ML20134G491

Summary of 970109 Meeting in Nab Conference Room 101 W/Listed Attendees to Discuss Status of Corrective Action Plan & Restart Issues.Employee Handout & Restart Issues Matrix Encl

ML20134G491
Person / Time
Site:	Crystal River
Issue date:	01/16/1997
From:	Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Beard P FLORIDA POWER CORP.
References
NUDOCS 9702100429
Download: ML20134G491 (78)

Text

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January 16, 1997 Florida Power Corporation Crystal River Energy Complex Mr. P. M. Beard. Jr. (SA2A)

Sr. VP, Nuclear Operations ATTN: Mgr. Nuclear Licensing 15760 West Power Line Street Crystal River, FL 34428-6708

SUBJECT:

MEETING

SUMMARY

MANAGEMENT CORRECTIVE ACTION PLAN AND MANUAL CHAPTER 0350 RESTART PANEL CRYSTAL RI'!ER - DOCKET NO. 50-302

Dear Mr. Beard:

This refers to the meeting on January 9,1997, at your Nuclear Administration Building (NAB) Conference Room 101. The purpose of the meeting was to discuss I the status of your Corrective Action Plan and Restart Issues. It is our )

opinion, that this meeting was beneficial. Our next meeting should include a i detailed discussion of the measurements used to assess the effectiveness of i

.your corrective action program and the results observed to date. We will also I discuss your plan for completing major milestones, so the NRC can effectively plan our inspections to assess your readiness for restart.

Enclosed is a List of Attendees and Florida Power Corporation Handout. The discussions included the following topics: Leadership Oversight and Involvement, Engineering and Configuration Management Operations Regulatory I Actions, and Restart Issues.

In accordance with Section 2.790 of NRC's " Rules of Practice, "Part 2.

Title 10 Cr* of Federal Regulations, a co)y of this letter and its enclosures will be p' , ed in the NRC Public Document Room.

Should you have any questions concerning this letter, please contact us.

Sincerely.

Orig signed by Johns P. Jaudon Johns P. Jaudon. Director Division of Reactor Safety i

Docket No. 50-302 License Nos. DPR-72

Enclosures:

1. List of Attendees

2. FPC Meeting Handout

3. FPC Employee Handout

4. FPC Restart Issues Matrix cc w/encls: Continued see page 2

[

9702100429 970116 PDR ADOCK 05000302 RMS )

FPC 2 cc w/encls: Continued Gary L. Boldt. Vice President Nuclear Product 1on.(SA2C)

Florida Power Corporation Crystal River Energy Complex 15760 West Power Line Street Crystal River. FL 34428-6708 B. J. Hickle. Director Nuclear Plant Operations (NA2C)

Florida Power Corporation Crystal River Energy Complex ,

15760 West Power Line Street i Crystal River. FL 34428-6708 l L. C. Kelley. Director (SA2A)

Nuclear Operations Site Support Florida Power Corporation Crystal River Energy Complex s

.15760 West Power Line Street Crystal River. FL 34428-6708 R. Alexander Glenn Corporate Counsel Florida Power Corporation MAC - ASA P. O. Box 14042 St. Petersburg FL 33733 Attorney General Department of Legal Affairs The Capitol Tallahassee. FL 32304 Bill Passetti Office of Radiation Control De)artment of Health and ,

lehabilitative Services 1317 Winewood Boulevard Tallahassee. FL 32399-0700 Joe Myers. Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Chairman' Board of County Commissioners-Citrus County 110 N. Apopka Avenue Inverness. FL 34450-4245 cc w/encls: Continued see page 3

. =

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l FPC 4 Distribution w/ encl:

L. Raghavan, NRR B. Crowley. RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL 34428 l

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nrrict ./ /O SIGNATURE ,

//k' NAME . ellen Klan is DATE 01 / A b 97 01 / / 97 01 / / 97 01 / / 97 01 / / 97 01 / / 97 COPY? h) NO /kS) NO YES NO YES NO YES NO YES NO Of f ICI AL htCvhD COFY 'i G,uMENi NAMt: b;\crystai\meetingsCR5uMjan.997

LIST OF ATTENDEES Florida Power Corooration 4

J. Baumstark. Director Quality Programs P. Beard. Senior Vice President. Nuclear Operations G. Boldt Vice President. Nuclear Production R. Champion. Corporate Relations G. Beuris. Investor Relations R. Bright. Site Support  ;

W. Conklin. Jr. . Director. Nuclear Operations Materials and Controls  !

R. Davis. Assistant Plant Director. Operations and Chemistry F. Frando. Licensing A. Glenn. Corporate Counsel B. Gutherman. Manager. Nuclear Licensing l G. Halnon. Assistant Director. Nuclear Operations Site Support M. Hendrix. Corporate Relations L. Kelley. Director. Nuclear Operations Site Support i M. Kirk. Quality Programs '

D. Kunsemiller. Director Nuclear Site Support K. Lancaster Manager, Nuclear Projects  ;

J. Maseda. Manager. Engineering Programs R. Maughan, Corporate Relations J. Richardson President and Chief Operating Officer D. Perkey. NUS Information Services D. Sells. FMPA. Minority Owners Representative J. Terry. Manager. Nuclear Plant Technical Support R. Widell Director. Nuclear Operations Training C. Wilder. Manager. Nuclear Safety Assessment Team Nuclear Reculatory Commission S. Cahill . Senior Resident Ins)ector. Crystal River C. Casto. Engineering Branch C11ef. Region II T. Cooper. Resident Inspector. Crystal River R. Hannah. Public Affairs F. Hebdon. Director. Directorate II-3. NRR J. Jaudon. Director. Division of Reactor Safety. Region II J. Johnson. Director. Division of Reactor Projects. Region II K. Landis. Branch Chief. Division of Reactor Safety. Region II L. Reyes, Regional Administrator. Region II L. Raghavan. Project Manager. Project Directorate II-1. NRR R. Schin. Reactor Inspector Region II G. Tracy. Regional Coordinator. EDO Members of the News Media Members of the Public Enclosure 1

l

. LIST OF ATTENDEES Florida Power Corooration  ;

J. Baumstark. Director Quality Programs  !

P. Beard, Senior Vice President. Nuclear Operations i G. Boldt. Vice President. Nuclear Production l R. Champion. Corporate Relations l G. Beuris. Investor Relations R. Bright, Site Support l W. Conklin. Jr.. Director. Nuclear Operations Materials and Controls R. Davis. Assistant Plant Director. Operations and Chemistry F. Frando. Licensing A. Glenn. Corporate Counsel B. Gutherman Manager. Nuclear Licensing G. Halnon. Assistant Director. Nuclear Operations Site Support .

M. Hendrix. Corporate Relations L. Kelley. Director. Nuclear Operations Site Support M. Kirk. Quality Programs D. Kunsemiller. Director Nuclear Site Support K. Lancaster. Manager. Nuclear Projects '

J. Maseda, Manager. Engineering Programs R. Maughan. Cor) orate Relations  !

J. Richardson 3 resident and Chief Operating Officer D. Perkey NUS Information Services l D. Sells. FMPA. Minority Owners Representative J. Terry, Manager. Nuclear Plant Technical Support R. Widell Director. Nuclear Operations Training D. Wilder. Manager.. Nuclear Safety Assessment Team i

Nuclear Reaulatory Commission S. Cahill. Senior Resident Ins)ector. Crystal River C. Casto. Engineering Branch C1ief. Region II ,

T. Cooper. Resident Inspector. Crystal River '

R. Hannah. Public Affairs F. Hebdon. Director. Directorate 11-3 NRR J. Jaudon. Director. Division of Reactor Safety. Region II l J. Johnson Director. Division of Reactor Projects. Region II l K. Landis. Branch Chief. Division of Reactor Safety. Region II  ;

L. Reyes. Regional Administrator. Region II L. Raghavan Project Manager. Project Directorate 11-1. NRR R. Schin. Reactor Inspector. Region II i G. Tracy. Regional Coordinator. EDO j Members of the News Media Members of the Public l

l Enclosure 1

I FPC/XRC MAXAGEMEXT MEETIXG AGEXDA January 9, :.997 A9hE.L;.. .

y=y ~~ -

e Opening Remarks Luis Reyes e Overview Pat Beard e Leadership Oversight Jim Baumstark and Involvement Jerry Campbell j i

e Engineering and Configuration Gary Boldt Management i

e Operations Ron Davis e Regulatory Actions Brian Gutherman e Closing Remarks Pat Beard i

Florida Power Corporation 1 ENCLOSURE 2

l I

i OVERVIEW 6M?i E Q T ?TT M l ,;;.c au e MCAP - Marc,95 to the present

! e IPAP and IDRP Integrated In':o MCAP il i

i e Root Causes Alreacy Icentifiec l e Discuss Progress and Results i

I t

i Florida Power Corporation 2

't i

l i

OVERVIEW ' cont'd>1

\

l r *z 2:2m , ~

.xxn i

l e Overall Progress i

l 167 Total MCAP ll Actions l Assigned Due Dates (Includes l

IDRP) l 60 Actions Complete (36%)

3 11 Actions Extenced (7%) l l e Senior Management l Assignments i

i i

Florida Power Corporation 3

i l LEADERSHIP OVERSIGHT AXD INVOLVEMEXT

- - - = = = = . _ = ...a:=== -

eMCAP Action Status 35 Actions Assigned Due Dates l 21 Actions Complete (56%)

1 Action Extencec {3%}

-Incoraorate Change Management into '97

Business Plan i

Florida Power Corporation 4 l

LEADERSHIP OVERSIGHT AND INVOLVEMEXT m_- =

w =-

o Significant Milestones Achievec New CAP Instruction Issued (11/22)

-PCSC/CARB Up and Running

- Adverse Trends Ic entified for Root Cause Determination l

New Self-assessment Guideline Issued (12/2) l Manager / Supervisor MCAP ll Standcown (12/11)

Florida Power Corporation 5 1

I _ - . - ,

l LEADERSHIP l OVERSIGHT AND i IXVOLVEMEXT ww _..

