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Discusses 971030 & 31 Meetings Re Status of Actions to Resolve Technical Issues & Progress Toward Readiness for Restart.List of Attendees & Handouts Encl
	ML20202C923
Person / Time
Site:	Crystal River
Issue date:	11/21/1997
From:	Jaudon J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Richard Anderson; FLORIDA POWER CORP.
References
	NUDOCS 9712040101
	Download: ML20202C923 (109)
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tkuember 21, 1997 j

Florida Power Corporation Crystal River Energy Complex

'Mr. Roy A. Anderson (SA2A)

Sr. VP Nuclear Operations ATTN:

Mgr.. Nuclear Licensing 15760 West: Power Line Street i

Crystal River. FL 34428-6708 r

SUBJECT:

MEETING

SUMMARY

, CRYSTAL-RIVER 3 ENGINEERING AND RESTART MEETINGS _

j

Dear Mr. Anderson:

]

This refers to the meetings on October 30. and 31,1997, at your Training

' Center. The purpose of the meetings were to discuss the status of your actions to resolve technical issues and your progress toward readiness for restart.

It is.our opinion, that these meetings were beneficial, g

Enclosed is a List of Attendees and Florida Power Corporation (FPC) Handouts.

The discussions included the following topics: Configuration Document Integration Project (CDIP) Update. Emergency Diesel Genera +cr Update. Control i

Complex Habitability Envelope (CCHE) Update. Appendix "R" Update, and FPC Restart Progress Status, l

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

i

-Title 10 Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

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

-i Sincerely.

Original signed by Johns P. Jaudon t

Johns P. Jaudon.-Director Division of Reactor Safety

Enclosures:

1.

List of Attendees

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2.

FPC Handouts

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. Docket No. 50-302:

pod)hfb License No.-DPR-72 J

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BSSRE.EIE sw

t FPC-2

- I cc w/encls:

John P. Cowan, Vice President i

Nuclear Production (NME)

FPC. Crystal River Energy Complex 15760 West Power-Line Street Crystal River, FL-34428 6708 i

C. G. Pardee. Director t

Nuclear Plant Operations (NA2C)

FPC. Crystal River Energy Complex 15760 West-Power Line Street Crystal River, FL -34428-6708 i

B. J. Hickle. Director

. Nuclear Plant Operations (NA2C) i Florida Power Corporation Crystal River Energy Complex 4

- 15760 West Power Line Street l

Crystal Rivar, FL 34428-6708 Robert E. Grazio. Director Nuclear Regulatory Affairs (SA2A)

FPC. Crystal River Energy Complex 15760 West Power L1ne Street Crystal River, FL 34428-6708 4

James S. Baumstark, Director Quality Programs (SA2C)

FPC. Crystal River Energy Complex 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 33733-4042 I

Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304

- Bill Passetti Office of-Radiction Control De)artment of Health and Rehabilitative Services

- 1317 Winewood Boulevard i

Tallahassee, Ft 32399-0700 cc w/eacis continued:

See page 3 1

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4 FPC 3

i cc w/encls:

Continued i

Joe Myers. Director Division of Emergency Preparedness Department of Contr. unity Affairs 2740 Centerview Drive Tallahassee FL 32399-2100 t

che rman Board of County Comissioners i

ritrus County 110 N.-Apopka Avenue Inverness. FL 34450-4245 Ocoert B. Borsum Framatome Technologies 1700 ( v kville Pike. buite 525 Rockv1He 19 2'?89-1631 Distribution w/cnc13:

L. Raghavan. NRR R. Schin. KIl P. Steiner. Ril B. Crowley Ril F. Wright. RII-L. $tratton. RIl PuuliC NRC Resident inspntor U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River. FL 34428 4

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LIST OF ATTENDEES I

Florida Power Corocration R. Anaerton, Senior Vice President. Nuclear Operations J. Andrews. FPC J. Saumstark. Director Quality Programs G. Beuris, investor Relations J. Breman PSC Staff Engineer 4

R. Bright. Nuclear Principal Lirensing Engineer R. Colthorpe. General Manager. NUS Information Services l

J. Cowan, Vice President. Nuclear Production A. Glenn. Corporate Counsel R. Grazio. Director. Nuclear Regulatory Affairs i

