 96-201-22. eel 96-201-i
...................................-o.....-oo-.--...............-~~......................................D................................................................
37.4 eel 96-201-24 Review Licensee Corrective Action Programs for SPO(!)
04/26/97 Effectiveness to include ACRs and NCRs l
05/16/97 To The NRC For Review On eel 96-201-13. eel 96-201-21. eel 96-201-22. eel 96-201-5/16/97
- 24. eel 96-201-26. eel 96 201 27. eel 96-201-28. eel 96-201-29, IR 96-04
.......................................................................................................................l.................................................................
37.5 eel 96-201-26 Review Licensee Corrective Action Programs for SPO(I) 06/03/97 06/23/97 To The NRC Effectiveness to Ir.clude ACRs and NCRs For Review On eel 96-201-13. eel 96-20121. eel 96-201-22. eel 96-201-24, eel 96-201-26. eel 96-201-27. eel 96-201-28. eel 96-l 6/10/97 20129. IR 96-04 Y
........................................-a...-~~~....-....-.........................-..~........e........................--..................................
(;
37.6 EEI 96-201-27 Review Licensee Correc ive Action Programs for SPO(1) 07/16/97 e
Effectiveness to include ACRs & NCRs l
08/05/97 eel 96-201-13. eel 96-201-21. eel 96-201-22. EEI 96-201
- 24. EEI 96-201-26. eel 96-201-27. eel 96-201-28. eel 96-20129. IR 96-04 I
I TBD = No Action Required From NtJ. NRC To Determine When Review To Be Completed.
l 9
1 i
I
s' Scheduled Date,,
EstimGled E-ResponsibJt ACRBeady for Date for NRG-Bi*"-
Zone /D9mment No.
' Description of NRC ttem Egg EP Rui y MRC Revegg Statug Comp _Itte 4.
t 37.7 eel 96-201-28 Review Ucensee Corrective Action Programs for SPO(I) 07/01/97 1 07/23/97 Effectiveness to include ACRs and NCRs eel 96-201 13. eel 96-201-21. eel 96-201-22. eel 96-201
- 24. eel 96-201 26. eel 96-201-27. eel 96-201-28. eel 96-201-29. IR 96-04 1
e
...-..-..............--.......----.m.m........mo..........-......m.....-............................................m.......
37.8 eel 96-201-29 Review Ucensee Corrective Action P ograms for SPO(1) 07/17/97 I 08/06/97 Effectiveness to Indude ACRs and NCRs eel 96-201-13. eel 96-201-21. eel 96-201-22. eel 96-201-
+
- 24. EEI 96-201-26. eel 96-201-27. eel 96-201-28. eel 96-I 201-29. IR 96-04
......m.................m..........-.o.m.....--......-.....................-.......L......m.--mm.........--..-..........m..m..
38.1 None Associated Review 0737 Ac1 ion items for Completion SPO(f) 07/15/97 08/05/97
-.....................................~..................................m.........m............................................
39.1 None Associated Review Engmeering Backlogs DRS 07/21 08/11/97
-.........................................................-..................................f.37)
..4............................................................
4.1 ACR 01895 EDG Sequencer CDA Signal Output "A" Train Components DRS 04/26/97 ) [
05/16/97 To The NRC Started For Review On 5/16/97
...........................m..---.a..mm-................--m.......---.......-m.m...............-.....-.o............
05/30/97 l 40.1 None Associated Review 50.54F lssues for Restart / Review Deterred Restart SPO 06/20/97 To The NRC ltems Ust For Review On 6/16/97 j
41.1 ACR 07007 Review Self Assessment Root Causes and Verify Corrective SPO(!)
07/25/97
- 08/09/97 Actions (IP40500) t ACR 7007. URI 95-81-01. VIO 96-09-04 (U1) mmmmm........m..--~~----.---.....-.....-...............mm..m...--......~................................-.................
41.2 URI 95-81-01 Review Self Assessment Root Causes and Verify Corrective SPO(f) 07/21/97 08/09/97 Actions (IP40500) g
[
ACR 7007. URI 95-81-01. VIO 96-09-04
)
I
........m.......-.m.m............m...m..-.~.............-.............-....----......J....-m....--.m......~.m.....~.......................-....
41.3 NOV 96-09-04 (U1)
Review Self Assessment Root Causes and Verify Corrective SPO(t)
Of/24/97 08/13/97 Actions (IP40500)
ACR 7007. URI 95-81-01. VIO 96-09-04
~........................m....~........-~....---....-.m==....--.-.-~~.m.-............-..........-..................m..................m......
42.1 None Associated Fire Protection Program DRS N/A 08/05/97 NRC Inspection Module 64704 Ready For inspection
.....m.......-~......ma.--.m-~~.---....~.---...--.--.--~~.~..-~.bma.mm.m..~...mm..~......-=......ma.m.~.---
i l
fBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
(
10 l
1 L
A Scheduled Date Estimated NRC Basepnsitple ACR Ready for Date for NRC.
Review ZonefDocument No.
Description eiNRC 199m 3_ahls CMte NRC EP Review NRC Review t
j, 43.1 Order ICAVP Phase 11of theICAVP SPO(O)
WA TBD No Acton
(,
Required From
.l '
NU
.....................................m......................,...........
44.1 ACR 12116 Cyde 6 Boron Dilubon Analysis Potentialty Non-Conservative DRS 02/14/97 03/05/97 To The NRC and PGS Flow Rate to Charging Pumps May Be in Error For Review On i
3/4/97
.................m.m.........................................I......m-...
44.2 ACR M3-96-0325 Cyde 6 Boron Dilution Analysis Potentially Non-Conservative DRS 04/19,97, 05/09/97 To The NRC and PGS Flow Rate to Charging Pumps May Be In Error For Review On 5/8/97
...m............................m.................................m..................................
1 44.3 LER 96-026-00 Cyde 6 Boron Dilution Analysis Potentially Non-Conservative DRS 05/03/97 05/23/97 To The NRC and PGS Flow Rate to Charging Pumps May Be in Error For Review On 5/9/97 i
44.4 LER 96-026-01 Cyde 6 Boron Dilution Analysis Potentially Non-Conservative DRS 05/16/97 06/06/97 To The NRC and PGS Flow Rate to Charging Pumps May Be in Error For Review On i
5/9/97
............................m...........................o..........m..................
44.5 LER 9S-026-02 Cyde 6 Boron Dilution Analysis Potentially Non-Conservative DRS 07/25/97 08/1397 and PGS Flow Rate to Chargmg Pumps May Be In Error l
......m...
.. m o......
m
...,...J....
.......m.
45.1 ACH M3-96-OS24 Initial Settings for ECCS Throttle Valves inadequate and SPO(t) 07/19/97l 08/08/97 Potenhaf Clogging ACH 08897. ACR M3-96-0524. URI 9646-14. LER 96-029-l
{
- 00. LER 96439-00 m.--..
-.=m
.ma
~..
....no-.m.-.
....f.
45.2 ACR 08897 initial Settings for ECCS Throttle Valves inadequate and SPO(t) 07/19/97 08/08/97 Potential Clogging i
ACR 08897. ACR M3-96-0524. URI 96-06-14. LER 96-029-l 00 LER 96-039-00
....................~.....m.m..~...................-.....m..m.m....-.......................................
45.3 URI 96-06-14 initial Settmgs for ECC5 Throttle Vafves inadequate and S,2O(t) 05/16/97 OWD6/97 To The NRC I
Potential Cloggmg lu For Review On ACR 08897. ACR M3-96-0524. URI 96-06-14. LER 96-029-
]
6/5/97
- 00. LER 96-039-00
........................~........................-...--...-........mo......m.~.................m............
I i i i
P TBC = No Action Required From NU. NRC To Determene When Review To Be Completed.
8 11 I
hg sI
.> L l
SciteduLlod Date Estinisted MC i
Responsitde ACR Rosev fet Date for NRC h
ZoneDoctment No.
Descrip!!ntLnt.NBC ltem NRC EP Review NRC Review Status M
4, 45.4 LER 96-029-00 Initial Setangs for ECCS Ttwotse Vahres inadequate and SPOg) 07/10/97 07/30/97 PolenBal Cloggmg s
ACR 08897. ACR M3-96-0524. URI 96-06-14. LER 96-029-i
- 00. LER 96 039-00
..................mm................m.i..m..........-~...m.....