= m= -

i o Significant Milestones Achieved (cont'd) l New OER Manager Hired (outside asset,12/18) i Licensing Self-Assessment Completed (12/19)

New NSAT Manager Hired (outside asset, reports 1/20)

Increasing / Enhancing QA Staf Size / Experience

- New QA Sr. Auditor Hired from Virginia Power (outside asset, reports 1/20)

- Recruiting Two Additional Auditors from Outside (engineering degree, former SROs) '

Florida Power Corporation 6

i

! LEADERSHIP i

OVERSIGHT AND i

INVOLVEMEXT 1 wwmcc c  ;..

v:= . . . ,

m- .w-l l e Significant Milestones Ahead l Transition to New Site l

Management Implementing an Effective CAP 1

l Successfully Executing the I

Remainder of MCAP ll and f

Restart Plan l -Issue Rev. 2 to MCAP ll By Mid-i February l Florida Power Corporation 7 4

j

1997

-e=ga Site Managmergggyent eme mm-,- - m _. Drivers t

1Q 2Q 3Q 4Q MCAP11 Site Direction / Top 10 Priorities Restart Plan 97 Business Plan

'98 Business Plan  :

I Florida Power Corporation

)

LEADERSHIP OVERSIGHT

!: & INVOLVEMENT 1

. _ . ,  ?

. .=:=e n _

4 l

i Maintenance Focus i

I l4 e Work Practices j Procedure Usage i

! Communications i

l Self-Checking i

4 i

Florida Power Corporation 8 4

l LEADERSHIP OVERSIGHT &

l IXVOLVEMEXT

.c

. . ,: m ir;. _. .,

,,, ~ . > y .

)

Why We Xeed to Focus 1

l e Inconsistent Field Leadership

! Expectations have not been clear No Structured Observation Criteria o Self-Assessments

! After the fact

Normally limited to unacceptable l aehavior i

i i

i Florida Power Corporation 9 l

LEADERSHIP OVERSIGHT &

INVOLVEMEXT m-. = nm .

What We Have Done o Initiated a Pilot Field Observation -

Program for the Electrical and Mechanical Shops ('3rd Qtr., '96)

Program Based on Event Free Operations Human Performance Tools (Factors a Worker uses to complete a task and prevent occurrence of errors)

Florida Power Corporation 10

1 LEADERSHIP OVERSIGHT & '

IXVOLVEMEXT

• ~ = =_

- , ,  ?!?"- ===

What We Have Done, Cont'd.

i e Performance Tools  !

Knowledge / Skill l Procedures  :

Communications Performance Verification Questioning Attitude Pre-Tob Briefings Teamworx Safety Worker Practices Florida Power Corporation 11

4 l

?

LEADERSHIP OVERSIGHT 4

& IXVOLVEMEXT i

m -= _ ._

== -

l Evaluated Effectiveness of the l Field Observation Program

l i

o Strengths j Good knowledge and skills 1 l Questioning Attitude i

! e Improvements Xeeded

Number of not observed (not clearly "yes" or "no")

l Inconsistency between observers I

Florida Power Corporation 12 1

4 l LEADERSHIP OVERSIGHT &

! INVOLVEMENT

~~

^

L.- =

; ,. - - ? ,

l Improvements to Field l Observation Program I e Complete Standard for each '

Event Free Operation Human Performance Tool e Fielc. Observation Criteria Based on Event Free Operation Human Performance Tools Florida Power Corporation 13

LEADERSHIP OVERSIGHT &

J IXVOLVEMENT

~

,..,,.....,m ;r . . . -

4 l i

! AdditionalInurovements ..

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(

i l e Coaching Skills Training i i

e Teamwork and Communications l Training 1

o STAR Simulator Training i

i e Expectations for Supervisors and 1

Lead Bargaining Unit Personnel

d LEADERSHIP OVERSIGHT &

I:NVOLVEME:NT

mv5ng musgenwr?giragy A27 rgaigy; gig msnm i

The Next Step 4

1

) e FullImplementation of Field

Observation Program Throughout Maintenance i Finalize standards and criteria l Provide training to observers

! Target number of field observations per supervisor per week l Trend Data 1

i I

Florida Power Corporation 15 4

1

LEADERSHIP OVERSIGHT &

I:NVOLVEMEXT

-w .... . . = -

==. -

What This Wil:. Give Us e Improved Fie:.c. Leac.ershi:p I which willleac. to improvec.

work : practices through:

Consistent Fielc. Observations Immediate Feedbacx Se..f-Assessment Florida Power Corporation 16 a

3

Mechanical Shop Tool Box Usage l

Knowledge and Skills 49 50 -

45 -

i M-35 -

30 -

}. 25 -

4 20 -

a 15 -

10 -

5- g 2 0

No Not Observed Yes Procedure Job Status Briefing 35 - 30 -

30 - 25 - k 21 25 -

20 - ' ,J; 20 - . ., ,

15 - . - )

15- 12 10 -

10 - >

I 5-5-

1 0 i i i 0 No Not Yes No Not Yes Observed Observed

' Data for Dates: l5/15/96 lTo l10/21/96 l

Electric Shop Tool Box Usage

'l Knowledgo and Skills i

30 ., l 25, 3

20 .

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15.

10.

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i No Not Yea l Observed Procedure Job Status Briefing

20. 25 .

18.

5 16. 20 .

14. 4

12. 15 10 .

8. 10.

, , , 0 , , ,

No Not Yes No Not Yes

Observed Observed i

Data for Dates: 1/10/96 To 12/05/96

Camdmeted By: Date:

Werk Groep Okeerved: Supervisor or lead:

Activity:

Workers:

YE3 NO N/A COMMUNICATIONS .

1. De those who need the information, have the informaation?

2. Do they understand the informathem?

KNOWLEDGE & SKILLS )

1. Do weder's have the knowledge to perform the tasks?

2. De weder's haow qualdications required to performs task?

3. Are werker's geslined to perform tasks?

PERFORMANCE VERIFICATION

1. Is woe being perforused accurately?

2. h there evidence of self-checking?

3. Is there evklence of peer checking?

PRE-JOB BRIEFING & TL1tNOVERS

1. Does the worker know & understand the hazards?

2, Does the worter imow the proper FPE7

3. Does the worker know what can so wrong with process?

d. Does the worker understand the scope of work to be performed?

5. Does the worker understand the limaits/condianoms? l

6. Does the worker understand areas that induce human error?

7. Does the worker understand the roles /resPh 44 mR?

r PROCEDURES & WORK DOCUMENTS

1. h procedure (or decomment) being fenewed as writtem?

2. Is precedure (or documsent) up-to-date?

3. Is procedure (or docusment) written with appropriate detail?

d. Does worker know what to de if problems found in precedure?

OUESTIONING ATTITUDE

1. Was sufficient clanpe=asa= ebtened to understand task?

SAFETY l'

1. Are safety policies & procedures being foBowed?

2. Is the proper FPE heing used?

3. Is the imiportance of safety being emphanlied via peer pressure?

d. Are safety concerns being idemedied promptly?

TEAMWORK I

1. Do the workers have an objective (or game plam)?

2. Do team members appear to be making a positive contribution?

3. Is the work being distributed fairly?

WORK PRACTICES

1. Is woher maaking pood use of allotted time to perform task?

2. Is the wod area properly identaned, and in good condition?

3. Is the proper tool being used & in the correct mammer?

d. Are there any de6ce==rian & what is being done to resolve?

Positive Feedback Given:

Corrective Feedback Given:

Mach'ne Shop Assessment Volume 1 issue 1 3rd Quarter 1996 Safety Procedures The machine shop had one injury (eye) during the third quarter Field supervisor observations show employees are requiring of 1996. Field supervisor observations show employees are coaching to ensure the proper use of procedures. The primary requiring coaching to ensure the proper use of standard areas are: (1) Not following as written, (2) Wrong procedure

, personnel protective equipment (gloves, safety glasses, and referenced in the work package, and (3) Not keeping the hard hats). Rese discrepancies are being identified by procedure up-to-date with the work in the field.

supenision, and not by master mechanics or co-workers who p g g, ,

2 may have been present at the time of the obsenations.

procedures. The primary areas are: (1) Quality of procedures,

! Precursor Cards for this quarter did not identify any adverse and (2) Not following as written.

items or trends for this EFO standard. . .

The procedures not being followed as written are limited to administrative requirements and deviations from the scope of work requests.

OSHA Reportable injuries 1

3 E1995 100 2 0 Proper Use g 80 t

g %M  %

60 L c c., g e l O1997 ,, aimproper Use c 0 40 b " _M l 1st 2nd 3rd 4th 20 Q D Not Observed Qtr Qtr Qtr Qtr 0 1 I

ist 2nd 3rd 4th I Qtr Qtr otr Qtt i Safety Effectiveness index ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Open NtJPOST Comments E Prpt N M' o ' ' '--*

60 i 40 A y h rnd Elmproper Use Not Followed 5 R ' O Not Observed 4 20 0 *b Not-up-to-date j ist 2nd 3rd 4th Wrong Referenced 2 e

4 Since 1995, there have been 11 minor injuries reported in the 2 machine shop. These include: 4 leg injuries,3 eye injuries 2 De quality Iprocedures will be tracked starting next quarter back or rib injuries, and 2 hand injuries. Six of these injuries by the number of outstanding NUPOST comments m the have been OSilA reportable. machine shop. Although sufTicient data is not available, adherence to, and demanding higber quality in the WR's is improving.

Challenges from Previous Ouarter: Injury rate, ladder Challenges from Previous Ouarter: WR completeness &

safety, securing.cquipment inside the plant, and eye protection. attention-to-detail, improve adherence, Use NUPOST,

• • 9 "*

Challenges for Current Ouarter: Improse use of personal protectise equipment through co-worker peer checking and Challenees for Current Ouarter: WR & procedure teamwork. adherence, and WR and procedure only high quality accepted.

I l

2 Machine Shop Assessment 1

1 Performance Verification Pre-Jobs & Briefings Field supenisor observations show by the large number of Field supervisor obsenations show a low effectiseness due to "Not Observed", applying this standard to mechanics has been the large number of"Not Observed" observations. This has a learning experience. He mechanics have attended the identified a difficulty for the supervisor to obsene more than S.T.A.R simulator training, and in fact, they have out one pre-job briefing. His is also a concern with the Safety performed all other maintenance disciplines. Coach observations (seldom obsene pre-job briefings).

4 Precursor Cards for this quarter did not identify any adverse Precursor Cards for this quarter did not identify any adverse l

items or trends for this EFO standard. items or trends for this EFO standard. '

Performance Verification Effecti,rass index Prom & Briefing Verification Effectiveness index 5 Proper Use 5 Proper Use 60

,'"* 5 improper Use 60

,_ Eimproper Use 20 EPn O Not Observed 20 "o -p n O Not Observed 0 CI O E- " *mM .

