ML20149H024

Summary of Restart Panel Meeting Conducted at Crngp on 970619 Re Items Included on NRC Mc 0350 Restart Matrix & FPC Restart List.Meeting Handout & List of Attendees Encl

ML20149H024
Person / Time
Site:	Crystal River
Issue date:	06/26/1997
From:	Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Richard Anderson FLORIDA POWER CORP.
References
NUDOCS 9707240176
Download: ML20149H024 (39)

Text

.

l i

['

i June 26, 1997 l

Florida Power Corporation Crystal River Energy Compley

- Mr. Roy A. Anderson (SA2A)

Sr. VP, Nuclear Operations ATTN: Mgr., Nuclear Licensing 1

15760 West Power Line Street l

Crystal River, FL 34428-6708

SUBJECT:

MEETING

SUMMARY

CRYSTAL RIVER 3 RESTART PANEL CRYSTAL RIVER 3 - DOCKET NO. 50-302 i

f

Dear Mr. Anderson:

i l

This refers to the Restart Panel meeting conducted at the Crystal River-facility on June 19. 1997. The purpose of the meeting was to discuss the j

items included on the NRC Manual Chapter 0350 restart matrix and the FPC-4 restart list. A list of attendees and a copy of your handout is enclosed.

l In accordance with Section 2.790 of the NRC's " Rule of Practice." Part 2.

l

-Title 10. Code of Federal Regulations, a copy of this letter and its enclosure p

will be placed in the NRC Public Document Room.

Should you have any questions concerning this letter, please contact me at (404) 562-4600.

9 l

Sincerely, Orig signed by Harold Christensen Johns P. Jaudon, Director Division of Reactor Safety i

Docket No. 50-302 l

L1 cense Nos. DPR-72 l

i l

Enclosures:

1.

List of Attendees 2.

FPC Handout cc w/encls:

John P. Cowan, Vice President Nuclear Production (NA2E)

.FPC.-Crystal R1ver Energy Complex 15760 West Power Line Street Crystal River, FL 34428-6708 cc w/encls:

See page 2 i

0FFICIAL COPY I

o ') O O Q O

1. hIy I

9707240176 970626 PDR ADOCK 05000302 k

l P

PDR L_.

Nj

I FPC 2

cc w/encls: -Continued 1

. B.:J. Hickle. Director-Nuclear. Plant Operations-(NA2C)

FPC Crystal River Energy Complex 15760 West Power Line Street

- Crystal River.-FL. 34428-6708 L

Robert E. Grazio, Director Nuclear Regulatory Affairs (SA2A)

FPC, Crystal River Energy Complex -

15760 West Power Line Street l

Crystal' River. FL. 34428-6708 James S. Baumstark. Director L

Quality Programs (SA2C)

FPC. Crystal River. Energy Complex i-15760 West Power Line Street l

Crystal River. FL 34428-6708

- R. Alexander Glenn. Corporate Counsel r

L Florida Power Corporation L.

MAC - ASA l

P. O. Box 14042 L

St. Petersburg. FL '33723-4042 l:

l-Attorney. General Department of Legal Affairs

-The Capitol Tallahassee FL' 32304 Bill Passetti l

Office of Radiation Control De)artment of Health and' Rehabilitative Services 1317.Winewood Boulevard l

Tallahassee. FL 32399-0700 L

l' Joe Myers. Director L

Division'of Emergency Preparedness l;

Department of Community Affairs

. 2740 Centerview Drive

-Tallahassee FL' 32399-2100 Chairman i

Board of County Commissioners

- Citrus County 110 N. Apopka Avenue Inverness. FL '34450-4245 Robert B.'Borsum Framatome Technologies

'1700 Rockville Pike. Suite 525 Rockville. MD: 20852-1631

1 FPC.

3 Distribution w/encis:

L,.Raghavan, NRR

'B, Crowley, RII' G.' Hopper, RII PUBLIC i

NRC Resident Inspector-U.S. Nuclear Regulatory Commission i

6745 N. Tallahassee Road Crystal River. FL 34428 i

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b 0FFICE SIGNATURE NAME SRu ' sail.

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DATE

~pL.d,(O 'I 97 06/fD/97 06 /'

/ 97 06 / '

/ 97 06 /

/ 97 06 / - / 97 COPY?

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L LIST OF. ATTENDEES plorida'PowerCorooration-J. Baumstark. Director, Quality Programs J. Cowan Vice President. Nuclear Production u

R. Grazio. Director. Regulatory Affairs l

G. Hanlon, Assistant Plant Director i

B..Hickle,. Director, Restart J. Holder.' Engineering Director D. Kunsemiller. Manager, Nuclear Licensing.

