ML20140A523
| ML20140A523 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/12/1997 |
| From: | John Nakoski NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9706040250 | |
| Download: ML20140A523 (152) | |
Text
i May 12,1997 )
LICENSEE: NORTHEAST NUCLEAR ENERGY COMPANY (NNECO)
FACILITIES: Millstone Nuclear Power Station Units 1,2, and 3 (50-245,50-336,50-423)
SUBJECT:
SUMMARY
OF THE APRIL 30,1997, MEETING WITH NNECO TO DISCUSS PROGRESS OF LICENSEE ACTIVITIES TO SUPPORT RESTART OF THE THREE MILLSTONE UNITS On April 30,1997, the Special Project Office (SPO) staff of the Office of Nuclear Reactor Regulation (NRR) participated in a publicly observed meeting with Northeast Nuclear Energy Company (NNECO) representatives. The purpose of this meeting was to discuss the licensee's progress in facilitating restart of the three Millstone units. During this meeting, discussions were held on the licensee's progress for'each of the three Millstone units, and an overview of the activities of the Nuclear Oversight organization and the Nuclear Safety Assessment Board (NSAB) were presented.
Attachment 1 provides a list of the principle attendees at the meeting. Attachment 2 provides the handout used by the licensee during its presentation to the NRC.
ORIGINAL SIGNED BY:
John A. Nakoski, ICAVP Program Coordinator ICAVP Oversight Branch Special Projects Office Office of Nuclear Reactor Regulation Dockets Nos. 50-245,50-336, and 50-423 Attachments: As Stated cc w/att: See next page C40011 ,
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. \ ..... j LICENSEE: NORTHEAST NUCLEAR ENERGY COMPANY (NNECO)
J FACILITIES: Millstone Nuclear Power Station Units 1,2, and 3 (50-245,50-336,50-423)
SUBJECT:
SUMMARY
OF THE APRIL 30,1997, MiETING WITH NNECO TO DISCUSS PROGRESS OF LICENSEE ACTIVITIEb TO SUPPORT RESTART OF THE l THREE MILLSTONE UNITS On April 30,1997, the Special Project Office (SPO) staff of the Office of Nuclear Reactor l Regulation (NRR) participated in a publicly observed meeting with Northeast Nuclear Energy Company (NNECO) representatives. The purpose of this meeting was to discuss the licensee's progress in facilitating restart of the three Millstone units. During ibis meeting, discussions were held on the licensee's progress for each of the three Millstone units, and an overview of the activities of the Nuclear Oversight organization and the Nuclear Safety Assessment Board (NSAB) were presented.
l Attachment 1 provides a list of the principle attendees at the meeting. Attachment 2 provides i the handout used by the licensee during its presentation to the NRC.
]
3 hn A. akoski, ICAVP Program Coordinator AVP Oversight Branch Special Projects Office Office of Nuclear Reactor Regulation Dockets Nos. 50-245,50-336, and 50-423 Attachments: As Stated cc w/att: See next page
'e a 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 Fx,jects 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 - Nuclear Work Services 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 Mr. Allan Johanson, Assistant Washington Nuclear Operations 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 Millstone Unit No. 2 Nuclear Recovery Officer First Selectmen Northeast Nuclear Energy Company Town of Waterford P. O. Box 128 i Hall of Records Waterford, CT 06385 200 Boston Post Road Waterford, CT 06385 Senior Resident inspector i Millstone Nuclear Power Station Mr. J. P. McElwain c/o U.S. Nuclear Regulatory Commission Millstone Unit No.1 Nuclear P. O. Box 513 Recovery Officer Niantic, CT 06357 l 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 l
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Northeast Nuclear Energy Company Millstone Nuclear Power Station Units 1,2, and 3 cc:
Mr. M. H. Brothers Ms. P. Loftus
, Vice President - Millstone Unit 3 Director- Regulatory Affairs for 1- Northeast Nuclear Energy Company Millstone Station P. O. Box 128 Northeast Nuclear Energy Company Waterford, CT 06385 P, O. Box 128 Waterford, CT 06385 Burlington Electric Department c/o Robert E. Fletcher, Esq. Mr. N. S. Cams 271 South Union Street Senior Vice President and .
Burlington, VT 05402 Chief Nuclear Officer l Northeast Nuclear Energy Company Mr. M. R. Scully, Executive Director P. O. Box 128 Connecticut Municipal Electric Waterford, CT 06385 Energy Cooperative 30 Stott Avenue Norwich, CT 06360 Mr. William D. Meinert .
Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.' O. Box 426 Ludlow, MA 01056 Emest C. Hadley, Esq.
1040 B Main Street )
P. O. Box 54g West Wareham, MA 02576 l
Joseph R. Egan, Esq.
Egan & Associates, P.C. j 2300 N Street, NW '
Washington, D.C. 20037 Citizens Regulatory Commission ATTN: Ms. Susan Perry Luxton 180 Great Neck Road Waterford, Connecticut 06385 The Honorable Terry Concannon Mr. Evan Woolacott Co-Chairs Nuclear Energy Advisory Council Room 4035 !