1 1st 2nd 3rd 4th 1st 2nd 3rd 4th j Challenees from Previous Ouarter: Verifying and Challennes from Previous Ouarter: flazard ID, )

reinforcing usage. Complacency, Distractions, Use S.T.A.R.

Challennes for Current Ouarter: Continue to show an Challennes for Current Ouarter: Improved observation l improving trend in the verification & reinforcement of usage. techniques, and develop Pre-Job Checklist.

Knowledge & Skills Questioning Attitude l Field supervisor observations show employees have the proper Field supervisor observations show employees have a strong technical knowledge and skills to perform their assignments. questioning attitude, yet this is difficult to observe. The QVV Ris is believed to be valid, but the observation data for this method identified by FPI, will provide a more standardized EFO standard has been limited. The use of visual observation method for observing and applying this EFO standard.

techniques and questioning personnel at the jobsite is needed to strengthen this data, along with other EFO tools. Precursor Cards for this quarter did identify the RB sump inadequate clearance as an adverse item for this EFO standard.

Precursor Cards for this quarter did not identify any adverse items or trends for this EFO standard. Questioning Attitude Effectiveness index Knowledge & Skills Effectiveness Index gg, 80 E Proper Use 100 g 5 improper Use 80 E Proper Use M O Not Observed (20 q

N E improper Use O Not Observed 20 0

1st 2nd MII 3rd 4th 0 *- l 1st 2nd 3rd 4th l'

Chaltenees from Previous Ouarter: Develop strength, Challences from Previous Quarter: Root cause plans, and demand high quality, self-critical.

Ee'ider Qualifications.

Challenees for Current Ouarter: Improved observation j Challenees for Current Ouarter: Improsed observation techniques, contractor control TPM's, & follow-up on tecWques, M usagt welder qualification computer program

3 Machine Shop Assessment Communications Worker Practices Field supervisor observations show a good effectiveness for Field supervisor obsenations in the 4th quarter of 1996 will this EFO standard, but the observation data and techniques has include the category of Worker Practices. This category been limited. The use of visual obsenation techniques and includes: Productivity,liousekeeping, Work Areas..

uestior ing personnel at the jobsite is needed to strengthen gg p g; or trends for this category.

Precursor Cards for this quarter did not identify any adverse items or trends for this EFO standard. Worker Practicles Effectiveness index Communications Effectiveness index g so a Proper Use 8 m Improw Use 100:soI - E Proper Use

"'~'*E O M Observed 60 . .- AImproper Use o 1 E" D Not Observed 1st 2nd 3rd 4th 0

ist 2nd 3rd 4th Challenges from Previous Ouarter: Not Applicable Challenges from Previous Ouarter: Audience ID, Changing game plans, Documentation, Procedure revisions. Challenges for Current Ouarter: Not Applicable i Challennes for Current Ouarter: Improved observation techniques, and communicate goals for 1997. )

1 Teamwork Kev Challenges:

" ~

Field supervisor observations show a good effectiveness for this EFO standard, but the actual performance appears to be lower. De use of visual observation techniques, questioning personnel, and documentation review at the jobsite are needed SAFETY PPE Usage & PEER Checking to improve the obsenation data and more clearly trend this PROCEDURES - Adherence & Demand liigh Quality I EFO standard. PERF. VERIFICATION - Continue to Use l Precursor Cards for this quarter did identify an adverse trend KNOWLEDG E/ SKILLS - Contractor Control & TPM's across work groups at CR3. This was identified to the PREJOB/ BRIEFINGS - Develop /use Checklist personnel, supervisor, and manager to attempt to improve this QUESTIONING ATTITUDE-QVV trend. COMMUNICATIONS - Discuss Goals for 1997 TEAMWORK - Develop Shop Goals for 1997 Teamwork Effectiveness Index go s. , -, a

- . P, , U.. Assessment Notes:

40 m ElmProm Use The INDEX parameters are calculated from field 2g E, m,, ,,,, g D Nohned observation data. The number of observations for each 1st 2nd 3rd 4th Parameter (i.e. Proper Use, improper Use, and Not Observed) is divided by the total number of observation opportunities, and then multiplied by 100. The "Best" index would be " Proper Use" as 100, and " Improper Use", and "Not Observed" as zero.

Challenges from Previous Ouarter: Day-to-day consistency.

Challenees for Current Ouarter: Improsed observation techniques, and Shop Goals (performance vs. individual performance) for 1997.

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i ENGIXEERING M R%?~TECP 2E U . . .; d i 1 C C C L '" "M 4

m =m: .- m um .. 4. . . . . . .

I

! o 26 Actions Assigned Due Dates l

l e 13 Actions Complete (50%)

l e 3 Actions Extended (11%)

j Establish an Engineering Tracking and Trending Program j Assure Tracking and Trending i j Indicators are Assessed to Address

! and Correct Adverse Trends f

l Implement a Program of l Engineering Self-Assessments

!. - Need to Formalize in Annual Pian l

l

.?

}

l Florida Power Corporation 17 i

i i I l

i EXGIXEERIXG  !

T-WI .-

.rm-----,=.

'I.'ll'2;w 4904 - i i

2:2 ~ .,. - . .

! e Expectations l Al-1700 " Conduct of Nuclear j Engineering and Projects"-

l Complete l -Mission & Management i Expectations i

l The Following Standarcs are l in Development:

l -Design Review Boards

! -Calculations i

-50.59 Reviews

! -Design Basis Ownership i

-Third Party Technical Reviews

- Project Scheduling

{

i -Communications Florida Power Corporation 18 i

i l EXGIXEERIXG

. :: .. .:.= -

o Effectiveness Monitoring l Resource Loading Project l Schedules and Other i Engineering Work

-Have Completed Filling the Seven Net New FPC Engineering Positions e All Hired from outside FPC Putting Together First Monthly Effectiveness Indicator Report Trends on Current Incicators Continue to Show Improvement Florida Power Corporation 19

1 1 i

i i

l EXGIXEERIXG

.. ,. 1 2 " o -

~~

-NH . .

l l e Management Oversight 1

l John Holden (from Salem /

l Davis Besse) Will Be the New l Engineering Director Effective j the Last Week in January l Don Shelton (from Davis j Besse) has Beco'me the l NGRC Engineering Subcommittee Chair

Warren Fujimoto (from Diablo l Canyon) Will Provide l Acditional Engineering / Plant l Expertise to NGRC i

j Florida Power Corporation 20 i

l l

l l

l EXGIXEERING l

mJ:n = _ + = = -

l l e Management Oversight (cont'd) l Have Parsons Power Senior l Engineering Manager Full i Time On-site i

-Will Lead a 24 Person Site

Engineering Support Team (all l positions namec - many already on-site)

Florida Power Corporation 21

COXFIGURATION

! MAXAGEMEXT l-i e MCAP Actions

8 Actions Assignec Due Dates l 3 Actions Complete (37%)

i

! 1 Action Extenced (16%)

-Include SSFI self-assessments in annual plan e IDRP Actions 60 Actions Assignec Due Dates 7 Actions Comalete (11%)

No Actions Extended Florida Power Corporation 22

i l

COXFIGURATIOX i

MAXAGEMEXT l

~ -,,= _gn _

4 l e Expectations i

! Completed NOD-55

! -Definition of Design Basis 1

l Published Design Basis Owners List l -Will Incorporate In Engineering

! Standard '

Developing Engineering Standards to Formalize Expectations for:

-Design Review Boards

-Conduct of Engineering Calculations

-50.59 Evaluations

-Design Basis Owners Florida Power Corporation 23

i l

COXFIGURATIOX l

i MAXAGEMEXT

-SmKC- . . . .

. . . .f 1 N-l e Management Oversight l Independent Technical l Assessment of Modifications by:

j - Framatome Technologies j -MPR Associates

-Sargeant & Lundy

-Parsons Power Held Preliminary Meeting with Duke Engineering to Discuss Sharing of Design Basis Lessons Learnec anc Corrective Actions Florida Power Corporation 24 1

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

COXFIGURATION l

MAXAGEMEXT

. . .~ m -_ , 5 "' " "

l e Management Oversight (cont'd) l l Safety Assessment Group l Reviewing Preliminary and '

Final 50.59's for Outage Oodifications Have Made a Decision to Assign Review of All 50.59's to a Select Group of Specialists

-Currently Addressing Staffing  !

and Training to Support this Decision I

i l

Florida Power Corporation 25 i

Open REA's annues i a c = n4 M Electrical = 120 L_~ } Mechanical = 53 i M Structural = 64 600 -- -

Tut.i = 3si I_

E N 351 i 300 - - - - - - - -

$ i Z '

0 i i i i t i i i i

l Nuclear Plant Technical Support Open REA's i

M i & C = 12 200 M Electrical = 9

~

F ~l Mechanical / Component = 15 M Rapid Response Team = 6 160 - -

Total = 42 -

U)

$ 140 - ,

8 120 N -

100 - --

80 - -

' F '

, 60 --- -

i

, 0 . -i  :- r - - - E i . _

j i j Jun Jul Aug Sep Oct Nov Dec Jan Feb . Mar Apr May, J_un .J.ul Aug Sep Oct Nov Dec

i Nuclear. Opera ana Engine;ering . -

Precursors Awaitina'Osolution > 90 Days ,

E NOE Ba klog I 200 r l 180  !

i i

160 i L

140 i

120  !

l l

4 i e 100 i 80 _ _

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.~iM9 9)

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Nuclear Plant Technical Support . -

Precursors Awaiting Resolutl'on >:90 Days -

.i -

E NPTS Backlog - '

200 180 160 g 30 -

' IA 120 G i k100 C-k 80 i

.h-- _

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MARS in " Design" umumma i a c = ss M Electrical = 50 180 I ~] Mechanical = 32 M structural = 15

~

140 - -- - -

120 - -----

100 -- -- -

80 - -

$ 60 - - - - -

0, i i i t i i Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

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Design Related Plant Workaround items

't

! M Design Related items -

Total # of items i .  ;

20 - -

\

15 - - --

- -~

_ _ _/

10 - - - -

5-- - - - - - - - - -

0 - 1 1 I I I l I  ! 1 1 1 l i Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sdp Oct Nov Dec 4