M.-Marano. Director.-Site and Business Restart J. Maseda, Manager. Engineering Programs, C. Pardee. Director, Nuclear Plant Operations

.F. Sullivan,' Manager. Nuclear Operations Engineering

-J.. Terry. Manager. Nuclear Plant Technical Support y

T.-. Taylor, Director, Nuclear Training E. Vilade, Communications l

l Nuclear Reculatory Commission -

.S., Cahill, Senior Resident Inspector. Crystal River L

K. Clark Senior Public Affairs. Region II C.' Christensen' Engineering Branch Chief. Division Reactor Safety M. Da]as. Executive Director' for Operations Regional Coordinator F. Headon. Director II-3, Office Of Nuclear Reactor Regulations-(NRR)

J. Jaudon. Director. DRS C. Julian Technical Assistant, DRS K. Landis. Chief. Branch 3 Division of Reactor Projects

,L. Plisco, Chief. 0versight Branch,'NRR

=

L. Raghavan, Project Manager, Project Directorate II-3, NRR Media Reoresentatives and Other Interested Parties L

R. Colthorse. General Manager; NUS Information Services Inc.

1 I. ' James. Re]orter St.. Petersburg Times L

lR. Russell, Research: Assistant Florida Public Service Commission.

D.' Sells. Consultant. Florida Municipal Power Agency M. Schmid. Producer / Reporter. Florida Public-Television A.LStruck Public J.' Struck. Public l;

J. Tunstall Reporter. Tampa Tribune L

l.

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-l FLORIDA POWER CORPORATION

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FPC CR-3 FPC RESTART PROGRESS June 19,1997

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6/19/97 cncksure 2

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FLORIDA POWER CORPORATION hr, CRYSTAL RIVER - UNIT 3 3

j FPC CR-3 l

FPC RESTART i

PROGRESS l

June 19,1997 i

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6/19,-

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l AGENDA i

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gC Opening Remarks J. P. Jaudon / J. P. Cowan 3

j Restart Status J.P.Cowan

=

Condition of CR-3 at Startup /

Metrics to Measure Performance B. J. Ilickle j

Operations Focus Areas C. G. Pardee

=

Engineering Progress J. J. Holden l

Configuration Document l

Integration Program G. H. Halnon l

Employee Concerns Program J. S. Baumstark I

MCAP Il Progress J. S. Baumstark i

a Concluding Statements J. P. Cowan / J. P. Jaudon 6/19/97 i

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Current Status

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FPC i

• Electrical

- 230 kV Line is Operable l

- 500 kV Line is Available

- A and B Diesel Generators Operable

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• Primary System j

- Filled with Nitrogen in Pressurizer

- Nozzle Dams for Steam Generator installed j

- Steam Generator Open for inspection l

- Decay Heat Removal Trains A and B s/19/s7 Operable i-i CR - 3 Readiness Program I

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3. )r7 Objectives 4

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1. Frequent Open Communications c

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2. Resolution of Confirmatory Action Letter issues

3. Close Book on First 20 Years of Operation j

4. Invest for the Next 20 years of Operation l

5. Integrate Startup Activities into 1.ong Term improvement Plan Do What is Right For The Long Haul, i

Not Just What is Required For Startup 6/19/97 4

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Design issue Description NRC Briefings NRC Submittal &

Modification Operations Tech Staff Restart Panel Follow-up Briefind Work Testing Acceptance j

A. HPl Pump Recirculation Line May 8 May 9 Jun 30 / Jul 10 %

Oct Nov I

B. HPl System Modifications May 8 May 9 Complete / Jun 24 40 %

Jul - Nov Nov i

C. LPI Pump Mission Time May8 May 9 Complete 95 %

Complete Sep D. Reactor Building Spray Pump May 8 May 9 IBD 70 %

Aug Sep l

- NPSH f

E. Emergency Feedwater System Mar 18 Mar 21 Complete / Jul 60 %

May - Sep Nov

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and Diesel Generator Load Impact F. Emergency Diesel Generator Mar 18 &

Mar 21 &

Sep 15 60 %

Jul - Sep Oct Loading May8 May 9 l

G. Failure Modes and Effects Jul Jul Jul 30 / Aug 90 %

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- Self-identified Precursors No less than 60 %

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a System Readiness

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- Temporary Modifications No more than S l

