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Summary of 970521 Meeting W/Nneco to Discuss Progress of License Activities to Support Restart of Plant Three Units. List of Attendees & Handouts Encl
	ML20148H293
Person / Time
Site:	Millstone
Issue date:	06/04/1997
From:	Stephen Dembek; NRC (Affiliation Not Assigned)
To:	; NRC (Affiliation Not Assigned)
References
	NUDOCS 9706100008
	Download: ML20148H293 (131)
	v • d • e

^

June 4, 1997 l LICENSEE: North:ast Nuclear Energy Company (NNECO) i FACILITIES: Millstone Nuclear Power Stati:n Units 1, 2, and 3 )

SUBJECT:

SUMMARY

OF MAY 21, 1997, MEETING WITH NNECO TO DISCUSS PROGRESS OF LICENSEE ACTIVITIES TO SUPPORT RESTART OF THE THREE MILLSTONE UNITS l 1

)

On May 21, 1997, the Special Projects Office (SP0) staff of the Office of I Nuclear Reactor Regulation (NRR) participated in a publicly observed meeting '

with NNECO representatives. The purpose of the meeting was to discuss NNECO's progress in facilitating restart of the three Millstone units. At the start of the meeting, NNEC0 stated that it decided to slow the restart effort on Unit 1 and focus on restarting Units 3 and 2 first. NNECO then made presentations on their issues management process, Independent Corrective Action Verification Program readiness assessment for Units 2 and 3, and restart readiness assessment for all three units.

Enclosure 1 provides a list of the principal attendees at the meeting.

Enclosure 2 provides the handout used by NNEC0 during its presentation.

Enclosure 3 provides the background material NNEC0 provided to the NP.C staff during the meeting. j Stephen Dembek, Project Manager Special Projects Office - Licensing l Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336, and 50-423

Enclosures:

As stated (3) cc w/ encl: See next page 'O\

HARD COPY KDecketifil(

PUBLIC SP0-L Memo \

SP0 Reading \

OGC (w/o encls 2&3)

ACRS (w/o encls 2&3) l E-MAIL (w/ encl 1 only)

Stollins/FMiraglia RZimmerman

'LBerry hh Dross (e-mail to SAM)

WDean (WMD) p.g gg 1 l

DOCUMENT NAME: G:\DEMBEK\52197MTG. SUM Ta roccive a copy of thle docurnent, Indicate in the boa: *C' = Copy without ettechment/ enclosure *E' = Copy with attachment / enclosure *N" = No copy I0FFICE SPO-L:PM _ SP0-L:LAN'\ , . SPO-L:0Ik l NAME nMenm i d , ,j d r LBerry _ NK > 4?McKeeM M /) -

D&f 1/97 SNcA 05/ *F/ W \

DATE OC/c 4 /97 i ou 0FFICIAL RECORD COPY 9706100008 970604 9 PDR ADOCK 05000245 P PDR

p Wicy , .-.

y" . }&- UNITED STATES ls j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 20555-0001 49

.***,o June 4, 1997 LICENSEE: Northeast Nuclear Energy Company (NNECO)

FACILITIES: Millstone Nuclear Power Station Units 1, 2, and 3

SUBJECT:

SUMMARY

OF MAY 21, 1997, MEETING WITH NNECO 10 DISCUSS PROGRESS OF LICENSEE ACTIVITIES TO SUPPORT RESTART OF THE THREE MILLSTONE UNITS On May 21, 1997, the Special Projects Office (SP0) staff of the Office of Nuclear Reactor Regulation (NRR) participated in a publicly observed meeting ,

with NNECO representatives. lhe purpose of the meeting was to discuss NNECO's progress in facilitating restart of the three Millstone units. At the start of the meeting, NNECO stated that it decided to slow the restart effort on i Unit I and focus on restarting Units 3 and 2 first. NNECO then made '

presentations on their issues management process, Independent Corrective Action Verification Program readiness assessment for Units 2 and 3, and ,

restart readiness assessment for all three units. ]

Enclosure 1 provides a list of the principal attendees at the meeting. ,

Enclosure 2'provides the handout used by NNECO during its presentation. l Enclosure 3 provides the background material NNEC0 provided to the NRC staff during the meeting.

4

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/ v 4(

Stephen Dembek, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation l Docket Nos. 50-245, 50-336, and 50-423

Enclosures:

As stated (3) cc w/ encl: See next page l I

- - . . - - - - - - . . - - - . - ~ . .

. +

e. t i

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LIST OF ATTENDEES ;

May 21, 1997 fLME QRGANIZATION .

Jacque Durr NRC i Tony Cerne NRC I' Steve Reynolds NRC Gene Imbro NRC Phil McKee NRC !

Bill Travers NRC i Dave Beaulieu NRC i Ted Easlick NRC Bruce Kenyon NNECO Mike Brothers NNEC0 -

Jack McElwain NNECO ;

Ray Necci NNEC0 !

Marty Bowling NNECO i Pat Loftus NNECO i Jay Thayer NNEC0 Dave Goebel NNECO i Tom White NNEC0 j l

i l

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l 1

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Enclosure 1 )

.. . . . , _ _ _ _ __ _ . _ . ~ _ . _ . _ _ . . _ . _ - _ _ . _ .._ _ _ ._,

e a t

I 1

Agenda

Opening Remarks Bruce Kenyon

lssues Management PatLoftus Northeast Utilities Briefing

'lCAVP Readiness !

.MP2&3 CMP ManyBowling for the NRC l navnecei Oversight Tom White l Restart Assessment Panel o,ve ooehei l

Restart Readiness Millstone Station . Unit 3 Update Brothe May 21,1997 , ungg 2 upg,,, Mike,y y,, gewg;,rs y

l . Unit i Update '

l Jack McElwam l

Summary Bruce Kenyon l . ; w 4_ ,v -

l l

I l

l Issues Management Template :

1 0 _..__.- . _ _ _

issues Management ,_~,.__

~

- ,, _, ". - oy: =,::: = ,,

c ---

Pat Loftus u .e en n..

Director of Regulatory Affairs

,n _

Common Gauses of Performance Decline M 1rt ::::" n.

~ ~ ~ - -

4 CorrecDwe Acts.n 8F und.snern. lCAVP Readiness

- " "'~

L";",;;;'""""" a.'~~,,,,, Millstone 2 & 3 CMP 1 D.ss9n and C.nfigur.h.m

l"' . Ray Necci to n.rt Cenir.s a ,i.nning DireCfor, CMP D ""'

, , , m.v.sw

__ _ _,, s ; .__ _ _,, -

i l

Page 1 Enclosure 2

l lCAVP Will Use a We Are Ready for Multi-Tier Approach ICAVP When:

Review of Selected Systems t

Review of Critical Design

Discovery Complete for 50% of Characteristics of Systems, with a Safety and Risk Significant Systems Focus on Accident Mitigation

Discovery Complete on Engineering Programs i Functions '

Review Examples of the

ICAVP Pesponse Team is in Place implementation of Processes to

Review of CM Processes is Complete Maintain or Change Plant Configuration

-~.n ~ . ,w er H , - w ,,

l Millstone 3 ICAVP Millstone 3 ICAVP Readiness Status Readiness Status 1

Unit 3 is Ready for May 27 Start

Oversight Review is On-going

Wave 1 System Review Activities

Operations & Maintenance Complete Procedures Reviewed 1

Wave 1 Design Basis Summary Documents are Prepared

Engineering Programs Reviewed

, ; ===.n nw , w,r H . ; a-a n aw ,w,v -

(

l l

1 l

l Independent Corrective Action CMP Reviewed for Verification Program Readiness l

Millstone 3 May 1997 ICAVP Readiness

"***"' U Z :".* T. " ' ' * " ' "'"

Design Configuration Management

,., Processes

- Design Change Manual was

, y,r Upgraded

~

3. }$ - Key Procedures Reviewed for I.. g,yg i Configuration Control Attributes

. E ER! - Engineering Self Assessments

~ ' ~ {-ME7j ~ ~ ~ Performed for Key Processes

n-rm,ar u n- w ,v & n-ra n nwo- w,1 k--

Page 2

. e i i I l l 1

4 i l l

l GMP Reviewed for ICAVP Millstone 3 is Ready !

l Readiness (continued) for ICAVP l Corrective Actions Reviewed l - Self Assessments, Engineering

Conclusions:

Assurance and Oversight Audits - Millstona 3 Reviews are Complete l - Nuclear Oversight Perfo.med - Oversight Review Continues l

Audit of Design Control Process

- Performed Engineering Self Assessments in Process Areas

- Performed Engineering Assurance Assessments

mons w w , - ,, ; u-rs =r aus.- we -

i Millstone 2 Working Status of Unit 2 ;

Towards ICAVP Readiness ICAVP Readiness Readoness for ICAVP is pmgressing; however, the target

Ready to Start on June 30 * *"'8d"'*" d *f '""' 38 ' 88 7 """8 ***a8'"8

'"' ~

+ Graded System Reviews and Program Reviews are On-going "' I ~'" I

Specific Corrective Actions "' \

Identified j a' g ==

l

Walkdowns for Separation. EEQ "'

/

and Botting are On-going n )

..............m..m...- I

,, ; ,.,- w. H ;..r, - w , r ICAVP Interface Has ICAVP Interface Has Been Established Been Established (continued)

Communications Protocol Established Between NRC. + Question / Response Tracking ICAVP Contractor and NU Systern Established Utilizing Passport / AITTS Database

NU ICAVP Response Team Established , Established Corrective Action Process (RP4) Utilized for Potential

Technical Review Team Conditions Adverse to Quality Established to Assure Clarity i

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Page 3

___ __ _ _ __ _ _ . . _ . _ . . _ . . _ _ _ _ _ . . _ . _ . _ . _ _ _ _ _ _ _ _ . _ . ~ . _ . _ .

1 r

L ;

CMP Organization Defined l CMP

, l . ICAVP Readiness .

MP3 ICAVP MP2 ' Oversight CMP Response CMP Tom White

' I Manager,50.54(f) Recovery Tech MP3 Review MP2 Nuclear Oversight ,

Response Group Response l

l

. ; .a an m w,T}- . ;.a, ,- wwl _ i l

I ICAVP Readiness Programmatic Oversight of

{

Oversight Activities in the Configuration Management ;

Design Basis Verification Plan Development I Process

Provided Feedback to the Line

Specific Unit 3 Assessment

Reviewed CMP and implementing Processes and Status Project instructions (Pis)

Specific Unit 2 Assessment

Assessed CMP Process, Processes and Status Conformance with 10CFR50

Summary - Oversight Efforts Appendix B, etc.

Continue

, ; marn,aa w w w - , ; ser astwww -

l Provided Oversight of CMP Performed independent implementation Assessments

Assessed Units 1,2 and 3

Developed independent Activities in-process (Licensing i Design Basis Verification, FSAR Assessment Process (IAP)

Annotations, SAs, Calculations, + Performing Unit System Assessments SSAs etc.)

Assessed Unit 2 Pts (Ongoing)

J Nachcess w ww f-l + 1 l mar ean w ww y i

Page 4 i _ _ _ _

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Unit 3 Independent Assessment Unit 3 Independent Assessment Process Activities Completed Process Activities Completed

Auxiliary Feedwater System Review (Continued)

- Completed May 2

- 8 Condition Reports (CRs)

Diesel Generator Sequencer System Review

- Resulted in 22 additionalitems i

-Completed May 20

- No significant issues identified

-Two Condition Reports

- Aggregate question stillremains

- No significant issues identified ;

- AdditionalIAP System Review initiated 1

, a-~ u m w,v-+ .. a- - w w ,, y I

1 I I Unit 3 Independent Assessment Unit 3 Assessment l

l Process Activities in Progress Activities Remaining '

Service Water System Review

Reviews of Completed Specific

-Initiated May 5 System Assessments (SSAs)

- Four Condition Reports - SSA information started May 19

- Scheduled for completion May 22 - Scheduled completion May 27 !

- Currently approximately 20 open

Comparisons of IAP with SSA results issues - Scheduled completion May 27 !

l * - - * - w ,, - ,. ; a-~ = wy, H l

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Unit 3 ICAVP Readiness U"I' I"d*P'"d'"'

Assessment Process Activities

_ = :--- 'f 7

' _- _ k-f{ ' Low Pressure Safety injection

{

-Completed May 9

g. .

. _ - Two Condition Reports

~

- No significant issue identified I =

' ~ ~ {

~

'Second System Review Planned '

! Prior to ICAVP

= .rt. ::= -- ::- - I Ev Y 8* ,F F

Page 5 l

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Unit 2 Assessment Act. .t.ivi ies in Progress Unit 2 ICAVP Readiness l

Engineering Topical Areas l NE* ]E f M - C Z _

l ' Graded System Reviews + Z -

l ij;:; ,

\ j . 5 l

Project Instruction implementation Sl .; F ,

~~==-~==,

..n, - e.,, H , ; ,-e -.

Summary - Oversight Efforts Continue

' Unit 3 - Review Not Yet Complete .

Millstone Unit 3 Update

Unit 2 Assessments Progressing i As Scheduled Mike Brothers Vice President- Millstone 3

Unit 1 - Challenge Board Successful

, - o,.,, -

.- - u.,, -

l Status of Unit 3 Status of Unit 3 Significant items List (SIL) Significant items List

""*~~ :,~::~.::;~. .::: ..:;;..=t'.~~==

' Closure Packages for the Unit 3 SIL 205

'Provided to the NRC for Review 19 h ~JW]

' Remaining Packages 186 l *,, ' ,,,,

f 'EO'Y"h m ar--

LI I. . . . . . .N,- .-s . ".

EU.D 'M e- M" j

.--- - me, r . ;.- -u, +

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Page 6

Status of Unit 3 Status of Unit 3 License Amendments License Amendments

" ' ' ' ~ ~ ~~ ~ ~ ~

Total PTSCRs Required for Start-up 24 "' *

PTSCRs Submitted to the NRC 13 *

,

No Significant Hazards Considerations

Schedule Challenges

" I.

l

T% ! ,

- Appendix G Curves a

\ '

/ I .

!m {

- AFW Valve Position

-Safety Grade Cold Shutdown h j

, l 'El !

wim-rwm

n-m-en - e-. ; n-

. , - , +

Challenges Facing Unit 3 Unit 3 Milestone Schedule

Leadership and Development

Employee Concerns

Ready for IcAVP May 27,1997

Work-Off Curves

+

Ready for oSTI Sept.30,1997

' -License Amendments

- AWos ePhysically Ready

- CMP completion for Restart Sept.30,1997

Arcor 4 MOVs

RSS Suction Voiding l nmmar w t=m ~ .

l naumur m eme -

i x

j Status of Unit 2

, Significant Items List (SIL)

ltems on the Unit 2 SIL 48 Millstone Unit 2 Update 'Significantiterns No Requiring Packages 7

Packages to the NRC for Review 11 Unit i er.M fis one 2

Remaining Packages - On Schedule 30

, ; nmmar w emw '

l nmmar nameimm;-

Page 7

. o i t

I Status of Unit 2 Significant items List Status of Unit 2 l Closure of items on the significant stems List are on License Amendments I track for delivery to the NRC by 8/1557

'; i v .. ,,

Total PTSCRs Required for Start-up 16 i

,, /t ""'*' ; 'PTSCRs Submitted to the NRC 6 l , ;* l",Ic'*** ! 'PTSCRs Approved by the NRC 1 l b 8; "'

! l ' Remaining PTSCRs Submitted by 7/30/97

" j

[ {

No Significant Hazard Considerations

! ..........,...g..., i

_ ; , - ~,, H ;.---, - - ,, - I

\

l

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l l Unit 2 License l Amendment Requests Challenges Facing Unit 2 License Amendments are approximately one monn

Operator Training behind tt,e origonal schedule l e gggy l l u A l vagege j

EEQ Documentation impact on HELB

-^

i g ',l _ _ . _

MOVs l ~~

' C, *. ____ --+w-= _._.

Work-Off Curves

-AWO

~-'

..,..,..,..,oc..,v.,..,.c...

/ -License Amendments j

- CMP Completion 1.u..........a.........-.".."."m m <

l

a.~ ,- a ,, -

. ;~- ~ -, - a ,v -

i Unit 2 Schedule l

Ready for lCAVP June 30,1997

Ready for OsTI Sept. 29,1997

' Phys.ically Ready Millstone Unit 1 Update '

for Restart Nov. 25,1997 Jack McElwain Unit Officer.nfilistone 1 l

l hwah.-, A4fCJ.F &#,.,F h NMMI #MF l

Page 8 i

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Unit 1 Priorities for 1997 To Unit.1 Priorities (continued) i Support Restart Readiness

. Compiete Diesei a Service Water Work i

' Priority Proiects

Provide Ongoing Unit 1 Support i

Discovery Complete for 50.54(f) . (necessary emergent wod, issues for 65 Systems by Dec.1,1997 sumeiHances, etc.)

'

Develop an Outage Schedule

Simplify limprove Work Processes j

Bring Overdue CR Assignments to

Transition to 5 4-3-2-1 Schedule and l Current Status and Maintain Current Reduce Physical Work Backlog i Going-forward

Prepare for Full Resumption of Physical (Outage) Work as Early as November 1997

. ,. ; r - - ,-s, -

N., - ,_s, -

i Resources' Will Be Adjusted To Accomplish Priorities ' Unit 1 Resources (continued) .;

Department Managers Are identifying !'

Individuals with Requisite Skills and

Project Leads for CMP, Outage Expertise to Loan to These Projects Schedule, CRs and the DGISW ;

lt is Expected That immediately

' Restoration Have identified the Following Memorial Day, Loaned 'j

" People" Resources They Need, and These Project Leads Have Individuals Will Join Their New i Project Teams to Help See These i Received Commitments of Support Jobs Through to Completion Before from Across the Unit 1 Team Rejoining Their Permanent Departments t l

. ; marn~naman-L-sv -

l N=m nr naam= s-er -

I h

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MP1 Pr6ertty Projects Through Year 4pd 1997 To support Restart Reashness

~

** ** ** ** l 3, \

~

Summary.

+ :-

*"'""~ .

Bruce Kenyon i N S 6 985 Q th* M4 - - -

1 NN M - ,, NOFIM 1

Page 9

Millatono 2 Rcstart Readinoso Task Completions Required for Startup May 1997 <

1 3000

-' Data through 2500 - N 5/15/97 i

';:s00 g 1500 1000 -

500 L 0 - -

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

' M Open (Restart) Open (Undetermined) -e-Work-off Goal '

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 2550 2708

) pen (Undeterrnined) 135 149 i Work-off Goal 2685 2485 2150 1849 1550 800 499 198 25 Definition The total number of tasks is defined as those requiring closure prior to restart. Items in PMMS (AWOs) are not included.

Undetermined are those assignments in AITTS that have not been screened as to required for restart.

Goal Comments The goal is to have all required tasks complete pnor to Data through 5/15/97 entenng the applicable mode restraints.

Analysis / Action Task completions have been re-assessed for restart readiness applicability.

Data Source: G. L. Alix x2200l Analysis by: S V. Heard x5600l Owner: S V. Heard x5600 caus,e u e.. - 1 "'

Enclosure 3

Millstono 2 Raatart Roadinass Condition Report Method of Discovery May 1997 100 Data Through gg 5/18/97

/

3 60 [

e t

g 40 20 0

' U' ' '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 5 Self identified DInternal Oversight D External Oversight O Event No.of CRs Jan-9'T Feb-97 Mar-97 Apr 97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Self identified 123 102 114 126 70 Internal Oversight 20 13 9 15 8 E xtemal Oversight 6 4 3 0 1 Event 16 9 6 7 6 Totalidantifed 165 128 132 148 85 Definition This indicator represents the percentage of CRs identified by each of the barners. CRs are categorized into the following five areas:

Event Dnven - Self-revealing, an event occurs.

External Oversight Identified by NRC, JUMA, INPO, etc.

Internal Oversight - Identified by OAS, PORC, ISEG, NSAB, etc.

Self identified - Supervisor observation, document review, Self-checking, independent / dual venfication, etc.

Goal Comments -

improvernent continues Analysis / Action Condition reports continue to be self identified with one external oversight CRs identifleo in the first two weeks of May. ]

Event dnven CRs remain low at 6.

l l \

Data Source G L Alix x2200l Analysis by: S V Heard x 5600l Owner: S V Heard x5600 l

l co s. os.i,,o 2 me l

Millctona 2 R.octcrt Roediacos Condition Report initiation and Evaluation Timeliness May 1997 200

, 150 E

x p>

c 100

\

x j j q Data Through j e 5/18/97 50 E-f_ ; - l/

l 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 5 Total CRs initiated DTotal Now Complete O Completed within 30 days 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 Total CRs initiated 181 163 166 173 47 Level 1 CRs initiated 7 7 7 11 2 Level 2 and 3 CRs initiated 174 156 159 162 45 Cortplated within 30 days 31 53 36 25 12 j Total Now Complete 115 80 42 25 12 l Success Rate 17.1% 32.5 % 21.7% 240*'. NA Definition i

This indicator depicts the initiation of Condition Reports (CRs) for the Unit and the number of evaluations which were completed within the goal of 30 days. The center bar shows the number of CRs for which the investigations have been completed to date.

l The graph shows CR data beginning 1/1/97, and represents the current status / effectiveness of Corrective Action initiatives.

I Goal Comments Goal is to complete all evaluations and identify appropriate Evaluations are considered open if they are either in an corrective actions within 30 days. open status or a pending review status pnor to the approval of the corrective action plan The latest month's data refects the status to date.

Analysis / Action NOTE: April data for completed within 30 days (24%) reflects that 25 were successfully completed out of a total of 104 which have had 30 days elapse to date.

1 Data Source: G. L Ahr x2200l Analysis by: S. V. Heard x5600l Owner: S. V. Heard x5600 cour,te xtsenmanan andinninness 3 sem

Millstone 2 Restart Readiness l Open Condition Reports May 1997 ,

2000 1600 f .