Legislative Office Building Capitol Avenue Hartford, Connecticut 06106 l
-_. _ _ .. ~ . _ . ..__ _._. _ _ . _ __...__ _ . _-_. _ _ ..- _ _ ._ _ ___ ._. .. _ . . .. _ ___ _ _
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LIST OF ATTENDEES )
i- April 30,1997 ;
i NAME ORGANIZATION POSITION i l
! Jacque Durr NRC Chief, inspection Branch, SPO )
I Steve Reynolds NRC Chief, Licensing Branch, SPO
( l 1
- Eugene Imbro NRC Deputy Director, ICAVP Oversight, SPO
- William Travers NRC Director, SPO l l
Phil McKee NRC Deputy Director, Licensing, SPO ]
Wayne Lanning NRC Deputy Director, inspections, SPO Tony Cerne NRC Senior Resident inspector - Millstone Unit 3 Dave Beaulieu NRC Senior Resident inspector - Millstone Unit 2 Ted Eastick NRC Senior Resident inspector - Millstone Unit 1 David M. Goebel NNECO Vice President- Nuclear Oversight l
Michael Brothers NNECO Vice President - Millstone Unit 3 Neil S. Carns NNECO Senior Vice President and Chief Nuclear Officer Pat Loftus NNECO Director - Regulatory Affairs for Millstone Station Mario Bonaca NNECO Chairman, Nuclear Safety Assessment Board Paul Hinnenkamp NNECO Millstone Unit 1 Recovery representative Martin L. Bowling NNECO Millstone Unit 2 Recovery Officer l
1 Attachment 1
l Northeast Utilities Presentation to the NRC Restart Assessment Panel Millstone Station April 30,1997 Attachment 2
. e ,
l a
! Agenda l
!
- Opening Buzz Cams
{ . Nuclear Oversight Dave Goebel
. Nuclear Safety Assessment Board Mario Bonaca e Unit 3 Update Mike Brothers
- Unit 2 Update Marty Bowling e Unit 1 Update Paul Hinnenkamp
- Closing Buzz Carns I
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Taale of Contents
~
- . Presentation Slides i
- . MP1 Reference Material i
. MP2 Reference Material
. MP3 Reference Material I
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. MP2 IR 96-201 Summary !
. MP3 IR 96-201 Summary 1
4
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Northeast Utilities Briefing for the NRC Restart Assessment Panel Millstone Station April 30,1997
. ~i s -
Agenda
+ Opening Remarks Buzz Carns
+ Oversight Dave Goebel
+NSAB Mario Bonaca
+ Unit 3 Update Mike Brothers
+ Unit 2 Update Marty Bowling
+ Unit 1 Update Paul Hinnenkamp ,
+ Closing Buzz Carns
/ x 2 Northeast Nuclear Energy
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i Nuclear Oversight i
Dave Goebei ;
Vice President !
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Success is When The Oversight Function ...
+ ls an integral part of management team i assessments l + Results in meaningful findings, and provides assessments of programs and '
l process through meaninaful reports l + Finds evidence that reports are l forwarded to the responsible manager and dealt with appropriately l !i e x 4
Northeast Nuclear Energy i
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Success is When The Oversight Function ...
+ ls adequately staffed with qualified and experienced personnel
+ Has _ clearly defined audit and surveillance programs that are proceduralized and implemented on schedule
/ x s Northeast Nuclear Energy i
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Key Tenants of Oversight
+ Thoroughness of self assessments
+1ntelligent intrusiveness of Nuclear .
Oversight
+ Penetrating reviews performed by NSAB* -
- NSAB will be discussed separately
< x 6 Northeast Nuclear Energy i
-l s -
Changes in Nuclear Oversight Nuclear Oversight is implementing an Aggressive Recovery Plan With... ,
Increased Number of Staff Positions
- positions filled by permanent staff
- line people rotating in
- meetings being held regularly with the line to address Oversight-identified findings and observations Revised Oversight Procedures
- new procedures communicate higher standards
/ x 7 Northeast Nuclear Energy i
1 N /
"l Oversight Changes (continued)
! + Training and Qualification Programs ;
-improved - new Training Advisory Councils established
+ QA Hold Point Program Revised l + Accountability of Oversight Staff
- Increased
-deal from facts, requirements-based
+ Oversight Feedback to the Line improved
+ QA Topical Report Revised to Reflect Organizational Changes
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- Operational Experience backlog
- Audit records not properly transmitted to vault
- 50.54(f) staff training and qualification deficiencies identified
- The number of years of QA experience of PE management team is low PE developed a Mission Statement and a Strategic Plan based on feedback from S/A to address this
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Self Assessment Challenges
+ Units must demonstrate their Self -
Assessment Program can, and will, deliver quality results
+ Continued management attention is needed to ensure improvements are long lasting
+ Oversight needs to perform an increased number of self assessments
/ x ,
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Sample Audit Results
- Document Control - too many "controIIed copies" - reducing number of libraries
+ Design Control - Manual ambiguous; S/A deficiencies not being resolved in a timely manner
+ Simulator Fidelity - Program to maintain not adequate
+ Housekeeping / FME - Program inadequate; requires upgrade
+ Fire Protection - Program lacks ownership; failure to correct previous audit findings
- s u Northeast Nuclear Energy
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Sample Surveillance Results
+ MP3 - MOVissues on vendor control, training, asbestos control
+ MP3 - QA and non-GA stainless and carbon steel stored together
- MP2 - identified need to increase shutdown risk margin
+ MP1 -inadequate control of bulk chemicals
+ MP1 - inadequate corrective action regarding work on the gas turbine air start valve
/ x Northeast Nuclear Energy
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Readiness for ICAVP is when...
+ Discovery is complete for 50% of safety and risk-significant systems
+The NRC has approved the Audit Plan .