43.5 LER 96-039-00 Initial Se tmgs for ECCS Throtse Valves inadequate and SPO(1) 07/15/9I 08/05/97 s
Potental Cloggmg i
I ACR 08897. ACR M3-96-0524. URI 96-06-14. LER 96-029-l
- 00. LER 96-039-00 l
m....
..-m...
m...........l om.
...m
...~... m
.m.
46.1 ACR M3-96-0183 Low Pressure Safety injecnon Penetra60ns SPO(I) 06/23/9Y 07/12/97 i
........--.....m..................--.m.....---......m.m...............m..~.............
i 47.1 ACR M3-96-0391 RHR Heat Exchanger Bolung hwwnnhle to Boric Acid DRS 04/25/97 05/16/97 To The NRC
~!
For Review On
[
f 4/23/97 i
i t
48.1 ACR 10397 LLRT *AS FOUND* Total Leakage Exceeded Max ANowable DRP 02/27/97 03/17/97 Closed I
.~..................--......-...mm....-....~..--........m.--...--.......
Closed i
49.1 ACR M3-96-0324 Fuel Transfer Tube BeNows Seal Connechon Not Tested DRP 05/14/97 06/04/97 To The NRC
'h For Review On l
I.
6/4/97 L
I!
t
...m................m..m.....~.....-...-~.............--........m.~..-:..........
t 5.1 ACR 01844 Failure to Enter an AcBon Staternent When MStVs Were SPO(f) 02/03/9Y 02/21/97 To The NRC Closed For Review On i
VIO 94-24-01. ACR 01844. LER 97-006-00 2/28/97
....m...mm..............--.~......~.-.m......m.-o...-~~........--Il....................m.......
t i-5.2 NOV 94-24-01 Fanure to Enter an Action Statement When MSIVs Were SPO (t) 06/02/97 1 06/21/97 To The NRC Closed VIO 94-24-01. ACR 01644. LER 97-006-00 l
For Review On 6/17/97 i
....mm..m........m..--..-~~~~..........--....-----=....-o.....--.....d.g r
6 -
......... ~......
..m........
5.3 LER 97 00G-00 Failure to Enter an Acton Statemnent When MSIVs Were SPO(t)
I No Action Closed in IR 97-02 Closed VIO 94-24-01. ACR 01844. LER 97-006-0C-Required By Dated 6/24/97 NU '
'i
......m......
....m m.....
-.mm m
-o.
....m.....
.....f
.......m 1*
50.1 ACR M3-96-0446 Docenentation of Contamment Systems Discrepancies DRS 07/01/97-07/23/97 l
. m m..
...........m.
....m.
.....~
... m m
...m..
m 51.1 ACR M3-96-0339 Walworth Valve Yoke Generic Issue DRS 07/10/97.!
07/30/97 ACR M3-96-0389. ACR M3-96-0339
.......................-=..
---.--. -.~.
.--. -~ --
.-~~......
.-[.r.
...............m 51.2 ACR M3-96-0389 Walwor1h Valve Yoke Generic issue DRS 07/10/97 ;
07/30/97 ACR M3-96-0389. ACR M3-96-0339 o-l....m.........m.......m.
m.......................~.--.m.--...-~~.-.....................
P TBD = No Action Required From NU. NRC To Determme When Review To Be Completed.
12 6~l
?
1 l
ScheduledDa m.
Estimatei E-ggspelMg CCR Ready for Date for NRC Beit*_
Ze.r- -y_ - _ ; No.
Description of NRC ltem
_m Meieg Mt_C Rg Status Complets 52.1 ACR 10795
. SWP Temperature Swtches Defeated by Bypass Jumper W SPO(I) 06/30/97,
07/22/97 SWP*P3A1B (Booster Pumps) l eel 96-201 23. LER 96-005-01. LER 96-005-00. ACR 10795
~..
o--
.......................<.m...................
52.2 LER 96-005-01 SWP Temperature SwitcheMefeated by Bypass Jumper for SPG(t) 05/03/97 05/23/97 To The NRC SWP*P3A13 (Booster Pumps) eel 96-201-23. LER 96-005-01. LER 96 005-00. ACR 10795 For Review On 5/22/97
...~..........m.....--..........-....-..........m............................,
.......mm..m....m..,
52.3 LER 96-005-00 SWP Temperature Switches Defeated by Bypass Jumper for SPO(f) 05/31/97 06/20/97 To The NRC SWP*P3A1B (Booster Pumps)
I
'For Review On eel 96-201-23. LER 96-005-01. LER 96-005-00. ACR 10795
.m.............~.m.....--........--........m....~..~..--............-mn...m-.m...
6/17/97
.-.......m...-mm.....-....m..
. 52.4 eel 96-201-23 SWP Temperature Swiches Defeated by Bypass Jumper for SPO(t) 06/30/97 07/22/97 SWP*P3A1B (Booster Pumps)
I.
i eel 96-201-23. LER 96-005-01. LER 96-005-00. ACR 10795 i
......m....
~....-........-a...............~....mmm.........m......
53.1 ACR M3-96-0449 Pieces of ARCOR Found in 3FiSS*E1 A and 3RCC E1C SPO 07/14/97 08/02/97 t
URI 96-09-11. LER 96-025-00. ACR M3-96-0449. M3 NRR 1007. M3-97-0727
............................-.--.....-.....-...--...-.....m......J......--..........m.-..m...............
53.2 URI 96-09-11 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/24/97 08/12/97 URI 96-09-11. LER 96-025-00. ACR M3-96-0449. M3 NRR 1007. M3-97-0727 m..
.-...m..-~
m-.----
-~.m.-
--.---... -~...
......~......m.......--........
m...
53.3 LER 96-025-00 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/24/97 08/12/97 URI 96-09-11. LER 96-025-00. ACR M3-96-0449. M3 NRR 1007. M3-97-0727
....mmmm.........m..mmm..m~~~.--~~~~-~--..---.mmn..--.-.m.....--.m.m..1=m..~..-m....m..~................
53.4 ACR M3-97-0727 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/14/97 07/30/97 URI 96-09-11. LER 96-025-00. ACR M3-96-0449. M3 NRR 1007. M3-97-0727
.......m.......--....--..m...-.m....m..-.......---.---.........-~~...~..-.'--.m..-.....m......m..-........m....m...
53.5 ACR M3-97-1007 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/14/97 07/30/97 O
URI 96-09-11. LER 96-025-00. ACR M3-96-0449. M3 NRR 1007. M3-97-0727
...m.........
~.
m..
-. --..-~
mo..-
- - ~~...~
..m.m m..
-~..........~
..~.m
.m................
54.1 ACR M3-96-0181 Numerous Botts on Back Door on 4160V Switchgear IWssing DRP 05/28/97 06/18/97 To The NRC For Review On 6/12/97
......................................mm......................J.......................................
55.1 ACR M3-96-0467 Fast Transfer Test FaBures DRS 08/01/97 08/13/97
.....m....-.....-..-.........mm..-....-.--.m.---...mm.m......
-...m.....m.......m......-.............
i TBD = No Action Required From NU. NRC To Determine When Review To Be CorEpleted.
f3 4
t
~~
S@tduled D e_
Estimated NRC_
Bess 8msjtLit
' AC!LBeasty for Date for NEC.
P'VitF-Zone / Document No.
DC.x,e of NRC ttem J4RC EP Revitu!
NRC Rh Status C9tnpi te
.m.
t 56.1 ACR 12495 Shutdown Margin Monitor Atarm Setpoint
'DRS 05/28/97 06/17/97 To The NRC j
For Review On 6/5/97
.m........................................-....................i..............
57.1 ACR M3-96-0080 Potential Electrical Separatiora Vdations DRS C512/97 06/02/97 To The NRC ACR M3-96-0081. LER 96-015-00. LER 96-045-00. LER 96-For Review On 049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 ACR M3-96-0080 6/2/97
......................m....
.m.......m.
(
57.2 ACR M3-96-0081 Potential Electrical Separation violations DRS 02/14/971 03/05/97 To The NRC ACR M3-96 0081. LER 96-015-00. LER 96-045-00. LER 96-For Review On i
049-00. LER 96-015-01. LER 96-015-02. LER 96 015-03 3/5/97 ACR M3-96-0000 I
...mo.......m..................-.~..-.....................i.........................m.....m......................
57.3 LER 96-015-00 Poter$at Electrical Separation Vdations DRS 07/0nfg7 07/28/97 ACR M3-96-0081. LER 96-015-00. LER 96-045-00. LER 96-049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 ACR M3-96-0000
..m............................~.-......-..m.......m.........m.......................................