2 e 4-l Total Open CRs as of 5/15/97 l

1200 ; )

5 n ,

y 800 '

g CRs open >120

_ ' days as of 5/15/97, 400 0 1 I I l l l l l l l l l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M CRs Open >120 Days -*-Total Open CRs 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 Open CRs 1335 1300 1255 1215 1258 CRs Open >120 Days 738 787 735 810 821 I l

1 Definition This indicator depicts the number of open condition reports (CRs) and CRs open > 120 days.

l l

i i

Goal Comments Analysis / Action The May (through 5/15/97) number of CRs open > 120 days is up slightly as we have concentrated on closure of Phase 2 system items. In the Corrective Actions Department (CAD) we have a population of between 150-200 CRs that are indicated as having all corrective actions complete and require only final review. We expect to meet our goal of less than 550 CRs open greater than 120 days by the end of June.

I Data Source: G. L A!ix x2200l Analysis by: S. V Heard x5600l owner: S. V. Heard x5600 COM619 xLS/CRs and Ogaww120(2) 4 b/21'97

' Milleteno 2 R00 tert Rocdinaco Restart Modifications Awaiting implementation May 1997 l

120 100 9 ~

I N ,*""

fsi , 9@

$5 .?S$

, 80 y ,- kg- @

8 $$ $m ? !

= Wl p - A i

, 60 O

[ g g [h.!$

g,; 4 3 i g- Data through 40 pg y} gy , 5/16/97 c%

a a% -

w &.

g gg; 20 $$ - _

d'l

.n n up~

i /

0 l

Jan i eb Mar Apr May Jun Jul Aug Sep Od Nov Dec I

. M Mods Released to Field C""l Mods Awaiting Engineering -rr-Work Off/ Goal i Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Mods Aeleased to Field 11 16 l

, Mods Awaiting Engineenng 81 103 91 86 Total Mods Remaining 81 103 102 102 Work Off/ Goal 103 102 96 89 81 66 48 30 14 4 Definition The total number of outstanding modifications identified as required prior to restart that have not been turned over to Operations.

I Goal Comments All start up related design modifications completed prior to Data through 5/16/97 r: start Three mods to be complete after power ascension.

Analysis / Action i The work off/ goal has been adjusted to reflect scheduling changes resulting from design resources being shifted

{ to support discovery issues and the preparation of new design / calculations to support the start of ICAVP.

l l

Data Source: M. Amadon x6249 Analysis by: M. Amadon x6249 Owrh9r: W. Corts.n x0626 cousis xtsenamaammne 5 sr.n w

i . .

l Mill 3 ton 3 2 Ractcrt Rocdinaco Procedure Revision Backlog i May 1997 l

l 250 l

200 Data through 5/16/97 l150 , [ ,

5 i 0 ;

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Restart Reg'd Proc. Rev. PUP -e-Restart Reg'd Work Off/ Goal -*-PUP Work Off/ Goal -

1 Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep 97 Oct-97 Nov-97 Dec 97 l Total Remaining 268 270 269 257 Restart Reg'd '

Proc Rev 94 106 115 103 90 86 77 64 60 0 0 0 l PUP 180 168 153 149 Restart Req'd I Work Off/ Goal 94 106 115 103 90 86 77 64 60 0 PUP Work

)

Oft / Goal 210 190 150 120 100 70 50 35 10 0 Definition Procedure Revision Backlog is the total number of new procedures or procedure revisions required for restart. <

l Millstone Procedure Upgrade Project (PUP)(Phase lit)- Upgrade the Technical Procedures at Millstone Station to a l Standardized Wnter's Guide and Verification and Validation (V&V) Process. The goal of PUP is to improve the technica!

l Quality and usability (human factors) of procedures; this will reduce human erruts and enhance plant reliability by supporting l quality of work.

j Goal Comments All restart required procedure revisions and PUP requirements Data through 5/16/97 have been r3 viewed and proper corrective actions have been taken pnor to restart.

AnalysisfAction One hundred fifty dehcient procedures have been identified to date. The majonty are EOP revisions and AOP development and upgrades. The remaining are actual deficiencies which are identified as needed for restart. This UPI I is expected to have constant input of newly identified procedure deficiencies, still with the goal of completion before restart.

I 4

PUP is 89% complete. The Centrahzed Procedure Group (CPG) is continuing to work down the number of procedures not yet upgraded.

Data Source: W J Chalfant x6416 l Anstysis by: W R Watson x6245l Owner: H L. Miller x0474 cousa xtswoc onc-m==c 6 ser

Millstone 2 Restart Readiness >

Operator Work Arounds I May 1997 45 40 Data through

\ 4- 5/12/97 i e 35 l E

8

\

j 25 y 20 K .

0 15 6

Z 10 0 : ::: C; 5

0 l I I l~ l i I I I I I l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l

Operator Work Arounds --t- Work Off/ Goal Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Operator Work Arounds 43 39 41 42 41 Work Ott/ Goal 41 35 29 23 17 to 10 10 10 10 Definition Operator Work Arounds are conditions requinng an operator to work with equipment in a manner other than onginal design which could:

1

1. Potentially impact safe operation dunng a plant transient

2. Potentially impose significant burden dunng normal operation

3. Create nuisance condition due to recurnng equipment deficiency {

4. Distract operator from recurring condition !

l i

Goal Comments l Goal < 10 Data through 5/12/97 I Analysis / Action Repairs are being made and the 16 Operator burdens chosen to be removed are starting to be cleared. The population of items that will remain after startup is being reviewed for aggregate and !r Jividual impact on the plant operators. New items will be evaluated as they make the list.

0:ta Source: W. Woolery x0698l Analysis by: W. Woolery x0698l Owner: M.J. Wilson x2081 cousie xwwwa co==c 7 sque7

Milletono 2 Roctart Readiness ,

Control Room and Annunciator Deficiencies May 1997 60 50 Data through h g._ 5/12/97.

o 40 E

o 30 10 N r : : .

O I I I I I I I I I I I I l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Total Deficiencies -E-Work Off/ Goal l Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jub97 Aug-97 Sep-97 Oct 97 Nov-97 Dec-97 Total Deficiences 41 39 45 52 51 Work Oft / Goal 52 42 32 22 12 10 10 10 10 Definition Control room instruments, recorders, indicators, and annunciators that function improperly or not at all that affect the ability of the operators to monitor and control plant condit;ons.

l Goal Comments i Goal < 10 Data through 5/12/97.

Analysis / Action The CRP Deficiency list is composed initially of Pnonty 3 TRs. As such, the individual deficiencies do not post an immediate challenge to safe operation. The concem is that the cumulative effect of many small deficiencies may cause a ent: cal j system to periorm improperty in an emergency situation.

Data Source: W. Woolery x0698l Analysis by: W. Woole,y x0698l Owner: M. J. Wilson x2081 cousto xtsoeconmwvc 8 52197

l Mill 0tena 2 Ractcrt Rccdin300 1

Temporary Modifications ;

May 1997 I

60 t g 50 , _

E '

Y 8 40 u:: -

45 ,,

l 30 '

e g20 E i

E %j Datathrough 5/12/97 !

$ 10 !

0 I I I I I I I i l I I I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Temporary Modifications C""3 Outage Support -C-Work-Off/ Goal !

Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97

Temp Mods 29 29 30 31 30 Outage Support 21 21 19 18 17 TotalInstallea )

50 50 49 49 47 1 Work Off/ Goal 50 50 49 49 49 45 35 20 10 10 10 10 !

Definition !

I A modification to plant design that is temporary in nature and not part of the permanent plant design change process that j receives penodic review for continued applicability after installation.

]

Temporary Modifications to permanent plant design are binned here two ways: ' Outage Support" are directly tied to physical work to plant equipment in an outage condition, and " Temp Mods

are all others.

l Goal Comments j

<10 TMs installed at startup Data through 5/12/97

{

With the plant shutdown there are temp mods that are i required to support shutdown work. There are currently seventeen temp mods for this purpose.

I l

AnalysisfAction There are 47 Temp Mods installed on the plant. One is an operator burden (BAST level indication nitrogen supply monitonng was improved but not permanently repaired). The number of mods has been increasing as the outage continues. A review of the Engineering work list compared with the Temp Mod list showed a dramatic reduction in the number to be installed j by startup. While future developments may require changes, current expectations call for fewer than 10 Temp Mods to j remain installed at startup.

Data Source: W. Woolery x0698l Analysis by: W. Woolery x0698l Owner: M. J. Wilson x2081 cousie xtswnnmo#commme 9 seie7

MillctEnc 2 Roctcrt Rocdinocs AWOs Required for Restart May 1997 2250 2000 1750 1500 E

j1250 - -

, Data through i e !k &'~

E* 5/12/97 ,

to 1000 O

3

< 750 500 - - - - ; ; c ; r =

250

]

O I I I i l 1 1 I I I i 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec <

l M MRAWO Other Pwr Block AWO -*-MR AWO Goal -C-Total AWO Goal 1

Jan-97 Feb 97 Mar-97 Apr-97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 Otner Pwr Block AWO 384 400 403 414 393 i MRAWO 964 976 1031 940 1032 l

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 Definition The Maintenance Rule Automated Work Order (AWO) backlog is defined as the total number of Corrective q Maintenance / Condition Dnven (non recurring) AWOs on systems identified as a Maintenance Rule System which are not restrained by plant conditions. The total excludes AWOs in retest, in close-out, work planned for future outages, AWOs supporting field work, and non-power block AWOs. ;

i Goal Comments Less than 200 and trending down pnor to readiness for restart.

Data through 5/12/97 Analysis / Action The Maintenance Rule Backlog remairis stable as new AWOs continue to be generated through the discovery process.

, Changes in process are being evaluated to increase the through put of AWOs to provide an improving trend that will support i goals established prior to restart.

Osta Source: R. Lally x4426l Analysis by: R.W. Poole x5338l Owner: S.J Jordan x4292 CoM519 xtScAWOtmignomm-twc 10 se

Licanco Amandmont Rcqucsto Millstone 2 - May 1997 Progress: License Amendments approximately one month behind original schedule.

20 15 Data through

, S/16/97 Good E

}L /

3 o z N Y Submittal Schedule 5 one month behind

\ Y 0 l I I I I f; I

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec l

LARs To Be Subm;;ted C LARs Submitted --D-Work-Off/ Goal Raw Data Jan 97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 sep-97 Oct-97 Nov 97 Dee-97 LARs Submitted 2 1 1 1 1 LARs To Be Submitted 13 12 11 11 9 Work-Ott/ Goal 15 13 12 12 7 1 0 Definition Analysis / Action License Amendment Requests (LARs) are changes to There has been one license amendment request Technical Specifications or other license changes that submitted to the NRC during the first two weeks of are needed for restart that are to be submitted to the May. Five license amendment requests were NRC for approval. scheduled for NRC submittal by 5/30/97. Delays are a result of additional analysis required by outside support and the sharing of intemal resources. The remaining LARs are required to be submitted to the NRC by 7/31/97.

Goal Comments Receive NRC approval pnor to testart. Data through 5/16/97 Dats Source: R Joshi x2080l Analysis by: A Joshix2080l Owner: A Joshi x2080 ces as=.commnre 11 series 7

Significent itsmo Liot l Millstone 2 - May 1997 Progress: closure ofitems on the significant items List are cn track for delivery '

to the NRC by 8/15/97.

i I

50 _

N Data through i 40 N 5/15/97 i

, f Good g /

3, 30 Y

. 20 Goal: allitems to '

f

, NRC by 8/15/97 :

10 Y

0 t i I I E i I i

Mar Apr May Jun Jul Aug Sep Total Remaining -C-Work Off/ Goal I

Raw Data

{

Mar 97 Apr 97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Total Remairurig 48 45 30 Work Off/ Goal 48 45 39 33 27 0 Definition Analysis / Action items on the Significant items Ust include those items Closure packages for issues related to 11 SILs have (48) chosen by the NRC which require closure prior to been submitted to the NRC for review. Closure start up. Of the 48 SILs,41 require closure packages to packages for 4 additional SILs have been partially be submitted to the NRC. In May, the NRC determined )'

completed.

that 7 SILs did not require closure packages. The work off/ goal hne in the graph above has been revised as of May to reflect the 41 SILs requiring closure packages.

1 I

Goal Comments 1 Goal: All closure packages to NRC by 8/15/97.

I I

Data Source: J Resetar x5411l Analysis by: J Resetar x5411l Owner: A Joshi x2080 couus xtass nom. 12 b?"87

Millctona 2 R00tcrt Rocdinoss l Open NRC Commitments for Restart l May 1997 '

150 1

125 g -

4 100 Data through g 75 s 4___... 5/16/97 5

0 50 i

25 0 -

2 '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Open items Overdue items -t- Work Off/Goaf 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 iterns 117 103 101 109 92 Overdue iterns 0 0 0 0 0 Work Oft / Goal 120 123 122 95 62 32 13 0 0 1 0 0 Definition An NRC Commitment is:

1. Any wntten statement that is docketed.

2. Any verbal statement to take a specific action, agreed to by an officer.

3. any requirement to take an action imposed ty the NRC.

The commitments courasd here are those that need final closure with the NRC pnor to restart of the unit.

l Goal Comments NRC commitments closed on due dates presenbed and Data through 5/16/97 all closed pnor to restart.

i l

Analysis / Action l These commitments consist of Unit ? URis, IFis, LERs, Violations, and docketed correspondence. I i

The total number has cecreased by 17.

l Data Source: D. W. Perkins x 4604 l Analysis by: D.W. Perkins x4604l Owner: R. Joshi x 2080 l

cOM6to XLSw _ _

13 s.2ie7 i

l Milletana 2 Rottert Roedinces

Licensee Event Reports May 1997 i 10 l 0 T l

$1V as 56 If 4 -

l 3

5/16/97 -

o 5% i !

Y

, y 2 m N f[! D fff:

m W E & 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec I l

ELERs-Recent DLERs-Historical:

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 LERs-Historcal 0 3 2 3 8 LERs-YTD 0 4 6 9 17 Definition Licensee Event Reports (LERs) are reports made to the NRC pursuant to 10CFR50.73.

LERS are defined as historical if the event did not occur within the last 12 months.

LERs are reported in the month of the Submittal to the NRC.

I Goal Comments Data tnrough 5/16/97 i

I Analysis / Action Through May 16th, there have been 17 Reportable Events year to date. Corrective Action Program improvements currently underway are expected to reduce reportable events over the next year.

l i

i Data Source: M. Ehredt x2142! Analysis by: M. Ehredt x2142l Owner: R. Joshi x2080 cousie xtss.p.vm.commtwe 14 60 e7

I Millstone 2 Rostart Readiness j 10CFR50.54(f) Readiness for Submittal May 1997

) 100 % -

. N en j \

j g Data through cn 60% N 5/16/97 i 5

'E 40%

>=

0% l i I i i l 1 ; l Jan Feb Mar Apr May Jun Jul Aug Sep 50.54(f) Readiness --0-Work Off/ Goal Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec-97 50.64(f) Readiness 100 % 98% 93% 90% 86%

Work Oft / Goal 100 % 95% 85% 70% 55% 40% 25% 10% 0%

) Definition This indicator measures progress in readiness for 10CFR50.54(f) submittal. U2 readiness for ICAVP is defined as System Review Packages (SRPs) complete and approved for all Phase 1 and 2 Systems, along with graded reviews completed and documented for all Unit 2 programs.

Goal Comments The Unit 2 goalis to be ready for 10CFR50.54(f) submittal Data through 5/9/97 by 6/23/97. Reflects an upward sidjustment es more conservative statistical approaches we apolied 5/9 data are hard figures. 4/1 figure adjusted upward to correspond .

Analysis / Action Project started slowly as structure was put into place and what was really needed underwent more precise definition Performance curve demonstrates an accelerating closure rate on the work off goal as project becomes more skilled in meeting performance goals.

Project wrestled with questions over the depth of review to be applied in the systems area and I breadth of scope of review questions regarding the number and depth of review for U2 programs.

U2 CMP has added more resources (i.e., professionals, hardware, and support staff), has forced greater focus on System Review Teams to reduce unproductive research or divergence from scope, and created task groups to tackle specific issues critical to maintaining schedule.

Data Source: W. Sawatzky x0016l Analysis by: W. Sawatzky x0016l Owner: M. Ahern x5426 cousie xtsso 64<F) Rosen. 15 saie

Millstone 2 Restart Readiness ICAVP Readiness May 1997 100 %

90%

80%

g 70%

60 %

C 50 % Data through E * - ~ - '

5/15/97 j 40%

$ 30%

20 %

10%

0% l l t i I t '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov

- Percent Remaining -t- Projected Work Off/ Goal Jan 97 Feb 97 Mar 97 Apr 97 May 97 Jun 97 Jul 97 Aug 97 Sep 97 Oct 97 Nov 97 Percent Remaining 100 % 92 % 82 % 65% 57%

Protected Work Oft / Goal 100 % 90% 70*4 45% 20 % 0%

Definition This indicator measures progress in completing the system reviews necessary pnor to initiation of Independent Venfication of Corrective Actions Program (ICAVP). System review involves evaluation of desiga and license basis documents for system and system components for incorporation into procedures.

1 I

Goal Comments Complete required system reviews prior to ICAVP start Upward adjustments were made since the last report that scheduled for June 30,1997. reflect a more precise approach to % complete !

measurerrent. About 3 weeks behind the onginal June 9 projection.

i Analysis / Action Phase 1 graded system review started and progressed more slowly than expected as structure was put into place. System review teams are gaining on work-off goals as they become more skilled in meeting periormance goals.

Project wrestled with questions over the depth of review to be applied in the systems area.

U2 CMP has added more resources (i.e., pafessionals, hardware, and support staff), has forced greater focus on System Review Teams to reduce unproductive research or divergence from scope, and created specific task groups to tackle discrete issues entical to maintaining set edule.

Data Source: W Sawatzky x0016l Analysis by: W. Sawatzky x0016l Owner: M Ahern x5426 COM519 xL&licAVP Reachness I5 U2W

Millct na 2 R30 tart Rccdinsca Configuration Management Plan - Program Assessments May 1997 100% r

\+ -

80 %

$ \ >

' 4: Data through

.g 60% +

e , 5/16/97 Q: g -

'1 \

f' 40% f i

0- 'l 20 % @ I h E 0% .

May Jun Jul Aug Sep Oct Nov Dec Apr MCAT 1 % Remaining CAT 2 % Remaining i ' CAT 7 % Remaining --L-Workoff/ Goal Apr-97 May-97 Jun-97 Jul-97 Aug-97 Sep-97 CAT 1 % Rernaaning 54 % 28%

CAT ? 4 Rernaining 86% 69%

CAT 7 % Rornaining 89% 89%

Workoft/ Goal 100 % 60 % 0% 0% 0% 0%

Definition Program Assessments will include a review of licensing commitmen's, program manuals for technical adequacy and configuration control, program implementation processes, databases, etc. It includes the review of past ACRs/PIRs and recent inspection reports for trentag. The unit (CMP) is doing full Pl21 assessments on 13 programs, partial assessments on 18 programs, and 9 programs will have their heensing commitments reviewed.

Goal Comments A total of 120 program reviews to be completed: Data through 5/16/97 CMP: 92 (CAT 1,2,5,6,7. 8) complete by Risk-based ranking has been used, this resulted in the new ICAVP start total number of programs.

Others: 28 (C AT 3,4) complete by unit restart Analysis / Action CAT 1: 13 programs identified for full P121 assessment (to be done by CMP)

CAT 2: 18 programs identified for partial Pl21 assessment (to be done by CMP)

CAT 7: 10 programs identified for evaluation of license commitment (to be cone by CMP)

CAT 3 & 4: 28 program assessments to be done Dy others CAT 5. 7 programs which are subsets of other programs i.e., HELB, MEPL (complete by IC AVP start)

CAT 6: 3 programs to be done with system reviews (complete by ICAVP start)

CAT 8: 41 programs identified as low risk, ranking has been done, no further action rieeded.

Changes in program numbers was ove to the incorporation of comments made by Nuclear Oversight.

F. Mattioli x2013l Analysis by: F. Mattioli x 2013l Owner: A P Neccix5739 Data Source:

cc i. uc%,

17 . . , ,

,a .

Indspondant Cerrcctiva Action Vcrificction Program R3adinsco Millstone 3 - May 1997 Progress; icA VP readiness is progressing; the target completion date of May 27,1997is achiavable.

d 100%

80%

s*

ICAVP work 60%

remaining as of j 5/15/97 Good

[ 40%

a Goal: Ready for I

/

0% i i l i M ' ICAVP - 5/27/97 Y f f I l- 1 I I Jan Feb Mar Apr May Juri Jul Aug Sep Oct Nov Dec ICAVP Remaining -e-Work Off/ Goal 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 ICAi/P Rernaining 73 % 61 % 43% 26% 11 %

Work Off'Gtal 74*. s6*<. 37% 19% 0%

Definition Analysis / Action This indicator measures progress in readiness for independent Good progress is observed with respect to ICAVP Corrective Action Venfication Program (ICAVP). For MP3 this readiness. As of 5/15/97:

consists of the following items for Wave 1 systems:

1. CMP task completions: 88% complete

1. Configuration Management Plan (CMP) task completions (weighted at 70%). 2. SSAs: 90% complete

2. Maintenance Rule Group 1 System Specific Assessments (SSAs) - (weighted at 25%) 3. 50.54(f) Program Reviews: 99% complete

3. 50.54(f) Program Reviews (weighted at 5%)

CMP trjdysis CMP Punch List items plus Licensing This leaves 11% of the total workload remaining to Commitment Validation, FSAR Change Request submittals, be completed prior to the May 27 ICAVP start date.