+ Oversight readiness concurrence
/ x 18 Northeast Nuclear Energy
1 x ,
l Oversight 50.54(f) Results
+ Efforts to date have focused on instilling quality into line processes with continuous feedback t
- earlyidentification ofprogrammatic weaknesses
- developed " gap analysis" to assess risks associated with process l elements -
/ x 19 Northeast Nuclear Energy
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x <. ^ .l MP3 ICAVP Readiness '
Unit 3 ICAVP Readiness it 3 Goals April 25,1997 OO lit 3 Status 100 % - - - - --
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Elements of the 54(f) Process j
/ N 2n Northeast Nuclear Energy i i
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Unit Response to Nuclear Oversight
+1s not where it needs to be, but is improving l + Even better response is expected as Oversight...
- improves the quality and consistency of its findings
- adds value through intelligent intrusiveness
/ x 21 Northeast Nuclear Energy
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Employee Concerns Progress
+ Meeting planned for mid-May .
+ Developed an ECP Comprehensive Plan
+ Increased staff numbers, training and qualification standards
+ Brought in experienced contractors to address backlog
+ Selected Little Harbor Consultants to act as Independent Third Party Oversight Program
/ N j 22 Northeast Nuclear Energy
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MP Nuclear Concerns Backlog 1
NOTE: No Resolmd/ Overdue During Dec. Jan. Feb. Mar.
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E Rec'd O Resolved(This Month) gTotalUnresolved E T otalResolved/PendingCosure gResolved/ Overdue s-(_
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/ x t 23 Northeast Nuclear Energy
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MP Nuclear Concerns by Type .
70 % j 60 % W;; -
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i e x i u Northeast Nuclear Energy '
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50 %
40% i E Anon 30 %
MConf 20 % g 10% ,
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. Jan %7 Feb S7 Mar B7 V N g . Northeast Nuclear Energy
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t Oversight Challenges
+ Implementing Oversight Recovery Plan while overseeing unit restart activities
+ Continuing to improve our own ability to identify and track problems
+ Providing accurate feedback based on small sample sizes
+ Assist in guiding overall site-wide t
improvement in working relations
/ x t a6 Northeast Nuclear Energy
'4 , on Nuclear Safety Assessment Board Mario Bonaca Chairman, NSAB
' x g Northeast Nuclear Energy
x / '!
How Do We Define Success?
+ NSAB is capable of identifying performance trends and limiting weaknesses not identified by the Line organization or Oversight ,
+ NSAB is able to influence improvements in Line self-assessment and Oversight
+ Problems are identified and resolved by the Line
' N -
28 Or$9BSt hClear hergy
x < -i NSAB Issues Being Addressed ,
+ NSAB ability to identify genenc issues and limiting weaknesses in the '
Line and Oversight
+ NSAB ability to track and gain resolution of issues
+ NSAB ability to play a nuclear safety advocacy role 1
' ~
x 29 Northeast Nuclear Energy t
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Changes Made to Enhance NSAB Effectiveness
+ Separate Board created for Connecticut Yankee - NSAB focused on Millstone
+ Membership includes Recovery and Oversight Officers
+ External consultants increased to 4
+ NU Board of Trustees providing oversight of NSAB
+ Increased focus on safety-significant issues
+ Formalized communication to CEO
/ x 30 Northeast Nuclear Energy
N / ';
Changes Made to Enhance NSAB Effectiveness
+ Five Subcommittees: l
- Operation and Maintenance
- Assessment and Quality
- Engineering +- M
- Safety Evaluations -
l i - Support FunctionsJ' l + Increased capability to monitor l
effectiveness of Oversight l
+ NSAB expectations for TS change l reviews N
31 Northeast Nuclear Energy l
O N /
Recent NSAB Contributions
+ Lay-up standards issues
+ Reactivity management program
+ Station-wide testing issues
+ ICAVP readiness differences between the Line and Oversight
+ Quality and timeliness of PORC-minutes
/ x 32 Northeast Nuclear Energy
i I NSAB Contributions
, + Strengthened the audit program by demanding expanded scope,. depth and focus on generic implications and strength of self-assessment
+ lssued Nuclear Safety Standards and Expectations document
+ Reviews all Safety Evaluations, sends 1 back to PORC for corrective action - , #j those in need of improvement or 4~
considered unsatisfactory
- / x sa Northeast Nuclear Energy
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SAFETY EVALUATION RATING (1997 YTD Review Results)
Nuclear Number (Nii Needs Unit Reviewed improvement (U) Unsat MP1 46 3 0 MP2 58 7 0 MP3 43 2 0 Total 147 12 0 Needs improvement (NI) - Correct conclusion; documentation is sufficiently flawed so as to require revision Unsatisfactory (U) - Wrong conclusion and/or major flaws
' \
l l 34 Northeast Nuclear Energy
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+ Keeping abreast of changes ongoing at the units and the impact of changes
+ Need for effective Key Performance Indicators for all three units
+ Assigning priorities commensurate with safety significance i'
l + Maintaining NSAB participation as a
< station priority l
/ x as Northeast Nuclear Energy
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Basis for NSAB Recommendation for Unit Restart
+ Corrective actions are effective and timely, and backlog is steadily trending down
+ Employee concerns are increasingly directed to, and addressed by, the Line
+ Line management and Oversight are identifying and resolving issues before they come to the NSAB Draft NSAB restart readiness review pian to be reviewed at May 1 meeting '
36 Northeast Nuclear Energy
\ /
Millstone Unit 3 Update Mike Brothers Vice President
' N 37 Northeast Nuclear Energy A
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Format for Presentation
+1nspection Report 96-201
+ eel / SIL
+ Corrective Action / CMP
+ Performance Indicators
+ Challenges
+ Milestone Schedule
' x 38 Northeast Nuclear Energy
- i x /
- MP3 - Status of IR 96-201 Eels
+ 28 Eels issued - 4 common causes
-inadequate management
! expectations
-inadequate Corrective Action Program
-inadequate Engineering Design and Configuration Program l - inadequate Oversight i
/ _ x 3e -
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MP3 - Corrective Actions for IR 96-201 Items :
+ Programmatic (50.59 process '
+ Modification / Setpoint Changes 7
+ Documentation
- (TRM/FSARCR/PTSCR/Cales) 6
+ 1mmediately Corrected 3 l
- / x 40 Northeast Nuclear Energy
_ _ - _ _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ ___-___-_____--_A
i s -
Status of eel 96-201-04 (MP3)
Procedures were
+ Corrective Action:
changed without a PTSCR to permit -modification to closure of Turbine- the AFW-36 Driven Auxiliary valves Feedwater discharge valves -50.59 procedure -
whenever the revision & i Motor-Driven tra. .ining Auxiliary Feedwater -PTSCR submittal pumps were used + Schedule 81519 7 for steam generator water control.