- - - - - _ - _ - - - - - - - - - - - - - - - _ - - - - - - - _ - - - _ - - _ - O

j

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i i

OPERATIONS

-- w= . a=-

l eMCAP Action Status 4

l 20 Actions Assigned

! Due Dates l

8 Actions Complete l

/40

%1>

l 2 Actions Extended

{10%}

! -EOP Upgrade n

-bOalS i

I Florida Power Corporation 26 l

l I

l l

l OPERATIOXS

, , - = -  ;;; ,

j e Moving to 5 Shifts (1/20/97 -

l 8/1/97)

! e 6 PPOs In RO License Class (6/98)  !

o 6 New SPOs (5/97) e 2 NSSs Rotated Off Shift (1/97) e 4 ROs Upgrading to SRO (6/97) e 6 Instant SROs in Class (6/98) e 6 New STAS (12/97) e Re-Establishing Peer Opera:or o EOP Project Support and Completion e Management Self-Assessments l l

Florida Power Corporation 27

4 i

OPERATIOl ~S

--===mc maame memmmawammmmmaesizesammeur*-*=~-~ +-u<-

l e Embedding Safety Culture i e OP Backlog Reduction in Progress l

i e AP Project has aeen Approvec and Funded i

e Communication and Teamwor< with

Engineering has been strengthened l

J e We Admit We have Proalems i e We Understand and Embrace the i Need to be Self-Critical 1

i Florida Power Corporation 28 a

, _ . . . - , . , m _ -.

l i

Operator Overtime Hours (1996)

I 3000-2500- 00 IIII" 2000-IIIII Hours 1500- -

l 1000 0 500 8

• i IIIIIIIIIsaillhl!!gg 1 3 5 7 9 11 13 15 17 19 21 23 25 i

Pay Periods

Monthly Average of Precursor Cards by Shift 25 Precursors A B C D E F Sg I

Shifts 8 Jan-Jun 96 EJul-Nov 96 l

i

k I

t I

t Watchstations Appraisals / Shift (1996) 5<

4-<

Appraisals

=

2-<

i 1--

0 i A B C D E F Shifts a Plant E Simulator This is an indicator of those appraisals that were performed by operatiom, managers and supervisors.

- - - - - - - - - - - _ - - - - _ - - - - - - _ _ - _ - - _ _ -_-__ m

Self-Assessment Strength / Weakness '

Ratio (1996)

Awareness '

.22 STA

, .57 Logkeeping

.67  :,

Throughness 1.60 Leadership

_- 3.00 conserv.

-- 5 00 STAR 13.00 I

i i I I I I O 2 4 6 8 10 12 14 Ratios

l l 1

PRECURSOR CARDS GENERATED PER SHIFT (Cumulative) 250 .

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< in 0 2 o A SHIFT B SHFT C SHIFT D SHIFT E SHFT F SHIFT SUPPORT JAN 96 8 6 5 7 4 8 21 FEB96 14 15 21 13 9 14 45 MAR 96 26 19 27 20 17 17 64 APR 96 47 22 46 36 22 23 86 MAY 96 63 36 56 42 31 28 104 JUN 96 87 52 81 50 38 36 129 JUL 96 125 76 91 79 54 60 156 AUG 96 148 98 127 84 69 77 181 SEP 96 186 116 154 106 77 87 200 OCT 96 194 125 168 119 87 96 218 NOV 96 207 132 176 123 95 121 232 DEC 96 l

l l

I i

1 l

I r

d i .

REGULATC'RY COMPLIAXCE

-==e=sc_;__sss=====

eMCAP Action Status 18 Actions With Due l Dates 8 Actions Complete  :

(44%)

4 Actions Extended

<22%',

-Regulatory Process improvements (Need Benchmarking)

Florida Power Corporation 29

b i

REGULATORY COMPLIANCE

.. . _- gymga__,_;3geg7 l

i '

e Significant Achievements l Licensing Expectations Complete

1 l Regulatory Process Training 1 Conducted

- 75% of Mgrs and Supervisors Attended

- Capture Last 25% in 1997 Compliance Reinforcement Complete  !

Reportability Procedure Issued Conduct of PRC Procec ure Revised i Procedure Control Process Revised to Enhance Safety Evaluation Fiorida Power Corporation 30 s

REGULATORY l COMPLIAXCE l - u desga__ _ _;g====9r -

i i e Self Assessment l On-Site Work Complete I

- Interviews

! - Process Modelling l - Staff Review of Of Findings

! - Senior Management Presentation 1

Report Drafted - In Review i Confirms IPAP, MCAP, SALP

! Findings

! Final Report 1/17 4 Regulatory Process Improvement Plan 2/97 i

- Benchmarking (1/27) l

- New Items Will Be Tracked in MCAP i l

l Florida Power Corporation 31 d

1 l REGULATORY

COMPLIAXCE

- = 2 s a g s ;_ _ _ _ s m c -

i e 50.59 Upgrade l New Compliance Procedure l Drafted j -Single Point Site Implementation

-Segregates Safety Assessment i and USQ Determination 4

-Training and Qualification

! Requirements Estab ished

Safety Ana ysis Group

! Refresher Training Complete Identifiec Personnel':0 be Qualified i Phased Implementation Start

! 3/3/97 Florida Power Corporation 32

i t  !

il REGULATORY l

COMPLIAXCE

. ?l*4$$W I '.T > Dkk .<' egg;&$$h{hh?f((jf, ~kffh.II{f))((,$hQfQ$?.jhTyc *ag

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

i l

l e FSAR Review Continuing  ;

j 37 Chapters to be Reviewed i

l 29 Complete (78%)

l 274 Findings to Date i

66 Items Resolved l

5 Potentially Significant Items j -Reviewed By Restart Panel l 88 Items Requiring Further

. Evaluation i

.i Will Docket Review Plan

}

i i

Florida Power Corporation 33 f

i

)

+

l 4

REGULATORY i COMPLIAXCE i

_ _ _ _ : m = m r =~' -

l e Organization l

New Director, Site Support l Net New Licensing Specialist Position Createc

! Hired ex-NRC Inspector

{ Hired Licensing Engineer From '

l Outside 4

i Added 4 Contractors

! 1 " Graybeard" Consul': ant l Additional Outage Support i

Planned Functional Re-

organization Florida Power Corporation 34

}

l SEMMARY y0 ,c og Mg:y 0 U$p!*  !' , ) g ygyQgg*ggg@Mpm l e MCAP Essentially On Track -

i l e Living Action Plan o Achieving Results in All Areas Improved Oversight

-NGRC, PRC, QPD Performance

- Better Quality Root Causes (CARB)

-Streng:hened Line Management Accountability Florida Power Corporation 35

f i

i i SCMMARY

\ mammer y a====en--

i i ,

2  !

l e Achieving Results in All Areas l

(cont'd)

Heightened Safety Culture

- Ops Stopping Work i - Continued Rate of PC Submittals l

(Questioning Attitude)

! - Maintenance Work Practices Upgraded i

! Improved Engineering l Effectiveness l - Reducing Backlogs l - Design Review Boards Improving

! Ownership and Quality of Mods

! - Operations / Engineering Interface Enhanced i

i Florida Power Corporation 36 I

i

l SCMMARY

$$umannm wemz 5 l

e Achieving Results in All Areas l (cont'd)

Improving Configuration

/ Design Basis Understanding and Control

- Plant Shut Down to Understand and Address Design issues

- Established DB Definition and Ownership

- Safety Analysis Group Reviews 50.59s Florida Power Corporation 37

i 1

J SEVIMARY

. m,. m

. _,,m

ymmmmm._

l j e Achieving Results in All Areas j (cont'd) i

! Regulatory Compliance j

Improving l

- Regulatory Awareness and l Understanding Increased Through l Training

- Better Quality Licensing Submittals (line l

management approval) l - Responding to Weaknesses in irs

}

t i

i i

! Florida Power Corporation 38 i

l

,1 . .

! Florida INTEROFFICE CORRESPONDENCE Power m Piant onerariam m2C si-37ss ~

CORPORATION OFFIC5 MAC TELEPHONE i suamcr: Barriers of Defense for Cae Safety i

l To: All Nuclear Operaiom Fmployees dam January 8,1997 i

i Attached for your information and use is a pamphlet entitled "Bolicy Statement on the Caduct j of Nuclear Ptmer Plant Operations". This pamAlet delineates the NRC xiicy on liceming of i Nuclear Facilities and the Operators of these faci ities. The intent in provk ing you this panphlet

is to hei the awareness of all erup,loyees of the stringent requmsnents inposed by the i Nuclear visory Commission in obtanng and ussi&g a Liceme to operate a Nuclear l Ptmer Plant.

$ As illustraed below, we are all responsible for protecting the Reactor Core at CR-3. The

{ lhrriers of Defeme in pucuirg the core are as follows:

1 i First Ihrrier of Defense: Engineering and Design i Second Barrier of Defeme: Maintenance and Prmdres l Third Barrier of Defense: Operatiam and Emeqgency Operaing Pimdnes i

i Whenever we rely on "Operatiom" for core safety, we are trameending two barriers directly to

! our last line of defeme. We should all think of ourselves as Opermars in enrareing our daily l work activities at CR-3.

l To this end we request each of you to familiarize yourselves with the enclosed Pblicy Statemsts

and keep the pamphlet nearby for j ready refertnce. By doirg so, you l

N Safety BARRIERS OF DEFENSE Wture at G3.

FOR CORE SAFETY d

i

gg k o.ecor i Assistant Director, .

l J

! Nuclear Plant Operaions Ta^'5N$

! ###2!#fses i '2?suoi2 4 ENCLOSURE 3 s

, Mq.y.,

l I 3

, l Agency:

eee .

I

Nuclear Regulatory Commission l l

Nuclear  : Action:

Regulatory '

Final policy statement Commission

summary

This policy statement is being issued to make

''"h' 10 CFR Parts 50aml55 management ' """'**i"" '*d operators withP"'

and hcense l respect to the conduct of nuclear power plant i operations. The Commission believes that it is PoliO tatement S on the

'"'""h"""'Y'"'"'8"*"'"'h nuclear power reactor facility establish and i Conduct ofNuclearPower '

maintain a professional working environraent i Plant Operations with a focus on safety in control rooms and I i

throughout the plant. The Commission also

' l believes that each individual licensed by the j NRC to operate the controls of a nuclear s

I

~

l power reactor must be keenty aware that he SupplementaryInformation:

or she holds the special trust and confidence of the American people, conferred through Backgroumi the NRC license, and that his or her first re. It is essential that control room operators are sponsibility is to assure that the reactor is in a (1) well trained and qualified, (2) physically safe condition at all times. This pohcy state- and mentally fit to carry out their duties, and ment specifically desenbes the Commission's (3) attentive to plant status relevant to their expectations of utility management and responsibilities to ensure the continued safe licensed operators m fulfilling NRC regula- operation of nuclear facilities.it is also tions and prior guidance regarding the ,

essential that management at each nuclear conduct of control room operations. The power reactor facibiy establish and maintain policy statement further provides the Com- a professional working environment in which mission's endorsement of industry initiatives i We hcensed operator may be fully successful to enhance professionalism by both manage- in discharging his or her safety responsibili-ment and plant operators. ,;c On a number of occasions, the NRC has re-Effective Date:

January 24.1989 ceived reports and has found instances of operator inattentiveness and unprofessional behavior in control rooms of some operating For Further Information

Contact:

Jack W.