Piping & Instrument Diagram Walk Downs, and Design Basis The final May 27 readiness call requires Summary completions.

management judgment and Nuclear Oversight

$1A_533ELrg; That documented license and design basis concu n nce.

documents are correct; that systems are operated, maintained and tested in conformance with the license and design bases; and identified discrepancies will be resolved.

50.54ffl orogram reviews include Programs such as High Energy Line Break. Equipment Environmental Qualification, Electrical Separation, etc.

GonI Comments The Unit 3 goal is to be ready for ICAVP by 5/27/97. Wave 1 systems: Auxiliary Feedwater, Quench and Recirculation Spray, Emergency Diesel Generators.

Electncal Distnbution, and Service Water.

MR Group 1 svstems: those systems that are safety anql nsk significant.

Data Source: G Clossus X4232MP l AnstysAs by: G Clostus X4232MPl owner: M H Brothers X43o3MP Page A-1

10CFR50.54(f) Rccdinro for Submittal Millstone 3 - May 1997 Progress: Submittal of this key document to the NRC is on track to meet the 8/t3/97 goal.

s om.

10CFR50.54(f) y gog , work remaining as g of 5/15/97 Good E

c: 60% -

y 1

Y h4m..

S Goal: Ready for 20% - 10CFR50.54(l) subrnitta! - 8/13'97 m'. I I I I I I I I I i i I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec a 50.54(f) Remaining Raw Data Jan-97 Feb-97 Mar-97 Apr-s7 l Mav-97 Jun-97 Jul-97 Aug 97 Sep-97 Oct-97 Nov-97 Dec-97 50 54(f) Remaining 0% 80% 66% 48% 36%

Work Off Goal Definition AnalysisfAction This indicator measures progress in readiness for As of 5/15/97 CMP Punch;st is 70% complete, Group 10CFR50.54(f) submittal- which is the NRC's 1 System SSAs are 45% complete. This results in requirement that management at each nuclear plant having 36% remaining to complete to be ready for verify in writing that the design and operation of their 10CFR50.54(f) submittal.

plants is consistent with what the NRC has approved. Progress towards completion of the work and that all changes and commitments since original necessary to atlow the 10CFR50.54(f) letter licensing are properly reflected in current licensing submittal by 8/13/97 is on track.

documents, such as the Final Safety Analysis Report (FSAR).

For MP3 this is made up of the:

1. Configuration Managemeni Plan (CMP) task completion (weighted at 75%) '

2 System Specific Assessment (SSA) completion (weighted at 25%).

l The CMP task completion includes: CMP Punch List Goal f

items plus Licensing Commitment Validation, FSAR The Unit 3 goal is to be ready for 10CFR50.54(f)

Change Request submittals, Piping & Instrument submittal by 8/13/97.

j Diagram Walk Downs, and Design Basis Summary I completions. l l The SSAs provide: assurance that documented license l and design basis documents are correct; documentation Comments supports the license and design bases; the system is Data through 5/15/97.

4 being operated, mainta'ned i and tested in conformance with the license and design bases; and identified discrepancies will be resolved.

l l Data Source: G Closius l Analysis by: G Clossua X4232l Owner: M H Brothers X4303 Page A-2

)

I

Teck Complationa Rcquired for Rootart Millstone 3 - May 1997 Progress: This goalis very challenging; management attention is being applied to l reduce the Open category andimprove the workolf rate of open tasks ;

required for restart.

4500 4000 g._ Open tasks as of 350 a 5/12/97 3000 2500

, 2o00 I

Goal: Complete all 1000 restart tasks by 8/13'97 0 - -$ '

~

Jan Feb Mar Apr May Jun Jul Aug Sep l Oct Nov oec (

m Open (Restart) Open (Undetermined) + Work Ott/G0al Raw Dats Jano7 Feb.97 Mar-97 Apr 97 Mav-97 ' Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 oec-97 Open ( Aestart> 3059 3076 3489 3753 3744 Open (Undetermiredi 438 407 Work Off/ Goal 3315 2393 1709 717 345 0 0 0 0 0 Definition AnalysisfAction The total number of tasks is defined as those requiring

This indicator includes open items in the Action closure prior to restart. Automated Work Orders (AWOs) Item Tracking and Trending System (AITTS), such as I required for restart are not included, as they are tracked NRC Open items, Significant items List issues, and I in a separate indicator. NOTE: the Open Condition Report (CR) corrective actions.

l (Undetermined) category are those assignments that

The number of tasks that must be completed are still being screened to determine whether they are prior to restart decreased slightly during the first required for restart, two weeks in May.

Increased management attention is being applied to this area to ensure that all tasks entered into AITTS are evaluated correctly to determine whether they are truly restart related tasks, or should be deferred until after restart. Management attention is also being directed toward completing restart-related tasks as scheduled and challenging requests for extensions to ensure that items that support restart are completed.

Goal Comments Goal is all complete poor to 8/13/97. Data through 5/12/97.

These tasks are tracked in Action item Tracking and Trending System (AITTS) and the P2 Schedule.

Automated Work Orders (AWOs) are not included.

Work off curve is based on a combination of AITTS due dates and P2 schedule dates.

oats Source: M R Strout x2299l Analysis by: B Pinkowitz x4302l owner: M H Bro"hers m4303 Page A-3

i Open Cendition Ropsrto l

i Millstone 3 - May 1997 l Progress: condition Reports requiring corrective action are stillincreasing. Increased i Management attention is being applied to this area to meet the restart goal. !

2400 2200 g Open CRs 2000 5/14/97 1

1800 1600 Good f400

$1200 ggg ._ Open CRs >120 y I days 800 600 400 200 0 1 I I I I I I I I I i Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

--#-CR's Not Closed (Total) CR's Not Closed (>120 Days)

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 CR's Not Closed (Total) 1827 1921 2003 2086 2186 Level 1 141 153 166 176 184 Level 2 1686 1768 1837 1910 2002 CR's Not Closed (>120 Days) 1223 1173 1109 1104 1134 Level 1 83 81 74 72 84 Level 2 1140 1092 1035 1032 1050 Definition Analysis / Action This indicator depicts the number of condition reports Significant attention has been focused on completing the (CRs) which have not had corrective actions implemented evaluation phase of recent and backlogged condition reports.

as CRs not Closed (Total). The number of these total This has resulted in a large number of corrective actions CRs which are over 120 days old and have not been being identified and tracked. Efforts are underway to deferred is dep!cted in the bar graph.

review the identified corrective actions to ensure that they are properly scheduled and that redundancies are Cond: tion Reports (CRs) are wntten to document eliminated. I degraded or non-conforming conditions associated with plant systems, structures or components necessary to support the generation of electricity.

1 l

l l

Gos! Comments The goal is to have all Level I Condition Reports closed Data through 5/14/97.

by startup unless they have been reviewed by the Plant Operations Review Committee (PORC) and approved by a Unit Officer.

Data Source: AITTS l Analysis by: S M Srnith x2277MPl Owner: D McCracken x0481MP Page A-4

Canditinn Rcpert initiction cnd Evclucti9n Timalinaco Millstone 3 - May 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

= 350 300 Data Through c: ,

5/14/97 j 250

" 200 /

150 5 100 f _ /

50 ;

j 0

Jan Feb Mar Apr May Jun Ji.d Aug Sep Oct Nov Dec 5 Total CRs initiated D # Evaluations Completed 0 Completed within 30 days Raw Data Jan-97 Feb-97 Mar 97 Apr 97 May-97 Jun-97 Jul-97 Aug 97 Sep-97 Oct-97 Nov-9 7 Dec-97 j Total CR6 initiated 358 303 284 239 95 level 1 CRs Inmated 46 24 16 10 6 Level 2 and 3 CAs initiated 312 273 247 169 89 8 Evaluations Completed 296 229 185 52 2 Completed within 30 days 79 92 91 52 NA success Rate 0 22 0 31 0 37 0 52 NA Definition Analysis / Action This indicator depicts the initiation of Condition Reports (CR) for NOTE: The success rate for April reflects the Unit and the number of evaluations which were not completing 73 of 129 evaluations which are over completed within the goal of 30 days. 30 days old as of 5/14/97.

The graph shows CR data beginning 1/1/97, and represents the initiation of CRs has declined since the beginning of current status / effectiveness of Corrective Action initiatives. the year but remains above the 1996 monthly average. The reason for the decline can be attributed to the completion of major portions of the discovery phases for several ;ecovery projects.

Slow improvement has been realized in completing evaluations within 30 days. Management attention has been focused in this area to enable the Unit to l complete a goal of having no evaluations over 30 l days old by July 5.1997.

l l

l Goal Comments Goal is to complete all evaluations and identify appropriate Data through 5/14/97.

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.

Data Source: AITTS l Analysis by: S M Smith x2277MPl Owner: D McCracken x0481MP Page A-5

e .

Cendition Ropert Mathsd of Discovary Millstone 3 - May 1997 Progress: Selfidentification of issues has improved significantly during the first part of 1997.

100 90 80 70 Data Through 5/14/97 i j 60 <

/

l vc

/ 40 ;

y 1 30 20 -

III n ., -

1 ,, 1 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug sep BsELF IDENTIFIED BINTERNAL OVERslGHT DEXTERNAL OVERSIGHT DEvENT Raw Data Oct-96 Nov-96 Dec-96 Jan-97 Feb-97 Mar-97 Apr-97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Number of CR's Unit idonbfied 103 122 169 297 268 256 202 88 Internal Oversight 22 13 48 36 25 25 27 7 E xtemal Oversght 16 11 3 4 2 0 1 0 Event 36 23 20 20 8 1 8 0 Total identified 177 169 240 357 303 282 238 95 Dept Self ID Ratlos Maintenance 0 42 0 35 0 33 0 53 0 47 0 45 0 33 0 31 Operations 0 56 0 68 0 48 0 57 0 60 0 54 0 48 0.33 Work Planning 0 29 0 36 0 19 0 27 0 36 0 16 0 73 0 29 Desagn Eng 0 35 0 39 0 30 0 43 0 49 0 15 0 30 0 21 System Eng 0 27 0 38 0 21 0 26 0 42 0 34 0 24 0 42 Licensing 0 42 0 40 0 40 N'A 0 00 N 'A NA N;A Definition Analysis / Action This indicator represents the percentage of CR's identified by Self identification of issues by Unit 3 has improved each of the barriers, CR s are categonzed into the following significantly dunng the first part of the year, One factor four areas: influencing this was the large number of CRs initiated by ,

the discovery phase of the different recovery plans. l

Event Driven - Self-reveakng, an event occurs. Increased emphasis on self assessment will help to

+ External Oversight - Identified by NRC, JUMA, INPO, etc. ensure that self identification of issues remains high.

+ Internal Oversight - Identified by OAS, PORC, ISEG, NS AB, etc.

Self - Supervisor observation, document review, Self-checking, independent / dual venfication, etc.

The department self identification ratios are a measure of the individual department s rate of identifying their own issues.

Dept Self ID ratio =

number of CR's ID'd /assioned to that de0artment number of CR's assigned to that department Goal Comments Data through 5/14/97, Data Source: AITTS l Analysis by: s M smith x2277MP l Owner: D McCracken r0481MP Page A 6

Opan NRC Commitmanto far Rastart Millstone 3 - May 1997 Progress: white the total number of open commitments to the NRC remains high, we are reducing the number that are overdue with a goal of closing commitments on their due dates, and none open at restart.

300 250 l\

Data through e 200 Good 5/1497 c

l t Y

.g150 0 100 l 50 0

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l M Open items C"'::IOverdue items -*-Work Off/ Goat i l l Raw Data Jan-97 Feb-97 Mar-97 Apr-97 Ma y-97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov-97 Dec 97 Open items 243 E37 224 284 285

)

Overdue items 0 3 23 10 2 Work Off/ Goal 270 232 59 23 6 2 1 0 o I

Definition Analysis / Action An NRC commitment is: As.of 5/14/97, twelve imms have been closed this month. However, new commitments requinng closure

! + wntten statement that is docketed. pnor to restart resulted in an increase in the number of a verbal statement to take a specific action, agreed open items. The number of overdue NRC items has to by an officer. decreased to two.

+ requirement to take an action imposed by the NRC.

To continue to focus management attention in this !

The commitments counted here are those that need area, the list of overdue items has been provided to I final closure with the NRC prior to restart of the unrt, responsible departments for action and updating'. The overdue NRC commitments and a two week look ahead have been included in the Unit 3 daily report since 4/7/97.

l l

Goal Comments NRC commitments closed on due dams prescribed Data through 5/14/97.

and all closed prior to restart Work Off/Goalis for end of month.

Data Source: H Kross x6656l Analysis by:

J Peschal15840l Owner: D Hicks x0326 Page A-7

Significant Itama Lict Millstone 3 - May 1997 Progress: closure ofitems on the Significant Items List (including items identified by the NRc for closure prior to restart) are on track for the 9/30/97 goal.

200 180 Data through 160 bI 140 m 120 Good 100 f5, 80 Goal: 4 items 9

}

k remaining by 8/13/97 '

i5 60 Goal: allitems 40 complete by 20 Y 9/30/97

/

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total Remaining -e- Work Off/ Goal Raw Dats Jan-97 F eb-97 Mar-97 Apr-97 May-97 Jun-97 JL+97 Aug 97 Sep-97 Oct-97 Nov-97 Dec-97 Totai Remarung 59 55 43 189 186 Work Ott/ Goal SS 45 191 177 121 74 4 0 1

1 Definition Analysis / Action items on the Significant items List include those The Significant items list was revised to include the l 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 wo'k 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. Significant item List closure packages l

1 continue to be turned over to tne NRC on schedulo.

I l

l l

Gos! Comments Goal: 4 items remaining by B/13/97 Data through 5/14/97.

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 Data Source: J. Gionet x550SMP l Analysis by: J Gionet x5505MP l Owner: J. Peschel x5840MP Page A-8

l l

, Licancee Evont R::pSrto Millstone 3 - May 1997 l Progress: Licensee Event Reports made to the NRC are trending down, reflecting that the discovery effort is concluding.

20 18 16 14

12 6 Good

$ b j8 Data thou[

5/14/97 y l

4 h

T f 7 /

/

2 ;j $

m gy3 - - . - - .

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M LERs-Recent LERs-Historical -+--industry Standard 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 0 2 1 1 0 LERs Histoncai 3 11 9 3 1 LERs-YTD 3 16 26 30 31 Industry Standard 1 1 1 1 1 1 1 1 1 1 1 1 Definition Analysis / Action Ucensee Event Reports (LERs): One LER has been submitted in May. This LER involves a historicalissue related to the RSS system

+ are reports made to the NRC pursuant to design.

10CFR50.73

+ are defined as historicalif the event did not occur within the last 12 months l

are reported in the month of the submittal to the NRC l Goal Comments Data through 5/14/97.

l l

o.,, ,_., Leen na_,, ,. e,, J e ee, .s 6 ,,

J ee .s-Page A-9

Lic;nco Amandmont Roqucsts Millstone 3 - May 1997 Progress: The May 31 goal for submittal of all License Amendment Requests needing approval prior to restart will be challenged by nine LARs.

28 LAR submitta! data through 5/14/97 16 2 +

g12 )

4 k]

0 , .

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec M LARs to be Submitted C""")LARs Submitted -s-Work-Off/ 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 LARs to be submmed 19 24 23 17 11 LARs submmed 0 0 0 7 6 Work Off! Goal 19 24 23 5 0 Definillon Analysis / Action License Amendment Requests (LARs) are changes to Daily review meetings are being conducted to monitor Technical Specifications or other license changes that status of activities and expedite completion of the are required for restart, and that must be submitted to LARs. Also, communications have been ongoing with the NRC for approval. the NRC staff to insure that the delays in filing the amendment requests do not significantly threaten the NRCs ability to support our restart schedule.

New dates are being evaluated for LARs that will not be completed by 5/31/97.

l Goal Comments All LARs requiring NRC review submitted by May 1997. . Data through 5/14/97

Five Proposed Amendment Requests are in final review.

Data Sowee: G Papanic x2069l Analysis by: J Peschelx5840l owner: J Peschel x5840 Page A-10 l

Roctert Modificatiana Awciting implomantation Millstone 3 - May 1997 Progress: completing design modifications required for restart by the 9/30/97 goal requires increased management attention.

180 160 40 Restart Mod 120 data through Good g / 5/14/97 pO

.9 100- . ..

lii 73. og l 5 Y

] 80 - z . 93 $

60 ify fh Goal: All 40

$ modifications M complete 9/30/97 20

/

0 '

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 5 Mods Released to Field DMods Awaiting Engineenng Raw Data Jan-97 Feb-97 Mar-97 Apr-97 May-97 Jun 97 Jul-97 Aug-97 sep-97 Oct-97 Nov-97 Mods Released to Field 20 29 21 Mods Awaiting Engineenng 83 81 80 TotalMods Aernaining 173 149 103 110 101 Work Off/ Goal Definition Analysis / Action The total number of outstanding modifications As of 5/14/97, the total number of design identified as required prior to restart that have not modifications is 259. Of these,101 are required to be been tumed over to Operations. 'emplemented prior to restart. This manth, field work has been completed on nine modtfications, engineering has been completed on 3 modifications which do not require any field impler"entation, and one modification has been deferred until after testart. Four new modifications were added.

Continued management attention is being applied to the proper screening of the modifications required / desired for restart to ensure those required for restart are properly identified and scheduled for implementation.

Goal Comments i All start up related design modifications completed by Data through 5/14/97 9/30/97.

Dara source: s. Sudigata x4204 l Analysis by: s sudigala x4204l Owner: D. Hicks x0326 Page A 11

AWOc Rcquircd for Rastart Millstone 3 - May 1997 Progress: The generation and completion of corrective maintenance work orders required for restart is high and currently does not support the restart timeline.

2250 2000 - g -

Work Order a data through 1750 - -

5/14/97 f

1500 - / Good 1250 -

N to 1000 -

o Y

k 750 -

500 - - - - -

= = = = =

0 0 0 0 c 0 0 0

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec MR AWO C":"l30ther AWO -e-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 I Total AWO Backlog 1637 2123 2170 2069 2000 MA 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 1203 1400 1409 1354 1325 Other AWO 434 723 761 715l 675 Definition Analysis / Action Automated Work Order (AWO) Backlog is the total The number of AWOs generated and completed number of corrective maintenance / condition driven (non- during the first two weeks of May have been less than recurring) AWOs required or desired for restart.

expected. Although the backlog decreased, the net reduction this month does not support meeting the The total does not include: AWOs awaiting retest, in goa! at start up. Approximately 275 AWOs will be closure, work planned for future outaaes, AWOs that added to the backlog for work on Motor Operated support field work already included in backlog (i.e- Valves. In order to meet start up goals, the net insulation, staging, etc.) and non-power block AWOs.

reduction in backlog needs to be approximately 400 AWOs per month.

Safety significant systems are defined as Maintenance Rule nsk and/or safety significant systems.

Goal Comments Goal < 500 total AWOs at start-up, less than 350 Data through 5/14/97.

Maintenance Rule risk and/or safety significant system AWOs at start up, and no AWOs that are required for restart at start up.

Data Source: G Rescek x2433 l Analysis by: R.Rothgeb x5241l0wner: R. B. Roy x5000 8_Mann a xt& Awot*4mamme Page A-12 rooW

Tomporary Modifications Millstone 3 - May 1997 Progress: Temporary Modifications are being reduced, with the expectation of having only 5 in place at restart (goalis less than 15).

60 Temp Mod

, data through ;

j # 5/14/97 j40 G od 1

t Y k20- Goal $5 1 i

I R '

O l l I l l l 1 i I l l l Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec i

MTemp Mods Outage Support -e--Work-Off/ Goal - Goa! <15 '

RawData 1 Jan-97 Feb-97 Mar-97 Apr-97 May 97 Jun-97 Jul-97 Aug-97 Sep-97 Oct-97 Nov 97 Dec-97 Temp Mods 48 45 46 38 37 Outage Support 5 6 6 9 7 '

Totalinctalled 53 51 52 47 44 Work-Oft /Goa! 52 52 51 44 35 22 15 11 4 Definition AnalysisfAction A temporary modification is a modification to plant The ' projected work off" and ' actual work off' curves design that is short-term in nature and not part of the are starting to diverge. The normal work planning permanent plant design change process. process does not expedite removal of the temporary modifications. Increase attention will be provided to Temporary Modifications to permanent plant design are expedite the removal of the temporary modifications categorized here two ways: " Outage Support

are once they are no longer needed.

those directly tied to physical work to plant equipment in an outage condition, and " Temp Mods' are all Five Temporary Modifications are currently scheduled others. to remain installed after restart.

It is exoected that the goal for this indicator will be met.

l Goal Comments

, <15 TMs installed at startup Data through 5/14/97 l

! None greater than one cycle without Unit Officer I approval.

Data Source: S. Stricker x5409l Analysis by: S. Stricker x5409l owner: G Swider x5381 Page A 13

Centrol Room cnd Annunciator Dcficicncioc Millstone 3 - May 1997 Progress: Goal of fewer than 10 deficiencies should be met by June 30,1997.

30

. ' Deficiency data 25 through A 5/11/97

.I 20 j ,

Gcal: <10 by G od 15 s June 30.1997 j10 .

= = = = = = f 5 ,

0 '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec I M Total Deficiencies --#-Work Off/ Goal ]

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 Total Defoencias 21 18 19 22 23 Work Off/ Goat 17 15 14 12 to 10 10 10 10 10 10 I

Definition Analysis / Action l Control room instruments, recorders, indicators, and Three new items were added this month (through 5/11) annunciators that function improperly that could affect and two were completed. Based on the current the ability of the operators to monitor and control plant schedule 14 of the remaining 23 items will be completed conditions. by 6f30/97.

Of the 14 to be completed by 6/30/97,

2 have the field work complete and are waiting normal plant operating pressure and temperature for testing,

7 are scheduled for work in May, and I

5 are scheduled for work in June.