G. Halnon. Assistant Plant Director. Nuclear Safety J. Holden. Site Director. Nuclear Engineering and Projects B. Hickle. Director. Restart P. Holmes-Ray. Senior Licensing Engineer E. Kane. Vice President. Engineering. Framatome D. Kunsemiller. Manager. Nuclear Licensing M. Marano. Director. Nuclear Site and Business Support J. Maseda. Manager. Nuclear Engineering Programs R. Haughan. Department Support Administration M. Clary. FPC

'R. McKeown. Vice President. Professional Development. CJRW J. Mckinnon. Chairman NGRC. FPC C. Pardee. Director. Nuclear Plant Operations A. Petrowsky. Manager. Nuclear Operations Engineering S. Powell. Principal Nuclear Licensing Engineer M. Rencheck, Director. Nuclear Engineering and Projects D. Sells Consultant. Florida Municipal Power Agency T. Taylor. Director. Nuclear Operations Training J. Terry. Manager Nuclear Plant Technical Support M. Van Sicklin Chief. Nuclear Operator E. Vilade. Communications Coordinator Nuclear Reaulatory Comission S. Cahill. Senior Resident inspector. Crystal River H. Christensen Chief. Engineering Branch. Region 11 (Rll)

K. Clark. Senior Peblic Affairs Officer. Ril F. Hebdon. Director. Project Directorate 11-1. Office of Nuclear Reactor Regulation (NRR)

J. Jaudon. Director. Division of Reactor Safety (DRS)

J. Johnson. Director. Division of Reactor Projects (DRP)

K. Landis. Chief. Branch 3. DRP S. Ninh. Project Engineer. DRP L. Raahavan. Project Manager. Project Directorate 11-1. NRR L. Reyes, Regional Administrator. RIl S. Collins. Director. NRR T. Cooper,' Resident inspector. Crystal Riter l

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R. Cundiff. Reporter.. Citrus County Chronicle i-H. Saeleno. Reporter. AP i

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AGENDA 1

= Configuration Document Integration Project (CDIP) Update a Emergency Diesel Generator Update a Control Complex Habita3ility Envelope (CCHE)

Update s Appencix R Upcate a Concluding Statements

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Design Basis Documents e Used Information. ' rom Extent of Condition Reviews as stated in the Confirmatory Action Letter m Deve.oping direction for future configuration contro o? t:1ese c ocuments i

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Translated into 2966 Document Changes

FSAR Related Document Changes......1836 s Total Issues Resolved This Outage...1131

Required for FS AR Revision 24............

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IA 2

Preliminary Test Results

<.g3 Toxic Gas e C;alorine a Sulfur Dioxide

'g 3

I MIb2 Control Complex

<p

.S.

Habitability Envelope a Su amit Revised Ha3ita3iLity Report 11/7/97

Identification of Current Licensing Basis

Dose Calculation Description

Leak Test Description

Basis for Acceptance of Revised Habitability Configuration a Su amit Tec anical Specification Change 11/21/97 m Preparc Operability Evaluation prior to Moc.e L iaw NRC GL91-18rl

..nnrw navy.n, w-M8

. Control Complex

.k Habitability Envelope I

I l

l Demonstrate Protection of the Control Room Personnel During Pos,tulated Events i

i

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Maintenance WRs Written.

Complete

Modification Field Work.

Complete

Modification Testing Complete

Remote Oil Fill Line Exemption.

Submitted

'O

. ~

dM, ES[h'*

1ppendix R Update Modifications

List of Issues and Modifications Provided to NRC 1

i l

7 of 20 Restart Issue Packages ready for review.

1 Field Construction Underway i

Design Work Continuing I

l I

i

a:a 1;s..m.

e

wshw_ _ <a

~

Appendix R Modifications W o rk j

l D e s c rip tio n N um be r D e sia n l P a cka c e l F ield W o rk ! T arno ve r i

D e g ra d e d S e a l M a te ria ls

97-06-07 01 11/17/97 i

RCP Lube O il C o lle c tio n 97-06-16-01 10/30/97 f

C T S e c o n d a ry P ro te ctio n i97-02-11-01 l

F G t1 - 1 (S tru c tu ra l) {

i F C id - 2 ( 5 0. 5 9)