57.4 LER 96-045-00 Potential Electrical Separation Violations DRS 07/25/97 08/09/97 ACR M3-96-0081. LER 9G-015-00. LER 96-045-00. LER 96-049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 ACR M3-96-0080
.........m....
...m m..m...
u..
.m.
............ m m....
.m.m..........................
57.5 LER 96-049-00 Potential Electrical Separation Vdations ORS 07/02/97 07/23/97 ACR M3-96-0061. LER 96-015-00. LER 96-045-00. LER 96-i 049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 ACR M3-96-0000
.~..m...m....m..m......=~-
. ~... - - -.. ~.. -. -
57.6 LER 96-015-01 Potential Electrical Separation Vdations DRS 07/08/97 l
07/28/97 ACR M3-96-0081. LER 96-015-00. LER 96-045-00. LER 96-049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 1
ACR M3-96-0080
........m.m m.==.
o-..
.....- -..~. ~.
-~..--...~i...-.m....--....m...m.m...m..~...............
57.7 LER 96-015-02 Potential Electncal Separation Violations DRS 07/08/97 !
07/28/97 ACR M3 9G 0081. LER 96-015-00. LER 96-045-00. LER 96-l 049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03 ACR M3-96-0080
..............................-.......................pl...................................................
57.8 LER 96-015-03 Potential Electrical Separation Violations DRS 09/03/97 09/24/97 ACR M3-96-0081. LER 96415-00. LER 96-045-00. LER 96-049-00. LER 96-015-01. LER 96-015-02. LER 96-015-03, i
3 ACR M3-96-0080
...................m.u-..m....m........~.~-...-..-....
i TBD = No Action Required From NU. NRC To Determine When Review To De Completed.
6'.
14 1
-. ~-
m
+
r b
Schedv!td_Date.
Estimated _
NEG-Bespontitgg ACR Really_f L Date for NBC Reh 9
Zone /D9sument No.
Description of NRC 11ent
_gRQ EP Revits l NRC Review Stahns CA"XJfM 57.9 LER 96-015-04 Potential Electrical Separation Violations ACR M? os-n081. LER 96-015-00. LER 96-045-00. LER 96-C19-00. LER 96-016-01. LER 96-G15-02. LER 96-015-03 ACR M3-96-0080
........................-.-.......~..-...........m.....................m..........
58.1 ACR M3-96-0557 Thermal Relief Valve Setpoints SPO(l) 03/15/97 04/02/97 To The NRC Closed in IR 97-02 ACR M3-96-0685. eel 96-201-33. ACR M3-96-0557 For Review On Dated 6/24/97 6/26/97
. mom....m........................-.m................-~.m..................m....................m.........m.....
58.2 ACR M3-96-0685 Thermal Relief Valve Setpoints SPO(t) 07/11/97 [
07/31/97 ACR M3-96-0685. eel 96-201-33. ACR M3-96-0557
.....m.m....m.m......mo.....~.m.........m.........................................
m.m m..
.m.m
.......m.m 58.3 eel 96-201-33 Thermal Relief Valve Setpoints SPO(t) 06/30/97 07/22/97 To The NRC ACR M3-96-0685. eel 96-201-33 ACR M3-96-0557 For Review On Updated in IR 97-02 6/25/97
.......................................... ~
i
'~
59.1 ACR M3-96-0775 Use of Boraflex in SFP Racks SPO(L) 05/24/97 06/12/97 To The NRC ACR 09124. ACR M3-96-0846. ACR M3-96-0775 For Review On LER 96-033-00 j
6/5/97
.m.m..-
ma.mm..m..om.m mmm m.=-
n-me...n.--.m...
.= nm
.w
- m...nm....-mm m mm.
i..mm.........m o.u.m..
.m...
umm...-..m....-.
59.2 ACR 09124 Use of Botaflex bi SFP Racks SPO(L) 05/24/97 06/16/97 To The NRC ACR 09124, ACR M3-96-0846. ACR M3-96-0775 For Review On LER 96-033-00 6/11/97 1
.....m.......m.....-.......-..~...-.....-~.................-....-.......,-...........................-..........~.m..m...m......
l 59.3 ACR M3-96-0646 Use of Boraflet in SFP Racks SPO(L) 05/31/97 06/20/97 To The NRC ACR 09124, ACR M3-96-0846. ACR M3-96-0775 For Review On LER 96-033-00 6/11/97
.............................--.... - -... m. m..- -..-~ ~.- ~.- -
.... m m = ~ m....... m m.. ~4........~........m......m.m...........m......
+
59.4 LER 96-033-00 Use of Boraflex in SFP Racks SPO(L) 07/15/97 08/04/97 ACR 09124. ACR M3-96-0646. ACR M3-96-0775 LER 96-033-00 m...m.o.......m.......-~.m...~......m.....=~..-.-~~~...m....-......m...............<,6m...m.....m.......m.....m.....m........
I 6.1 ACR 04199 RCP Seal injection Filter "B* Gasket Failed Resulting in Spill DRP 04/25/97 05/16/97 To NRC for
[
of Coolant to Floor Drains Review on 5/15/97 m
..........om m.........m..
--.am.....~
..**.=m-m.
.--. -- m.m=
m..m.m m..
.m.m.
......m...m=.-am.............................
60.1 ACR M3-96-0718 Analysis of SOV Failure Modes Due To MOPD SPO(I) 07/25/97 08/13/97 ACR M3 96-0821. eel 96-09-16. ACR M3-96-0718 i
.............m...m.m...-.-.-...--.m.--.m..--.m.-----~.......m.mm.~....4*m.m..........-...-...-.o.m....................m......
60.2 ACR M3-96-0821 Analysis of SOV Failure Modes Due To MOPD SPO(t) 07/02/97 07/23/97 ACR MS-96-0821. eel 96-09-16. ACR M3-96-0718
......m......mmo..~....~.......--.m.....m..................m...............m......m.................m..............
t TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
l e
f5 a
1 y
1
- =- -
e:
liicheduled Date Estimated M C_
ReSponsittig ACR Readylot.
Dele _for.
MRC BfY!f*-
Zone / Document No.
Description of NRCltem Mg EP Reylew NRC Review Sahts GDW9 A
60.3 eel 96-09-16 Analysis of SOV Failure Modes Due To MOPD SPO(t) 07/25/97 08/09/97 ACR M3-96-0821. eel 96-09-16, ACR M3-96-0718
.........m....................m...................................
61.1 1ACR 7923 (U2)
EEO Process Orts 09/09/97 09/09/97
...........m.............................................~m.m.........L..m....................................
62.1 ACR 13788 TSP Basket Safety Evaluation Possibly Not Valid SPO(l) 02/03/97 02/21/97 To The NRC Closed in IR 97-02 For Review On Dated 6/24/97 2/21/97
.................-......mm...............mo...........m.m...mo.......m........,.....................................
63.1 ACR M3-96-0396 3 MSS *MOV17D Missed IST Surveillance Requirement DRP 05/31/97p 06/20/97 To The NRC For Review On 5/22/97
........--...........-..m.......................m.m.m..........m...4.....................m..m..............
l 64.1 ACR 08614 Reactor Protection Lead Lag Circuits May Be Set DRS 02/21/97) 03/11/97 Closed Closed Nonconservatively
.m.o......mm....m.-.....-..--...........-.......~......~.mm...,t*"********************"*********"""*****************-****
65.1 ACR M3-96-0745 SilJSiH Valves Powered From NonSafety Train SPO 07/25/97 08/13/97 LER 96-036-00. ACR M3-97-0742. ACR M3-96-0745 NRR I
.-.---..........mo..--.......-m..mm-.........-.-..mm......4................................................
65.2 ACR M3-97-0742 SillSlH Valves Powered From NonSafety Train SPO 07/25/97l 08/13/97 LER 96-036-00. ACR M3-97-0742. ACR M3-96-0745 NRR
.............m..--.mm.---....-.........-.....~............--o.....mo...-.........m..................m..........m.....
65.3 LER 96-036-00 SIL/SlH Valves Powered From Nonsafety Train SPO 07/26/97!
08/13/97 LER 96-036-00. ACR M3 97-0742. ACR M3-96-0745 NRR
........-.m...........m..m.-o-........mo..---.-..................--......momm.m.............mm.m.................m.....m...