)

Goals Comments ;

e Fewer than 10 at startup. Data through 5/11/9:' '

None greater than 6 months old without Unit Officer Projected work off curve is based on less than 10 approval. items by 6/30/97.

Data Source: B Pamsh x0184l Analysis by: D Beachy x4980l Owner: R. B Roy x5000 Page A 14

Oporcter Werk Aroundo Millstone 3 - May 1997

/YOgreSS: A workoff plan has been developed to support the goal of S 10.

I i

45 40 35 ; Work Around data .

e j30 0 ' 00 f'0 g2 S

/ Y 15 a

10

~. l

= = a 5

0 I l l l l l 1 l t I i l Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec Operator Work Arounds -e- Work Off/ Goal RTw 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 wrator Work AroundG 21 24 23 21 21 Work Off/ Goal 20 17 15 13 10 10 10 10 Definition AnalysisfAction Operator Work Arounds are conditions requiring an operator Some progress was made in the last month in the to work with equipment in a manner other than original design disposition of these deficiencies. Research on the which could: status of design changes and Engineering Work Requests continues.

1. Potential ly impact safe operation during a plant transient,

2. Potentially impose significant burden during normal operation,

3. Create nuisance condition due to recurring equipment dr.ficiency,

4. Distract an operator from noticing a recurring condition.

l l

[

i Goal Comments !

Goal <10 Data through 5/11/97 I 4

Vone greater than 6 months old without Unit Officer Work off curve reflects end of month goal. ;

dpproval.

I Data Source: L Palone x4737 l Analysis by: B Parnsh x0184l Owner: L Palone x4737 Page A 15

, e f

Proc duro Rovicien Bccklog l Millstone 3 - May 1997 t

l Progress: Procedure revisions will be completed by the 8/13/97 goal with significant l progress expected in the next two weeks.

1 l

l 300 l

250 Data through poo 5/14/97 Good i

B 150 y

100 I Goat complete h- D$

P . corrective actions l

h h Is by 8/13/97 0 '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Other Procedures PUG Procedures -*-PUP Work Off/ Goal - Other Work Off/ Goal Raw Data Jan-97 Feb-97 Mar-97 Apr 07 May-97 Jun 97 Jul-97 Aug-97 sep-97 Oct-97 Nov-97 Dec 07 Total Rernaaning 349 309 288 244 234 Other Procedures 251 213 198 162 153 PUP Procedures 98 96 90 82 81 PUP Work Off/ Goal 0 94 78 69 43 27 8 0 Other Work Off/ Goal 240 208 l 169 131 101 70 36 0 Definition AnalysisfAction 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. PUP is the abbreviation for Procedure Upgrade applicable. This will minimize the number of times the Program. procedure must be modified, reviewed, and approved.

Revisions are in progress, there should be a significant decrease in the backlog in the next two weeks.

Operations is working primanly systern operating procedures in order to complete PUP. These procedures include the system operating instructions Comments and valve /electricalline ups.

Data through 5/14/97 The biggest barrier to completion of PUP for Operations is Licensed Operator review support (independent Work off curve is based on 100% complete by 8/13/97 review, validation). The training shift is now dedicating 10 hrs of overtime per shift member for procedure Goa; reviews. An additional resource from the Station Procedure Group is now being used to put the All open items have been reviewed and proper remaining Operations procedures in the upgrade format corrective actions are completed prior to 8/13/97, so that the procedure is ready for operator review.

! Procedure reviews and the number of procedure revisions started have increased.

Data Source: Departments l Analysis by: T Kutterman 15421l owner: L Palone/J Moyer Page A-16

Millstone Nuclear Power Station Site Integrated Schedule DRAFT l l l

l i

i l As of May 15,1997 l

l DRAFT l i

.. . .- . . - - 1

4 l

l MILL STONE SITE INTEGFATED SCHEDULE l

l A5 OF $'15/97

, e

w n s i s i i n, si-*. e.,s i v e

s -,e i..s : t -t u t t

}FLC7 SITE FINISH 12 V499 L, ]ld E E E ** CN t

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-.. 4 . - - y 13 23 l i Pct E t ri hp r t 1,2 DATs. DATE 1smyg7 FFOJECT<2 93A1

$ncT ssE Ar s E STAPT E FIN 5w ' ODES INTEPvAL: 1 WJ4T w ' t ) S M DULE EAP C ht PT .

! I l {

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+e u t 3 CgNFIGUFATIONMGMTPROGCMPL 14 JUL f 1 11 l l l CONFIGUPATION MANAGEMENT PROGRAM l

LjCENSEAMENDMENTSAFPVDlbOCT l

2 i 2 LICENSE AMENDMENTS APPPOVED i

Fj57 ART, UNIT,323,DEC CgISSI,0NEP,FESTAPTPPIEFING19DEC PHYSICALLY D FDP FESTAPT ' 3t SEP PEA'Y P s i t \

3 i 3 e i i i i i !

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1;AvPCOMPLETE22OCT 4 I i 4 ]

CONTRACTOR ICAVP 1

pPCICAVPCOMPLETEtoNov 5 I i 5 NRt ICAvP OyT 3 COMP'.ETE 24 NOV b I I b OSTI

- L9e11 8 LyCENSEAMENDMENTSAPPVD25NOV 7 i 7 LICENSE AMMENDMENTS APPROVED Cgf% P,ESTART bPIEF]NG 23 JAN (FFDJ)

PHYSICALLY FEADY FDP FESTART 25 Nov F i 1 8 i 8

-l l l l MILLSTONE UNIT 2

[STAPTUNIT227JAN (PPOJECTEDI ,

j CyNFIGUPATIONMGMTPROGCMPL 28 SEP r ) i 9 l l

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C)' T I C OMPL E T E 2 7 OCT (FFDJECTED) 12 I i 12 OSTI ne sai i l l CyNFIGUPATIONMGMTFFDGCMPL 26 JAN 13 i 13 CDf6IGUFATION MANAGEMENT P PDG R At1 PjSTAPTUNIT 1 12ND OTP)

CDy. FESTAFT EFIEFIN5 r2ND OTP) 14 1 14 '

m i i i PHYSjCALLY, P E A D,Y FDP FESTAci c7 NR MILL 5 TONE UNIT 1 3 LgENSEAMENDMENTSACFF0VED21 MAD 15 1 1 15 i LICENSE AMENDMENTS APPPOVED l l l 4 IjAVPCOMPLETEE7 MAP {

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l DRAFT

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Millstone Nuclear Power Station !

l Millstone Units 1,2 and 3 l l

Level 1 Schedules !

l DRAFT l l

l As of May 15,1997 l l

l l

i I

i l

DRAFT

...---,v -. - - _ _ _ - , , , - . _ , . - - - - - . - - , , - , , - - , -

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1997 1999 App MAY JUN JUL AUG SEP OCT Nov DEC 3 44 FEB MAR APR MAY JUN Coef!CuaATION PMNRCENDR PROGRAM 1 25FEB TU i bJAN TU l CONFI$UPATION MANA EMENT PROGRAM (52.54F) :

l l l 2 BNOV SA I .

I

? MAR SA l INDEPENDENT CONTRACTOR ASSESS PROG COMPLETE J l l l l 3 . F .b J AN TU CMP FINAL LETTER S!)BMITTAL i I l I I l 4 7JAN WE C~) 26JAN MO '

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7 25FEB TU .

I 7 MAR SA ALL MODIFICATIONS REGUIRED FOR SU B F SFEB TH hL l lL'PHYSICA'LWORKFORRELDA l l l 9 F SFEB TH hL 10 lL'MODIFIChTIONSREQUIREDF l l bFEB FR 010FEB TU DOC REVIEWS L' APPROVAL TO LOAD FUEL (PORC) l l l l 11 11FEB WE D 15FEB SU ;

CORE RELOAD !

12 ,F 7 MAR SA UNIT 1 3HYSICALLY READY FOR STARTUP RECAAT0er l

l 13 80CT TU i 21 MAR SA TECH SPEC AMENDMENTS IMPLEMENTED l l

l>RA T-i> ATE:S & EVEllTS 40 B EVE RlFil:D p a, nags PAGE 1 l

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I l 7 2bDEC TH .

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MAJOR MODIFICATIONS TOTAL . (108) '

HIGH ENERGY LINE BREAK ( 9/27)

RBCCW PROJECT (10/15)

I CHECK VALVE REPLACEMENT (11/15) l MOTOR OPERATED VALVES (31/2 3) l l 8 17FEB MO i15JUL TU

! PERFORM DRAINED DOWN Lf0RK (DEFUELED)

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RE AMNF.SS FOR RESTART REVIEW OPERAT10t%L READINESS REVIEW 13 13UL TUi F i 1SEP MO READINESS REVIEWS l l READY FOR OSTI 14 F

29SEP MO Q .270CT.MO NRC REVIEW ASSESSMENT OSTI PLardT 15 2AUG SA.D 6AUG WE.

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R EADY' FOR RE'fTART l l l 20 F .16DEC TU COMMENCE HEATUP l l l 21 F 27JAN TU M'0DE'2 l

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1997 i 1998 APR P%Y JUN JUL AUG $1P CCT NOV DEC JAN Ff8 POR APR P%Y JUN COWIGURAT10N PMNRGEMENT PROGRAM WAVE 2 L 3 , FSAR/DBS (7/14/97)

WAVE i (5/17/97)

P 1 13AN WE i 14JUL M0 CONFIGURATION MANAGEMENT PROGRAM COMPLETE SYSTEM SPECIFIC ASSESSMENTS DESIGN BASIS (FSAR/DBS) l l l l IMPLl: MENT PROCEDURES (8/13/97)

F MANUALS COMPLETE (7/1/97) 2 1JAN WE i 13AUG WE ENGIN{ERINGPROGRAMS 3 27MAY TU i l1 l l l l i 20CT TH CONTRACTDR ECAVP l l l 4 30JUN M0I i 14NOV FR NRC ICAVP l l l 5 23JUL WEI i 230CT TH ~

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psev51W @K PLANT PHYSICALLY READY (9/38/97) 7 1JAN WE .

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MAJOR MODIFICATIONS (TOTAL 8167)

MOTOR OPERATED MODIFICATIONS i

l OSS/RSS PIPE MODIFICATIONS i

CCP PIPE SUPPORTS MOD i APPENDIX-R MODIFICATIONS

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8 13AUG WEi i 30SEP TU MO 3IFICATIONS' TO REACTOR C00LAN" PUMPS i

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I 14 19DEC FR 0 23DEC TU COMMISSID'NER!i RE 3 TART BRIEFING amT 15 F 30SEP TU PERF')RMA'NCE'IND CATOR (P.Ii DN GRAPH CURVE l l l l 2ND MODE d L3 (11/15/97) 1ST MODE 4 11/03/97) 16 300CT TH i F 1.23DEC TU HEAT UP PLANT L EVALUATIONS l vD {E DRAFT

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- CHEMISTRY SELF ASSESSMENTS

- R ADIOL OGICA' EFFLUENT PROGRAM SUPPORT

- SYSTEM CHEMISTRY ASSESSMENTS ,

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- STATION EMERGENCY RESPONSE ORGANIZATION MRDA AND AMRDA NRC COMMITMENT t

- EMPLOYEE CONCERNS TASK FORCE '

NRC COMMITMENT

- EMPLOYEE CONCERNS PEER REPRESENTATIVES

- NSAB PLANT SUPPORT SUB-COMMITTEE I I I I I l 1 I I I i 3 F 30MAY FR l l l l l l C. O, M. P. L. E. T.. E. . C.

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- RESPONSE TO NRC LETTER A1296b

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R. C R. .

- SUPPORT RESPONSE TO NRC 50.54(F) LETTER l . . . . C. O. O. R. D. .I N. A. .T. E. D. . . W. .I T. H. . . U. N. I T. 5 0. 5. 4 .( F. ). . P. R. O I I I i l l 1 1 8 F 30JUL WE I l l 1 I.M. PL. E. M. E. N. T. . C. H. E. M. I S. T. R.. Y. . D. A. T. A. . M. AN. A. G. E. M CY 7- .

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- INPO CY.7-1 AND NRC INSPECTION ITEM PRIOR TO START-UP.

- MULTIPLE ITEMS C00RDINATED WITH UNIT

. . . .P.R. I. O. R. I. ....................

T. I.E. S. . ...........

I I l i I I I 1 l l 10 F 31 AUG SU l l l l l l INSTALL' i I I UNIT 3 LABORATORY 1 :

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- RESPONSE TO M3-97-109b PRIOR TO START-UP l I I I I

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- RESPONSE TO M3-97-129b EEEEEEEW5EE&EBSSS35SSS55EE.5 PRIOR 3 E R S E BTP AEB START-UP B E E E f3 E E E 5 FIMIA 13 15MAY THIabMAY FR l l APPROVE I l I I PLANNING I I PPOCESS i

14 15MAY TH l ibMAY FR l l l lIBENCHMARK I I I DATAi iASSEMBLED1 15 lbMAY FR l lbMAY FR l l l lIDEVELOP i i i HI-LEVEL i i l STRATEGIC I l l DBJECTIVES 16 lbMAY FR .I 17MAY SA l l l l l l lIDEVELOP 1 I i HI-LEVEL NUCLEAR GOA'S 17 lbMAYFRI16MAY.SUl l l l l CONDUCT NUSCO SLA REVIEW II I I i l l l 18 17MAY SAi19MAY M01 ( l il lDEVEL'OP l i l NUCLEAR i I i BUSINESS l l PLAN 19 19MAY MOl19MAY MDj l l l l l l CORPORATE EXECUTIVE PLANNING CONFERENCE II I I I I i l i 1 20 ~ 2JUN MD 27JUN FR l l l l

l lllIMANAGERS 1 i l i REVItW I I LCCl BUDGETS i

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30 OSEP MO D 12SEP FR l EXEC. REVIEW MILLSTONE BUDGET I I I I I 31 .F _bOCT MD I .

1990 BUDGET SIGNOFF i i l i i i ,

32 15DEC MDI15DEC M0 l l l lEMPLOYEECOMMUNICATIONS 33 15DECMOI15DECMDl l l NU BOARD APPROVES BUDGET l res ceae em,x stmas l l 14 F 29APR TU SUPPORT STATE INGEST REHERSAL

.J l l l 15 F 9MAY FR SDRC ON VALIDATE] PROCEDURE i l I i l 36 F 5JUN TH l

'OMBINED C FACILITY DRILL 23 MAY, 23 JUN, 25 JUN 37 F bJUN FR l '

EXERCISE MGMT REVIEW l i I l 36 F 12JUN TH i

DRILL l l 39 F 19JUN TH MP3 EXER ISE - NRC REGION 1 40 F 7AUG TH MP1REjERSAL 41 F 14 AUG .TH EX{RCISEMGMTREVIEW 42 F 21 AUG, TH. l MP1 EXERCISE - NRC L FEMA l [^div'*E' DRAFT

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PACE 1/1 ENEfT 44 3A SCMEDJLf PAD CHART l l 1997 1996 APR MY JUN JUL AUG SEP OCT NOV DEC JAN FEB MR APE PVa Y JUN EDS (MERGENCY PLMNIT. EERVICES 43 F 22AUG FR NRC PROGRAM' INSPECTION I I I 1 44 F 11SEP TH l STATE INGESTION REHERSAL I i 1 l l 45 90CT TH I100CT FR l STATE' INGEST 30N EXERCISE - NRC L FEMA I I I I 46 F 230CT. TH MP2 DRIL_

ENW ENVIPMh7A6 E.E E v 3 CL 5 47 12MAY MD D lbMAY FR ENVIRONMENTAL SERVICES WEEK OF 5/12 COMPLETE DRAFT OF DPDES WATER QUALITY PERMIT APP FOR INTERNAL REVIEW.

SUBMIT INFO TO DEP - MP3 HYDRAZINE DISCHARGE FR MP3 CPF TO RESILVE WATER QUALITY STARTUP ISSUE.

SUPPORT COMPLETION OF NUCLEAR GROUP ENVIRONMENTA POLICY.

48 19MAY MO D 23MAY FRll l l l l l l ENVIRONMENTAL SERVICES WEEK OF 5/19 INITIATE NEAR TERM ACTS - ENVIRO. SYS ENHANCEME A. EVALUATION OF DEPT STAFF TRAINING NEEDS B. BENCHMARK BEST PRACTICES

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NOPOSE I I I I fR E L5 CEbONEbf l 1 49 2bMAY MO D 30MAY FR j [ l ENVIRONMENTAL SERVICES LEEK OF 5/2b INITIATE FORMAL NPDES PERMIT COMPLIANCE PROCEDURAL REVIEW PROCESS AND APPLY LESSONS LEARNED FROM BENCHMARKING AND ANALYSIS OF REGULATORY REQUIREMENTS.

HOST INTERNAL NPDES PERMIT CHALLENGE SESSIONS 13 TEST ADEQUACY 3F THE PERMIT APPLICATION.

I I I I ) l I 50 2JUN MO D 6JUN FR l l l ENVIRONMENTAL SERVICES LEEK OF b/02 SUBMIT NPDES PERMIT APPLICATION TO CT DEP.

COMPL BENCHMARKING OF MP ENVIRONMENTAL PROGRAM COMPLETE iST DEPT SELF ASSESSMENT REGARDING EFFECTIVENESS OF CORRECTIVE ACTIONS FOR NPDES PERMIT SAMPLING REQUIREMENTS.

HOST MEETING WITH CT DEP TO INITIATE ACTIONS NECESSARY TO FILE THE NEWLY REQUIRED AIR QUALITY PERMIT APPLICATION FOR MP EY YEARS END.

Cu3i N CSEMEDHT 51 SMAY MO D ibMAY FR~

SECURITY ' (FFD)

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57 13UL TU1 1 31AUG SU l l 58 lll ,SPE{IAq AUDIT - MAINTENANCE RULE 14JUL MO O 253UL FR l l l

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59 lll lTECHNICA 21JUL MO O 1AUG FR SPECIFICATIONS l

60 lll4AUG MO O 15AUG FR l ENVIRONMENTAL l

61 ll18AUG l l TRAINING OPERAT[0NS)

M0 D SSEP FR l l l lSPECIALAUD{T-FIREPROTECTION 62 25AUG MO O SSEP FR l

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l l l t l l 63 iSEP MO 30SEP TU l l l SPE{IA AUDIT (TBD) 64 15SEP MO O 2bSEP FR l (PLAN /TRA;:NING AND QUALIFICATION) l l l SECURITY 65 60CTMOO170CTFRl l l lCORRECTIVEACTION bb 3NOVMOO21NOV.FRl ,

MEASURING AND TESTING EQUIPMENT wa w:awmrew 67 27MAY TU D 2JUN MO CURR. TESTS lOPSNLCT/LORTCYCLE97-4 68 1EJUN M0 D 203UN FR l l l l l l (OPERATIONS) lllCOMPANYAUDITEXAMS 69 183UN WE D 24. HUN TU l l l l INPD'ASSIT VISIT - SIM INSTRUCTOR PERFORMANCE 70 F13ULTul l l l l ES COMPLETE CLER-96-254-ti) l MP1 EMI/RF} CL ASS 71 73UL MO D 113t$L FR l l l l l

72 lll lMP3LOITNRCOPERATOREXAMS 14JUL MO 0183UL .FR l l l l OPS N.CT/LORT CYCLE 97-5 CURR. TESTS 1

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I i i i l 14 2SEP TU 0 BSEP MO l [

OPS'NLCT/LORT CYCLE 97-b CURR. TESTS 75 F 100CT FR l l l l GENERIC FUNDAMENTALS EXAM - FALL 97 CLASS 76 200CT MO D 240CT FRl l l l l l OPS NLCT/LORT CYCLE 97-7 CURR. TESTS 77 BDEC MD I 11DEC TH l l '

NUCLEAR TRAINING DEPARTMENT CIT LIEEK (ALL NTD)

MGT 1% CLEAR PWALEMEW

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78 F 13MAY TU E'MPLOYEE t. COMMUNITY DISCUSSION Jl l I 79 F 13MAY TU NRC NEETING TO DISCUSS OVERSIGHT AT MILLSTONE 1l l l 80 F 13MAY _TU NRC MEETING ON MILL'5 TONE COMPREHENSIVE !3LAN

.Ll l l 81 .F iSMAY TH NU/NRC MEETING - OPERATOR TRNG CORRECTIVE ACTION 82 ,F l bMAY FR l l NCAT VISIT T ] M}LLSTONE 1 I I 83 F 12JUN TH j MP3 ASSOCIATE PARTI IPANTS MEETING ;

I i i l I 84 F 173UN TUl l :

ANNUA S AREHOLDERS MEETING I 86 F 13UL TU l l DPUC COMMISSIONER S V: SIT TO MILLSTONE Bb F 29JUL TU l l l MP STAT::0N INPD EVALUATI JN RESPONS E DUE I I I i l 87 F 300CT TH l NU/NRCfTAFFBRIEFINGOFCOMMISSIONREGARDINGMP 88 F 2JAN FR l l PERATO'R TRAINING ACCREDITATION TEAM VISIT I l l 1 l 89 F 2JAN FR l NU/NRC STAFF BRIEFING OF COMMISSION REGARDING MP l l

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Millstone Unit No. 2 NRC Significant items List SIL FINAL DUE NUMBER 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 issues. Refer to MC 0350 for items to be addressed 4 Employee Concern Program: Refer to MC 0350 for items to NOTE 1 ,

be addressed I i

2 l 5 Failure to implement timely corrective action for identified NOTE 2 significant conditions adverse to quality

, ' Corrective Action Program timeliness anc! effectiveness l *Self-Assessment program implementation and effectiveness

Commitment Tracking Refer to MC 0350 for items to be addressed i Effectiveness of the Corrective Actions Program 6 Work Planning and Control; Plant Maintenance program 7/17/97 I effectiveness; significant hardware issues resolved; maintenance backlog managed and impact on operation assessed; surveillance testing; plant housekeeping. Refer to l MC 0350 for items to be addressed.