e N ,
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Status of eel 96-201-18 (MP3)
Controls were not established to + Corrective Action: i coordinate lubrication interval comprehensive revision incorporated into of procedures procedures necessary to implement all aspects of Tech training in Tech Spec Amendment 100, S ec changes and II**"**
includingreconciliation .
" *"d " *"
of the vendor recommended pre- + Schedule: 7/22/97 Iubrication interval for AFWpumps.
' N n Northeast Nuclear Energy
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MP3 Closure Package Schedule i
Schedule for submitting closure packages:
+ Closure packages due by 5/16 - 2
+ Closure Packages due by 6/23 - 3
+ Closure Packages due by 7/23 - 10
+ Closure Packages due by 8/13 - 12
+ Closure Packages due by 10/7 - 1 !
' N 43 Northeast Nuclear Energy
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- s -
MP3 - Configuration Management / 50.54(f)
Total C/As since ACR 7007 CMP inputs to Corrective -
Action Program 3949 700 (ACRs and CRs)
LERs 83 43 i
Restart Modifications 109 30
/ x a4 Northeast Nuclear Energy j
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l MP3 Significant items identified "*"
ggggp ,gg- MCMn~h' CM PROJECT RSS Fluid Ambient No
____ Temperature _ _ _ _ _ . _
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' N 48 Northeast Nuclear Energy
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Unit 3 - Condition Report Method
- of Discovery 100 90 AjinT[hta Thmugh 4/19'97 70 2 eo 3so
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/ x 49 Northeast Nuclear Energy
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Unit 3 - Open NRC Commitments for Restart -- _ - -
Data through g _
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Unit 3 - Licensee Event Reports 20 g
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/ x s1 Northeast Nuclear Energy ' i
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Unit 3 - License Amendment Requests 25 --
Data through 4/25/97 20 .
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/ x 52 Northeast Nuclear Energy i i
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Unit 3 - Restart Modifications i Awaiting Implementation
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4/21/97 l 1750.
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54 Northeast Nuclear Energy I
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30 Data through 4/20/97.
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< x ss Northeast Nuclear Energy i
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56 Northeast Nuclear Energy i
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Unit 3 - Operator Work Arounds 45 __
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/ x 57 Northeast Nuclear Energy ;
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Unit 3 - Task Completions Required for Restart 1 I l
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' N 59 Northeast Nuclear Energy .
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4/23s 7 160 .
8 140 E
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l l
i.
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Unit 3 - 10CFR50.54(f) Readiness for Submittal D51Dhrough 4/25/97 80% ,
m
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/ _. x s1 Northeast Nuclear Energy ,
i
s -
Unit 3 -lCAVP Readiness 100 % ____ . _ . . . _ . _ __
4/23/97 a 80%
Y -
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$ i 0% 8 I I I I I I t I I !
Jan Feb IVbr Apr May Jun Jul Aug Sep Oct Nov Dec !
gICAVP Remaining
. i i
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Northeast Nuclear Energy i
s2 i
s - -
MP3 Challenges
+ ICAVP
- Electrical Separation
- Completion of SSAs
+ OSTI
- Employee Concerns
- Corrective Action j
- Configuration Management Program ,
- Arcor j
- MOVs j
- AWO Backlog
' x sa Nortineast Nuclear Energy
- j
n!,
s - n i MP3 Milestone Schedule
+ independent Corrective Action Verification Program 5/27
+ Complete Remaining SSAs
<'< Wave 2 and Wave 3) 7/14
+ lssue 50.54(f) letter to NRC 8/13
+ Plant Physically Ready 9/30
/ \
s4 Northeast Nuclear Energy
N T
/
Millstone Unit 2 Update i
Marty Bowling l Recovery Officer - Unit 2 f
/ x ss Northeast Nuclear Energy -
oy x <
Raising Standards i
- Nuclear Safety .
+ Leadership and Management Expectations
+ Training
+Self Assessment 4
+ Corrective Action
+ Procedure Upgrades
' N i
66 Northeast Nuclear Energy 1
y s -
MP2 - Status of IR 96-201 Eels l
f
+ 14 Eels issued - 4 common causes '
l
-inadequate Management Expectations
. inadequate Corrective Action Program
-inadequate Engineering Design and Configuration Program
- inadequate Oversight
' x 67 Northeast Nuclear Energy
_________-____..-___-_____-___.___m - - _ _ . _ _ . _ _ _ _ - + _-_.u_ _ _ - - - _ __ _- =__, _- --
\
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MP2 - Corrective Actions for IR 96-201
+ Programmatic 11
+ Modification / Setpoint
- Changes 3 i
i
' s ;
68 Northeast Nuclear Energy I i
I
s - -
MP2 Closure Package Status
+ Total number of closure packages presented to the NRC to date -5
. + Schedule for submitting closure packages:
- closure packages due by 5/16 - 2 i
- closure Packages due by 6/13 - 2
- closure Packages due by 7/18 - 2
- closure Packages due by 8/15 - 3 I
i
' N s9 Northeast Nuclear Energy l
s s -
Status of eel 96-201-25 (MP2)
Corrective actions + Corrective Actions pertaining to initial "as found" maintenance and testing of the 23 dual function valves testm.a of 23 dual has been completed function ORP has been containment issued to address isolation valves programmatic I'*"**
were not completed as required. CAD established to track commitments i
e x .