Roe, Office of Nuclear Reactor Regulation, . facihties. Reported instances include: (1) li-U.S. Nuclear Regulatory Commission, Wash- censed operators observed to be appr.rently ington, DC 20S55, Telephone: (301) 492- sleeping while on duty in the control room 2004, or otherwise being inattentive to their license obligations, ( 2 ) operators using entertainment 2 3

i control room to ensure that the operator at devices (for example, radios, tape players, the controls is able to perform the actions and video games)in the control room in a and/or mitigate an accident is required by way that might distract their attention from $50.54(mX2Xiii). Commission regulations in l required safety-related duties, and 10 CFR Part 55 establish standards for (3) unauthorized individuals being allowed licensing nuclear power plant operators.

to manipulate reactivity controls. Such conduct is unacceptsble and inconsistent The Commission has addressed operator i with the operators' licensed duties. training and qualifications and fitness-for- ,

t duty in policy statements. 2The policy state-The Commission has previously addressed ment on training and qualifications endorsed its expectations of operator conduct in the Institute of Nuclear Pcwer Operations Commission regulations and regulatory (INPO)managedTraining Accreditation guidance. Under 10 CFR 50.54(k), "An Program. The policy statement on fitness-for-operator or senior operator licensed duty endorsed the concept that the work pursuant to Part 55 of this chapter shall be pl ce at nuclear power plants is to be drug present at the controls at all times during and alcohol free. Fitness-for-duty rulemaking the operation of the facility" ' The continu. is under consideration by the Commission. 8  ;

aus presence of a senior operator in the i Guidance regarding the conduct oflicensed  !

' Copies of nie 10. Cnde of redera! pee,hnnm Parn o to so and Parts $1 to 199 (revbned January 1.19HH). may he purchawd from j the supenntendent ur Documents. C.s Government Pnnnng ofrice. ,

1. P"D S'd'"*C"'"n Traimng and Quabrwatum or Nuclear Power {

hy callms (202) 275-2060 or by wriung to the U.s Governrnent Plant remnncI t 60 FR 11147. March 20.19Hi. and amended 53 rR 1

Pnntmg office. P o boa 3'082. Washington. DC20013-70H2. 46603. Nosemler lH.19HM) and Polwy statenwnt on htnewfor-nuty l Copics may alau be purchawed from the Nanonal Techn cal obudear Power Mani Per*mnel(41 FH T921. August 4 1986) i f

Informauon serde. 52H5 Port Royal Road. spnngfwld. vA 22161 A *

• P"'Ined Rule on 10 CTR Part 26 hineo-for-Duty Pnigram* I%3 FR Copy or 10 CFR i* as allable for ingwtnon and< or cuppng br a fee Weinher 22. IM in the NRC Pubhc Document Room 2120 t. street. NW. Washmgton.

• 5 4

I i

operators and control room operations has .

IE Circular 81-02.

been addressed in an NRC Circular and in NRC Information Notices 4 Specifically,IE In information Notice 87-21, the NRC .m-Information Notice 79-20, Revision 1, empha- forn ed all nuclear p wer react r facil ties and sized that only licensed operators are permit- II""**d P"'"' 'S"h "*'*"i"li'#"'*d P' ted to manipulate controls (10 CFR 50.54(i)1 catms bserved to be apparently sleeping and that a licensed operator is re9uired to be while on duty.The notice reaffirmed the ne-present at the controls during facility opera- cessitYfor high standards of control room pro-tion [10 CFR 50.54(k)]. IE Circular 81-02 fessionalism and operator attentiveness to provided the following guidance: (1) knowl- ensure safe operation of nuclear power edge of the plant's status must be ensured f cilities. Further,Information Nouce 88-20 during shift changes by a formal watch yeiter ted the concern about unauthonzed turnover and relief,(2) licensed operators ndividuals manipulating controls and per-must be alert and attentive to instruments f nning c mmt room aMues.

and controls,(3) potentially distracting activi-ties in the control room must be prohibited' .

The Comm.ission is aware that the m. dustry, (4) access to the control room must be has taken action to foster the development of limited, and (5) eating and training activities P*I*I"" ** "" P"# "'

should not compromise operator attentive- and has IwmW mwarkstaMng may ness or a professional atmosphere. Informa- - ment principles f r enhancing professionalism tion Notice 85-53 reiterated the guidance of of nuclear personnel. The Commission believes that such an opera'or code of

' tr Cirtular Hi 02. d.ned Februars 9.19N1. Information Nake *'9 20. ggg g.EOed by operators and sup-Resnion 1. daico Septemler 7.199. Inlurmanon Nn e MS 53. dated ported by utility management can contribute July 12.19Hi. Informanon Nur H521. dated May 11.19H". and informatum Nitre NH-20. dated May 5.19Hx (.n adable ai the NRC to operator professionalism and commends Pubhc rkunrnt Room .it 2120 L Street. NW. Wlungton, DCL the industry and especially the operators who 6 7

contnbuted to these efforts. The Commission Policy Statement encourages and supports the prompt and effective implementation of these industry The Commission believes that the working initiatives at each licensed power reactor. environment provided for the conduct of op- ,

erations at nuclear power facilities has a i The Commission has decided to issue this direct relationship to safety. Management has i policy statement to help foster the develop. a duty and obligation to foster the develop- t ment and maintenance of a safety culture at ment of a " safety culture' at each facility and l I every facility licensed by the NRC, and to t pr vide a professional working environ- ,

make clear its expectations of utility manage- ment, in the control room and throughout  ;

ment and licensed operators in fulfilling NRC the facility, that assures safe operations.  ;

regulations and prior guidance regarding the Management must pmvide the leadership {

conduct of control room operations. that nurtures and perpetuates the safety culture. In this context, the term " safety culture"is defined as follows: .

1 I i~

"The phrase ' safety culture' refers to a very general matter, the personal dedication and  !

accountability of all individuals engaged in

, any activity which has a bearing on the safety

, of nuclear power plants.The starting point ,

4 for the necessary full attention to safety l j matters is with the senior management of all .

organizations concerned. Policies a re estab-  !

j lished and implemented rhidi ensure correct l i practices, with the recognition that their 8 9 l

. ._..-.,._._.,_.. m .y..- ,

w - ._ __ -. ,, - _.

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

importance lies not just in the practices are committed, their admission is particularly themselves but also in the environment of encouraged. By these means, an all pervad-safety consciousness which they create. Clear ing safety thinking is achieved, allowing an lines of responsibility and communication are inherently questioning attitude, the prevention established; sound procedures are devel- ] of complacency, a commitment to excellence, oped; strict adherence to these procedures is and the fostering of both personal accounta-demanded; internal reviews are performed of l bility and corporate self-regulation in safety safety related activities; above all, staff matters."

training and education emphasize the reasons behind the safety practices estab- Nuclear power plant operators have a profes-lished, together with the consequences for sional responsibility to ensure that the facility safety of shortfalls in personal performance. is operated safely and within the requirements of the facility's license, including its technical "These matters are especially important for specifications and the regulations and orders operating organizations and the staff directly cf the NRC. Mechanical and electrical systems engaged in plant operation. For the latter, at and components required for safety can and all levels, training emphasizes the signifi- do fail. However, the automated safety cance of their individual tasks from the features of the plant, together with the standpoint of basic understanding and operator, can identify at an early stage ,

knowledge of the plant and the equipment at degradation in plant systems that could affect  ;

their command, with special emphasis on the reactor safety. The operator can take action to i reasons underlying safety limits and the mitigate the situation. Therefore, nuclear  ;

safety consequences of violations. Open }

attitudes are required in such staff to ensure l

]

that information relevant to plant safety is . unte,nannai suao, sarety w,ory c,nup rissAc>3. tiae sareiy i freely communicated; when errors of practice ennepies ro, suao, enm., pun., j 10 11

power plant operators on each shift must The following criteria reflect the Commis-ham knowledge of those aspects of plant sion's expectations concerning the conduct of status relevant to their responsibilities, operations in control rooms and licensed op-maintain their working environment free of I erators at nuclear reactors consistent with 10 distractions, and using all their senses, be  ; CFR 50.54 and guidance provided in an NRC alert to prevent or mitigate any operational j Circular and Information Notices:

problems. Each individual licensed by the NRC to operate the controls of a nuclear

• Conduct within the control room should power reactor must be keenly aware that he l

, always be professional and proper, re-or she holds the special trust and confidence flecting a safety-minded approach to of the American people, conferred through routine operations. The operator "at the the NRC license, and that his or her first re. controls" and the immediate supervisor sponsibility is to assure that the reactor is in a must never relinquish their safety respon-safe condition at all times. sibilities unless properly relieved, including a thorough turnover briefing, by a qualified operator.

. Activities within the control room should be performed with formality. Operator

! actions must be in accordance with ap-proved procedures. Verbal communica-l tions should be clear and concise.

I Appropriate consideration should be

{ given to the need for acknowledgement and verification ofinstructions received.

l 12 l 13

~

1 i

. The control room of a nuclear power Provide the direction, facilities, and re-plant, and in particular the area "at the S "'Ces needed to accommodate activities controls , must be secure from intrusion. n t directly related to plant operations.

Access should be strictly controlled by a designated authority; only authorized . Activities outside the control room with the personnel should be permitted to be p tential to affect plant operations, such as present in the control room; and regulatory n-line m intenance and surveillance, f should be fully coordinated with the control restrictions concerning manipulation of the controls must be meticulously observed. f

m. Effective methods for communication with or notification of the operator at the

. The operator at the controls, and the im- l c ntrols should be established and main-mediate supervisor, must be continuously tained throughout each evolution.