7 Bypass Jumpers. Operator work-arounds & Control Board 7/20/97 l Deficiencies. Refer to MC 0350 for items to be addressed 8 Weaknesses in procedure classification system 8/15/97 Procedure Quality and Adherence l

Surveillance Quality l

Establish procedures required by Tech Spec I

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

' Closure Package not required 2

Closure Package submitted to NRC

Millstona Unit No. 2 NRC Signific::nt it:ms List SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE 9

Operating procedures to be consistent with FSAR 8/15/97 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months versus the 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months previously docketed in a letter addressing l NUREG 0737 response i Change made to OP2305 was inadequate n that it failed to lock open the valves. This was corrective action for the seismic issues associated with the refueling drain line l

l 10

Progress of EOP Upgrades 7/25/97 I

Acceptability of deferring AOP Upgrade Refer to MC 0350 for items to be addressed 11 Quality Assurance and Oversight NOTE 1 Refer to MC 0350 for items to be addressed 12 Licensee Restart Punch List - Review items deferred until 6/30/97 after the restart. Refer to MC 0350 for items 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 l secondary and support systems; System Lineups; Results of pre-startup testing; Power ascension testing. Refer to MC 0350 for items to be addressed

Millstone Unit No. 2 NRC Significant items List l SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE 16 1) Train on-shift personnel to perform dose assessments 6/16/97

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 Regulatory issues; Licensee Amendments; NOTE 1 Exemptions; Reliefs; Orders; Significant Enforcement issues;

. Allegations; 10CFR2.206 Petitions; Coordination with NOTE 1 interested agencies and parties. Refer to MC 0350 for items to be addressed i

18 Failure to adequately control standards resulted in 5/29/97 inappropriate downgrade of QA Cat 1 equipment to a Non-QA status Failure to prevent the use of potentially non-conforming materialin safety related applications due to lack of adequate i MEPL dispositions j 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 l

20 Failure to provide up to date data or reflect results of 8/15/97 l dynamic tests in GL 89-10 Closure Report Failure to address the leaking of check valve 2-CS-15A and to take action to assess the impact of water being present on ;

the sump side of 2-CS-16.1 A '

Failure to adequately evaluate information on pressure locking and thermal binding LAW PIR procedure Failure to document review of Vendor QA design services l IAW NU procedures l 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.

I

l Millstona Unit No. 2 NRC Significant itsms List i L i

l. I SIL FINAL DUE NUMBER ITEM DESCRIPTION DATE l Refer to MC 0350 for items to be addressed ,

Resolve Thermo Lag issues

{

l l

f l !

l 22 Failure to identify and implement corrective actions 6/30/97 .

concerning CTMT Sump Screen discrepancies. '

Failure to adequately evaluate the installation of electrical j 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 l concerning 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 -

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 i inoperable due to insufficient air flow and not taking a l representative sample i 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months versus the 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 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 NCTE 2 26 Response to industry operating experiences were NOTE 2 inadequate. Excessive fast starts were performed compared 1 to industry practice. Failure to determine root cause for the ]

l

9 bearing failure in March 1196 j 27 Adequate design control measures not established for 8/1597 verifying the accuracy of the DBDPs 6/13/97 I

.= .-

i

, Millstone. Unit No. 2 NRC Significant items List i j a SIL - FINAL DUE NUMBER ITEM DESCRIPTION DATE l i

28= Inadequate design verification for RBCCW Surge Tank NOTE 2 . !

seismic restraint modification !

Failure to adequately control the installation of a temporary i 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 i

30 Failure to effectively track and implernent corrective actions NOTE 2 !

l concerning " dual function" isolation valves !

31 Failure to address the SBO issues identified in the VECTRA 7/15/97 I

assessment 32 Failure to take appropriate corrective actions for audit issues NOTE 2 involving trending and prioritization of NCRs L 33 Inadequate corrective actions concerning a seismic design 6/30/97 deficiency for a Vital Switchgear room cooler 34 Change made to OP2305 was inadequate in that it failed to NOTE 2 .

l lock open the valves. This was corrective action for the seismic issues associated with the refueling drain line.

35 Inadequate corrective action in LER 96-024 6/2/97 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.

l 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 l-l 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 l analysis -

j Calculate available HPSI system flow rates utilizing fluid temperatures predicted for post accident conditions 1 40 Complete reanalysis and mods if any for a single MSIV 6/27/97 ,

i closure event . l; I

l l' _ . _ - , _ _ - _ _ - - . _ .. -

. . 5 i

l Millstone Unit No. 2 NRC Significant items List SIL FINAL DUE i NUMBER ITEM DESCRIPTION DATE Reanalyze secondary side pressure for a single MSIV l closure event !

41 Submit the revised LBLOCA Analysis 6/16/97 )

42 EDG fuel oil supply questions 7/7/97 l i

43 Appropriateness of the SUR Trip removalin 1978 7/17/97 )

i 44 Ensure that the plant response to a MSLB event will not 8/15/97 result in exceeding the design requirements of CTMT l

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45 Reanalyze secondary side pressure for a single MSIV NOTE 2 I closure event l 46 Evaluate 2-HV-210 and associated procedures. Review and 8/15/97 l validate operator actions included in safety analysis 1

47 Determine the effect of SPEC 200 electronics on response 8/15/97 i time testing and determine if testing additional components should be considered during response time testing 48 T.S. Limits for inoperable MSSV non-conservative 8/15/97 1

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--a 8.1 ACR 01535 White Dewatering Spent Resin the Waste Temperature in the Liner DRP 02/26/97 03/15/97 Closed Raised from 90 to 310 degrees F 68.1 ACR 10397 LLRT *AS FOUND* Total Leakage Exceeded Max Allowable DRP 02/27/97 03/17/97 Closed 18.5 URI 96-201-17 Control and Use of Vendor Information DRS 03/10/97 05/09/97 To NRC for Review eel 96-201-15. eel 96-201-18. EEI 96-201-19. URI 96-201-17. G.2 on 4/14/97 58.1 ACR M3-96-0557 Thermal Relief Valve Setpoints SPO(l) 03/15/97 04/02/97 To NRC for Review ACR M3-96-0685, FEl 96-201-33. ACR M3-96-0557 on 4/2/97 14.2 URI 96-01-07 Safety Grade Cold Shutdown Operational Configuration Control ACR SPO(1) 04/19/97 0509/97 To NRC for Review 07745. URI 96-01-07 on 5/8/97 44.2 ACR M3-96-0325 Cycle 6 Boron Ditution Analysis Potentially Non-Conservative and PGS DRS 04/13/97 05/09/97 To NRC for Review Flow Rate to Charging Pumps May Be in Error on 5/8/97 47.1 ACR M3-96-0391 RHR Heat Exchanger Botting Susceptible to Doric Acid DRS 04/25/97 05/16/97 To NRC for Review on 4/23/97

~ .

6.1 ACR 04199 RCP Seal injection Fitter "B" Gasket Failed Resulting in Spill of Coolant to DRP 04/25/97 05/16/97 To NRC for Review Floor Drains on 5/15/97 W.1 URI 93-07-07 Safety Analysis (50.59) Process SPO(L) 04/26/97 05/16/97 To NRC for Review URI 93-07-07. eel 96-201-02. EEI 96-201-06. eel 96-201-07. eel 96-201- on 5/15/97 08 37.4 eel 96-201-24 Review Licensee Corrective Action Programs for Effectiveness to include SPO(t) 04/26/97 05/16/97 To NRC for Review ACRs and NCRs on 5/16/97 eel 96-201-13. EEI 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 ........

TDD = No Action Required From NU. NRC To Determine When Review To Be Completed.

2

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ZonetDo_cumenWo. Descriptforlof_NRC_ Item _MBQ EP_Beylew NBC.Reyleg Status 4.1 ACR 01895 EDG Sequencer CDA Signal Output *A* Train Cmwas Started DRS 04/26/97 05/1G/97 To NRC for Review on 5/16/97 18.4 eel 96-201-19 Control and Use of Vendor information DRS 04/2697 05/16/97 To NRC for Review eel 96-201-15, eel 96-201 18. EEI 96-201-19, URI 96-201-17. G 2 on 5/16/97 12.2 ACR M3-97-0317 Containment Foundation Erosion NRR 05/03/97 05/23/97 ACR D6323. URI 96-04-13. URI 96-04 14. URI 96-04-15. IFI 94-11-09 M3-

97-0317 522 LER 96-005-01 SWP' Temperature Switches Defeated by Dypass Jumper for SWP*P3A1B SPO(1) 05/03/97 05/23/97 (Booster Pumps) eel 96-201-23. LER 96-005-01. LER 96-005-00. ACR 10795 80.1 ACR M3-97-0348 Procedure Adequacy and Adherence / PUP Process SPO(l) 05/03/97 05/23/97 OSTI ,

44.3 LER 96-026-00 Cycle 6 Boron Dilution Analysis Potentially Non-Conservatrve and PGS DRS 05/0397 05/2397 To NRC for Review Flow Rate to Charging Pumps May Be in Error on 5/9/97 l 33.2 LER 96-003-00 Seismic 11/1 DRS 05/06/97 05/27/97 IR 96-201. G.2. IFI 97-01-xx. LER 96-003-00, ACR M3-96-0563. CR M3 0850 26 4 ACR 12862 Motor Operated Vafve Program GL 89-10 DRS 05/07/97 05/29/97 ACR M3-96-0277. ACR M3-9G-0278. M3-96-0627,12862. LER 96-019-00.

LER 96-020-00. LER 96-035-00. URI 95-17-09. IFl 95-01-01. IFl 95-17-01, i IFl 95-17-02. IFl 95-17-03, IFl 95-17-04. IFI 95-17-05 G52 LER 97-003-00 Other RSS and Related Design Basis Concems DRS 05/10/97 05/31/97 ,

ACR M3-96-0496. ACR M3-96-0497. ACR M3-06-0620. ACR M3-96-1078 NRR ACR M3-97-0039. ACR M3-97-0128. ACR M3-97-0409. LER 97-003-00 LER 97415-00. LER 97-021-00 . . . . . . . .

15.1 ACR M3-96-0159 Letdown Heat Exchanger Leakage anu Design Discrepancies SPO(f) 05/10/97 05/31/97 ACR M3-96-0159. eel 96-06-15 49.1 ACH M3-96-0324 Fuel Transfer Tube Bettows Seal Connecton Not Tested DRP 05/14/97 06/04/97 1 i

TBD = No Action Required From NU. NRC To Determine When Review To Be Completed. {

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70.2 LER 96-002-01 Review TRM for Techrucal Specifcations Interpretations. Evaluate T.S. DRS 05/22/97 06/12S 7 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 14.1 ACR 07745 Safety Grade Cold Shutdown Operational Configuration Contral ACR SPO(l) 05/23 S 7 06/13/97 07745, URI 96-01-07 59,1 ACR M3-96-0775 Use of Doraflex in SFP Racks SPO(L) 05/24/97 06/12/97 ACR 09124, ACR M3-96-0846, ACR M3-96-0775 LER 96-033-00 12.5 URI 96-04-15 Containment Foundation Erosion NRR 05/24/97 06/16/97 ACR 06323, URI 96-04-13 URf 96-04-14, URI 96-04-15. IFl 9411-09, M3-97-0317

. . . . . . . . . . . . . . . . . . . . . . ~ ..... ~.~. a . ~.

12.4 URI 96-04-14 Containment Foundation Erosion NRR 05/24/97 06/16/97 ACR 06323, URt 96-04-1.*. URI 96-04-14, URI 96-04-15. IFl 94-11-09. M3-97-0317 32.1 NOV 94-16-05 Resident Ernphasis: AWO Quality and Backlog Control G.2, NOV 94-16-05 DRS 05/24/97 06/14/97 12.3 URI 96-04-13 Containrnent Foundation Erosion NRR G5/24/97 06/16/97 t

ACR 06323, URI 96-04-13, URI 96-04-14, URI 96-04-15, IFl 94-11-09, M3-97-0317

- . .. . ~. . -. .-

59.2 ACR 09124 Use of Borarlex in SFP Racks SPO(L) 05/24/97 06/16/97 ACR 09124 ACR M3-96-0846. ACR M3-96-0775 LER 96-033-00

~- ..

54.1 ACR M3-96-0181 Numerous Botts on Back Door on 4160V Switchgear Missing DRP 05/28/97 06/18/97

. . ~ _ . . . ..-

56.1 ACR 12495 Shutdown Margin Monitor Alarm Setpoint DRS 05/28/97 06/17/97 15.2 eel 96-06-15 Letdown Heat Erchanger Leakage and Design Discrepancies SPO(f) 05/29/97 06/19/97 ACR M3-96-0159. eel 96-06-15 TBD = No Action Required From NU. NRC To Determine When Revew To Be Completed.

5

_ . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ . _ _ ._.__m - _m.___ -_ m_.~.- - . .e- . _ . _ ,, . _ - _ - . _,------...w,. . . , - ,. ---r.r -r . -- ---

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04. eel 96-201-05 70.4 LER 96-038-00 Review TRM for Techrncal Specifications Interpretations, Evaluate T.S. DRS 05/29/97 06/19/97 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

. .< . -..- ~.- . ~ . - . . . . . . . .--

44.5 LER 96-026-02 Cycle 6 Doron Difution Analysis Potentially Non-Conservatwe and PGS DRS 05/30/97 Oti/19/97 Flow Rate to Charging Pumps May Be in Error 76.9 IFl 96-08-17 Cracking of Fuse Ferrules DRS C5/30/97 06/19/97

..... - . . o . . . - - . . . ~ . ~ . . .-

37.1 eel 96-201 13 Review Licensee Corrective Action Programs for Effectrveness to include SPO(1) 05/30/97 06/19/97 ACRs and NCRs eel 96-201-13. eel 96-201-21. EEI 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

~ . . - - .

- . . ~ .

C3.1 None Associated Review 50'54F !ssues for RestartHeview Deferred Restart ftems List SPO 05/30/97 06"20/97

~ ~ - ~ ~ . . . . .--.

513 LER 96-005-00 SWP Temperature Switches Defeated by Bypass Jumper for SWP*P3A18 SPO(1) 05/31/97 06/20/97 (Booster Pumps) eel 96-201-23. LER **6-005-01. LER 96-005-00, ACR 10795 24.1 URI 96-01-08 Overlap Testing of RPS/ESF SPO(1) 05/31/97 06/21/97 LER 97-017-00. URI 96-01-08

- . . . .~... .

63.1 ACR M3-96-0396 3 MSS *MOV17D Missed IST Surveillance Requirement DRP 05/31/97 06/20/97

- . . - . . ~ . . . . . . . . . . . . . . ~ . . - .

59.3 ACR M3-96-0846 Use of Borafles in SFP Racks SPO(L) 05/31/97 06/20/97 ACR 09124. ACR M3-96-0846, ACR M3-96-0775 LER 96-033-00 3

t TBD = No Action Required F' rom NU. NRC To Determine When Review To Be Completed. ,

6 !

6

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Besponsible ACfLBeedrJnr_ tot NRC.

Z90eL@hE,6Uhl. OtSctlptl9ttofJf8C_ Item _NRQ EP_ftylen NRCJgylew Status 74.1 URI 96 08-18 ISI/IST Program Control DRS 05/31/97 OW20/97 URI 96-08-18. LER 96421-00 74.3 LER 96-021-01 ISI/IST Program Control DRS 05/31/97 - 06/20/97 URI 9648-18, LER 96-021-00 74 2 LER 96-021-00 ISI/IST Program Control DRS 05/31/97 OGTO97 L URI 96-08-18, LER 96-021-00 ;

73.2 IFI 96-06-17 Review OA Program for Adequacy and improvement NRR 05/31/97 06/2097 NOV 96-05-12, IFI 96-06-17 OSTI 57.1 ACR M3-96-0080 Potential Electrical Separation V'FJlations DRS 0512/97 06/02/97 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 M3-96-0080 57.8 LER 96-015-03 Potential Electrical Separation Violations DRS 06/02/97 06/21/97 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 M3-96-0080 70.14 LER 96-002-00 Review TRM for Technical Specifications interpretations, Evaluate T.S. DRS 06/02/97 OG73,97

and Opar. 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 5.2 NOV 94-24-01 Failure to Enter an Acton Statement When MSIVs Were Closed SPO (1) 06/02197 06/21/97 ,

VIO 94-24-01, ACR 01844 i 73.1 NOV 96-05-12 Review OA Program for Adequacy and improvement NRR 06/02/97 06/21/97 NOV 96-05-12,IFI 9646-17 OST1

. . . ~ . --

26.15 LER 96-019-01 Motor Operated 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 96419-00, LER 96420-00 LER 96-035-00, URI 95-17-09. IFl 95-01-01, IFI 95-17-01 IFl 95-17-02, IFI 95-17-03. IFl 9517-04, IFl 95-17-05 TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.

7 4

Sctwduledpeet. EstimetetDete_. .

Desponsilde ACRBeadylot foL 28BC.

ZenstDocumentN9. Descriptio!L9f_tfRC_ftem _fmG EP Review tRC_Reflew Status 83.1 Letter B16195 Effectiveness of Emergency Response Organization Coordriation with DRS 0603/97 06/23,97 Offsite EP Officials; Dose Assessment Capability IFl 95-36 Of

. . . . . ~ . . ~.

85.4 ACR M3-96-1078 Other RSS and Related Design Basis Concems DRS 06/03/97 06/2397 ACF, M3-9644%, ACR M3-964497, ACR M3-964620, ACR M3-96-1078. NRR ACR M3-97-0039, ACR M3-97-0128 ACR M3-97-0409, LER 97-003 00, LER 97-015-00 LER 97-021-00 37.5 eel 96-201 26 Review Licensee Corrective Action Programs for Effectiveness to include SPO(I) 06/03/97 0673/97 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

~~ . - ~ . .~

84.1 eel 96-05-15 Secunty issues . Corrective Action and Review DRS 06/03/97 06/23/97 eel 96-05-15. eel 97-03-01 eel 97-03-02, eel 97 03-03, U1 VIO 96-09-20

.. . _- ~

61.1 ACR 7923 (U2) EEQ Process DRS 06/03/97 06/23/97

. ...... . - - . . . . . . . ~. .-- .~.

85.1 ACR M3-96-0496 Other RSS and Related Design Basis Concems DRS 06/03/97 06/23/97 ACR M3-96-0496, ACR M3-96-0497, ACR M3-96-0620, ACR M3-96-1078 NRR ACR M3-97-0039, ACR M3-97-0128, ACR M3-97-0409 LER 97-003-00 LER 97-015-00. LER 97-021-00 33.3 ACR M3-96-0563 Seismic 11/l DRS 06/03/97 06'23/97 IR 96-201, G.2, IFl 97-01-xx LER 96-003-00, ACR M3-96-0563, CR M3 0850 37R eel 96-201-21 Review Licensee Corrective Action Programs for Effectiveness to includo SPO(I) 06/03/97 06/23/97 ACRs and NCRs eel 96-201-13, eel 96-201-21, EEI 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

. . . . . . . . ~.~ .- . . . ~ ~ . . . -

81.3 LER 96 432-00 Testing of Safety Systems DRS 06/03/97 06/23/97 eel 96-201-32 eel 96-201-34 LER 96-032-00 34.1 NOV 96-09-18 Effluent /E e-Jai Sampreng and Analytical Proficiency DRS 06/03/97 06/2397 NOV 96-09-18, NRC Inspection Moduel B4750

. ~ .. . . - ~ . . . . . . . - . . .

TDD = No Action Required From NU. NRC To Deterrmne When Review To Be Completed.

8 ;

l

\ '

Scheduled _Dett. Estimated _Dete_

Bisponsibin ACRBeedy fot. f9L fE--

genorpocumentL*t. De.scIlptfortotNRC_ Item _NRQ EP_Beview NRCBqvign S.tatus 13.3 URI 96-08-20 CCP System Operation Above Design Temperature: 3 RHS*HCV 606/607 SPO(1) t@03/97 06/23/97 Failing Open and Other Fafure Modes ACR 13427, URI 96-08-20, IR 96-201, M3-96-0326 LER 96-028-00. LER 96-040-00 18.1 ACR 10562 Control and Use of Vendor Information DRS 06/07/97 06/27/97 eel 96-201-15, eel 96-201-18. eel 96-201-19, URI 96-201-17, G 2

- ~ . ~.~ - m .~.~ -

36.1 None Associated Heat Exchanger Performance (GL 89-13) DRS 06/1G17 07/01/,7 s m .

26 D URI 95-17-09 Motor Operated Vatve Progmm GL 89-10 DRS 06/1697 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 95-17-09, IFl 95-01-01, IFl 95-17-01, IFl 95-17-02, IFI 95-17-03, IFI 95-17-04, IFl 95-17-05

- - - -- -~~ . .-

. . . . . . . .~.

25 2 URI 95-07-10 Material Equipment and Parts List (MEPL) Program Evaluation DRS 06/16/97 07/07/97 ,

URI 95-07-10. eel 96-201-43, ACR M3-96-0912 NRR

- ~ . . ... .

25.3 EEI 96-201-43 Material Equipment and Parts List (MEPL) Program Evaluation NRR 06/19/97 07/10/97 URI 95-0710 eel 96-201-43, ACR M3-96-0912 DRS .

3.1 ACR 05715 Reactor Power increase When Unborated Cation Demin Placed into DRP 06/19/97 07/11/97 Service 3CHS-DEMIN2 ,

t 70.9 LER 96-051-00 Review TRM for Technical Specifications interpreta' ions. Evaluate T.S. DRS 06/20/97 07/07/97 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 ,

75 2 IFl 96-09-17 TIA issues (EDG Exhaust and Required # of Service Water Pumps) NRR 06/20/97 07/11/97 IFl 96-08-15, IFI 96-09-17 ,

79 2 eel 96-201-35 Design Control Process Review (Part of Phase I of the ICAVP) SPO(O) 06/21/97 07/12/97 eel 96-201-09. EEI 96-201-35. eel 96-201-37. eel-96-201-39 -. - . ~ -

1 i

D = No Action Required From NU. NRC To Determine When Review To Be Completed.