70 Northeast Nuclear Energy
- - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - _ - _ - - _ - - - _ - ---- ---- J
Status of eel 96-201-41 (MP2)
The piant + Corrective Action configuration for the An engineering
- Containment report has been Gaseous and issued which defines Particulate the licensing basis. ,
Radiation Monitors, This will be used to Hydrogen generate the Design Monitoring System Change to repower the _i solation valves '
and Post-Accident to prevent single Sampling System failure. The was outside ofits Hydrogen monitors design basis. and containment RMs will also be replaced.
/ N 71 Nodfreast Nuclear Energy
si s, -
I MP2 Configuration Management ,
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CM PROJECT ._
Containment Sump No Screen Installation Environmental Qual No 1
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Start-up Ikate Trip es Removal . . _ _ _ _ _ _ . . . . _ _ . . . _ . _ ._..__..,_ _. _ __
Single MSIV Closure -
Yes l
_________,________._.,,_.,__._m_._. _ , . . _ _ _ . , _ _ _ _ . _ _ ___ _
' x 73 Northeast Nuclear Energy
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MP2 Challenges
+ Healthy Safety Environment
+ Self Assessments
+ Operator Training
+ Work Control Process
+ Modifications
+ Heatup / Cooldown Operations i
+ Technical Issues
-Thermo-Lag and Appendix R ^#
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/ x i 74 Northeast Nuclear Energy i
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MP2 - Key Schedule Milestones
+ 6/23 Ready for ICAVP Start i
+ 6/30 Complete License Amendment Submittals
+ 8/6 Complete Reactor Core Reload
+ 8/15 Complete NRC Significant item List (SIL) Closure Package Submittals
+ 9/5 Complete CMP for Group 1 and 2 Systems
+ 9/29 Ready for OSTI
~
+ 11/14 MP2 Ready for Restart .
+ 11/25 Complete Preparations for Heatup e x i 75 Northeast Nuclear Energy
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i Millstone Unit 1 Update Paul Hinnenkamp .
Director, Unit 1 Operations l 4
' x ,
t 76 Northeast Nuclear Energy
x / *;
Unit 1 Update
+ Leadership '
+SIL Status i
+ Configuration Management
+ Performance Indicators
+ Challenges
+ Schedule i f
l I
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78 Northeast Nuclear Energy i
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Corrective Action CMP (Post-ACR 7007)
Inputs to Corrective Action 3183 170 Program LERs 88 4 Restart .
Modifications 49 0
- s 79 Northeast Nuclear Energy
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Item Description Discovered by CMP !
ElectdcalSeparation No Bdting/Seisnic No PACIFlow/ Gas Turbine Yes Tining Condensateissues Yes Torus Coating No ADSSingle Failure No l
/ \
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/ x l Northeast Nuclear Energy
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' x Northeast Nuclear Energy -
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+ Developed and issued site-wide nuclear safety standards and expectations
+ Clarified STA roles and expectations
+ Increased licensed operator training on l unit's operational limits and margins ,
i + Evaluating licensed operators on conservative decision-making l competencies
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/ x Northeast Nuclear Ene.gy
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+ Developed operations standards on command & control, communications, and reactivity control
+ Focused outage repairs and corrective l actions on most important safety ;
systems
+ No significant events i
i Northeast Nuclear Energy
s s - c; Leadership and Management
- Expectations
+ Providing and reinforcing clear
! expectations for nuclear safety, defense-in-depth, meeting commitments, self .
assessment, and addressing employee concerns
+ Conducted leadership training for first-line supervisors and above with periodic follow-up
+ Conducting leadership training for licensed operators during LORT
/ x Northeast Nuclear Energy l
_ _ _ _ _ - - - - - - - - - _ - - - - - - - _ _ _ - _ - - - - - - _ _ -_D
e N / }
Leadership and Management Expectations
+ Identified key behaviors critical to team success which stress accountability
- + Improved professionalism in the control room and in the conduct of operations --
automated log keeping
+ No missed NRC commitments in 1997
/ x Northeast Nuclear Energy l
N / 'l l
- Tra. .ining
+ Established line ownership for
. training
+ Provided expectation of 100% .
attendance
+ Established unit and executive
- committees to monitor and enhance training
+ Management is observing training l
/ x !
I Northeast Nuclear Energy
- _--_-------------_---------- -------------- -- - -__ --- - _---------------- a
\ / #l SelfAssessment I
+ Set clear expectations
+ Training being conducted for first-line i
- supervisors and above
+ Developed department self-assessment plans for 1997 i
I t
i
/ N !
Northeast Nuclear Energy i i
i
_--__ __ __- ______________-__-__ ___ _-__-_ - ___ -___- ___ __ - -__-_-_____ - __ O
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+ Continuing benchmarking with recent efforts in: ,
- chemistry
- ALARA- .