{

alert to plant conditions and ongoing activities affecting plant operations, includ. I

. Written records of plant operations must be ing conditions external to the plant such as carefully prep red and maintamed in accor-grid stability, meteorological conditions i dance with requirements for such records and change in support quipment statu ; and it. sufficient detail to provide a full operational occurrences should be antici- understanding of operationally significant pated; alarms and off-normal conditions m u ers.

should be promptiv responded to; and problems affecting' reactor operations

• The working environment in the control should be corrected in a timely fashion. +

r m should be maintained to minimize dis-

! tractions to the operators. Management

. Activities within the control room should should act to remove distractions that would be limited to those necessary for the safe l interfere with the operatc. , ability to operation of the plant. Management should m nitor the plant either audibly or visually,

{

14 15

I

! including work activities that are not related to the operator's immediate respon. hipleinentation ofPolicy sibility for safe plant operation. Considera-tion should be given to reducing environ-mental distractions such as lighted alarms The Commission intends this Policy State-that are not operationally significant, or ment to make clear the Commission's ex-l pectations and to provide guidance to alarms that signify normal operating conditions. licensees in improving and assessing the conduct of operations in the control rooms

• Foreign objects and materials not neces- of nuclear power plants. The Commission sary for plant operations, ongoing mainte- believes that utility management should nance, or sun eillance testing should be routinely monitor the conduct of operations at the plant, particularly in the control restricted from the area at the controls' to precludein dvenent actuation of the room, and review their procedures and controls or contamination of control policies on the conduct of operations, con-devices. sidering the guidance of this policy state.

ment, to assure they support an environ-ment for professional conduct.

I j Nothing in this policy statement limits the l authority of the NRC to take appropriate j

enforcement action for violations of Com-

} mission requirements or on matters other-wise affecting the safe operation of the plant and thus the public health and safety.

16 17 4

l I

Dated at Rockville, Maryland, this 17

• day of Notes:

January,1989.

For the Nuclear Regulatory Commission.

1 I'

L"nd w

.x 3

SamuelJ. Chilk Secretary of the Commission.

18

.. ...m _ . _

~

U.S. Nuclear Kegulatory Conunission '

3F12%-05 Attachment B RESTART ISSUES Approved: _ ll/

Regulatory Iteses - B. Gutherman 6. L. Bold Restart Pa 1 Chainnan r

ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS R-1 GL 96-01 review. GL 96-01 testing J. Maseda AITTddedOW^EUsi _

PR496-0129 associated'wIth1PR-96-0129 Address issues identified as a result of GL PR-96;0435 at#.tER{96-011100 b i* ' "

96-01 reviews (SP-130). LER 961 011-00 bomplete(yCorrective..,

LER 96-025-00 Action:Stepf2loffPRf96i,  ;

D435MPerfonn SP-130 prior "

%Modejgisjt,(onlylopen  !

item?

R-2 T.S. amendment (s) for EDG load uprate: LER 96-020-00 B. Gutherman IM E Jpd % F Nir$150 M -

- diesel generator load ratings LER 96-025-00 6pgrade :has]heenidraftedif

- fuel storage Awai.tii@ Engineering / Ops /  ;

- kw meters LicensingTpositjons;on ptherjtoprocee Supports resolution of EDG USQs through modifications. Involves changes to technical specifications and bases.

l (See item D-6)

Acronyms listed below correspond to those items listed in the Issue Identifier colunn

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel l IFI - Inspector Follow-up Item i IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report i MCAP II - Management Corrective Action Plan, Phase 11 OCR - Operability Concerns Resolution '

PC - FPC Precursor Card PR - FPC Problem Report. _

f REA - Request for Engineering Assistance WARN - FPC Workaroundlist i URI - Unresolved Item  ;

VIO - Violation i

January 9, 1997 l

I ENCLOSURE 4 -

, i

+_ - .-_ - - . _ _ _ _ _ - . _ _ . . . _ _ _ - - . _ _ _ . _ _ _ . _ _ - . . _ - - _ - _ _ - _ . . _ _ _ _ _ _ - _ _ _ . _ . _ _ _ _ - , . - . - - - . - - . -

U.S. Cuctcar Regulatory Comission '

3F1296-05 Attachment B Page 2 of 21 ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS R-3 Complete maintenance rule structural baseline N/A J. Terry RB'walkd dnIl$spe d f d . ,

inspection of the RB. schedule will be-issued,by 1/10/972 JAdditional_ .,

engineers will-be on-site the week of?1/13/97;to~ ' '

somence ~ the' walkdowns7 R-4 ASV-204 license amendment to resolve USQ. PR-96-0419 B. Gutherman see[IisU$"R M M ,T C h i w w ,..a .x m a :

Supports resolution of USQ(s) generated as a result of these modifications.

(See item D-5)

R-5 DH-45-FI license amendnent. PR-96-0444 B. Gutherman iGiaifiEi[gia5It[drild calculation from^' ~

Inoperable flow instrument contradicts Engineering".bhicii'li license condition 2.C.(5). Resolution may purrentlybeingfinal) zed,)

require license amendment.

Acronyms listed below t.c-respond to those items listed in the Issue Identifier colum

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Ir.spector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9, 1997

t!.S. Nucleir Reguistory Ccmmission 3F1296-05 Attachment B Page 3 of 21 ISSlJE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS R-6 FSAR table 8-1.8-2 update (EDG load listing). FPC letter to NRC B. Gutherman [ngineerihd3dddlit'ionsld' ' " ~

3F1196-01, dated progressj " ' ~ "

New loads are being calculated to support November 18, 1996 post-modification configuration. Revised FSAR Revision 23 FSAR table will be submitted prior to restart.

R-7 Possible short term ITS change to allow DCV PR-96-0041 B. Gutherman SeAfib[dili'thi35edjoj 17/18, 177/178 modification. PR-96-0220 this with; Pro {ectlieaml Installattan may simultaneously block valve control for two DH trains. Safest time to install is MODE 3 or higher, when RCPs are running and DTSG cooling is available.

(See item D-10)

R-8 Complete and submit the 10CFR50.54(f) letter NRC letter to FPC R. Widell in"pfdgEeEs7]EDiafdetty response. dated 10/9/96 scheduled to be.outifor_.

somentMl/10/97:to meete '

usuei date - 2/5/97f ~ ~'

R-9 Submit LPI mission time test results. PR-96-0311 B. Gutherman 6shind Ehghieerind}4ji.es (See item D-3) bf draft copy}

Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist tJRI - Unresolved item VIO - Violation January 9,1997

U.S. Cuclesr Regulatory Connaission 3F12%-05 Attachment B Page 4 of 21 ISSUE ISSUE i DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS R-10 Submit and receive approval for T. S. N/A B. Gutherman MESEE65ift7aM._

amendment for dRT, Appendix J, option B. bilPitCB1/6/97fiSchechsled to W rgo..w...RC$rev.l'e.w' IIG au~ - na C "

50 h?*?55k?I?hW$kY5$?hh Class l.2;3? inspection programiand i

b.k55kb kDS fYY$255YS gojnfieltinschedu' led N.SPo(yj h an Q d y,rns[ p p[a( N 3 t # etlon}_daltelpr;F M d 28 519976 Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution -

PC - FPC Precursor Card PR - FPC Problem Report ,

REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9,1997 -

U.S. Cuclesr Rautstory Comission 3F1296-05 Attachment B Page 5 of 21 RESTART ISSUES Design Readiness / Extent of Condition It ms - F. Sullivan ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-1 HPI pump recirculation to the makeup tank. CR3 D.I.1 F. Sullivan fiEUin{55ffsdirk"AE6pffd PR-96-0440 D3MpifNy develop IWt currently ^'in' Changes needed to eliminate or control Bj;Vaughn progressf ' '^ ~ ~~ ~

recirculation flow to MUT post-LOCA to FPC letter to NRC preve it relief valve from lif ting. 3F1096-22, dated 10/28/96 Item 1.

D-2 HPI system modifications to improve SBLOCA CR3 D.I.2 F. Sullivan M/X bil5h' M 16 M Jj margins. LER 96-006-00 B3.Vsujhri

'~ ~

Cosceptual:DRB

~^""

to.'be LER 96-006-01 scheduledfj Revise to close MUV-27 on 1500 psig HPI IFI 96-003-16 initiation signal instead of 4 psig RBIC signal. FPC letter to NRC 3F1096-22, dated 10/28/96. Item 2.

WARN #2 Acronyms listed below correspond to those items listed in the Issue Identifier colunn

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workeroundlist URI - Unresolved item VIO - Violation January 9, 1997

u. . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _

~'

U.S. Nuclear Regulatory Consnission i 3F1296-05 L Attachment B Page 6 of 21 ISSUE i ISSUE # DESCRIPTION IDENTIFIER (*)- ACTION ASSIGNED TO STATUS D-3 LPI pump mission time. CR3 D.I.3 J.' Terry ifAIIMENIE57W LRI 96-201-01 inissionlthan%pbr$jd  !

Extend allowed low-flow time using test data .0CR:DH-96-DHP- 1/2/9 % Report *currentl and evaluation of results (pump teardown and. 1A/1B-3 bAingbyegbi"~""~y

. inspection). Engjneering.j _ i PR-96-0311 ,

FPC to NRC letter l 3F1096-22. dated  !

10/28/96, Item 3.

t D-4 Reactor building spray pump 1B NPSH. CR3 D.I.4 J. Terry Cds%$@asyy6sisi"3k URI 96-201-02 oQsparejptating; assembly,*

Tear down pumps, perform flow test (and OCR:BS-96-BSP-1B Modification 3c[gsinj g  ;

modify impeller, if required) to reduce NPSH [6gspl@$1rogfessA. " [

required. FPC to NRC letter j 3F1096-22, dated ,

10/28/96, Item 4.

s I

Acronyms listed below correspond to those items listed in the Issue Identifier column [

t

(*) EE! - Escalated Enforcement Item t EA - Enforcement Action -

IDRP - Independent Design Review Panel IFI - Inspector Follow-up item i IPAP - Ir,tegrated Performance Assessment Process I GL - Generic Letter LER - Licensee Event Report [

MCAP II

• Management Corrective Action Plan, Phase II '

OCR - Operability Concerns Resolution -

PC - FPC Precursor Card  ;

PR - FPC Problem Report  ;

REA - Request for Engineering Assistance i WARN - FPC Workaroundlist i URI - Unresolved item

• VIO - Violation  ;

January 9, 1997 j

' i l

f

, a

U.S. Nucletr Regulatory Conraission 3F1296-05 Attachment B Page 7 of 21 ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-5 Emergency feedwater system upgrades and CR3 D.I.5 F. Sullivan IMid % onE6F id3dij diesel generator load impact: URI 96-12-01 J2Endsley shipped off-siteifor

- cavitating venturis VIO 96-09-07 SiK61eff inodificatibn?/Conceflsil

- automate cross tie valve EFV-12 COHille? DRB'd

- EFIC compensating module PR-96-0419

" " ~ " '

be @ pproved'and:MARsis' develop

- Add ASV-204 "A" auto signal have. fr.am, at.o..m..efd.o.,[.ac_tsaf.