65.4 LER 96-036-01 SIUSlH Valves Powered From NonSafety Train SPO 07/26/97' 08/13/97 LER 96-036-00. ACR M3-97-0742. ACR M3-96-0745 NRR
........~.....................--.........--~.m.o.m.---.m...~.......-.-m.......................m.........m...
66.1 ACR M3-96-0483 CCP and CCE Nord Cormonents Cause O-Components SPO(1) 07/28/97 08/13/97 Not To Fail Safe l
........................................--o.m........m...-....~......-...--.....j
..-.....m.................................................
67.1 ACR M3-96-0621 SBO Possible Overload in Event of an SIS Actuation and SPO q2/03/97 02/21/97 Closed Closed Design issues I
TAC No. M96054. URI 96-201-14. ACR M3-96-0621. Infor s
Notice 97-21
..........-.........m...m.m....mm.mm.....m.--.........m.......-.....m..........m................m...........................
67.2 URI 96-201-14 SBO Possible Overloadin Event of an StS Actuation and SPO 07/02/9/
07/23/97 Design issues TAC No. M96054. URI 96-201-14. ACR M3-96-0621. Infor
^
i Notice 97-21
--...........-.....-..--.....-m~.......m.........1.==..~...............m...............m..
h l
TBD = No Action Required From NU. NRC To Determme When Review To Be Completed.
f6 S
s, Sc_heduled Det.
Estimated _
NBC--
t Besponsittle ACILBeady for Date for NRC BtMtM.
Zone / Document No.
Dw: ;;,... of NRC ftem feRq EP Reyi s NBC Review Status C9m_pfelt t
67.3 TAC M96054 SBO Possible Overload in Event of an SIS Actuation and SPO 07/25/97 08/13/97 Design issues TAC No. M96054. URI 96-201-14. ACR M3-96-0621. Infor lj.
t 4
Notice 97-21
..............................m...........m....................i.................
68.1 None Associated Review Allegations for Restar11ssues SPO N/A TBD No Response l
Required From t
NU 69.1 None Associated Review All Operability Dete. 6 ew and By-pass Jumpers SPO 07/24/97' 08/12/97 Before Restart i
m.....m...........................m.................~...~..............m.o...m..................................
.1 ACR 06092 RCS Check Valve Body to Bonnet Leak; 3RCS*V146 DRP 02/10/97 02/28/97 m.
.m
...m.m mom-
..m
. Closed
.....................m...
70.1 URI 96-08-16 Review TRM for Technscal Specifications Interpretations.
DRS 05/15/97 06/06/97 To The NRC i
Evaluate T.S. and Oper. License issues 1-For Review On URf 96-08-16. LER 96-002-00 -01. 96-037-00,96-038-00.96-6/5/97 042-00,96-043-00.96-048-00.96-051 00,97-004-00,97-007-
- 00. 97-018-00. 97-019-00. CAL 1-97-010
.....-~~o.m.....m m m
.m.
.m.--
..m
..omom....
.ti.no.m............-~...................m..m.
70.10 LER 97-004-00 Review TRM for Technical Specifications Interpretations.
DRS 07/15/97 08/05/97 Evaluate T.S. and Oper. License issues URI 96-08-16. LER 96-002-00 -01,96-037-00,96-038-00,96-042-00.96-043-00,96-048-00,96-051-00.97-004-00.97-007-
- 00. 97-018-00,97-019-00. CAL 1-97-010
.........................................................................................[...................................................................
70.11 LER 97-007-00 Review TRM for Technical Specifications Interpretations.
DRS 07/02/97 '
07/23/97 I
Evaluate T.S. and Oper. License issues i
I URI 96-08-16. LER 96-002-00,-01,96-037-0196-038-00.96-f i
042-00.96-043-00,96-048-00.96-051-00,97-004-00,97-007-00,97-018-00,97-019-00. CAL 1-97-010 6
. m m.................. - -........... m.......... m....... m... - - -..
m o
... m.o m -....... m o m.....;.... m.. ~
o m o...................... m..
70.12 LER 97-018-00 Review TRM for Technical Specifications Interpretations.
DRS 07/15/97:
08/05/97 Evaluate T.S. and Opc. License issues URI 96-08-16. LER 96-002-00.-01,96-037-00. 96-038-00.96-042-00,96-043-00,96-048-00.96-051-00,97-004-00,97-007-j
- 00. 97-018-00,97-019-00. CAL 1-97-010
?
--........................................-~.om.=m.on...........~.......m.....................9*
..........................m...........................
70.13 LER 97-019-00 Review TRM for Technical Spedu im Interpretations.
DRS 07/25/97~
08/13/97 Evaluate T.S. and Oper. License issues URI 96-08-16. LER 96-002-00.-01,96-037-00. 96-038-00,96-
,{
042-00.96-043-00,96-048-00.96-051-00,97-004-00.97-007-00,97-018-00,97-019-00. CAL 1-97-010 I
I
...................-..mm...........m...-~~..m..--.......... mom..mm....--6...m.o.on..mm.............m.......m.......
TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.
17 I
t P. l t'
w-(
Sche @ led Datt.
Elstimated.
Nf!C.
Besponsitg, ACRBeesty for Date_ tot.
NRC Btvi wf.
Zone h.a-ANo.
Dese.iotion of NRCltem
_dq~
EP Reviear NRC Review
~ Sl411!1 D EIM I
70.14 LER 96-002-00 Review TRM for Technical Specifications interpretations.
DRS 06/02/97 06/23/97 To The NRC Evaluate T.S. and Oper. License issues
(
For Review On URI 96-08-16. LER 96-002-00.-01,96-037-00. 96-038-00.96-6/6/97 042-00.96-043-00,96-048-00.96-051-00.97-004-00,97-007
........--o.
70 2 LER 96-002-01 Review TRM for Tecivwcal Specifications interpretations.
DRS 08/02/97 08/13/97 Evaluate T.S. and Oper. License issues URI 96-08-16. LER 96-002-00.-01. 96-037-00,96-038-00.96-042-00.96-043-00,96-048-00.96-051-00.97-004-00,97-007-00,97-018-00. 97-019-00. CAL 1-97-010 6
70.3 LER 96-037-00 Review TRM for Technical Specifications Interpretations.
DRS 08/12/97 1 08/13/97 Evaluate T.S. and Oper. License issues l
p URI 96-08-16. LER 96-002-00.-01,96-037-00. 96-038-00.96-I f
042-00,96-043-00.96-048-00,96-051-00,97-004-00,97-007-4 00,97-018-00,97-019-00. CAL 1-97-010
.............................no.....-..........................................................................
70.4 LER 96-038-00 Review TRM for Technical Specifications Interpretations.
DRS 07/25/97 08/13/97 Evaluate T.S. and Oper. License issues URI 96-08-16. LER 96-002-00.-01. 96437-00,96-038-00,96-042-00.96-043-00,96-048-00.96-051-00.97-004-00.97-007 l l
- 00. 97-018-00. 97-019-00. CAL 1-97-010 l.
70.5 LER 96-042-00 Review TRM for Technical Specifica' ions Interpretations.
DRS 09/22/97 09/30/97 Evaluate T.S. and Oper. License issues URI 99-08-16. LER 96-002-00.-01. 96-037-00,96-038-00,96-042-00,96-043-00.96-048-00,96-051-00,97-004-00,97-007-00,97-018-0). 97-019-00. CAL 1-97-010
. -.=
.......---oooo-......4.
uo......-.o...............................
4 70.S LER 96-043-00 Review TRM for Technical Specifications Interpretations.
DRS 07/25/97 i 08/13/97 Evaluate T.S. and Oper. License issues d
URI 96-08-16. LER 96-002-00 -01. 96-037-00,96-038-00,96-l 042-00.96-043-00,96-048-00,96-051-00.97-004-00,97-007-
- 00. 97-018-00. 97-019-00. CAL 1-97-010
(
70.7 LER 96-048-00 Review TRM for Technical Specifications interpretations.
DRS 07/02/97 07/23/97 Evaluate T.S. and Oper, License Issues URI 96-08-16. LER 96-002-00.-01, 96-037-00. 96-038-00.96-042-00.96-043-00,96-048-00.96-051-00,97-004-00,97-007-lll 00,97-018-00. 97-019-00. CAL 1-97-010
........................-...............-o............-.-..--.o-o.................-o.....--4.......on...........................................
e TBD = No Action Required From NU. NRC To Determene When Review To Be Completed.
f8
l Scheduled.Date.
Estimated NBC-at Zone /cm. - No-Dt1Criotion of NRC ltem Besponsitde ACRBeadr$E.