- self assessment
- corrective action :
- environmental qualifications t
- configuration management
+ Operational readiness assessment ,
planned
+ Restart readiness assessment planned
' x l Northeast Nuclear Energy j i
1 u
s / '
Procedure Upgrades
+ Established centralized procedures group
+ Conducting self assessment to RG 1.33 i
+ Remaining for restart as of 4/30/97
-procedure upgrade project - 151
-emergency operating procedures - 13
-abnormal operating procedures - 57 i
t
/ \
Northeast Nuclear Energy l i
i
\ / ,
Corrective Actions
+ Addressed programmatic weaknesses in revision to RP4 i
+ Strengthened implementation with multi-discipline management review team and training
+ Verifying corrective actions before closure
+ Completing first trending and self-assessment reports
+ Lowered threshold for generation of ,
Condition Reports ('10% more CRs generated year-to-date in 1997 compared i to 1996 i
/ x Northeast Nuclear Energy l l
. . f
s -
t Corrective Actions
+ More timely reportability reviews of condition reports are taking place. -
t
+ Investigation of CRs are taking place within 30 days (backlog >30 days expected to be eliminated by May i 1997) :
+ Twenty closure packages provided to NRC
/ x !
Northeast Nuclear Energy
O I 4
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Unit 2 - Open Power Block Condition Reports
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/ \
Northeast Nuclear Energy
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Status of Millston2 Unit 2 Open itsmo rt@sulting from the 96-201 Inspection ,
Reference item Description Closure Status SIL Modification / V, Number Package Number Potential i Due Date Modification eel 96-201-03 Failure to adequately eveluate Submitted
- Additional training of personnel performing 23 No the installation of electncal 10CFR50.59 reviews has been implemented. ;
jumpers for a malfunction of a
- The Programmatic aspects correcting this ,
different type as required by 10 issue was addressed in the 50.59 procedure CFR 50.59 changes eel 96-201-09 Adequate design control Submitted
- Configuration Management Plan is being 27 No measures not established for implemented. Engineering Programs verifying the accuracy of the Department formed to follow administrative DBDPs Discrepancies noted requirements. CMP has replaced DBDP's with ;
but not dispositioned. DB's and LB's. DBDP's are identified as i
- Reference Only" ;
- Design Change Manual has been revised to i
prevent recurrence.
- This issue deals with a programmatic concem ,
which is being addressed by the CMP and DCM '
changes.
eel 96-201-11 Failure to adequately control Submitted
- Improvements in management expectations as 28 No the installation of a temporary well as an overall effort to raise standards has l t
modification to the RBCCW been implemented through the ORP Surge Tank. A number of
- A new rigging manual has been approved.
deficiencies in the design Training for the manual has been completed j documentation and
- Design documentation deficiencies have been l implementation were noted. corrected and engineering training completed. !
- This issue concems programmatic deficiencies t which have been addressed by the above !
actions. j i
p.ucadmcewn6s doc i
._ _ .. _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ _ _ - _ _ _ _ - - _ _ = - - _ - _ _ _ _ - _ _ - -__-___ - __ _ ____ - _ - -_
e-Status of Millstona Unit 2 Open Itam. desulting from the 96-201 Inspection Reference item Description Closure Status SIL .
Modification / ht Number Package Number Potential Due Date Modification-eel 96-201-12 Failure to establish and 8/15/97
- A Design Change Record is currently being
. 29 Yes-maintain measures and design prepared to address the single failure and Note 1 controls to maintain design separation concems. The DCR and DCN are basis for the WR NI Channels currently in review. The DCR is scheduled to be presented to PORC on 5/14/97 with the installation scheduled for 7/25/97 i
- The closure package will be a partial package since the modifications will not be fully tested by 8/15/97.
- This design issue covers both the ;
programmatic concems from original construction as well the physical modifications needed to address the potential single failure !
concems. -
t eel 96-201-20 Failure to promptly resolve 8/15/97
- Door seat restoration will be completed after 19 Yes i deficiencies in the analysis and completion of engineering design. There is a Note 2 design of MCC enclosures parallel effort to determine best course of action
- 1) A specification has been prepared for new t MCC Enclosure coolers and 2) Engineering is !
evaluating modification to prevent the harsh !
environment versus protecting individual components within the harsh environment.
- The Corrective Actions Department has been I formed for better tracking accountability of ;
commitments
- A HELB study of the Auxiliary building I environment will be completed prior to startup l
- The CAD improvements will address the l programmatic concems. The physicalissues will be addressed by referenced modifications.
1 i
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_ _ _ . =____ __-__-____-_- - --_____ _ __ _-_- - - - _ _ _ - - - _ _ _ _ _ - _ _ _ . _ - - _ _ _ _ _ - _ _ - _ - _ _
' i Status of Millstona Unit 2 Open It:ms isesulting from the 96-201 Inspection- -
e Reference Item Description Closure Status SIL ModificationI Ef Number Package- Number Potential Due Date Modification .
eel 96-201-25 Failure to effectively track and 5/16/97
- The 23 dual funcbon valves were tested. 30 No implement corrective actions
- The Corrective Actions department has been conceming " dual function" fully implemented isolation valves
- The Corrective Actions department is wortung to effectively track open commitments for better accountability
- The CAD improvements will address the programmatic issues.
eel 96-201-28 Failure to address the SBO 7/18/97
- An SBO coordinator has been established 31 No issues identified in the VECTRA
- Assignments have been made to track open assessment items from the VECTRA assessment
- CMP will be performing an assessment of the ;
SBO issues '
- Programmatic improvements associated with tracking of commitments will be addressed by the CAD i eel 96-201-29 Failure to take appropriate Submitted
- The Corrective Action has developed trending 32 No ccirective acbons for audit tools to track and evaluate NCR issues.
issues involving trending and Additionally, the CR process will be used to prioritization of NCRs ensure timely NCR closeout j
- This issue dealt with a programmatic _
deficiency will be corrected by the CAD.
eel 96-201-30 Failure to implement timely Submitted
- The closure of backlog ACRs is being 5 No
- corrective action foridentified addressed through the phased system !
significant conditions adverse to approach to the schedule. A significant effort is quality underway to maintain current CR closure in a !
timely fashion to prevent fuither bacideg.