Reverses previous modification which removed FPC to NRC letter "A"-side auto-start signal from steam inlet 3F1096-22, dated 45E2dO[C6Eileihil5EDR(

valve to "B"-side EFV pump. These 10/28/96. Item 5. approved and MAR is.bein modifications address the NPSH issue and/or ifevEloped[~ "~ ^ "~ g reduce operator burden.

EF M ZIst6dissG d DRB ip;Eoved and. .MA..R31.6be..,il.ij diki(NIiikVeUUfEs)hk being1 verified?? Final DRS has been' scheduled? ~ ~

Acronyms listed below correspond to those items listed in the Issue Identifier coltznn

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9, 1997

ti.S. Nucletr Regulatory Comission 3F1296-05 Attachment B Page 8 cf 21 ISSUE ISSUE i DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-6 Emergency diesel generator loading: CR3 D.I.6 F. Sullivan sedidddrifEiiEffAN15sdsi

- capacity uprate EEI 96-12-02 CG Miller DRB?to>belrescheduledjfMAR

- remove nonessential load (s) OCR:EG-96-EGDG- Jj]Endslej $ bein[ developed [ " ~^

- kw meter accuracy improvement SIA/IB

^DT/PTM3Hdd f5I3eNf5idOEdiredeh$

- talibid ios equipment upgrade LER 96-020-00 bcckpted O Concept M DRS

- extend the 30 minute rating to a 90 minute LER 96-025-00 ApprovedfjHQaJmcst~~

rating complete!

~ ~ ~ ~ "

FPC to NRC letter Increases the centinuous 2000 hr. and 200 hr. 3F1096-22 dated EU3AlibfiU5n'eq$ipses ratings. Thirty (30) minute rating duration 10/28/96. Item 6. has;beec yrderedj'~~ ~ ~

may be increased. Reduces connected load.

Allows more accurate testing measurement of IDdThiiiAEftFUjidit'siMkAR EDG output. Us'ued M ield work?td'"^ l begin % ekidfi d13/97?? l Acronyms listed below correspond to those items listed in the Issue Identifier colum

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP !! - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance

%?ARN - FPC litorkaroundlist URI - Unresolved item VIO - violation January 9, 1997

U.S. Nuclear Regulatory Conmissica 3F1296-05 Attachment B Page 9 of 21 ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASslGNED TO STATUS D-7 Failure modes and effects analysis (FMEA) of CR3 D.I.7 J. Maseda TAA 2Fiff FMEAI B Ail Q loss of DC power. Methodology; doc'ument .has FFC to NRC letter k'kn corepletedOLl. 5ysters '

Extensive review of scenario cr d ting several 3F1096-22. dated betlewsihave bend '~ ~

recent design basis problems. 10/28/96, item 7. prioritized and.'aliMfiDis scheduled t'o!beimpleted^

byl4/21/97dThe schedule" bhange5(from 3/4/97)?was_.

duel to the 'addi.tional. work 4

needed to: evaluate the impactiop12DV;VitaliAC eircuitsi Acronyms Listed below correspond to those items listed in the Issue Identifier colum

(*) EE! - Escalated Enfoi h m...t Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-tp Item IPAP - Integratej Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved item VIO - Violation January 9, 1997

U.S. Nuclear Reguistory Commission 3F1296-05 Attachment B Page 10 of 21 ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-8 GL 96-06 (thermal overpressure protection for CR3 D.I.8 F. Sulli. van ShWoffrp'aniiEn*chaEtied containment piping, penetrations, and IFI 96-08-02 D(Mopjbg has_heen ORB: approved;and coolers). OCR: RB awaitingFRCfreviewy _

penetrations 5 argent 1&ft. undy;calculattog Will address overpressure issue with hardware for;5V-system received g mods. Vill evaluate and address FPC to NRC letter Will' develop a MAR to "g^

susceptibility to other issues. 3F1096-22, dated addNss'the:otherdwo.._

10/28/96 Item 8. issues 'offGU 96-06' wtilcfj wilTbebasedortjhe, m

Sargentl&'Lundyi . . . . , .

reconciendations :of. the ca lcul.ition ? ' ' ~ '

D-9 Discrepancies in HPI design basis analysis. URI 96-01-02 F. ViiSSr'islidjeNiradisj C.1Sullivan

Hiller

~ ' ~ ~ "

pnistop-checE valve to Re-confinn key hydraulic model inputs. va lidate' hydraulic" mode 12 0-10 DCV 17/18, 177/178 positioners (Mode 3 er URI 96-201-04 K. Lancaster Ocs3EIt'i6gio%iWMAR0s 2 7 above). linei(MODE.;1)withaf.].((."

PR-96-0041 currently: anticipated date Addresses non-safety related controllers on PR-96-0220 of 6/26/970 t  !-.Referencei SR valves. Install.T-MAR.(94-04-01) andiinstall. permanent (MAR l (94-09J02)s"~'

Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EE! - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARM - FPC Workaroundlist URI - Unresolved Item '

VIO - Violation January 9, 1997 4

4

. . . _ _ _ . _ _ _ ..____________.______m________ _ _ _ _ _ _ _ _ ____ __m_ ___ _ .__

U.S. Nuctetr Regulatory Connission 3F1296-05 Attachment B Page 11 of 21 ISSUE ISSUE f DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-11 Appendix R review: VIO 96-06-06 W. Rossfeld Ccir$plAfedlIdddielsd55 .

- transformer protection devices assessment;;q.[Draf tl report .

- hot short effect on remote S/D panel fuses of3the(assessment'curiently,

- approval of NI detector TSI removal jnthereviewcycleg Addresses design / licensing basis issues found in Appendix R review.

D-12 EDG protective trips not bypassed during IFC962d!64 2 F. Sullivan 5039ETEieEfe2d5^7Erici e emergency mode of operation. PR464263 f[EridslEy is estrentlylindergeview/

BSKnoll

' ' ~ ' ~

New EDG trips added by plant modification not bypassed during emergency mode of operation.

D-13 Develop system timelines for EF, MU, DH, BS, N/A P. Tanguay Nofk3biFrintg;Nydgeal EG modifications, analysis and related Licensing correspondence.

Extent of Condition element.

D-14 Re-perform the diesel loading calculation. EEI 96-12-04 F. Sullivan cdFF66tlipojict'i%'on K Endsles

~ ~ ~ ' ~ ~ '

hold.-?. Workingon 500 ki Confirmation of existing calculation. backfeed calculation) "

Acronyms listed below correspond to those items Listed in the issue Identifier column

(*) EEI - Escatated Enforcement item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP 11 - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resutution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9, 1997

U.S. Nuclctr Regulstory Comission 3F1296-05 Attachment B Page 12 of 21 ISSUE ISSUE i DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-15 Review a sample (20) of past modification N/A R. Knoll 6M${EifS(id'l OAGided?..

50.59's. Arranging:for second level feVtew of 50.53's[ ^ "^

Extent of Condition element.

D-16 Perform an integrated safety assessment of N/A F. Sullivan $Afit[AsyissEtTbEIdg.

current outage modifications. }nitiated.'on...L.ED..G,we. ek. 3o.f,

' ~ ~ ~

Back-end look at modifications made this outage to assess aggregate safety impact.

D-17 Complete NPSH review of EFP suction swapover REA 96-0788 F. Sullivan f[n1IMEicl5651Ari4efeSEd from EFT to CST. QMiyer from Parsons? $hird party review by NOE AsTire Hydraulle issue. No check valves between hropessy;~' " ' ~

tanks.

0-18 Resolve NPSH concern when SFP's are used tc, PR-96-0360 P2Eisly ~

X"nsEU s his" % En recirc BWST. scheduledfor)1/17/97td T disc 6ssithisxissued~

Hydraulic issue. LOCA during SFP i recirculation of BWST would add to friction loss in a portion of one train's ECCS suction lines. ,

Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Pha ,e II OCR - Operability Concerns Resolution -

PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance i WARN - FPC Workaroundlist .

URI - Unresolved item VIO - Violation January 9, 1997

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ .

U.S. Cuclear Regulctory Conunission 3F1296-05 Attachment B Page 13 of 21 ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS D-19 Correct RMG-29/30 seismic mounting. PR-96-0267 F._Sullivan dirid5hTGij.1milkd$wii. _ _

BnVaughn completeJ ' Minor MAR / calc Control board mounting of high-range required:to resolvefiNo containment radiation monitor instrumentation DRBylanned.iorLrquiredj is not seismically qualified.

D-20 Correct RWP cyclone separator fouling. PR-96-0441 F. Sullivan DUfrediE^dhyeldpir@Tri . ..

D[ Jopling action plan ,tol address this SR seawater source of RWP bearing flush issue]

water. Addresses repetitive plugging of fouling / corrosion.

t D-21 ESCP-1 upgrade from non-safety to safety l PR-96-0195 PrEhsdnWorc6nsjptE$I J F._Sullivan related. J.EEndsley

" ^'

DRBS LER 96-019-00

()}22 dmpiithlrnjeKif:ihi'cailili~ bad m (If[Iss0e (Rf N $ 57 F((SuIlGan ;Infofmaij6E6fbil'ig r .,

and eddress;any operability concerns;that. . . . . . .

JQEndsley gathered-in. preparation to arise; P,C #96:3705 developing analytical model2 Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EEI - Escalated Enforcement item EA - Enforcement Action IDRP - Independent Design Review Patal IFI - Inspector Follw-up Item IPAP - Integrated Performance Assessment Process GL - Generic letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase 11 OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Droblem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9,1997

. t U.S. Nuctetr Regulatory Comunission '

i 3F1296-05 '

i Attachment B Page 14 of 21 {

RESTART ISStlES '!i hintenance/hteriel Condition Items - J. Campbell /J. Terry l

I ISSUE i ISSUE f - DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS -[

l M-1 Toxic gas monitoring (CL2 Channels) -

Repetitive failures.