Date for NBC-Mf"-
3Rg EP_Bevley NRC RaL Status CD!DPitte h
70.8 CAL 1-97-010 Review TRM for Twi.a.; Speofications interpretations.
DRS 07/15/97 08/05/97 Evaluate T.S. and Oper. License issues I
URI 96-08-16. LER 96-002-00 -01. 96-037-00,96-038-00.96-042 00,96-043-00,96-048-00.96-051-00,97-004-00,97-007-00,97-018-00. 97-019-00. CAL 1-97-010
..................-m........m.......................................m....
70.9 LER 96-051-00 Review TRM for Techmcal Specifications interpretations.
DRS 06/20/97 07/07/97
...........................m.....
Evaluate T.S. and Oper. Ucense issues URI 96-08-16. LER 96-002-00.-01,96-037-00. 96-038-00.96-042-00,96-043-00.96-048-00.96-051-00,97-004-00.97-007-00,97-018-00. 97-019-00. CAL 1-97-010 mm....mmm.............
.m..
....m..
.........m.mm.m 71.1 None Associated Review Licensee Event Reports for Restart issues SPO(t)
N/A TBD No Response Required from I
NU l
...................................-...~.....m......m.
T m--m......................................
72.1 None Associated Review Enforcement and Unresolved Items for Restar11ssues.
SPO(!)
N/A TBD No Response Required from NU
- m..................m.....m.-m.-........-a.~.mmm........,i..........................
73.1 NOV 96-05-?2 Review OA Program for Adequacy and improvement NRR 06/02/97 06/21/97 To The NRC NOV 96-05-12. IFl 96 06-17 OSTI For Review On 6/18/97
- ~.. m...............
. m..- - o m.- - -...- -...
........ m m...
.. m o.-
o-m.m-m......................m.........
73 2 IFl 96-06-17 Review OA Program for Adequacy and Improvement NRR 07/21/97 09/09/97 NOV 96-05-12. IR 96-06-17 OSTI
...........m............m...~.mm.-.o......----..m--....-~~.........-~.
.-m.o.......mm.......o=~..........
74.1 URI 96-08-18 ISI/IST Prog am Control DRS 05/31/97 06/20/97 To The NRC URI 96-08-18. LER 96-021-00 For Review On
[
..........................................m.....................................................l...........................6/9/97 i
74.2 LER 96-021-00 ISf/IST Program Control DRS 07/18/97 08/08/97 URI 96-08-18. LER 96-021-00
.........m.m..........
-o...
. -~.-~
~.m
......~.
m.mm.m m 74.3 LER 96-021-01 ISI/IST Program Control DRS 07/18/97 URI 96-08-18. LER 96-021-00 08/08/97 l
......m..........-.....-.mmm..-.---........~.......-.....---mmm...........,......................................................m.
75.1 IFl 96-08-15 TIA Issues (EDG Exhaust and Required 8 of Service Water NRR 08/12/97 I 08/13/97 Pumps) 6 IFI 96-08-15, IFI 96-09-17 i
........................--.m--.....-~~..........-......-..m...m.m.o-m..........................................
TBD = No Action Required From NU. NRC To Det... A.e ".b Review To Be Completed.
f9 I
t
t g4m f
Schedule @ t.
Estimated E
Besponsib_It ACB_ Beady for Date for NRC RCMt4L Zone / Document No.
Descriotton of NRC ttem japq EP Review NRC Review Status Comphit 75.2 IFl 96-09-17 TIA issues (EDO Exhaust and Required # of Service Water NRR 06/20/97 07/11/97 k
Pumps) j IFl 96-08-15. IFI 96-09-17 mm.mm..m....................-.........m.................................m.....m..........
76.1 IFl 96-06-17 Cracking of Fuse Ferrules DRS 05/30/97 1
06/19/97 To The NRC For Review On 6/16/97
.....m......m..........................ono..........m.............-.................m.......
77.1 IFI 95-44-06 Potential of Freezing Service Water Backwash Lines SPO(l) 05/16/97 i G/06/97 To The NRC For Review On 5/20/97
.....m.m.m...m.........mm.........-..mmm......m.n................i....I..............-m.....................
78.1 URI 93-07-07 Safety Analysis (50.59) Process SPO(L) 04/26/97 05/16/97 To The NRC URI 93-07-07. eel 96-201-02. eel 96-201-06. eel 96-201-
- 07. eel 96-201-08 For Review On 5/15/97
..........................................._........m................................................._..................
78.2 eel 96-201-02 Safety Analysis (50.59) Process SPO(l) 07/21/97 l 08/09/97 URI 93-07-07. eel 96-201-02. EE! 96-201-06. eel 96-201-
- 07. eel 96-201-08 78.3 eel 96-201-06 Safety Analysis (50.59) Process SPO(L) 07/16/97 P
08/05/97 1
URI 93-07-07. eel 96-201-02. eel 96-201-06. eel 96-201
- 07. eel 96-201-08
.............mm....m......m....._
..mm................-~~..........m.........-................m..m...
78.4 eel 96-201-07 Safety Analysis (50 59) Process SPO(L) 07/16/97 08/05/97 URI 93-07-07. eel 96-201-02. eel 96-201-06. eel 96-201-
- 07. eel 96-201-08
...........m.m.............-......-.....-...................m......-......mm............................................
78.5 eel 96-201-08 Safety Analysis (50.59) Process SPO(L) 07/16/97 i
08/05/97 URI 93-07-07. eel 96-201-02. eel 96-201-06. eel 96 201-
- 07. eel 96-201-08
.................................-....---m......m...-...........m............-....................................................
79.1 eel 96-201-09 Design Control Process Review (Part of Phase I of the SPO(O) 07/16/97 08/05/97 ICAVP) eel 96-201-09. eel 96-201-35. EEI 96-201 37. eel-96-201-39
..m....m...m..........m..m.....~...ao........~o...-~..--........................m.mm..............................
79.2 eel 96-201-35 Design Control Process Review (Part of Phase 1 of the SPO(O) 06/21/97 t
07/12/97 ICAVP) eel 96-201-09. eel 96-201-35. eel 96-201-37. eel-96-201-39
...mm.....m.....m.mm......-.m.....-..-...m...m..mm............4................................................
79.3 EE1 96-201-37 Design Control Process Review (Part of Phase I of the SPO(O) 06/21/97 l 07/12/97 I
BCAVP) eel 96-201-09. eel 96-201-35. eel 96-201-37. eel-96-201-39
................~...mm..mmm.................................g....m..............m.................
TBD = No Action Required From NU. NRC To Determne When Review To Be Completed.
l A
Scheduled Date Estimated.
E E-Responttt, AGR!kadt.fm.
Da!v.for NRC ReWew ii Zone /Cesa.m No.
Description of NRC ltem
.NRQ EP Rey.itW NRC Review Status Complete 79.4 eel 96-201 39 Design Cun;w; Process Review (Part of Phase I of the SPO(O) 06/21/97 07/12/97 (CAVP) eel 96-201-09, eel 96-201-35. eel 96-201-37. eel-96-201-39 8.1 ACR 01535 While Dewatering Spent Resin. the Waste Temperature in DRP 02/26/97 03/15/97 Closed the Uner Raised from 90 to 310 degrees F
.-...............................................-..............................i.....................................
80.1 ACR M3-97-0348 Procedure Adequacy and Adherence / PUP Process SPO(t) 05/03/97 05/23/97 To The NRC OSTI For Review On 5/22/97
+
81.1 eel 96-201-32 Testing of Safety Systems DRS 06/30/97 07/22/97 To The NRC eel 96-201-32. eel 96-201-34 For Review On 6/25/97
......................................--o........--.......................-.................................................................................
81.2 eel 96-201-34 Testing of Safety Systems DRS 09/30/97 f 09/30/97 eel 96-201-32. eel 96-201-34 81.3 LER 96-032-00 Testing of Safety Systems DRS 06/03/97 06/23/97 To The NRC Closed in IR 97-02 eel 96-201-32. eel 96-201-34. LER 96-032-00 For Review On Dated 6/24/97 6/23/97
--...........................-..-............-.................-.......4..................-..................
82.1 eel 96-201-10 Qualty Assurance Records SPO 07/17/97 08/06/37
.....................-............--...-o-.........-...-.-....(l) 83.1 Letter B16195 Effectiveness of Emergency Response Organization DRS 06/03/97 06/23/97 To The NRC Coordmation with Offsite EP Officials; Dose Assessment Capability For Review On IFI 95-36-01 6/20/97
.......-.....-o....-....................................-.......-..............-......-...................-.......................................