- Requests for Engineering Assistance No more than 200 Open I

- Restart Modifications 0

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- Systems Accepted by Operations All 105 Systems Accepted 11 i

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Condition of CR-3 3

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1 FPC CR-3 PerfornianCe Indicators Goal at Startup i

l Operations Readiness

- Co.itrol Board Deliciencies No more than 10

- Operator Work Arounds No more than 7 i

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- Operating Procedures No more than 25 i

Comments l

Emergency Operating Procedures All [0Ps issued Abnormal Procedures No more than 15 I

Comments Regulatory Readiness Ucense Amendments and Tech Spec Submittals All Submittals Made

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- Opportunity to Tour Plant All Elected Officials and.

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- Open Communication with Media Editorial Boards, j

interviews, and Plant Tours l-Conducted for Those who Routinely Comr CR-3 6/19/97 13 i

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 6/19/97 22

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- Goal no more than 10 at Start Up

-Actual 20 -

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1997

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FPC CR-3

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900 -

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Regulatory Readiness License Amendments and Tech Spec Submittals FPC c

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1997 6/19/97 30 1

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Regulatory Readiness i

Total 1997 Commitments I

FPC CR-3 200 -

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'g 5 140 -

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120 -

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u '00 ~

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' 60 -

's \\

40 -

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5 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 6/19/97 32

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Point-Based System 4

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-Technical Content f

-Timeliness

-Need for Supplement i

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l Regulatory Readiness j

Submittal Quality c

bR 3 g,

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 6/19/97 34

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6/19/97 36

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Communications Plan l

Organizational l

Otk[4 Communications Effectiveness l

FPC i

ca-3 AREAS I-My direct supervisor keeps 4

me informed II I understand critical a

restart issues a

e 111 I understand safety regulations and standards l

IV I know wiiat is expected of 2

l me and how I fit into the

{

" big picture" j

V Support communications 1

materials enhance my l

understanding of CR-3 1

issues o

i on,.jor

.,...............,,..v Operations Focus Areas rec 5

CR-3 j

Improve Performance m.

1 i

-Operations Ownership

-Plant Configuration Control 6/19/97 38

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l Operations Focus Areas l

ENf3

• Reduction in Watchstander l

Distractions

-Move Non-Critical Functions Outside of Control Room i

-Focus Operating Staff on

• Striving for Flawless Execution Proactively identifying / Driving issues 6/19/97 39 l

=-

Operations Focus Areas

.p as EIS

• Consistent Application of Standards

-Control Room Formality

-Pre 40b Brief Quality

-Self Assessment Effectiveness t

6/19/97 40

1 I

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Operations Focus Areas d

i 1

FPC CR.3 Staffing / Organization Structure j

-Clarity of Roles and Responsibilities l

-Staffing Levels i

1 i'

{

t. -

j 1

6/19/97 l

41

(

4 l

(

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d-b l

L l

FPEC GUG3 i

l 1

l Engineering Progress i

i i

I i

6/19/97 42 l

1.

I

i j

1' i

i Design issues identified in FPC Letter of 10/28/96 i

!ES

. B.

HPI SB LOCA Improvement Mods l

- HPI Cavitating Venturis 1

Installed / Tested / Removed /

j Spool Pieces Re-installed l

-HPI Crosstie Piping / Valves

• 4 Additional Valves installed-Locked l

Closed

-Normal Make-Up Automatic isolation 6/19/97 o

L i

l l

Design issues identified in

~"

t 6

l FPC Letter of 10/28/96 SES l

F.

Emergency Diesel Generator j

Loading i

-Upgraded Both EDG Engines

-Currently Planning Radiator l

Change Out

-Improved kW Meter Accuracy I

j 6/19/97 j'

44 4

1 1

l Appendix "R" issues i

rec ca.3 l

Reactor Coolant Pump Oil Collection

• Independent Assessment of Fire Study l

Remote Shutdown Capability l

information Notice 92-18 Evaluation l

• Atmospheric Dump Valves 1

l 6/19/97

]

45 Appendix "R" issues j.

i rF l

!NS I

i

• Control Room Evacuation Procedure

• Source Range Nuclear j

l Instrumentation Detectors l

• Thermo-l_ag i

i

~

-Implementation Plan Schedule l

l

-Exemption Requests

?

j 6/19/97 46 1

i l

l

i i

l Restart issue Modifications s

3

• Total Modifications 43 l

l

• Design Issued 19 i

l

• Ready For Field 16 6/19/97 47 i

i j

System Readiness Review j

Assessment Completion

!KS i

• Level 1 Systems 100%

i l

• Level 2 Systems 67%

4

• Level 3 Systems 19%

6/19/97 48

p.