9 ,

SCf!tduled_Date. Estimated _ppte._ -

ACILReady fot. for_ NRC_ i Beshonsibh

' Z9fte/pocumeAN% Descriptl9npf_NflC_ Item .NflC EP Review NRC_.B,vign Status 79.3 eel 96-201-37 Design Control Prucess Review (Part of Phase 1 of the ICAVP) SPO(O) 06/21/97 07/12/97 eel 96-201-09. EEI 96-201-35. eel 96-201-37. eel-96-201-39 79.4 eel 96-201-39 Design Control Process Review (Part of Phase I of the ICAVP) SFO(O) 06'21/97 07/12/97 eel 96-201-09. EEI 96-201-35. eel 96-201-37. eel-96-201-39 182 eel 96-201-15 Control and Use of Vendor information DRS 06'21/97 07/12/97 eel 96-201-15. eel 96-201-18. eel 96-201-19. URI 96-201-17. G 2 46.1 ACR M3-96-0183 Low Pressure Safety injection Penetrations SPO(I) 06/23/97 07/12/97

~ - - . - - -

.............. . -_ . -. .~ .~ .

33.4 ACR M3-97-0850 Seistnic II/I DRS 06/24/97 07/15/97 IR 96-201 G.2. IFI 97-01-xx. LER 96-003-00, ACR M3-96-0563. CR M3 0850 10.1 URf 96 201 16 Resolution of AFW Valves HELB Concem SPO(f) 06f24/97 07/1697 58.3 eel 96-201-33 Thermal Relief Valve Setpoints SPO(f) 06/30/97 07/22/97 ACR M3-96-0685. eel 96-201-33. ACR M3-96-0557

. _ . . . ~ . _ . _

81.1 eel 96-201-32 Testing cf Safety Systems DRS 06/30/97 07/22/97 (

eel 96-201-32. eel 96-201-34 t 12 eel 96-06-13 RSS and OSS Peping Temperature May Be Higher Than Anatyzed (NRR NRR 06/30/97 07/21/97 Review Engineering Analysis. DRS Inspect Installation) DRS ,

ACR 10773. eel 96-06-13. LER 96-007-01. LER 96-007-02 52.4 eel 96-201-23 SWP Temperature Swrtches Defeated by Bypass Jumper for SWP*P3A1B SPO(1) 06/30/97 07/22/97 (Booster Pumps) ,

eel 96-20123. LER 96-005-01. LER 96-005-00. ACR 10795 -... -

52.1 ACR 10795 SWP Temperature Switches Defeated by Bypass Jumper for SWP*P3A1B SPO(1) 06/30/97 07/22/97 l (Booster Pumps) eel 96-201-23, LER 96-005-01. LER 96-005-00. ACR 10795 ,

-- . . 1 TBD = No Action Recurred From NU. NRC To Determine When Review To Be Completed.

f0

e Scheduled.fpit_ EstimetetlJete_, .

Desponsible ACB_Readyjor. fot, NRC.

ZefWD9cumenLNo, pe#Stiption_plNBCJtem .NRC EP_f!tvkw fmC fteview Status 0.1 ACR 10543 Need for Additional Review of Response Time Testing for Procedures SPOO) 07/01/97 07/22/97 33.1 IFl 97-01-07 Seismic fill DRS 07/01/97 07/22/97 IR 96-201, G 2. IFl 97-0107. LER 96-003-00, ACR M3-96-0563. CR M3-97-0850 18.3 eel 96-201-18 Control end Use of Vendor Informaton DRS 07/01/97 07/22/97 eel 96-201-15. EEI 96-201-18. eel 9&201-19. URI 96-201-17 G 2 37.7 eel 96-201-28 Review Licensee Corrective Action Programs for Effe 6% to include SPO(l) 07/01/97 07/23/97 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

. -. . . ~ ~ ~ . . - ~ . . . . ~

50.1 ACR M3-96-0446 Documentation of Cw 6.e-4 Systems Diww as DRS 07/01/97 07/2397

.- ~ . - - ~ ...... .~. ~.

13.6 LER 96-040-00 CCP System Operaton Above Desgn Temperature: 3 RHS*HCV 606/607 SPO(1) 07/01/97 07/22/97 Failing Open and Other Failure Modes ACR 13427, URI 96-08-20,IR 96-201, M3-96-0326, LER 96-02840, LER 96-040-00 26.14 IFl 95-17-05 Motor Operated Vahre Program GL 89-10 DRS 07/02/97 07/23/97 ACR M3-96-0277. ACR M3-96-0278, M3-96-0627.12862. LER 96-01940 LER 96-020-00 LER 96-035-00, URI 95-17-09, IFl 95-01-01. IFl 95-17-01 IFl 95-17-02. IFl 95-17-03, IFl 95-17-04. IFl 95-17-05

. - . ~ . . . . -~

67.2 URI 96-201-14 SBO Possible Overload in Event of an SIS Actuation and Design issues SPO 07/02/97 07/23/97 TAC No. M96054. URI 96-201-14 ACR M3-96-0621 70 11 LER 97-007-00 Review TRM for Technical SpecificaMons Interpretations. Evaluate T.S. DRS 07/02/97 07/23/97 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, 96-04 B-00,96-051 -00. 97-004-00, 97-007-00, 97-018-00, 97-019--

00, CAL 1-97-010 26.10 IFI 95-17-01 Motor Operated Vaive Program GL 89-10 DRS 07/02/97 07/2397 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 95-17-09, IFl 95-01-01, IF195-17-01, IFl 95-17-02. IFl 95-17-03, IFl 95-17-04, IFl 95-17-05 TBD = No Action Required From NU. NRC To Determne When Review To Be Completed.

91 4

_ _ _ _ . _ _ _ _ . _ . . _ - . . _ . _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ . _ . _ . . . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __._________________m

SC!MduledDett. Estimpted.Dete_

BesponsitHe ACB ReedrJot. tor _ NRC_

ZoMIDecumte!1.M9, pescriptforto!J4RC_ Item .NRQ i EP_Httty N!iCJltylgw Sistus 26.11 IFI 95-17-02 Motor Operated Valve Prog am GL 89-10 DRS 07/02/97 07/23/97 ACR M3-9&O277, ACR M3-96-0278, M3-96-0627,12862. LER 96-01940 LER 96 020-00, LER 96-035-00, Unl 95-17-09, IFl 95-01-01. IFl 95-17-01, IFl 95-17-02. IFl 95-17-03, IFl 95-17-04. IFl 95-17-05 26.12 IFI 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 95-17-09. IFl 95-01-01, IFl 95-17-01, IFI 95-17-02. IFl 95-17-03, IFI 95-17-04, IFl 95-17-05 26.13 IFl 95-17-04 Motrer Operated Valve Program GL 89-10 DRS 07/02/97 07/2T97 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 95-17-09, IFI 95-01-01. IFl 95-17-01, IFl 5 5-17-02. IFI 95-17-03, IFl 95-17-04, IFl 95-17-05 70.7 LER 96-048-00 Reidew TRM for Tectuwcal Specifications interpretations. Evaluate T.S- DRS 07/02/97 07/23/97 t,id 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 e 57.5 LER 94 049-00 Potential Electrical Separation Violations DRS 07/02/97 07/23/97 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 M3-96-0080 i

20.1 VIO 96-59-13 Review Output from Hanno#s Employee Concems Report SPO(L) 07/02/97 07/23/97 VIO 96-59-13 60.2 ACR M3-96-0821 Analysis of SOV Failure Modes Due To MOPD SPO(t) 07/02/97 07/23/97 ACR M3-96-0821. eel 96-09-16 ACR M3-96-0718 26.9 IFl 95-01-01 Motor Operated Vatve Program GL 89-10 DRS 07/07/97 07/26/97 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 95-17-09, IFI 95-01-01, IFl 95-17-01, IFl 95-17-02. IFl 95-17-03, IFl 95-17-04. IFl 95-17-05 57.6 LER 96-015-01 Potential Electrical Separation Violations DRS 07/08/97 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 M3-96-0080 57.7 LER 96-015-02 Potential Electrical Separation V' o tatens DRS 07/08/97 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 M3-96-0080 6

TBD = No Action Required From NU. NRC To Determine When Review To De Completed.

f2 r t

o Scfmfu. led _ Data. Estimated patt_ .

Responsible ACILReady_fot 19L fMC_

Zo0e/Docume0LNo. Description of NRC_ftem .NBC EP_Btylgg fmC Rttlew S18N1 57.3 LER 96-015-00 Potential Electrical Separation Violations DRS 07A)8/97 07/28/97 ACR M3-96-0081. LER DG-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 51.1 ACR M3-96-0339 Wa! worth Valve Yoke Generic issue DRS 07/10S 7 07/30/97 ACR M3-96-0389, ACR M3-96-0339

. . . . . . . . . . _ - . . ~ . . . -.. -- ..

51.2 ACR M3-96-0389 Walworth Valve Yoke Genenc issue DRS 07/10/97 07/30/97 ACR M3-96-0389, ACR M3 96-0339 85.3 ACR M3-96-0620 Other RSS and Related Design Basis Concems DRS 07/10/97 07/30/97 ACR M3-96-0496. ACR M3-96-0497. ACR M3-96-0620, ACR M3-96-1078 NRR ACR M3-97-0039. ACR M3-97-0128, ACR M3-97-0409 LER 97403-00.

LER 97-015-00. LER 97-021-00 45.4 LER 96-029 40 Initial Settings for ECCS Throttle Vatves inadequate and Potential Cloggmg SPO(l) 07/10/97 07/30S7 ACR 08897. ACR M3-96-0524 URI 96-06-14, LER 96-029-00. LER 96- ,

039-00 58 2 ACR M3-96-0685 Thermal Relief Valve Setpoints SPO(l) 07/11/97 07/31/97 ACR M3-96-0685 eel 96-201-33, ACR M3-96-0557 !

I 53 4 ACR M3-97-0727 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/14/97 07/30/97 l URI 96-09-11 LER 96-025-00 ACR M3-96-0449. M3-97-1007 M3-97-0727 NRR i

53.1 ACA M3-96-0449 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/14/97 08/02/97 URI 96-09-11. LER 96-025-00, ACR M3-96-0449, M3-97-1007, M3-97-0727 NRR r 53.5 ACR M3-97-1007 Pieces of ARCOR Found in 3RSS*E1 A and 3RCC*E1C SPO 07/14/97 07/3097 I URI 96-09-11, LER 96-025-00, ACR M3-96-0449, M3-97-1007. M3-97-0727 NRR

._ . -. ~. . . . .

45.5 LER 96-039 4 0 Initial Settings for ECCS Throttle Valves inadequate and Potential Clogging SPO(t) 07/15/97 08/05/97 i ACR 08897, ACR M3-96-0524. URI 96-06-14. LER 96429-00. LER 96- [

039-00 ;

I-i i

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TBD = No Action Required From NO. NRC To Determine When Review To De Completed.

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290WDocumenLNo. pgs;ttptigr uo!.NBC ltem _NRC EP_Beview HBC Beview status 11.4 eel 96-201-05 Turbine Driven Auxiflary Feedwater Design Concems SPO(t) 07/16'97 08/05/97 ACR 10780, ACR 10774. NU Letter B15397. URI 96-201-40. EE196-201

04. eel 96-201-05 78.3 EEt 96-201-06 Safety Analysis (50.59) Process SPO(L) 07/16/97 08/05G7 URI 93 07-07, eel 96-201 -02, eel 96-201-06. EEI 96-201-07, eel 96-201-08 78.5 eel 96-201-08 Safety Analysis (50.59) Process SPO(L) 07/1697 08MSM7 URI 93-07-07, eel 96-201-02, eel 96-201-06 eel 96-201-07. eel 96-201-08 37.6 EEI 96-211-27 Review Licensee Corrective Action Programs for Eftectiveness to include SPO(1) 07/16S 7 08/05/97 ACRs & NCRs eel 96-201-13. eel 96-201-21. eel 94201-22. eel 96-201-24. eel 96-201-

26. eel 96-201-27, eel 96-201-28. eel 96-201-29, IR 9604 811 eel 96-201-10 Quality Assurance Records bPO(t) 07/17/97 08/06/97

. . .. . ...... ~

37.8 eel 96-201-29 Review Licensee Corrective Action Programs for Effectiveness to include SPO(l) 07/17/97 08/06/97 ACRs and NCRs eel 96-201-13. eel 96-201-21. eel 96-201 22. EEI 96-201-24. eel 96-201-

20. EEI 96-201 27. eel 96-201-28. eel 96-201-29, IR 96-04 70.3 LER 96-037-00 Review TRM for Tectwveal Specifications Interpretations, Evaluate T.S. DRS 07/18/97 08/07/97 )

and Oper. License *lssues URI 9648-16, 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

. . . . . - . . . . ......~ .

45.1 ACR M3-96-0524 initial Settings for ECCS Throttle Valves inadequate and Potential Clogging SPO(l) 07/19/97 08/08/97 )

l ACR 03897. ACR M3-96-0524. URI 96-06-14 LER 96-029-00, LER 96-l 039-00 )

. . . . . . . . . . . .- i l

45.2 ACR 08897 Initial Settings for ECCS Throttle Valves inadequate and Potential Clogging SPO(I) 07/19/97 08/08/97 ACR 08897 ACR M3-96-0524, URI 96-06-1d, LER 96-029-00. LER 96-039-00

. . . . . . . . . . . . . . . . . ........... . . . . . . . .~. -

39.1 None Associated Review Engineenng BacMogs DRS 07/21/97 08/11/97 TBD = No Action Required From NU. NRC To Detemine When Review To Be Completed.

15 I

Scheduled Dett. E_s_timatedDatt .

Bewonsible ACRBeedrJ9t. tot. tMC.

Zone h muvnNo. Description _off4RC. Item .NRC EP_Bevkor imCBeview status 41 2 URI 95-81-01 Review Self Assessment Root Causas and Verify Corrective Actions 07/21/97 08/09/97 SPO(l)

(IP40500)

ACR 7007. URI 95-81-01, VIO 96-09-04 37.3 eel 96-201-22 Review Licensse Corrective Action Programs for Effectiveness to include SPO(t) 07/21/97 08/11/97 ACRs and NCRs eel 96-201-13. eel 96-201-21, eel 96 201-22. eel 96-201-24, eel 96-201-

26. EEI 96-201-27. eel 96-20128 eel 96-201-29, IR 96-04 78.2 eel 96-201-02 Safety Analysis (50.59) Process SPO(l) 07/21/97 08/09/97 URI 93-07-07. eel 96-201-02. eel 96-201-06, eel 96-201-07, eel 96-201-08 i

84 2 eel 97-03-01 Security issues - Corrective Action and Review DRS 07/2397 08/12/97 eel 96-05-15. eel 97-03-01. eel 97-03-02, EEI 97-03-03, U1 VIO 96-09-20 1.1 ACH 10773 RSS and OSS Piping Temperature May Be Higher Than Anatyred (NRR NRR 07/23/97 08/12/97 Review Eiy;+,;,y Analysis. DRS Inspect "nstallation) DRS ACR 10773. eel 96-06-13. LER 96-007-01, LER 96-007-02 84.4 eel 97-03-03 Security issues - Corrective Action and Review DRS 07/23/97 08/12/97 eel 96-05-15. eel 97-03-01, eel 97-03-02 eel 97-0343. U1 VtO 9649-23 84.3 EE! 97-0342 Security issues - Corrective 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 11.6 Letter 015397 Turbine Driven Auxitary Feedwater Design Concems SPO(1) 07/23/97 08/12/97 ACR 10780, ACR 10774. NU Letter B15397. URI 96-201-40. eel 96-201-04 eel 96-201-05 53.2 URI 9649-11 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. M3-97-1007, M3-97-0727 NRR !

J l

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 13.4 LER 96-028-00 CCP System Oparation Above Design Temperature: 3 RHS*HCV 606/607 SPO(l) 07/24,97 08/13/97 Faiing 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 TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.

16

ScheduledEste_ EstJl neted_Dete_ .

Besponsib_lg ACR_Beadylor . _

(pr_ NRC_

Zone!D9cumenWo. Descriptiottof_NBC3em EBQ EP_ Rey _lew NBC.Beview Status 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, M3-97-1097, M3-97-0727 NRR 611 None Associated Review All Operability Determinations and By-pass Jumpers Before Restart SPO 07/2d/97 08/12/97

. . . . . . . . . . . . . . . . . . . ..... . . . -- . ~~

I ACR 13.1 M3-96-0326 CCP System Operation Above Design Temperature: 3 RHS*HCV 606/607 SPO(l) 07/24/97 08/13/97 Failing Open and Other Failure Modes !

ACR 13427. URI 96-08-20 tR 96-201, M3-96-0326, LER 96-028-00 LER 96-040 00 12.1 ACR 06323 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 I

. . . . . . . . . . . . . . . . . . . . . . . - . _ - ..~... ~ . . . . .~ - ~ . . ...

41.3 NOV 96-09-04 (U1) Review Self Assessment Root Causes and Verify Corrective Actions SPO(l) 07/24/97 08/1397 (IP40500)

ACR 7007. URI 95-81-01, VIO 96-09-04

. .. . .. . . t 65 2 ACR M3-97-0742 SIL/StH Vatves Powered From Nonsafety Train SPO 07/25/97 08/13/97 i LER 96-036-00. ACR M3-97-0742, ACR M3-96-0745 NRR f

. . . . . . . . . . . . . . . . . . . . . . . . ~ . . . ~ . . ~ . . ~ . . . ~ - . . . . ..... ~.-.

[

85.10 LER 97-021-00 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 M3-96-1078, NRR ACR M3-97-0039, ACR M3-97-0128. ACR M3-97-0409, LER 97-0034)0, I LER 97-015-00, LER 97-021-00 65.1 ACR M3-96-0745 SIL/StH Vatves Powered From Nonsafety Train SPO 07/25/97 08/t3/97 LER 96-036-00 ACR M3-97-0742, ACR M3-96-0745 NRR 85.6 ACR M3-97-0128 Other RSS and Related Design Basis Concems DRS 07/25/97 08/1397 ACR M3-96-0496, ACR M3-96-0497. ACR M3-96-0620 ACR M3-96-1078 NRR ,

ACR M3-97-0039, ACR M3-97-0128, ACR M3-97-0409 LER 97-003-00, ,

LER 97-015-00. LER 97-021-00 31.1 PPR G.1.C, G 2 Resident Emphasis: Work-Aroumis and Abuse of Use-As-Is Deficiencies SPO(1) 07/25/97 08/09/97 3

b TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.

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BesponsMe ACB_Beedy for fot. NRC_ ,

ZonolpecymentNo. DesctlptiorloLNBC ltem _NBC EP_Beries fMC. Bey!tM StaNs 66.1 ACR M3-96-0483 CCP and CCE Non-Q Components Cause O-Conyv u Not To Fail Safe SPO(1) 07/28/97 08/1397

. . ~ . . ;

26 6 LER 96-020-00 Motor Operated Valve Program GL 89-10 DRS 08M1/97 0811397 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 95-17-09, IFl 95-01-01, IFl 95-17-01, IFl 95-17-02. IFl 95-17-03, IFl 95-17-04, IFl 95-17-05 26.2 ACR M3-96-0278 . Motor Operated Valve Program GL 89-10 DRS 08M1/97 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, URt 95-17 09, IFl 95-01-01, IFl 95-17-01, !

IFl 95-17-02, IFl 95-17-03, IFl 95-17-04, IFl 95-17-05

. . . . . .. . . . . . . . . .- i 55.1 ACR M3-96-0467 Fast Transfer Test Failures DRS 08/01/97 08/13/97 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, LER 96-019-00, LER 96-020-00. LER 96-035-00, URI 95-17-09, IFl 95-01-01, IFl 95-17-01, IFl 95-17-02, IFl 95-17-03, IFl 95-17-04, IFl 95-17-05 .

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 96-02tMO, 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 95-17-04, IFl 95-17-05 26.7 LER 96-035-00 Motor Operated Valve Program GL 8910 DRS 09/06/97 09/27/97 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 95-17-09. IFl 95-01-01, IR 95-17-01, I IFl 95-17-02. IFI 95-17-03, IFl 95-1744, IFl 95-17-05 70.5 LER 96-042-00 Review TRM for Technical Specifications Interpretations. Evaluate T.S. DRS 09/22/97 09/30ial 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 -

17.1 ACR 07266 RCP Seal Housing Leakage and Bolt Corrosion DRS 09/23/97 09/30/97 I TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.

20

Scheduledppte, EstimatedEste .

Responsible ACfLReedy_ tot. fot. NB4-ZoneGocumenLN4 DesCIlptfortpf NBCltem flRC EP_Beview NRCRtylew Status 01.2 eel 96-201-34 Testing of Safety Systems DRS 09/30/97 09/30/97 eel 96-201-32. eel 96-201-34 ...

35.1 None Associated Radwaste Systems /Controts DRS N/A 06/21/97 NRC Inspection Module 86750 Ready For In%uvn 42.1 None Associated Fire Protectum Program DRS N/A 08/05/97, NRC Inspection Module 64704 Ready For Inspection 29.1 PPR G.1.C Resident Emphasis: Feedwater Harnrner DRS N/A Complete Closed IR 96-01 21.1 None Associated Fatigue Cycle Open items IP 37750 DRS N/A Complete Closed IR 96-01 (Unit 2 issue) . - . . . . - . . . . . . . . . . . .. - . . . .

22.1 None Associated Part 70 Storage and inventory IP 84750 DRS N/A Complete Closed IR 96-05 (Unit 1 Issue) . . . . . . . .