83.2 IFl 95-36-01 EffecWveness of Emergency Response Organization DRS 05/15/97 06/06/97 To The NRC Coordination with Offsite EP Officials: Dose Assessment Capability For Review On IFl 95-36-01 6/5/97 84.1 eel 96-05-15 Security issues. Correc5ve Action and Review DRS 06/03/97 i
06/23/97 To The NRC eel 96-05-15. eel 97-03-01. eel 97-03-02. eel 97-03-03. U1 VIO 96-09-20 For Review On 6/23/97
....................................................................................a.........................................
84.2 eel 97 03-01 Secunty issues - Correenve Action and Review DRS 07/23/97 08/12/97 eel 96-05-15. eel 97-03-01. eel 97-03-02. eel 97-03-03. U1 VIO 96-09-20
+
-....-o.
1 TBD = No Action Required From NU. NRC To Determme When Review To Be Completed.
l 21
)
i i
l i
v6 SchedvfetDate Estimath1
- NRQ, BeSpgntikt, ACRBesdyJnt.
Date for NRC BRYlevt.
a Zone /Dornment No.
Dtscription of HRC tte RRQ EPftv_i w NRC Review Status C9Eplett 4
t 84.3 eel 97-0342 Security issues - Corrective Acton arwl Review DRS 07/23/97 !
08/12/97 eel 96-05-15. eel 97-03-01. eel 97-03-02. eel 97-03-03. U1 I
VIO 96-09-20 84.4 EEI 97-03-03 Security issues - Corrective Actiori and Review DRS 07/23/97 i 08/12/97 eel 96-05-15. eel 97-03-01. eel 97-03-02. eel 97-03-03. Ut f
VIO 96-09-20 84.5 NOV 96-09-20 (U1)
Security issues. Correct!ve Action and Review DRS 07/16/97; 08/05/97 eel 96-05-15. eel 97-03-01. eel 97-03-02. EEI 97-03-03. U1 VIO 96-09-20
...............................................................................................(.........................................................
85.1 ACR M3-96-0496 Other RSS and Related Design Basis Concems DRS 08/02/97 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACH M3-96-0620. ACR NRR yl M3-96-1078. ACR M3-97-0039, ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 M3-97-1029
.......a....-................--...f.......a..............................-....-....-....
I
-......--....-.-....~..........an~n...wa...u.. ann-.==....-..==.............-.
85.10 LER 97-021-00 Other RSS and Related Design Basis Concems DRS 07/25/97j 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR 3
M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-974409. LER 97-003-00. LER 97-015-00. LER 97-021-00 M3-97-1029
..........................--.u-o....-...........a.................-....=~..-~~.~.....-.........--...~............a.......-.......-.o.................................
I 85.11 ACR M3-97-1029 Other RSS and Related Design Basis Concems DRS 8
ACR M3-96-0496. ACR M3 96-0497. ACR M3-96-0620. ACR M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-l 97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00, 1
M3-97-1029
.........................n..~.~.....-=....no.............................--........-....~~~.a.............~.~...-....----.......................-.....................................
85.2 ACR M3-96-0497 Other RSS and Related Design Basis Concems DRS 08/02/97 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR
'j
{
M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00. LER 97-015 00. LER 97-021-00 1
M3-97-1029
-..........................--...............--...a==......~o.--.............~...~-..-.-~~....~...........L......................................................................
85.3 ACR M3-96-0620 Other RSS and Refated Design Basis Concems DRS 07/10/97 -
07/30/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 M3-97-1029
............................-=.....~.--..................--....~.=au-...........--.......-.u..............................................................
t' i
TBD = No Action Required From NU. NRC To Determine When Review To Be Comoteted.
22 I
i
Schedulest_Qat1L Estimated E G-Respongih_lg A._.CH Ready for Date for_
g Revie_w_
Zone /Ds._
No.
Description of NRC ltem fiRQ EPJeyi y NRC Revlegg Status CDEPle!A t
y 85A ACR M3-96-1078 Other RSS and Related Design Basis Concems DRS 08/02197 08/13/97 3
ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3 96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-y 97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 M3-97-1029
..~....-.......................
.....~....
....~.m...
..m..........~.......
.................~.
85.5 ACR M3-97-0039 Other RSS and Relate (1 Design Basis Concems DRS 07/25/97 l 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1078. ACR M3-97 0039. ACR M3-97-0128. ACR M3-
.l 97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 M3-97-1029 i
~...m...-.............................................~...........................-.m...............~.m..........
85.6 ACR M3-97-0128 Other RSS and Related Design Basis Concems DRS 07/25/97 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 l
M3-97-1029 I
I
............m.....~.....-........................~...~..........omuo.....e.....i.....................~.......--
.o 85.7 ACR M3-97-0409 Other RSS and Related Design Basis Concems DRS 07/26/97 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1078. ACR M3-97-0039. ACR M197-0128. ACR M3-i 97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00 i
M3-97-1029
+
........--..............~...--....a~............~.m...~...-............~.....~......--....-.~............
85.8 LER 97-003-00 Other RSS and Related Design Basis Concems DRS 08/02/97 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1070. ACR M3-97-0039. ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00,
]'
t M3-97-1029
......~.~.m..-...mo....--~~~~~....mm.mo=====-=~mamm.-~.m=====}-mi.m==--~~.mmo===...~....-~..o.~
85.9 LER 97-015-00 Other RSS and Related Design Basis Concems DRS 07/26/97 i 08/13/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620. ACR NRR M3-96-1078. ACR M3-97-0039. ACR M3-97-0128. ACR M3-l 97-0409. LER 97-003-00. LER 97-015-00. LER 97-021-00, i
4 M3-97-1029 f
.....~....................-~.--~~..--..--.--.~..--.---..~-~.-~..~....t - -
- ~..
... - ~ ~.. ~...
9.1 ACR 10543 Need for Additional Review of Response Time Testing for SPO(l) 07/01/97.
07/22/97 Procedures i
...............~.........~......~.~..--.....-................4.....I If 91 TBD = No Action Required From NU. NRC To Detemune When Review To Be Completed.
f 23 a
It i
6 1
Millstona Unit No. 2 NRC Significant it ms List SIL FINAL DUE NiJMBER ITEM DESCRIPTION DATE 1
Management Oversight and Effectiveness: Licensing Staff 7/15/97 Safety Culture Refer to MC 0350 for items to be addressed 2
Complete 10 CFR50.54f for MP2 Refer to MC 0350 for items NOTE 1 to be addressed 3
MP1 UFSAR has inaccuracies in design basis and system NOTE 1 description info. Corrective actions are applicable to MP2 Resolution of 59 design issuer.. Refer to MC 0350 for items to be addressed
~ ~ - ^ Employee Concern Program: = Refer to MC'0350 for items to ~~ ~ ~
OTE 1
_ be addressed _
5 Failure to implement timely corrective action for identified NOTE 2 significant conditions adverse to quality
- Col.ective Action Program timeliness and effectiveness
- Self-Assessment program implementation and effectiveness
- Commitment Tracking Refer to MC 0350 for items to be addressed Effectiveness of the Corrective Actions Program 6
Work Planning and Control; Plant Maintenance program 7/17/97 effectiveness; significant hardware issues resolved; maintenance backlog managed and impact on operation assessed; surveillance testing; plant housekeeping. Refer to MC 0350 for items to be addressed.
7 Bypass Jumpers, Operator work-arounds & Control Board 7/29/97 Deficiencies. Refer to MC 0350 for items to be addressed 8
Weaknesses in procedure classification system 8/15/97 Procedure Quality and Adherence
- Surveillance Quality
- Establish procedures required by Tech Spec
- Review Operating Procedures to preclude water hammer events Refer to MC 0350 for items to be addressed Loss of DC Bus Event Shutdown Cooling system water hammer investigation 9
- Operating procedures to be consistent with FSAR 8/15/97
7 1
Millstono Unit No. 2 NRC Significant items List SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE description of operation
- Adequacy of procedure change process to ensure operation in accordance with license.