l t

l System Readiness Review l

Attribute Evaluation a

FPC j

Attribute C"'

l Checks 11648 l

SAT Discrepancy Reportability 4

l 10529 1119 operability Work Controls Restart Process Issue l

9 960 159 i

i I

i j

Configuration Document i

integration Project FPC

' " ~ '

l' Project input Information From

- System Readiness Review, Precursor l

Cards, Problem Reports, Docket Review, l

independent FSAR Review, Individual j

Reviews, Modifications, Analyses Consolidate information into Specific Plant System Information Sets Resolve'Open items Update the Plant Documents 6/19/97

- FSAR, EDBD, ITS Bases, ABD 50

~

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Configuration Document i

$gMg Integration Project Status 4

FPC i

Scope of FSAR Revision 24 Revision 24 Will Be Technically Accurate

- Restart issues Will be incorporated i

- Freeze Date for Non-Restart issues is J

L August 18,1997 l

- Chapter 14 Accident Analyses Being l

Reviewed to Ensure Properly Reflected

- Design Basis Documents, ITS Bases, and s.

l Procedures Will Reflect the Same Changes ofi.for l

Configuration Document Integration Project Status 1

l Currently Compiled 21 of 49 I

System Information Sets I

~

Currently 1500 Open items in the Database

-37 Items Currently Resolved

-142 Items Currently Being Worked

-Remainder of items Will be Addressed 6/19,97 52

~_

L l

i i

Configuration Document integration Project Status

!!S j

16 of 49 FSAR Sections are l

Currently Being Revised i

l Integrated Configuration l

Management Institutionalized in l

/

Nuclear Operations Department l

Procedure l

-Carry Concepts Forward to i

Facilitate Change Processes o,io,,,

Employee Concerns Program

!KS Established by Nuclear Operations Department Procedure (NOD-36) in May 1991 Program Statistics Year input 94 (outage) 110 95 14 96 (outage) 63 97 (to date) 13 6/19/97 54

l i

l W '

Employee Concerns Program j.

M-.g 1996/1997 Totals by Receipt Method 4

FPC l

C R-3

(

Comment I

Office 20%

I'/'

Anonymous 8%.

i MaH Assigned l

13%

3%

Mail. written by station personnel Ofnce. interview witti ECP Representauve Comment. Suggestion related to site or company process Exit Assigned. Management request 6/19/97 49%

l l

55 i

a i

i Employee Concerns Program 1996/1997 Totals by Category i

FPC 2

CR-3 CIS H&l 20%

NSIQ 7%

9 MP 23 %

POIE 17%

NS/Q. Nuclear Safety iQuauty POIE. Plant Operahons f Engmeeting S/S. Industrial SafetyISecurtty RS Radiological Safety MP Management and Personnel H&l. Harasstnant and intimidation RS ciS. comm.niiSuggesuo" S/S 11 %

6/19/97 17%

$6

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Employee Concerns Program

7 l

S,L5 Assessments m

EES

• June 1996 NRC i

• August 1996 Third Party l

l

• August 1996 NRC i

l l

• June - July 1997 Third Party f

6/19/97 I

57 4

Employee Concerns Program Assessment Conclusions

!KS l

• Program is Effective Based on:

-Types of Concerns Submitted

-Employee Willingness to Use Management and Our Corrective Action Process 6/19/97 58

l.

i i

l Employee Concerns Program l

Initiatives 3

Third Party Assessment in June -

l l

July 1997 l

-Evaluate Program Design and l

Implementation With industry Best l

Practices l

-Determine Program Visibility and j

Credibility l

6/19/97 59 I.

j MCAP 11 Progress I

i 4

Rescrub For Restart Complete -

7 Additional items identified Status Update Provided Weekly On Track With Revision 2 Effectiveness Assessment in August 6/19/97 60 a

i l

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1 MCAP ll Progress

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7 14 l

FPC l

CR3 140

-e Workoff 120 -

-Actual l

,E 100 -

j 7

j 80 i

2 60 -

s E

40 -

N S

4 l

20 -

N % N*'

i 0

--e sits 5:525: 85is1 sis 1996 1897 1998 i

6/19/97 61 1

i

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i i

FPC CR-3 i

i j

j Concluding Statements 4

k I

6/19/97 62

NRC RESTART LICENSING SUBMITTALS Restart License Amendments Submittal Issue Date

1. Small Break LOCA Analysis Complete

2. Decay Heat - Flow Instrument Removal 7/11/97

3. Appendix R Thermolag Resolution Schedule (address exemption request) 7/25/97 41 Appendix R (III.O - Reactor Coolant Pump Oil Cooling) Potential Exemption 10/8/97 Withdrawal / Revision - When "A" pump is in compliance