23.1 None Associated Formality of Non-Routine Security Activities and New Fuel Security IP DRS N/A Complete Closed IR 96-05 81064 ....

23.1 PPR G.1.C Resident Emphasis: Dilution Events SPO(1) N/A Complete Closed IR 96-08 27.1 PPR G.1.C. G.2 Resident Emphasis: Missed Surveillances/ Test Control SPO(1) N/A Complete Closed IR 96-08 43.1 Order ICAVP Phase 11 of the ICAVP SPO(O) N/A TBD No Action Required From NU 72.1 None Associated Review Enforcement and Unresolved items for Restart issues SPO(1) N/A TBD No Response Required from NU TBD = No Action Required From NU. NRC To Determine When Review To Be Completed.

2f

SchedviedJhde. EstimeledDett_ .

ELesponsibit AGRBeedylot fot ffRC-Zens/DocumentMo. DescLiption_plNRCJtern _tfBC EP_Revitw i - f#LC_Rtriew Status 68.1 None Associated Review Aftegations for Restart issues SPO N/A TBD No Resportse Required From NU 71.1 None Associated Review Licensee Event Reports for Restart issues SPO(!) N/A TBD No Response .

Required from NU

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5 TDD = No Action Required From NU. NRC To Determine When Review To De Completed. ;

22

l REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP siss/s7

.l !

NRC No. TAC No. D2 D133 TS/ OPS SNSHC All Sianed E2BG NEAB hLR.& ,

1 M94105 11 i Descriotion .

This PTSCR modifees applicabiltty and actions associated with Steam Generator Blowdown Monitor. Modifies applicability for Condensate Polishing Facility Waste Neut Sump.

License Lead: Paul Russell Technical Lead:

I NFC No. TAC No. D2 Du3 TSIOPS SASH _Q Att filaned PORC NSAB hlBE

~2 M97746 25 Description This PTSCR (2-5-97) supersedes PTSCR 21 97. It proposes to modify the minimum instrument accuracy in Table 3.3-8 for the Met Tower instrumentation. l License Lead: Paul Russell Technical Lead:

NRC No. TAC No. 112 Drag TSIOPS SNSHC All Sioned ECLEG NEAR NBg 3 M97741 26 I Description This 'PTSCR provides changes regarding the orgatational structure and titles. Approved by NRC on 4/10/97.

License Lead: Bob Walpole Technical Lead:

NRC No. TAC No. D2 Drag IS] OPS SNSHC Aff Sianed EQBG NSAB NBG 4 14 Description i

This change will eliminate the reference to the measurement location for the Ultimate Heat Sink in TS 3.7.11. An NRC committment per LER B16115 exists to submitted the PTSCR by 3/31/97.

License Lead: Paul Russell Technical Lead: Mike Dain l l

BG.N9 TAC No. If.2 Dran TS' OPS SNSHC ' All Sianed E282 NEAR NEG 5 15 Description This PTSCR would eliminate the requirement to enter LCO 3.0.3 when the enclosure building is breached, due to making both trains of the enclosure building ventilation system inoperable (unable to create vacuum within specifed time period)

License Lead: Paul Russel! Technical Lead: Mike Bain I

NRC No. TAC No. 112 prg3 TSIOPS SAfSHC AII Sioned EQBQ NEAR NRQ 6 M94623 16 5/1&S7 Description l

, This PTSCR redefines containment integnty to permit operator action dunng periods when containment isolation valves may be j l opened under admin controls. Also relocates the list of containment isolation valves from TS to the TRM. The current PTSCR i

' needs to be modified to add a discussion of administrative controls to the bases. i License Lead: Paul Russell Technical Lead: Rick Bonner Page 1 of 3 i

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REQUIRED LICENSE AMENDMENTS FOR MP2 STAF TUP siis/s7 NRC No. IAM ISD DM TS' OPS SA/SHC AllSioned PORC NSAB NEQ 7 18 5/19/97 5/23/97 5/30/97 6/6/97 6/11/97 6/19S7 6/27/97 Description Tt.:. ITSCR modifies the b;;:es M resolve the EDG fuel oil storage capacity issue.

Ucense Lead: Paul Russell Technical Lead: Paul Wagner NRC Nm TAC No. 119 DgLf1 TS/ OPS SWSHC All Sioned EQEQ RSAB NEQ 8 104 5/19/97 5/23S7 5/30S 7 6/497 6/12S7 6/20/97 Description Errors in the RCS Pressure / Temperature Curves. Will require a change to the Tech Spec P-T curves. Amend.151 removed wording that 3 0.4 is not applicable from the PZR PORV TS. Need to add 3.0 4 exception. LTOP setpoint needs to be changed.

Ucense Lead: Paul Russell Technical Lead: Nelson Azevedo NRC No. TAC No. 119 DnB TSIOPS SA/SHC All Stoned E93Q $$AQ NEQ 9 68 5/19/97 5/23/97 5/30/97 6/ 6/97 6/11/97 6/19/97 6/27/97 Deseriotion TS 3.4.1.3 Action could require Mode 5 witn no SDC loops operable.

Ucense Lead: Hal Young Technical Lead: Rick Bonner NRC No. TAC No. Il2 DM TS' OPS SA!sHC All Stoned PORC NSAB NEQ 10 M92879 12 i

Description )

This PTSCR revises severa! surveillance requirements regarding Control Room Emergency Ventilation System.

Ucense Lead: Paul Russell Technical Lead:

NRC No. TAC No. 119 DM TSIOPS SNSHQ AllSioned PORC NSAB NEQ l 11 150 5/15S7 5/19S7 5/28/97 6/2/97 6/12/97 6/2W97 Description RPS and ESAS tnp action statements a!!ow indefinite bypass of an inoperable channel This will be changed to allow only 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before placing channelin the inpped condition.

License Lead: Paul Russell Technical Lead:

NRQ N9, TAC No. 119 Drift TStOPS SNSHC All Sioned EQEQ NSAB NHQ 12 148 5/30/97 6/ 3/97 6/ 6S7 6/12/97 6/16S7 6/19S7 6/30/97 Descriptio3 Certain RPS and ESAS inps did not consider the uncertainity associated with a Harsh environment. Some RPS and ESAS setpoints were based on 24 rnonths instead of 18 months.

Ucense Lead: Paul Russell Technical Lead: Mike Kai Page 2 of 3

REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP sli m 7 NRC No. TAC No. 11Q QtLf1 ISLQP1 SA'SHC All Sioned PORC NSAB NEG 13 82 5/30/97 6/3/97 6/6/97 6/12/97 6/16/97 6/19/97 6/30/97 QLscription Reactor trip setpoints for SG safety valves in Table 3.7-1 based on 107% power instead of 106.6%, so nonconserviaive.

License Lead: Paul Russell Technical Lead: Josh Spalter NRC No. TAC No. lig pra_ft TSIOPS SA/SHC Aff Sioned EQE2 NSAB NBG 14 155 5/19S7 5/23S7 5/30/97 6/ GS7 6/11/97 6/19S7 6f27/97 Descriotion Verbatim compliance issues. ECCS throttle valves. AFW sury.

j t.icente Lead: Paul Russell Technical Lead: '

I NRC No. TAC No. Ifg Qtaft TSIOPS SA/SHC AllSianed PORC NSAR NBq f 15 1 5/16/97 5/21/97 5/30/97 6/2/97 6/12/97 6/20/97 Descriotion This PTSCR deletes TS 3/4 9.14 and Table 3.9-1, modifes LCO 3.9.15 to require two EBFS trains to be operable and adds the requirement to have at least one train in operation wtienever fuel movement or crane operation is in progress, adds a requirement regarding spent fuel pool area ventilation integnty, changes the associated actions requirements, changes the surveillance requirements, and the bases. This change removes the requirement for the " blue lights."

License Lead: Paul Russell Technical Lead: Mike Bain i

l NRC No. TAC No. Igg Drafi TSIOPS SA'SHC AllSioned EQEG NEAR N82 l 16 67 5/30/97 6/697 6/11/97 6/19S7 6/27/97 l l

Description l

Need to add 2 second time celay to ESFAS Table 3.3-4 6a to be consistent with 8b and ITS. I License Lead: Hat Young Technical Lead: Rich Ewing NSQJa IAQ No I}_g Qraj T$10PS SA/SHC All Signep EQBq NSAB NSg 17 153 5/30 S 7 6/ 6S7 6/11/97 6/16S7 6/1BS7 & 26/97 6/30S 7 Description LTOP setpoints need to be changed.

License Lead: Paul Russell Technical Lead: Nelson Azevedo 17 TOTAL ISSUES i

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Proposed Technical Specification Chanae Request Schedule !

(data as of 5/20/97)-

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1. Appendix G Curves _ 6/15/97

2. AFW Valve Position 6/15/97 !

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.c , 3. RSS Testing 5/31/97

4. DCR 96065 USQ 7/1/97 !

5. DWST Level 6/9/97

6. Containment Isolation Valves 6/15/97

7. Table 2.2-1 Math Notations -5/31/97 )

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8. Containment Airlock Math Notations 5/31/97

9. MSIV Full Stroke Testing - 7/1/97 l

l 10. Main Steam Pressure Relief Bypass Valves 6/15/97 11.RCS Loops / Mode 4 Surveillance 6/15/97 j l- 12. Rec 4rc Spray TBD 1

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NU RESTART SUCCESS CRITERIA ICAVP READINESS Success Criterion Measurements of Effectiveness

1) Audit Plan finalized 1) NRC approval !

2) Discovery phase complete 2) KPis (Line and Oversight) i for 50% of safety and risk significant Self and independent systems and associated assessments (Line and Engineering programs Oversight concurrence) l i

3) ICAVP Contractor and 3) Management expectations I NRC Inspection support communicated in place Support Team resources in place

]

Station personnel awareness l

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NU RESTART SUCCESS CRITERIA (CONTINUED)

PHYSICAL PLANT READINESS l Success Criterion Measurements of Effectiveness l

l 1) Systems functional Applicable to All Criterion KPis (Line and Oversight)

2) Satisfactory pre-startup test results Self and independent i assessments (Line and

3) Adequacy of system Oversight concurrence) line ups

! Station programs ready

! 4) Restart hardware issues to support restart resolved (including SIL)

Integrated site schedule in

5) Maintenance backlog managed place and impact on operation assessed Adequate staffing in place Startup and power ascension

6) Restart related ICAVP issues i program in place dispositioned

7) Adequate plant materiel condition

8) Operator work-arounds and control room annunciator deficiencies addressed

9) Plant drawings reflect as-modified conditions 1

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NU RESTART SUCCESS CRITERIA (CONTINUED)

OSTI READINESS Success Criterion Measurements of Effectiveness

1) Plant operated within Applicable to Criterion 1-8 regulatory requirements i 2) Organizations that KPis (Line and Oversight) control and support operations are Self and independent functioning effectively assessments (Line and Oversight concurrence) i

3) Staff and plant are fully prepared for Station programs ready ,

resumption of to support restart power operation '

Integrated site schedule in l

4) 0350, Sll, ISP and place restart items closed or disposition scheduled Adequate staffing in place ,

with work-off controlled ;

and tracked and results Restart related ICAVP issues showing favorable trend dispositioned ;

or at goal

5) 10 CFR 50.54(f) responeas on schedule

6) Corrective action plan implementation addre?ws root causes of perforrr &nce ,

decline l l

7) Startup and powr .

ascension pro?.am in place ,

1

8) Long term performance i program in place l

9) Operator readiness 9) Successfully complete refresher course which includes training on plant modifications, as appropriate ;

l 10)- NRC inspection support 10) Management expectations in place communicated l Support Team resources in place Station personnel awareness 3

.. . . - - . . . _ . . - . - ~ . - . . . . - - . - . - - . . . . - - .

NU RESTART SUCCESS CRITERIA (CONTINUED) ,

-l READY FOR RESTART Success Criterion Measurements of Effectiveness ,

1) Restart related ICAVP, Applicable to All Criterion '

OSTI,0350, inspection, <

ISP,10 CFR 50,54(f) KPls (Line and Oversight) and licensee identified items resolved and Self and independent deferred items Assessments (including i dispositioned Line and Oversight readiness) ;

2) . Compliance with Station programs ready i regulatory requirements to support restart j (including T/S changes, and license amendments) '

Integrated site schedule in

3) . Startup and power ascension place program in place Adequate staffing in place l

4) Long term performance Restart related items i

. program in place resolved and deferred items dispositioned l f

5) NRC Restart Assessment 5) Management expectations ,

Panel response support communicated in place Support Team resources in place Station personnel awareness l

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i e

May 21,1997 Attached are Northeast Nuclear Energy Company's (NNECO) responses to NRC letter from W. D. Travers to N. S. Cams," Questions and Comments on NNECO's Plan for Addressing Employee Concerns," dated April 22,1997.

Contained within various responses throughout the attached document are the terms "open,"" resolved" and " closed." To ensure a consistent interpretation of these terms, the ;

following definitions from the ECP Program Manual are provided:

Onen Concern A concern that has been entered in the ECP log and assigned a concern number, where the investigation is not complete Resolved Concern An open concern that has a, (1) acceptable solution, (2) clear owmer for corrective action, (3) material commitment, and (4) corrective action completion plan.

ClosedConcern A concern where the investigation is complete, the investigation report has been reviewed and approved, and corrective action, if required, is documented as complete.

The various individual action plans of the Comprehensive Plan are not considered restart items. Our goal is to show progress in attaining a safety conscious work environment !

prior to requesting restart authorization.

The completion dates provided in the attached responses are based on intemal schedules and are therefore not considered commitments to the NRC.

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l t Responses to NRC Questions and Comments On ,

l Northeast Nuclear Energy Company's !

Comprehensive Plan *

. i The following provides Northeast Nuclear Energy Company's (NNECO) response to the NRC letter W.D. Travers to N.S. Carns, dated April 22,1997 ;

I 1. '

Northeast Utilities Plan for Addressing Employees Concems (Plan) emphasizes handling concerns once they emerge outside line management. Discuss those actions in j the Plan focused on improving and providing for a safety-conscious work environment ;

as the long-term goal. '

l Of the 155 action assignments contained in the 10 action plans,85 of the <

assignments (or roughly 55%) are line management's initiatives designed to.

address the provision of a safety conscious work environment. Of the remaining 70 action assignments,42 deal with improvement efforts for the Employee l Concerns Program (ECP) and 28 deal with the Employee Concerns Oversight Panel.

l The action assignments with line management focus are:

. Establishing clear expectations of management and non-management individuals regarding the handling of employee concerns and establishing a safety conscious work environment.

. Expanding and improving management skill-sets through the provision of revised training programs including Partnership: Beyond 2000, Managing for Nuclear Safety, Plant Access Training, as well as a new program that addresses proper methods for handling professional dissent issues.

. Increasing communications regarding employee concerns and the ECP at Millstone.

. Modifying position descriptions and job postings to add emphasis on sensitivity to employee concerns and management / employee interaction.

. Modifying the performance review competencies to include components relating to employee interaction for supervisory personnel and teamwork for non-supervisory personnel. These ensure accountability for behaviors l which support the expectations regarding a safety conscious work environment.

. Modifying the Nuclear Leadership Assessment Survey to include specific employee concerns-related questions as a means of assessing

performance of management individuals and assessing the work environment. i i

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2. ESCP should report to a sufficiently senior level in the organization to establish the f

independence and credibility of the ESCP. Also, reporting to a high level in the i organization supports effective and lasting corrective actions. The Plan does not identify !

the location or reporting chain of the ESCP within the organization. What is the structure j of the F.SCP organization? What are the responsibilities and authority of the ESCP i Director? l l

The Employee Concerns Program (ECP)is part of the Nuclear Oversight ;

organization. The ECP Director reports directly to the Vice President - Nuclear i Oversight. See Attachment 1 for a Nuclear Oversight overall organizational chart.

The specific structure of the ECP is depicted on Attachment 2.

The ECP Director has ready access ta alllevels of the Northeast Utilities (NU)

Nuclear and corporate executive management. The Employee Concerns Program l

charter, which is signed by the Chairman of the Board of Trustees, provides for functional and administrative reporting relationships. The Director periodically meets with the Nuclear Committee of the NU Board of Trustees and the NU Chairman and the Nuclear Committee Advisory Team. The ECP provides monthly reports to the Board of Trustees. On concerns that are related to, or potentially related to, the Nuclear Oversight organization, the ECP Director has been tasked to keep the President and Chief Executive Officer (CEO) of NU Nuclear closely informed.

l

! The ECP Director has the responsibilities delineated below. He has the authority to carry out these responsibilities and is authorized direct access to any individual within Northeast Utilities including members of the Board of Trustees.

Responsibilities include:

a. Development and execution of the comprehensive Employee Concerns Program at NU Nuclear,

b. Assisting line management in improving the Employee Concerns environment within NU Nuclear, l

c. Keeping senior line management informed of employee concern issues,

! d. Evaluating the employee concerns climate at NU Nuclear facilities, l e. Clearly communicating Employee Concerns information to NU L stakeholders.

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ATTACHMENT 1 I .a b Nuclear Group i

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Employee Concerns CEO Nuclear Committee Oversight Panet Board of Trustees 'I ' k Board of Trustees President & CEO B. D. Kenyon Voce Premdent Nuclear Oversight

u. M. Uvetici Laecunve becretary Laecutsve Assistars.

b. J. AillOI) A M. MGUrtts)

"Communicassons

v. L. tseauchamp i ! I I Das actor Director Director Director Audsts & Performance Analysis & Employee !

Evaluation Evalu e rlon Programs . Concerns j K., Kutin ( Acting) I'. M. h r dus) M.U.Urown L. L. Morgan 1 i i

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3. Discuss how independent assessment of discrimination concems at Millstone will be l performed pending completion of in-house training.

Discrimination concerns at Millstone Station are normally investigated by the !

staff of the Human Resources Department's EEO/ Diversity Unit.They receive referrals from ECP and investigate concerns related to personnel policies and practices as well as those involving discrimination, harassment, intimidation or !

retaliation. In addition, the EEO/ Diversity staff provides on-the-Job coaching of the !

ECP staff relative to employment law, personnel policies and procedures, as well I as investigative and interviewing techniques. Staff of the EEOIDiversity Unit have l extensive experience and training in confidential and sensitive complaint i investigations, in addition, the ECP is utilizing the services of highly experienced contract !

investigators. These individuals have extensive experience in the area of 1 investigating discrimination concerns. They are assisting with the routine investigations being performed by the ECP as well as mentoring existing in-house staff.

The ECP also has access to private investigative services that are well versed in the investigation of highly sensitive and broad scope discrimination investigations.

The Employee Concerns Oversight Panel is chartered to independently review l and assess the handling of concern investigations conducted through the ECP.

NNECO response to question 12 provides additional information which pertains to these issues.

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4. Discuss the resources necessary to achieve timely and thorough resolution of the action items.

Extensive resources have been committed to achieve timely and thorough resolution of the action items. To date, the quantity of committed resources has been adequate to complete plan implementation as scheduled. Examples of the committed resources include:

The ECP staff has increased from 3 to 16 in the past year.

A full time Human Resource Director has been assigned to the Millstone Station and two Human Resource EEO specialists have been committed to i address concerns at Millstone Station.

l e A full time ECOP administrator has been assigned and members, alternates, and support staff have been selected.

An ECP training liaison has been assigned from the training department. The j training resources necessary to develop or modify specified courses, and to !

conduct required training, have been committed. '

. The Communication Department has committed the resources necessary to l produce required video and other communications tools.

i e The Internal Audit & Security Department (IAD & S) is committed to providing the resources necessary to support ECP investigative needs.

Senior Line Management has demonstrated its commitment to the ECP program through both personnel and financial commitments which will support the actions specified by the plan for both NU and contractor personnel. i

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5. Discuss how the Plan will use acceptable performance indicators. Section 2.4 discusses training for the new ESCP and states that "The goal of creating a healthy work environment can be considered to be fulfilled when the majority of concems are successfully handled between the employee (s) and their first line supervisor." How will this be measured? Similarly, items 2-10 and 10-11 establish a 90 percent goal when 100 percent would appear achievable.

l l The Comprehensive _ Plan implementation Progress curve (Attachment 1) is the L performance indicator used to determine the adherence to the scheduled

! implementation time table. NNECO recognizes that the goal of creating a safety conscious work environment will be supported by, but is not dependent upon, the l completion of all comprehensive plan action items. Our goal is to show progress in

! attaining a safety conscious work environment prior to requesting restart L authorization.

l Various ECP performance indicators have been developed to monitor critical performance and to assist with the identification of trends. Also attached is a l copy of the latest trend chart (Attachment 2). Analysis of this data also provides l other indications of the effectiveness of the Comprehensive Plan implementation.

l The determination of when "The goal of creating a healthy work environment can l be considered to be fulfilled when the majority of concerns are successfully i handled between the employee's and their first line supervision" has been met l will be made using the following as measurements:

. The FPI cultural survey results and trends.

I e The leadership survey results and trends.

. An analysis of concerns coming to the ECP vs. Industry norms and historical data.

An analysis of the concerns made to the ECP vs. allegations received by the i NRC.

A sampling of the work force by personalinterview to determine the existence and prevalence of chilling effect.

e in addition, for concerns raised to the ECP, there are three things the ECP investigates. The first is the concern itself to determine the validity of the Issue (s). The second is to determine why the concern came to the ECP instead of line management. The third is a review for " chilling effect" in the workplace. Through this three attribute investigative process, the ECP is able to assess the workplace environment.

Our preference is to achieve 100% participation in employee surveys. We l recognize however that because of absences for various reasons,100% !

participation is not achievable, hence the 90% minimum participation goal. 90%

will provide the information necessary to determine statistically accurate results.

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6. How does the Plan address the findings and recommendations of the independent, l third-party oversight program (ITPOP) organization?