Refer to MC 0350 for items to be addressed Failure to prepare a safety evaluation for borating RCS during cooldown to Cold S/D Evaluate 2-HV-210 and associated procedures. Review and validate operator actions included in safety analysis Failure to update the FSAR which states that the H2 monitoring system is manually initiated in 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
~
change'rHFde to OP2305 was triaditiuiiiti'ritha it failed to
' ' - ~
lock open the valves. This was corrective action for the seismic issues associated with the refueling drain line 10
- Progress of EOP Upgrades 7/25/97
- Acceptability of deferring AOP Upgrade Refer to MC 0350 for items to be addressed 11 Quality Assurance end. Oversight NOTE 1 Refer to MC 0350 for items to be addressed 12 Licensee Restart Punch List - Review items deferred until NOTE 2 after the restart. Refer to MC 0350 foritems to be addressed 13 Licensing Operator staffing; Control room formality; NOTE 1 attentiveness to duty; attention to detail; off-hour plant staffing; overtime usage; awareness to plant security; awareness of equipment status; log keeping practices.
Refer to MC 0350 for items to be addressed 14 Operating Training issues. Refer to MC 0350 for items to be 8/15/97 addressed 15 Augmented inspection coverage during restart inspection; NOTE 1 Operability of Technical specification systems; Operability of secondary and support systems; System Lineups; Results of pre-startup testing; Power ascension testing. Refer to MC 0350 for items to be addressed
3
.A I
Millstona Unit No. 2 NRC Significant items List SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE 16
- 1) Train on-shift personnel to perform dose assessments NOTE 2
- 2) Revise E Plan to indicate on-shift assessments Effectiveness of ERO; Coordination with offsite emergency planning officials. Refer to MC 0350 for items to be addressed 17 Disposition of Regulatoryissues; Licensee Amendments; NOTE 1 Exemptions; Reliefs; Orders; Gignificant Enforcement issues; Allegations; 10CFR2.206 Petitions; Coordination with NOTE 1 interested agencies and parties. Refer to MC 0350 for items to be addressed 18 Failure to adequately control standards resulted in NOTE 2
{
inappropriate downgrade of QA Cat 1 equipment to a Non-i QA status Failure to prevent the use of potentially non-conforming materialin safety related applications due to lack of adequate MEPL dispositions 19 Failure to promptly resolve deficiencies in the analysis and 8/15/97 design of MCC enclosures Failure to adequately establish the qualification of connectors for seven solenoid valves Complete HELB analysis of Turbine Bldg as well as analysis of CST trench i
20 Failure to provide up to date data or reflect results of 8/15/97 dynamic tests in GL 89-10 Closure Report Failur3 to address the leaking of check valve 2-CS-15A and i
to take action to assess the impact of water being present on the sump side of 2-CS-16.1A Failure to adequately evaluate information on pressure locking and thermal binding IAW PIR procedure Failure to document review of Vendor QA design services i
IAW NU procedures Dynamic testing of steam admission valve Numerous GL 89-10 MOV items to be resolved 21 Fire Protection Program; App R related AOPs; App R 7/15/97 compliance associated with Thermolag.
Refer to MC 0350 for items to be addressed Resolve Thermo Lag issues
y Millstona Unit No. 2 NRC Significant items List SIL-FINAL DUE NUMBER ITEM DESCRIPTION DATE 22 Failure to identify and implement corrective actions NOTE 2 conceming CTMT Sump Screen discrepancies.
Failure to adequately evaluate the installation of electrical jumpers for a malfunction of a different type as required by 10 CFR 50.59-23 Failure to identify and implement corrective actions 8/15/97 conceming CTMT Sump Screen discrepancies.
. Failure to adequately evaluate the installation of electrical JDmpers for a malfunction of a~differentlype"as i;equired By-
' ~
-~' ~~
~
10 CFR 50.59 Failure to maintain the plant configuration within the Licensing Bases for the CTMT Gaseous and Particulate Rms, H2 monitoring system and PASS Full review and assessment of the function of the Pass, H2 Identifies the condition where both H2 monitors were inoperable due to insufficient air flow and not taking a representative sample Failure to establish adequate design controls when CTMT response analysis was changed during the SGRP Failure to update the FSAR which states that the H2 monitoring system is manually initiated in 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 0703 response 24 ERT item resolution - Complete the commitments and 8/1597 recommendations identified in the ERT report 25 Shutdown Cooling system water hammer investigation NOTE 2 26 Response to industry operating experiences were NOTE 2 inadequate. Excessive fast starts were performed compared I
to industry practice.' Failure to determine root cause for the
- 9 bearing failure in March 1196 27 Adequate design control measures not established for -
NOTE 2 verifying the accuracy of the DBDPs 28 Inadequate design verification for RBCCW Surge Tank NOTE 2 seismic restraint modification Failure to adequately control the installation of a temporary m,
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I Millstona Unit No. 2 NRC Significant Itsms List SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE modification to the RBCCW Surge Tank 29 Failure to establish and maintain measures and deign NOTE 2 controls to maintain design basis for the WR NI Channels l
30 Failure to effectively track and implement corrective actions NOTE 2 concerning " dual function" isolation valves j
31 Failure to address the SBO issues identified in the VECTRA 7/15/97 assessment 32 Failure to take appropriate corrective actions for audit issues
- 7/28/97 i~~~
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involving trending and priontiza_ tion of NCRs,
Inade% e wereertw w a.; w..b.,s,u 33 d
NOTE 2 deficiency for a Vital Switchgear room cooler 34 Change made to OP2305 was inadequate in that it failed to NOTE 2 lock open the valves. This was corrective action for the seismic issues associated with the refueling drain line.
l 35 Inadequate corrective action in LER 96-024 NOTE 2 36 Corrective actions for Turbine Bldg crane usage as a heavy NOTE 2 load did not adequately prevent the Unit 1 crane from carrying loads over Vital Swgr 37 Failure to properly implement the requirements of the 8/15/97 Technical Specifications during the formation of an ice plug in the SW Trainer backwash line 38 SFP Enforcement Letter response on FSAR Updates NOTE 2 39 Failure to identify the cause and to take corrective actions for 8/15/97 the incorrect RBCCW flow rates used in the CTMT accident analysis Calculate availrble HPSI system flow rates utilizing fluid temperatures predicted for post accident conditions 40 Complete reanalysis and mods if any for a single MSIV NOTE 2 l
closure event l
Reanalyze secondary side pressure for a single MSlV closure event 41 Submit the revised LBLOCA Analysis NOTE 2 l
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n Millstons Unit No. 2 NRC Significant Itams List SIL 4
FINAL DUE NUMBER ITEM DESCRIPTION DATE 42 EDG fuel oil supply questions 7/7/97
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'43 Appropriateness of the SUR Trip removalin 1978 NOTE 2 44 Ensure that the plant response to a MSLB event will not 8/15/97 result in exceeding the design requirements of CTMT 45 Reanalyze secondary side pressure for a single MSIV NOTE 2 closure event
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- 46 Evaluate 2-HV-210 and associated procedures. Review and -- 8/15/97 validate operator actions included in safety analysis 47 Determine the effect of SPEC 200 electronics on response 8/15/97 time testing and determine if testing additional components i
should be considered during response time testing 48 T.S. Limits for Inoperable MSSV non-conservative 8/15/97 i
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Proposed Unit 3 Technical Specification Chanae Reauest Reautred for Restart Schedule (data as of 6/30/97)
- 1. Appendix G Curves 7/15/97
- 2. Main Steam Pressure Relief Bypass Valves 7/15/97 o
(NOTE - Since the weeklyJerformance indicator date of 6/25/97 when we reported six required for startup, Unit 3 has reduced the number to two)
r REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP s/ms7 NRC No.
TAC No.
IRQ Q188 TSIOPS SNSHC AllSlaned EQBG H&&B j$G 1
M94105 11 Descriotion This PTSCR rnodifes app 6cabihty and actens associated with Steam Generator Slowdown Monitor. Modifos aftheahany for Condeneste PohsNng Facihty Weste Neut Surnp.
IBG.Nn. IAG.Na.
IES Qta8 TSiOPS SA/SHC AllSianed EQBG
$$AR jEG j
2 M97746 25 i
Descriotion This PTSCR (2-5 97) supersedes PTSCR 21 97. It proposes to modify the rninimurn instrument accuracy in Table 3.3-8 for the Met Tower instrumentation.
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NRC No. TAC No.
IRQ Drag TS/ OPS SA/SHC All Slaned EQBG NEAR fBG 3
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Descriotion This chan0e wul almnate the reference to the mes.surement locaten for the Uthmate Heat SirA in TS 3.7.11. An
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per LER B16115 exists to submttted the PTSCR t y 3/31/97.