5. System Readiness Review - Potential License Amendment if needed 6/23/97

6. Low Temp Over Pressurization (LTOPs) - Code Case N-514 exemption Complete

7. LTOPs - 15 Effective Full Power Years (EFPY) License Amendment 7/16/97

8. Emergency Operating Procedures (EOP) - Operator Actions License Amendment 7/1497 (Ifrequired)

9. EOP Letdown Rupture Line (Manual Action-Potential USQ) 7/14/97

10. Integrated Leak Ibte Test, App. J Option B Complete

11. Integrated Leak Rate Test, App. J Option B, Rev.1 Complete

12. RWP Cyclone Separator Fouling (Potential USQ) 6/23/97

13. Control Complex Habitability Envelope Technical Specification Change 7/28/97 Items 14-20, Potential USQ's Submittals

14. High Pressure Injection Pump Recirc 6/30/97

15. MUV-31(Pressurizer Level Control Valve) Control Logic 6/30/97

16. Emergency Diesel Generator Protective Trips during Engineered Safety Complete l

Actuation and Loss of Offsite Power

17. High Pressure Injection Analysis (without cavitatic; venturis)

Complete

18. High Pressure Injection Nozzle Cycles (Contained in the FSAR R.23 letter) 7/7/97

19. Air Handling Filter-1/2 6/30/97

20. Makeup Supply Valve (MUV-27) - Add automatic closure upon receipt of Complete

1. 1500 signal l

l l

J

I

21. Once Through Steam Generator (OTSG) License Amendment 211 Complete t

22. OTSO, License Amendment 211, Resubmit Sholly Notice Complete 23.OTSG Response to Additional Information Request from NRC 8/1/97 24 500kV Backfeed Revise Bases 3.8.1 & 3.8.2 9/1/97

25. License Amendment to revise Table 3.3.18-1 for functions /instmments 9/27/97

26. Reg. Guide 1.97 Issue (EDG kW Meters) 7/15/97 Licensing Restart Submittal (Non-License Amendments)

1. Boron Precipitation Letter (If needed) 9/2/97 2.- Appendix R Issues - Independent Assessment Summary 8/4/97 2a. Appendix R - Revise response to address 72 hr. cold shutdown 9/1/97

3. System Readiness Review - Summary Report 11/5/97 1

4. Generic Letter 96 Summary Report 7/21/97

5. FSAR Revision 23 - USQ Review 7/7/97 1

6 Generic Letter 96 Summary Report 7/10/97

7. Tendon Surveillan'ce Report (If needed) 9/15/97

8. Maintenance Rule Structural Baseline - Walkdown Summary Report 7/15/97

- 9. Integrated Safety Assessment of Current Outage Modifications - Summary Report 10.27/97 4

10. FSAR Rev. 24 upgrade program description 12/4/97

11. Restart Request Letter 12/1/97

12. RCS Attached Piping - Respond to NRC 4/7/97 Letter Complete

13. Supplemental response on jet impingement, Re: FPC Letter 6/5/97 on Dynamic 9/28/97 Load analysis

14. Loss of DC Power, Failure Modes Effect Analysis - Summary Report 7/30/97

)

i s

4

15. FSAR Rev. 24/25 Upgrade Program Description 7/28/97

.16, 50.54(f) Letter to address discrepancies (If needed) 8/19/97

17. HPI Nozzle Cycles Fatigue Analysis - change in Licensing Basis -

Under.

Review

18. Review ofImplementation of License Conditions Complete I

19; Licensing Basis for Dynamic Loads - Response to' NRC 4/10/97 letter

' Complete 20, Low Pressure Injection - Mission Time Complete i

21. Appendix R-Atmospheric Dump Valve 30 day Response Complete

)

22 System Readiness Review Plan Complete

23. EOP/AP Operator Action - Commitment Date Change Complete

24. GL 96-06, Letter regarding Service Water fittings Complete

25. ASME Section XI - Code Case Relief Request Complete

26. MCAP-II, Rev 2 '

Complete

27. ITS Bases Submittal Complete -

4 9

n

- - -. -