- The Corrective Actions department has been ,
fully implemented !
- The Corrective Actions department is working ,
to ef7 actively track open commitments for better -i accountability
- CAD and the revision to RP4 will address !
programmatic concems l t
h 1
c, Status of Millstone Unit 2 Open items desulting from the 96-201 Inspection f Reference item Description Closure Status Sgt. - Modificationf Ei Number Package Number Potential Due Date Modification eel 96-201-31 Inadequate design verification 5/16/97
- Training of Design Engineenng personnel has 28 No for RBCCW Surge Tank seismic been formally developed and bemg restraint modification implemented.
- Changes to the Design Change Manual have !
been made and training completed.
- The Design Change Manual has been revised 33 No conceming a seismic design and personnel training is in progress -
deficiency for a Vital Switchgear
- The Engineering Report for the design basis ,
room cooler for leakage from seismic class 2 piping is due to be completed by 6/16/97 i
- Similar to the previous issues, the DCM improvements will correct the programmatic concem.
Failure to maintain the plant 8/8/97
- The system power supplies will be modified to 23 Yes I eel 96-201-41 configuration within the meet single failure criteria. Additionally, Note 3 [
Licensing Bases for the CTMT modifications to the H2 monitors and CTMT Gaseous and Particulate RMs, Radmonitors will be made. The Design Basis H2 Monitoring system and has been established . A preliminary .
PASS Engineering Report has been issued to form the !
.- basis of the DCR.
- The Design Change Manual has been revised and training is in progress. _;
- The DCM will address programmatic issues.-
eel 96-201-42 Failure to adequately control 5/30/97
- A change to the MEPL Specification has been 18 No !
standards resulted in made and has been implemented.
inappropriate downgrade of QA
- Actions to prevent inappropriate downgrades Cat 1 equipment to a Non-QA have been made implemented in the form of status. . required reviews for downgrades. :
- Addibonal resources have been made ;
available for programmatic MEPL issues :
- Virginia Power MEPL personnel have !
provided an assist visit .
- This issue was corrected procedurally. '
p:\2cadnrccom6a doc 4
Status of Millstona Unit 2 Open items nesulting from the 96-201 Inspection ,
Reference item Description Closure Status SIL Modification / k Number Package Number Potential Due Date Modification eel 96-201-43 Failure to prevent the use of 5/30/97
- Resolution of the final outstanding issue 18 No potentially non-conforming associated with 2-CN-241, CST to Hotwell materialin safety related makeup valve, is scheduled to be completed by applications due to lack of 5/16/E6 adequate MEPL dispositions
- This was also a programmatic issue which is being administrative!y controlled.
~
NOTES:
- 1. The annunciator wiring will be modified and the circuit voltage changed from 125Vdc to 24Vdc to minimize single failure concems.
pA2cadnrccom6a_ doc
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Status of Millstone Unit 3 Open items Resultina From the 96-201 NRC Inspection ;
Reference Item Description Closure Status SIL Modifications /
Number Package Number Potential >
i Due Date Modifications eel 96-201-01 Six examples where the MP3 8/5/97 Setpoint change 2 Yes, setpoint- !
FSAR was not maintained up modification, FSAR to date or did not reflect actual change, FSAR plant configuration and change procedure operating practices. revised eel 96-201-02 The safety evaluation for 8/9/97 Pumps started and 78 No Service Water Bypass Jumper run at time of 3-90-20 was inadequate discovery, revision of because it did not address OPS procedure for substitution of a manual action alarm response, BJ for an automatic feature and removed the defeat of an automatic actuation.
eel 96-201-04 Procedures were changed 8/5/97 Modification to the 11 Yes with out a PTSCR to permit AFW - 36 valves, closure of Turbine-Driven 50.59 procedure Auxiliary Feedwater discharge revision and training, valves whenever the Motor- and PTSCR submittal Driven Auxiliary Feedwater pumps were used for steam generator water control.
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Reference item Description Closure Status SIL Modificrtionst '
Number Package Number Potent;al Due Date Modifications eel 96-201-05 The TDAFW isolation valves 8/5/97 PTSCR submittal, 11 Yes were closed during low power procedure revised to operations or when MDAFW no longer isolate pumps were in service. Failure TDAFW discharge to ensure that at least three flow paths, 50.59 independent AFW pumps and revision and training.
associated flow were operable with the reactor in either Mode 1,2, or 3 is a violation of Tech Specs.
eel 96-201-06 The FSAR description of 8/5/97 Safet/ evaluation 78 No automatic start feature for the done on as-built Turbine-Driven Auxiliary starting feature of Feedwater Pump was TDAFW,50.59 and corrected without a Safety FSAR Change Evaluation, to reflect the as- Request built configuration, and to be improvements and consistent with other sections training in process.
of the FSAR.
eel 96-201-07 The Emergency Diesel 8/5/97 Safety Evaluation to 78 Yes, setpoint Generator (EDG) room low be completed, 50.59 temperature alarm setpoint procedure revision was changed without and training, DCM to performing a safety evaluation control setpoints 2
4 k
Reference item Description Closure Status SIL Modifications /
Number Package Number Potential Due Date Modifications eel 96-201-08 The description of the SBO 8/5/97 FSAR changes, SBO 78 Yes, minor mod.