2 l
4 NRC No.
TAC No.
18.9 Qgag TS/ OPS SA/SHC AllpjgDad EQBG 8888 LEG l
4 15 i
Descriotion This PTSCR would ehminate the requirement to rnter LCO 3.0.3 when the enclosure building is breeched, due to meldng both trains of the enclosure building ventilaten system inoperable (unebie to create vacuum within specifed time period).
NRC No.
TAC No.
I19 QtaR TS/ OPS ENSMC AllSinned EQBG NEAR fBG 5
M94623 10 Descriotion
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The PTSCR redefines containment integrity to perma operator acten during periods when containment isolation volves may be opened under admin controis. Also relocates the list of containment inciaten valves from TS to the TRM. The current PTSCR needs to be modifed to add a docussion of administrative controls to the bases.
NRC No. TAC No.
112 Ogan TS/ OPS SNSHC AllSioned EQBG.
NB&B jgG 6
. M92879 12 Descriotion This PTSCR revlees several survemance requirements regarding Control Room Emergency Ventilation System.
IBG.Ns. IAG.Nn.
IES Qtan IIM21 SA/SHC AllSioned EQBG Ng&R jgG 7
18 7/ 3/97 7/7/97 7/16/97 7/18/97 Descdahon This PTSCR modifies the bases to inofve the EDG fuel oil storage capacity issue.
NRC No.
TAC No.
IRQ QEER TS/DPS SA/SHC AllSinned EQRG NEAR jgG B
148 7/3/97 7/8/97 7/1@97 7/14/97 7/16/97 7/24/97 7/31/97 Descrintion Certain RPS and ESAS trips chd not consider the uncertainityassocated with a Harsh environment. Some RPS and ESAS setpomts were based on 24 months instead of 18 months.
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REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP scomr naENe, IAG.!kh 159 Dran TS/ OPS 3&lattG m Sinned EggG jia&a tmG 9
32 7/3/97 7/847 7/1047 7/14/97 7/16/97 7/2497 7/31/97 Descriotion Reactor trip setpoints for Sr3 esfety whos in Table 3.7-1 based on 107% power instead of 106.6%, so nonconservette NRC No. I&qjkL IRE Qtg8 TS/ OPS SA/SHC AHSiened 2QRG fi1&B 3RQ 10 104 7/397 7/1047 7/15/97 7/21/97 7/23/97 7/31/97 8/5/97 Descriotion Errors in the RCS Precms/ Temperature Curves. Will require a chen9e to the Tech Spec P.T curves. Amend.151 remond wordn0 that 3.0.4 is not WNa from the PZR PORV TS. Need to add 3.0.4 exception. LTOP setpoint needs to be changed NRC No.
IAG.jkL '139 ggg3 IE52EE SA/SHC AH Sinned EQBG 11883 jBG 11 160 7/347 7/ 8/97 7/1157 7/16S7 7/18/97 7/24/97 7/2647 n_
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DeSGrintlGil Meadmum containment pressure needs to be reEmed from 2.1 psig to 1.0 poig to'aupport accident M assumphons
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NRC No. 18G.tht.
Igg Dgag TS/ OPS SA/SHC All Sioned 2QBG N&&B JBQ 12 159 7/11/97 7/15/97 7/18/97 7/25/97 7/28/97 8/1/97 8/8/97 Description The safety hmft cure may not be correct because of changes to mawnum RCS flow assocated with the DNB Margin Technical Specircebon. The curve may need to be modified.
NRC No. IAG.jkL 11Q Drag TS/ OPS galgtlG
&E,1lgriggi EQBG
$$&B BEG 13 155 7/397 7/1097 7/1447 7/2497 7/25/97 Descriotion Verbohm comphence issues. ECCS throttle vehes. AFW sury. CS/ CAR acten statement.
NRC No.
TAC No.
139 gggR TS/ OPS SA/SHC AIL 81oned EQBG l DEAR BEG 14 150 7/747 7/947 7/16/97 7/18/97 l
Description RPS and ESAS trip action statements allow indefinite bypees of an inoperable channel. This wul be changed to abow only 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before placin0 channel in the tripped condition NEG.thL IAEjkt IRQ Drat 185221 SalttlG Au Stoned EgBG NEAR REG 15 1
7/11/97 7/18/97 7/24/97 7/2847 Descrintion This PTSCR dolotes TS 3/4.9.14 and Table 3.91, modifies LCO 3.9.15 to require two EBFS trains to be operable and adds the requirement to how et inest one train in operaten whenever fuel mowment or crene opershon is in progrees, adds a -~ ' _..;
regeren0 spent fuel pool eres ventgehen Weegrity, changes the secocleted schans requirements, changes the sunmalence requirements, and the bases. TNs change remows the requirement for the idue sghts?
BEG.thL IAG.tht.
I89 Dra8 InstEt AalttiG AHSinned EQRG N&&B NRG 16 67 7/947 7/17/97 7/21/97 Danctiotion 1
Need to add 2 eeoond time doisy to ESFAS Table 3.34 Os to be consistent with 8b and ITS.
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REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP saom7 i
1 NRC No.
TAC No.
189 Dra8 TS! OPS SA/SHC Aff Sioned EQBG hl&&B jdfLG t7 66 7/747 7/9/97 7/1N97 7/16/97 7/2N97 7/28/97 Descrintion TS 3.4.1.3 Acton could require Mode 5 with no SDC loops operable.
17 TOTALISSUES 1
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Liconso Amondmont Roquosts Millstone 1 - June 1997 Progress: Unit 4 is on schedule forsubrnittat atticense amendment requests to 1
support reloadandrestart 1
10 8
6 LAR submittal data through 6/30/97 g
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct -
Nov Dec h LARs to be Submitted miBB LARs Submitted -e-Work-Off/ Goal
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Raw Data Jan-97 Feb-97 Mar-97 Apr-97 Mey-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 LARs to be Submrtted 4
3 2
2 1
1 1
LARs Submitted 2
3 4
4 5
5 5
4 Worit-OM/ Goal 4
3 2
2 1
1 1
i Definition Analysis / Action License Amendment Requests (LARs) are changes to There are two License Amendments required for Technical Specifications or other license changes that are reload, both are submitted.
required for restart, and that must be submitted to the
- 1. Response Time Testing, submitted on 2/7/97 NRC for approval.
- 2. Allowed Outage Time (AOT), submitted on 316/97, approved on May 28,1997.
NRC verbally requested additionalinformation (RAl) regarding Response Time Testing-sent 4/3.
There are four license amendments required for start-up, three are submitted.
- 1. SBGT Vent and Purge
- 2. SRV Electric Lift
- 3. Neutron Monitoring For the SBGT Vent and Purge amendment, the NRC Comments issued RAI which has questioned the approach for the Data through 6/24/97.
PTSCR. Engineering is conducting a review of other utilities to determine an attemate approach for venting and purging containment.
The fourth issue is GL 87 09. This will be submitted by Goaf 7/31/97 All LARs requiring NRC review submitted by Oct 21, 1997.
Data Source:
R. WaWe X2191l Analysis by-R. Walpole X2191l Owner:
R. Walpole X2191 11,UR EsAmm PAOP4 in
MILLSTONE UNITS 2 & 3 CMP STATUS June 27,1997 STATUS Unit 2 Unit 3 Total
% Complete Total
% Complete Program Reviews 51 Programs 76%
51 Programs 90 %
FSAR Annotation Wave 1 15 Systems Complete 16 Systems Complete Wave 2 _ ;_ _.16 Systems 0
- - _31 Systems a _. 90%
Wave 3 32 Systems 0
28 Systems 85%
Tech Spec /TRM Review Wave 1 15 Systems Complete 16 Systems Complete Wave 2 16 Systems 0
31 Systems Complete Wave 3 32 Systems 0
28 Systems 98 %
Calculation Reviews Wave 1 15 Systems Complete 16 Systems Complete Wave 2 16 Systems 0
31 Systems Complete Wave 3 32 Systems 0
28 Systems 60%
Design Change Reviews Wave 1 15 Systems Complete 16 Systems Complete Wave 2 16 Systems 0
31 Systems 40%
Wave 3 32 Systems 0
28 Systems 0
Regulatory Commitment Validation 10987 70 %
5075 80%
System Reviews / Summaries Wave 1 15 Systems 73 %
16 Systems Complete Wave 2 16 Systems 0
31 Systems 10%
Wave 3 32 Systems 0
28 Systems 5%
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