PR-96-0382 J. Terry filifeifTsi(55%QQ

,1apcoweireliab"illtf;are ,

effectiveMlong tem lplari  ?

N189M)3 start-up lop *l3Pr1?Cto  ;

i i

f I

[

4 I

I i

Acronyms listed below correspond to those items listed in the issue Identifier coltan l

(*) EEI - Escalated Enforcement Item [

EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item .

IPAP - Integrated Perforsence Assessment Process  !

GL - Generic Letter [

LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II ,

OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report .

i REA - Request for Engineering Assistance <

WARN - FPC Workaroundlist URI - Unresolved Item [

VIO - Violation I 3 i January 9, 1997 7 i

i-i s

k

U.S. Nuclear Ergulatory Connission 3F1296-05 Attachment B Page 15 of 21 M-2 Main control board deficiencies - too many. WARN f47 J. Campbell Updale'TasjoflN2/97$

(Goal <10). Maintenance; work!d%9 Planning' hold e 1 Resolve all that can be resolved without de- Schedulinghold@

fueling or having to be at power. Material.holdM11@.,

Engineeping hold $

Engineering;needtto .

~ .

evaluate whyl_4lto--5fnew deficienciesjarebeing edded to.the[11stlweekly;as 1

thi.s xhallenges the goallto get'the number below 102 M-3 MUV-103 - repetitive seat leakage. PR-96-0121 J. Terry ConcepEial M I.lgn?d6snge developoentfi(progress (

WARN #49 M-4 Surveillance (charcoal) tr.sti'.g complete on OCR: AH-96-AHFL-1 J. Terry Nis5TsE*disdEihicjlsif6 air handling system. AH-96-AHFL-2A )niplace filterf testing ^  ;

AH-96-A6L-2B criterlajfor;

~~" ~ ~~^"'"'" ~

AHFL-1/2?

AH-96-AHFL-2C AH-96-AHFL-20 i

Acronyms listed below correspond to those items listed in the Issue Identifier colmn ]

(*) EE! - Escalated Enforcement item EA - Enforcement Action IDRP - Independent Design Review Panet ,

IFl - Inspector Follow-up Item i IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensea Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaromdlist URI - Unresolved Item VIO - Violation January 9, 1997

a

~

U.S. tuclear Regulatory Connission ' I 3F1296-05  !

Attachment B l Page 16 of 21 4

M-5 Turbine lube oli piping failure analysis. PR45435d J. Terry PR$96435005EIN~rf6sn"E -

(frspArtic6fsN hamponentifallsre.Lanalysjs '

Determine cause of piping failure and Cohect19eLActi66 Pki96635(4057 2 i ~s bfftheierAbkitinithefp' peg implement actions to prevent recurrence. $teps'jjM][" hyDonovjpMjfpsFij du RJa g )0 $ 99 f _

PR461 0356-Off PRW0s@01CNff6fiii

$[yas,%@ddjjyjhy fo M roof c k jna) $jj pht h event;1sidug Febrdri41#199F' r i

r

?

s t

I I I

t Acronyms listed below correspond to those items listed in the Issue Identifier colunri f

?

(*) EEI - Escalated Enforcement Item "

[

EA - Enforcement Action IDRP - Independent Design Review Panel  ;

lFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Ietter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II ,

OCR - Operability Concerns Resolution -

PC - FPC Precursor Card ,

PR - FPC Problem Report i REA - Request for Engineering Assistance <

WARM - FPC Workaroundlist URI - Unresolved Item VIO - Violation f

January 9, 1997 d

s b

d 9 .

U.S. Cucteer Regulstory Comission 3F1296-05 Attachment B Page 17 of 21 RESTART ISSUES Orgaalzational and Programatic (0 & F) Itens - D. Wilder ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS OP-1 Improve safety culture: MCAP II P. Beard R$ltsR/DWe"dG5tliff97

- establish site wide priorities which emphasize a safety culture Standdownishcurred BE1997. JHandoutsFgiven t *Jsidiir)6

- comunicate, ad'certise, coach, and hl) persohnel outlinedjthe constantly reinforce safety culture down Restartflanf Restarf "' '

throughout the organization Management Guideline?

- conduct a Safety Culture Index which will jii esent! sta_tusiof; the, be evaluated at periodic intervals ~

Restart?

Nucleklophrat1ons*Vislo Issues?andithe _h_3 OP-2 Upgrade the problem reporting (CP-111) IPAP Report J. Baumstark (fjIll[Riyfs(5fi}3$,(.

program. MCAP II !ssued2LEffectfyedatQ QQ2/964 Eliminates problem reports and replaces with one graded precursor approach.

Acronyms listed below correspond to those items listed in the Issue Identifier column

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundtist URI - Unresolved item VIO - Violation January 9, 1997

U.S. Nucletr Regut& tory Consnission 3F1296-05 Attachment B Page 18 of 21 ISSUE ISSUE i DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS OP-3 Upgrade the root cause (CP-144) program. IPAP Report J. Baumstark Soyk35(feAtjjiik)rogfed}

EEI 96-12-03 OP-4 Upgrade the operability /reportability (CP- VIO 94-27-02 R. Davis CPfl50'dfaft)'onylskiMCPj 150/151) program. VIO 94-27-03 151W Revision C Aissued!

pfective;_ dater 1,1/22/96}

Separate and better define the two processes.

Provide better guidance for decision making.

OP-5 Upgrade the 50.59 review process. EEI 96-12-03 B. Gutherman HMCPf65fthdEExpeR spprovalfofsll?affected a

Improve program and provide training to the p[ocedure{by';;-2/28/97f people to be qualified for writing and reviewing 50.59s.

OP-6 Upgrade the engineering calculation process. EEI 96-12-04 K. Baker C0freAih5N'Eddii5fcitie%IE EA 95-126 NOV 1.D.' HNarchl193R Address issue of using unverified case studies.

Acronyms listed below correspond to those items listed in the Issue Identifier colunn

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panet IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase !!

OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9, 1997

'i U.S. Nuclear Regulatory Comunission ,

3F1296-05 Attachment B' Page 19 of 21 ISSUE i ISSUE # DESCRIPTION IDENTIFIER (*) ACTION ASSIGNED TO STATUS I i

OP-7 Upgrade the design basis program to include: IDRP Report K. Baker M Yin W %i R in 0 ' ' '

RevistoE0!Osssed.T[5f!

- ownership IPAP Report ,

- definition &ffectfjjgtejQj[30[56}

- documents included in scope (clearly define intent) j OP-8 Establish a high-level configuration control VIO 96-05-05 K. Baker flifffisi?MPefdd?Md i procedure (N00). VIO 96-09 gjunej l99[f '~~ ~~~^~'

Establish and document management i expectations for the program. ,

t t

[

r l

t L

s r

Acronyms listed below correspond to those items listed in the Issue Identifier column i

(*) EEI - Escalated Enforcement Item t EA - Enforcement Action j IDRP - Independent Design Review Panel  ;

IFI - Inspector Follow-tp Item  !

IPAP - Integrated Performance Assessment Process I

GL - Generic Letter LER - Licensee Event Report I MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution i PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance f WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation .

January 9, 1997 ,

{

t t

. _ . . _ . _ _ _ _ . _ _m . _ , . _ _ . . ..______..__._.________m.. _ _ _ . _ . _ _ ._____._ _ _-m___ m._.._ ._ ._ - . _m._______.__m__ _ _. .___ _ . _ ___ ..._. _ _ _ _ _ _ . . . _ _ _ . _ _ . . _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ - _ _ _ . _ _ _ . +

U.S. Nucle 4r Regulatory Comitsion 3F1296-05 Attachment B Page 20 of 21 RESTART ISSUES Operator Readiness Items - R. Davis ISSUE ISSUE # DESCRIPTION IDENTIFIER (*) ACTION AS$1GNED TO STATUS (RI 96-201-03 J. Ma:, eda 0-1 OP-103 A&B curves - need to be validated. Flih{.E'{R5feElf[EUNeA URI 96-201-05 )n-progresst;s Scheduled Verify and validate whether curves are design EA 95-126 NOV I.C.2 completion-date.R 3/972 basis and what that basis is. WARN #21 & #24 Phase'l2idimp;tementatitR6f recomendations' fra Phase' 1.43cheduled ccxnpletion '

date t 8/972 Phasp3SIspj%iiQKo(

procedurefchanges4 Scheduled~~'c..o.m.

pl.~et.1ElsEF3 9

Acronyms listed below correspond to those items listed in the Issue Identifier colum

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Inspector Follow-up Item IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9,'1997

U.S. Nuctser Reguistory Consnission 3F1296-05 Attachment B Page 21 of 21 0-2 - Verify SP's for containment integrity: SP- LER 96-018-00 J. Maseda fr5}idli*d$ ai n U ly[40s 324, 341, 346. LER 96-018-01 ' omplete>3To?dateZfortyi c

enfpenet/$tlons?have'been

- Develop new detailed as-built mechanical hompletelf walked-down ' ^^

penetration drawings. Seven'mismatchesibetween

.he.F$ $ dndlthe 315'scops t

- Address tests, vents, and drains issue. havelbeenfoundRTwelve'"~

mo_re: penetrations.areMn_

warious!walkhdown" status 20, Aidesiston:hai:been madestc halkddoweithe M netifat' ions' hlafed .t'olth$ thermal' ' "

heliefsIbefore(that~ "

hodificattoisstarts;%N go back7to$ verify;the-MAR co$ponents"oncMcompleted3 0-3 Complete operator training on E0P/AP/0P N/A R. Davis (UIrWnil{AssjffdhAR' changes resulting from restart issues. package 1 Acronyms listed below correspond to those items listed in the Issue Identifier cotten

(*) EEI - Escalated Enforcement Item EA - Enforcement Action IDRP - Independent Design Review Panel IFI - Inspector Follow-up Item  ;

IPAP - Integrated Performance Assessment Process GL - Generic Letter LER - Licensee Event Report MCAP II - Management Corrective Action Plan, Phase II OCR - Operability Concerns Resolution PC - FPC Precursor Card PR - FPC Problem Report REA - Request for Engineering Assistance WARN - FPC Workaroundlist URI - Unresolved Item VIO - Violation January 9, 1997 s

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _____ __