Diesel Generator system procedure revision, component design, testing and 50.59 procedure maintenance contained in revision and training, .
FSAR did not accurately FSAR training reflect actual plant configuration or current maintenance and surveillance practices.
eel 96-201-09 Adequate design control 8/5/97 Resolve and 79 No measures were not incorporate DBDP established for verifying and discrepancies prior to checking the accuracy of the startup, revise design information contained in the control process Design Basis Documentation Packages (DBDPs).
EEI 96-201-10 Supporting technical 8/6/97 Requirements for 82 No evaluations listed in Proposed technical evaluations Technical Specification established, review of Change Request (PTSCR) , previously submitted although available, were not PTSCRs, DCM retained within QA records revisions system.
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Reference - Item Description Closure . Status SIL Modifications / . .
Number Package Number . Potential Due Date Modifications eel 96-201-13 Prompt action was not taken 6/19/97 Technical 37 No to address unusable CST Requirements Manual -
volume after determination was revised, Tech that the Tech Specs required Spec Change l an increased Demineralized submittal Water Storage Tank /
Condensate Storage Tank 1 (DWSTICST) minimum by 30,000 gallons.
eel 96-201-15 Design controls were not 8/12/97 AFW valve 18 Yes established to verify adequacy modification for of angle-type SOVs to containment design properly remain isolated pressure, review of :
against containment design other valves .
bases accident pressures by suitable qualification testing :
under the most adverse !
design condition - ;
eel 96-201-18 Controls were not established 7/22/97 Lubrication interval 18 No i to coordinate comprehensive incorporated into !
revision of procedures '
procedures, training necessary to implement all in Technical aspects Tech Spec Specification changes Amendment 100, including and License .
reconciliation of the vendor Amendments !
recommended pre-lubrication interval for AFW pumps. '
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Reference item Description Closure Status SIL Modifications / .
Number Package Number Potential -
Due Date Modifications eel 96-201-19 Failure to establish 5/16/97 Inspection of various 10 No -i instructions or procedures to manufacturer's ensure that Fosemount transmitters, revision transmitters would be installed of I&C procedures and subsequently inspected, and review of vendor consistent with the vendor technical manuals manuals.
eel 96-201-21 Temporary, unsecured 6/23/97 I-beam removed, work 37' No [
I-beams installed above three control procedure ,
of four containment modified, improved r recirculaSn spray system corrective action (RSS) heat exchangers were program ;
not promptly identified and i corrected !;
t eel 96-201-22 Reactor Plant Closed Cooling 8/11/97 Modifications to 37 Yes (2) !
Water system temperatures increase allowable were not maintained below piping temperatures, !
limits specified by procedure support modifications, [;
(and, in some cases, piping requirements to issue analysis limits) and no ACR a CR for similar !
was initiated to document the condition. ;
condition.
I
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Reference item Description ' Closure Status SIL Modifications /
Number Package Number Potential '
Due Dats Modifications eel 96-201-23 A bypass jumper (BJ) was 7/22/97 Bypass Jumper (BJ) 52 No- 1 installed that changed the was removed, safety ,
starting circuits for the SW evaluation being supply to MCC/RCA air performed on all handling units. The tech eval remaining BJs, and !
for this Bij was inadequate efforts to reduce the and several opportunities numberof BJs, .
were missed to identify the installed inadequacies. !
eel 96-201-24 Damaged concrete on the 5/16/97 Pedestal repaired, 37 No servicewater boosterpump other pads inspected, ;
pedestal was not promptly sealant will be applied identified and corrected to pedestal i eel 96-201-26 Non compliance with 7/23/97 Scaffolding was re- 37 No requirements to maintain evaluated, post appropriate clearances installation walkdowns :
between scaffolding and now required safety-related equipment was ,
not promptly identified and i corrected. l eel 96-201-27 Protective relay setting criteria 8/5/97 Overcurrent setpoint 37 Yes ;
for safety related motors will be modified for !
prescribed in the FSAR were Quench Spray Pump . [
inconsistent with the control Motor, FSAR change, !
setting sheets and criteria Specification -
used in calculations revisions.
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6 !
r Reference itera Description Closure Status SIL Modifications /
Number Package Number Potential Due Date Modifications eel 96-201-28 Failure to promptly correct 7/23/97 Evaluate 37 No station blackout diesel audit communications and deficiencies lighting during Station Blackout, heat tracing, and EDG Reliability Program eel 96-201-29 Nonconformance reports 8/6/97 Condition Reports 37 No (NCRs) remain uncorrected written for all NCRs, with no work assignments open NCRs to be against them or trend analysis. evaluated prior to Appropriate corrective actions startup, procedure have not been taken despite revisions several audits identifying NCR programmatic issues eel 96-201-32 The ASME code hydrostatic 7/22/97 ASME Code Case 81 No test required because of a approved for use at change in design pressure of Millstone, hydro at High Pressure Safety injection correct pressure, piping was deferred without revision of the ISI obtaining authorization from program manual the Director, NRR.
eel 96-201-33 The hydrostatic test pressure 7/22/97 ASME Code Case 58 No utilized to test thermal relief approved for use at valves was 110% of the valve Millstone, hydro at setting instead of 125% as correct pressure, required by Section XI of the evision of the ISI ASME Code program manual 7
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