The Comprehensive Plan does not explicitly provide for responses to independent Third party Oversight Program (ITPOP) recommendations.Section IV of the October 24,1997, NRC order requires the iTPOP to provide reports on its oversight activities, findings and recommendations to both the NRC and NNECO.

Section IV also requires that NNECO will provide a response to each recommendation.

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7. Is there a distinction between identity-protection and confidentiality and associated ;

measures needed to protect individualgajsing concems?

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Identity protection consists of those actions taken to ensure that the identity of a l l concerned individualis not normally divulged without the prior permission of the ;

individual. i Even if a Concernee doesn't specifically request confidentiality, the ECP process identifies a Concernee only when deemed necessary to support effective conduct )

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8. The method used to link actions identified m the Plan to the Action items identified in the ;

Employee Concems Task Force Report and the root causes identified in the Millstone Independent Review Group Report is difficult to follow and it is not clear that all root causes have been addressed.

We agree that the Plan correlation of sciions to the Millstone Independent Review Group Report (MIRG) is difficult to follow. The difficulty arose because we combined root causes from a number of sources including the MIRG. In addition, we turned the resulting root cause combinations into success objectives. The action items were correlated to these success objectives.

We believe all root causes of the MIRG report have been addressed and are in the process of developing a better correlation table which is expected to be completed and provided to the Commission at the next NRC rublic meeting on June 3,1997.

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9.

The Plan emphasized the importance and need for training on many aspects related to i handling employee concerns. The Plan also refers to action plans to develop and '

implement this training. Regarding these training plans:

a. What training will be provided to persons working at the Millstone Station related to the new ESCP? What training will be provided to persons who work in the corporate offices but have responsibilities at Millstone? What training will managers receive related to improvement of management and interpersonal skills?

l As part of the roll-out of the Comprehensive Plan, an employee meeting was held to discuss the new Plan, of which a discussion of the revised

ECP process was a part. A video of the meeting was periodically played on

! the site video system for about 10 days after the meeting. Copies were i

provided by the. Nuclear Communications Department site wide to show at department meetings. Members of the ECP are attending department i meetings to discuss the purpose and process of the ECP and to answer-questions. As a follow-up communications method, a new ECP video is in the development stage that will address not only the new ECP process and other mechanics but will address other employee questions.

In addition, the existing training course entitled Partnership: Beyond 2000 was recently modified and now includes a fully revised ECP Indoctrination, including the new ECP process. Partnership: Beyond 2000 is given to non-l management employees. Overall, Partnership: Beyond 2000 discusses the importance of raising safety concerns and discusses the employees role in maintaining a hostile free work environment in which employees may feel free to raise safety concerns.

Employees who have previously attended Partnership: Beyond 2000 will l

receive revised ECP Indoctrination through annual Plant Access Training ;

(PAT). PAT requalification has been revised to address the issue of l employee concerns and the ECP specifically. Initial PAT and the i subsequent annual requalification is required of both NU employees and l contractor personnel with unescorted access to Millstone. The new PAT {

courses will replace the existing computer version by May 20,1997. j Corporate individuals who have unescorted access to Millstone will !

receive the information on employee concerns and the ECP contained in the PAT initial training or annual requalification. l l

l With regards to management, two training programs are specifically applicable. The first is Managing for Nuclear Safety, which is given to l management individuals from first line supervisors through executives. It focuses on interpersonal communications, expectations for an environment conducive to the raising of employee concerns and an ,

understanding of nuclear concerns as a protected activity. This course has been revised using the same material that has been added to Partnership: i Beyond 2000. An additional course currently under development is Professional Dissent. This is intended to build further management skills in effectively dealing with concerns and concerned individuals. The course 13

. . t is ccheduled to be available in June 1997. !

l b. When will training on " management - employee relations" be developed, !

l implemented, and completed? What is tra:ning on " management - employee l l

relations?" Will all personnel onsite complete the training? Will this training be l l . provided to corporats personnel? How will the effectiveness of this training be ;

measured?

Development:

Three management - employee relations courses are being revised or developed to support the comprehensive plan. Managing for Nuclear L Safety (MFNS) is an existing course taught to managerial personnel that has been revised to include new material on employee concerns and the ;

l ECP. Professional Dissent is another management course being developed L with completion scheduled for June 1997. Partnership: Beyond 2000 is a management-employee relations course provided to line employees. It has .

already been revised to reflect the initiatives of the comprehensive plan l

l Implementation:

All nuclear group management personnel (first line supervisor through l senior executive) are required to attend both MFNS and Professional l Dissent. All nuclear group line employees are expected to attend Partnership: Beyond 2000.

I Completion:

l Our plans call for current management to attend MFNS by June 30,1997.

l Current management personnel are scheduled to attend Professional l Dissent not later than December 31,1997. New management hires or promoted individuals will be required to attend MFNS and Professional >

Dissent within 90 days of assuming their management position.

Management-employee relations, with respect to tha comprehensive plan, means those interpersonal and communications skills necessary to l support an open and questioning safety conscious workplace environment. MFNS focuses on communication skills while Professional Dissent will provide management staff a framework for properly resolving instances where professional or technical disagreements arise among fellow workers, or between employees and management. Partnership:

l- Beyond 2000 is the complement of MFNS. It stresses the importance of entering into a success partnership with fellow employees and management in order to attain a safety conscious work environment.

Partnership informs employees of techniques they can use to most I

effuctively communicate concerns to their supervision and what behaviors they can expect of their managers in responding to concerns.

All NU nuclear management personnel will complete the two management-j employee relations courses. All NU non-management nuclear personnel

will complete Partnership: Beyond 2000. The training program does not l discriminate between " corporate" and other personnel. NU nuclear

. personnel may be employed by Northeast Nuclear Energy Co. (NNECO) or 14

Ncrthret Utilities Service Co. (NUSCO). Regardless of employing entity, j l Millstone nuclear workers, line and management alike, will receive job )

appropriate training as specified in the plan 1 f

The best indicator of effectiioness for this type of training is consistent !

and appropriate workplace behavior. The following measurements will be ' i l used to assess workplace behavior; the FPI culture survey, the leadership assessment survey, investigation and analysis of concerns received by the i

ECP and work force sampling.

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l c. When will training of " Senior Management" be completed? What training will ;

senior management receive? How many senior managers will receive this ;

training? How will the effectiveness of the training be determined? '

All senior management training is scheduled for completion by June 30, !

1997.

Senior management will receive Managing for Nuclear Safety and Professional Dissent training. Senior managers are defined as Vice j Presidents and Recovery Officers. There are eight individuals in this category. i The best indicator of effectiveness for this type of training is consistent and appropriate workplace behavior and the support of improving the l workplace environment by senior management. The following measurements will be used to assess workplace behavior; the FPI culture survey, the leadership assessment survey, investigation and analysis of concerns received by the ECP and work force sampling.

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d. What training wUl be provided to " Managers and First Line Supervisors 7 When will this training be completed? Will all managers and first line supervisors be required to attend? How will comp 6 tion of training be tracked? How will the effectiveness of the training be d'etarmined?

Managers and first line supervisors will attend Managing for Nuclear Safety (MFNS) and Professional Dissent. All current management personnel are expected to attend MFNS by the end of June 1997. Newly promoted management individuals will be required to attend Managing for Nuclear Safety and Professional Dissent within 90 days of assuming their management position. Present plans call for management individuals to complete the Professional Dissent course by 12/31/97.

Training will be tracked using the Nuclear Training Departments tracking system, NUTIMS.

The best indicator of effectiveness for this type of training is consistent and appropriate workplace behavior. The following measurements will be used to assess workplace behavior; the FPI culture survey, the leadership assessment survey, investigation and analysis of concerns received by the ECP and work force sampling.

e. When will "All Employees" training be completed? Will this training include contractors and other non-NU personnel? What training will be provided? How will the effectiveness of the training be determined? '

l Non-management employees who have previously attended Partnership:

Beyond 2000 will receive new ECP Indoctrination through annual Plant !

Access Training (PAT) and by watching the new ECP video in the work j place. PAT requalification has been extensively revised to address the j issue of employee concerns and the ECP specifically. Initial PAT and the j subsequent annual requalification is required of all employees and 1 contractors with unescorted access to Millstone. Completion of initial PAT i is required before unescorted access is granted, in addition, all new non-management employees take Partnership: Beyond 2000. This course discusses the importance of raising safety concerns and 1 discusses the employees' role in maintaining a hostile free work l environment in which employees feel free to raise safety concerns. The I issue of peer harassment and intimidation is addressed in the course. This training is required for all NU Nuclear non-management employees.

The best indicator of effectiveness for this type of training is consistent and appropriate workplace behavior. The following measurements will be used to assess workplace behavior; the FPI culture survey, the leadership assessment survey, investigation and analysis of concerns received by the i j ECP and work force sampling. 1 I.

} f. Discuss the training that will be provided to *ESCP Investigators and intake .

Staff " When will the training be developed? Who will develop the training? What l is the expected completion date? Will investigators and staff be required to complete the training prior to conducting investigations?

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I The ECP Director, the ECP staff and the Nuclear Training Department have I

' analyzed job specific tasks and courses which will increase the ECP staff 'i skills and knowledge. ECP staff training has commenced on the l recommended courses outlined in the Northeast Utilities Plan for Addressing Employee Concerns. These core subjects include; !

" Interviewing Skills", " Legal issues in Employment", " Effective Report '

Writing", " investigative Planning", " Time Management", " Interpretive Skills" and " Communicating with Regulators and Auditors". Additional .

training courses, such as " Plant Systems" and " Team Building" identified ,

by the ECP Director, ECP staff and the Nuclear Training Department will be ;

developed and/or delivered accordingly. !

r The ECP training program is being developed by the Nuclear Training {

Department, if external, contracted courses are appropriate for inclusion in l l the program, they will be obtained through Nuclear Training.

l l Core process training in ECP staff courses is scheduled to be developed l by 6/1/97 and dallvery complete by 9/30/97.

ECP staff is presently conducting investigations, prior to completing the specified training. Experienced contract investigators are assisting ECP with workload and the mentoring of in-house representatives. 1 1

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g. Discuss the training that will be provided to

Human Resources Staff" When will the trrining be developed? Who will develop the training? How many people will receive this training? Will these people be assigned harassment, intimidation, and discrimination (HI&D) investigation responsibilities on a full-time basis? Will the human resources staff be required to complete the training prior to conducting investigations?

HR staff routinely involved in the investigation of employee concerns will receive the same formal training courses provided to ECP staff. In addition, HR is currently assessing individual training needs of its staff and will either design internal programs or secure external programs based on specific needs.' HR will also secure the resources needed to deliver the training. A total of approximately ten individuals assigned to the EEO/ Diversity Unit and the nuclear personnel department will be trained. Presently, the staff of the EEO/ Diversity Unit already has exte'isive training and experience in investigating discrimination, l harassment, intimidation and retaliation matters and will, therefore, I investigate all ECP referrals until such time as the nuclear HR staff is fully l trained. .

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10. Section 1.2 states that line management is responsible for mod'fying the existing work

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environment. How far up the management chain does this responsibility go? i l' The responsibility extends all the way to the top. Bruce Kenyon, the President &

l CEO of NU Nuclear is ultimately responsible for modifying the existing work l l environment. L

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O O 11.' Section 2.2 states that the ultimate measure of success will be employee confidence in first-line management's ability to address and resolve concerns. How will employee confidence in those managers above the first-line level be measured? How will employee confidence in the revised ESCP be measured?

Employee confidence in both these areas will be measured by an analysis of the following indicators:

. The FPI cultural survey results and trends.

. The leadership survey results and trends.

. An analysis of concerns coming to the ECP vs. Industry norms and historical data including the level at which a concern originated or failed to be resolved.

. A sampling of the work force by personal Interviews to determine the existence and prevention of chilling effect and the level at which it originated, and the confidence of the work force in managers above the supervisory level.

In addition, for concerns raised to the ECP, there are three major elements the ECP investigates. The first is the concern itself to determine the validity of the concern. The second is to determine why the concern came to the ECP instead of line management. The third is a review for " chilling effect" in the workplace. Through this three attribute investigative process, the ECP is able to assess the workplace environment, and the confidence level in managers above the supervisory level.

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12. Discuss the process for referring concerns, which are brought to the ESCP, back to line management or other corporate offices. Discuss how these concerns will be tracked to completion using the ESCP. )

l The ECP refers concerns back to line management or other corporate officers in I several ways.

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First, during the initial contact with a concerned individual, the possibility of his l or her concern being resolved by line management is discussed. If the concernee, I is amenable, the ECP representative will assist the concernee in pursuing l resolution with line management. In this case the concern will not be designated as an " official ECP concern". If the concerned individual is not amenable to this approach, the concern passes to the intake Phase and an investigation is conducted. Depending on the specific nature of the concern, the Employee i Concerns Program Director determines if the concern will be referred to line or corporate organization for investigation.

L The " ownership" of the concern stays with the ECP and investigation progress is 'l l

tracked by the Investigation Manager.

Once an investigation is completed, a closure board meets to determine the actions necessary to address the investigative findings. Line management is an l Integral part of this process and is responsible for the preparation and execution of the determined actions. The ECP monitors the process to ensure it is completed as scheduled.

The effectiveness of corrective actions in eliminating the root causes of the ,

investigative findings is also a responsibility of line management. The ECP also monitors these actions.

The ECP is in the process of updating its database so that it can carry out its ,

monitoring responsibilities effectively and efficiently. !

l The process described above is followed for all concerns. However, the degree to !

which each concern generates actions, and the subsequent monitoring for '

effectiveness,is a function of the concern significance.

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13.

What are the procedures to be followed if it is not possible to notify an individual that l

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his or her identity could be compromised?

Only in those circumstances where there is a real or potential immediate safety issue, discovery of a violation of Federal or State law or the need to make a time-sensitive report to a regulatory agency will the ECP compromise the ,

confidentiality of an individual that requested it.

When the ECP must compromise confidentiality, extensive efforts are made prior ;

to the compromise to notify the ind'vidual. If efforts are unsuccessful to reach the ?

individual beforehand, he or 65e will be advised as soon thereafter as possible. I The confidentiality agreement each person filing a concern with the ECP is required to review and sign describes the above outlined procedure.

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14. What are the criteria for becoming a member of the " Triage team?" Will the individuals be assigned on a full-time or part time basis? Will their activit es as triage team members be considered primary or co!!ateral duties? What training will the team ,

members receive?

The Triage team is not a standing organization. Triage teams are established based on the nature and circumstances of a particular concern. Selection is based on the skills and knowledge required for a specific Triage. Except for those triage team members who work within ECP, participation on a team is a i collateral duty. Duration and scope of involvement will vary with each concern.

No special training is required since Triage team members are specifically selected based on existing skill-sets.

Prior to an individual serving on their first Triage Team, the ECP director will I insure that they understand the purpose and process of Triage, and their ,

obligation to protect the confidentiality of the process.

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15.

Discuss how concems presented to the ESCP will be tracked and trended.

Concerns received by the ECP are categorized using various criteria, some of which are still under consideration. Categorized data is entered into a data base.

l The data from the data base can be, and is, reformatted in various ways to provide trending information useful to various groups, including the ECP, line management, and the Board of Directors.

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16. Will the ESCP be able to identify the inability of some line management to communicate i with employees? If so, how will such cases be dealt with?

l The ECP will and has identified the inability of some line management to !

communicate effectively with employees during the investigation of concerns. In addition, leadership and cultural surveys, interviews with employees and analysis ,

of trend data can also identity communication inadequacies by members of line {

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The method for ciaaling with these situations is case specific and depends on the i severity of the communication problem and the willingness and ability of the '!

individual to respond to remediation. !

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17. What information will be provided to an individual that is not satisfied with the outcome of the Concerns Oversight Panel (COP) review?

A concerned individual that is not satisfied with the outcome of the Employee Concerns Oversight Panel review will be provided with an explanation of why the ECOP made their decision, and given guidance on how to proceed. Possible additional avenues open to an employee in this circumstance include:

. Presentation of the concern to the Vice President of Nuclear Oversight and/or the Chief Nuclear Officer.

Presentation of the concern to the President and CEO of NU Nuclear.

Presentation of the concern to the CEO of NU.

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. Submittal of the concern to the Nuclear Regulatory Commission or other l Government agency.

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Section 2.6 describes the COP. How many persons will be on this panel? The Plan ;

only refers to the " intended" responsibilities of the COP. What will be the actual #

responsibilities of the COP? Who will select the members of the COP? What training will ,

the COP members receive? What are the criteria for COP membership? l The ECOP is comprised of a Panel Administrator, seven NU members, two I external members and seven alternates. The Panel reports to the President & :

CEO, NU Nuclear (Ref. 2, page 3). The demographics for the NU ECOP members ,

are three non exempt employees, two exempt non-supervisory, and two l management employees, at least one of whom is a first line supervisor. ;

The actual roles and responsibilities of the ECOP are being further developed and defined by the ECOP as an integral part of protocol development. The protocols i l are due to be approved by early June 1997.

I Required training for ECOP members is under review and will be determined in l l June 1997.

The ECOP members and alternates were selected through a formal process. The process began with a solicitation of the entire Millstone community for volunteers. Over 100 individuals expressed interest. Orientation sessions were held for these individuals to give relevant backgrou'.id information on the general i' purpose and scope of the ECOP. Of the initialinterested individuals, I

approximately 40 that submitted formal applications were selected to go through i an interview conducted by a panel of three individuals with a fourth person i serving as a process assessor. The seven NU members and alternates were l announced on April 18,1997.

The interview process evaluated the following attributes:

Integrity Analysis

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Judgment l

Objectivity Knowledge of the concerns environment at Millstone i Teamwork j

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! 19. What is a " Chilling Effect Evaluation?" Who' conducts this evaluation? Who are possible recipients of the evaluatica?

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! " Chilling effect"is defined as:

" Consequences of actions taken by an employer, company representative, or another employee who takes, or threatens to take, retaliatory action against

. someone who identifies or reports probl

. These actions manifest themselves -

in the form of an atmosphere in which em ees are unwilling and/or reluctant to report discrepancies and concerns" ,;

l The investigation ~of each concern includes an assessment by the investigator of l the existence of chilling effect. When a chilling effect is discovered or suspected

), it is reported to and evaluated by the ECP Director. He in turn informs the ;

appropriate level of line management. Appropriate corrective actions are then i l determined and affected. Instances of chilling effect will also be reported to the

! ECOP,

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20. What is the purpose of ' employee peers" who serve as an interface between concerned i individuals and the ESCP? What is the new corporate Peer Review Process, which '!

supersedes the existing NU grievance procedure? !

The ECP Peer Representatives provide a neutral point of contact for individuals to l express their concerns and are a conduit for that information. ;

L A new corporate peer review process (totally separate from the ECP Peer :

Representative Program) is under development but has not yet superseded the. !

existing NU grievance procedure. Development of the new peer process is !

l scheduled to start during the third quarter of 1997.

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! It is anticipated that the new process will be similar to the process used in other I

! industries, in which a peer panel is empowered to rule on whether or not l: disciplinary, or other actions were applied in accordance with Company policies <

l. and procedures in the specific instance under review. :

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21. How will an investigation be performed, especially in a case that requires technical '!

expertise that the ESCP staff does not have and was referred to the ESCP because the case could not be resolved by the line organization?

Based on the nature of an investigation, the ECP can and does call upon any technical expertise necessary to accurately assess the concern. If not available ,

within NU, the ECP has the latitude to seek assistance from any external source l through a contractual arrangement. This approach is not limited to technical Issues, but encompasses all issues, regardless of nature or scope.

The line organization does not refer technical issues to the ECP for resolution due to a lack of technical expertise. An employee concern being resolved in the line .

organization would receive the necessary technical expertise from within NU itself l or from a qualified contractor as appropriate. This activity would be independent j of the ECP.

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22. Discuss the mechanisms and controls that will be in place to ensure that the ESCP will continue to receive management support in the intermediate to long-term. i Senior Line Management has committed to the Board of Trustees to develop and maintain a safety conscious work environment in which employees are free to raise concerns. The Board of Trustees demands such a commitment because it is necessary for business success. They will hold us accountable. We must definitely hold ourselves accountable. l The Employee Concerns Program exists under the terms of a charter ratified by the Board of Trustees and signed by the Chairman of the Board. The charter continues the existence of the ECP essentially in perpetuity. The dissolution of the ECP, or any changes to its scope of activities, can be altered solely by board 1 action. !

These topics were covered to various extents in Northeast Utilities' February 28 and March 27,1997, letters to the NRC that approved action plans related to elements of the comprehensive plan. Discussion of these topics could include amplification on the information already provided. I i

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@@ Line 3,551: / Line 3,551: @@
 i
 : 22.          Discuss the mechanisms and controls that will be in place to ensure that the ESCP will continue to receive management support in the intermediate to long-term.                            i Senior Line Management has committed to the Board of Trustees to develop and maintain a safety conscious work environment in which employees are free to raise concerns. The Board of Trustees demands such a commitment because it is necessary for business success. They will hold us accountable. We must definitely hold ourselves accountable.                                                              l The Employee Concerns Program exists under the terms of a charter ratified by the Board of Trustees and signed by the Chairman of the Board. The charter continues the existence of the ECP essentially in perpetuity. The dissolution of the ECP, or any changes to its scope of activities, can be altered solely by board                  1 action.                                                                                             !
-                          *These topics were covered to various extents in Northeast Utilities' February 28 and March 27,1997, letters to the NRC that approved action plans related to elements of the comprehensive plan. Discussion of these topics could include amplification on the information already provided.                                                                       I i
+                          *These topics were covered to various extents in Northeast Utilities' February 28 and {{letter dated|date=March 27, 1997|text=March 27,1997, letter}}s to the NRC that approved action plans related to elements of the comprehensive plan. Discussion of these topics could include amplification on the information already provided.                                                                       I i
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                ._,                                   _}}

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