RSP H o t S h o rts n 9 7 -0 3 -0 2 -01 11/27/97 F C ?J - 1 (S e p a ra tio n s ) l F C tJ -2 (tJ e w U S G D) l l

F C fJ - 3 (" A " B u s s it e m s )

F C t) - 2 (~B " T rain Ite m s ) l 11/17197 F C tJ -G (~ A ' T ra sn ite m s) b 11/20/97 D H V -3, 4 C a b le S e p a ra tio n

,97-02-18-01

'12/12/97

! 97-02-18-02 12/12/97

{

if4 9 2-18 M O V s l 9 7 -0 6-13 -01 11/25/97

}

F C tl - 1 l

1 112 7197 E m e rg e n c y Lig h tin g j

11/28/97 F C tJ - 1 (E D G A C C E S S )

10/30/97 1 P e n ding l

P e ndin g

{

11/28/97 l

A H F -2 2 0, C, D C a b le s (E D G ) j 9 7-0 5-19-01 11/17/97

~

l 9 7-0 5-17-0 2 12/1/97 j

EDG D e tu g e R ise r

[97-06-11-01 T h e rm o-L a g Circuit H e ro u te s i 97-05-17-01 11/12/97 1

i i

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1ppendix R Update l

IN 92-18 l

l

Re-evaluation Cornpleted. Hot Shutdown Valves being l

Modified.

Design / Field Work Package Issued i

j

Completion Scheduled 11/27/97 l

Review of New Plant Modifications continuing i

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FPC CR-3 FPC RESTART

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PROGRESS l

l l

October 31,1997 l

1 i

~

l 10/31/97 l

1 i

I..-...

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

AGENDA Y

w.g FPC CR-3 Opening Remarks R. A. Anderson Restart Status / CAL Status J.P.Cowan l

Operations Status / Update C. G. Pardee

~

Operations Training / Development T. H. Taylor Technical Issues M. W. Hencheck l

Corrective Action Program J. J. Holden j

Regulatory Submittal Status R. E. Grazio Restart Readiness / CH-3 Metrics B. J. Hickle i

o/3 Concluding Statements R. A. Anderson 2

i l

j 7,,7 l

~-

Current Status MiI.

m FPC CR-3 Plant Conditions Preparation for Final Vacuum Control Complex Habitability Envelope (CCHE) Tests

~

Diesel Generator Work 10/31/97 3

CR

- 3 Readiness Program et&p Objectives FPC CR-3

(

1. Frequent Open Communications

2. Resolution of Confirmatory Action Letter Issues

3. Close Book on First 20 Years of Operation

4. Invest for the Next 20 years of Operation

5. Integrate Startup Activities Into Long Term l

Improvement Plan Do What Is Right For The Long Haul, Not Just What is Required For Startup l

10/31/97 l

4

m i

Restart Schedule

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= 3rd Otr96

= dth tr 98

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i l

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Plant Modifications Enni ;;;ina 2

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Procedures And Training EOPIAPIOP Training m

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10/31/97

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% Complete FPC CR-3

1. Design Issues Identified in FPC 95 %

l Letter of 10/28/96

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2. Extent of Condition Reviews 100 %

i l

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Operator Training Self-Evaluation 10/31/97 20 l

l Operations Readiness for i

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Performance Measures in Place

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l "+F Technical Issues

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Ensergency Diesel Generator l

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I[

Diesei Generator Margin l

FPC 3500 kW CR-3 30 Min. Rating 3400 kW 3300 kW l

200 Hr. Rating 3250 kW (ITS Ilpper SR L.imit) 1

-~ s 3200'kW 3159 kW Auto Cormect Load MGR I

i

~~ ~

~'

- %W"N5b. ! - 3kWi ITS Lower SR Limit 3100 kW 3000 kW 2000 Hr. Rating

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2850 kW Contin. Rating 10/31/97 Sept. '96 Oct. '97 24

p.

Control Complex m

l r%Y*4 Habitability Envelope 9

4 FPC I

i l

CR-3 l

Assess and Seal Penetrations i

Initial Phase for Conduits Completed on 10/10/97 Perform Information Test i

Test Complete Install Redundant and New Dampers in Each Isolation Path Modification Package issued, Completion by 11/17/97 Revise and Consolidate Calculations Calculations in Final Review, Completion by 11/14/97 Demonstrate Operator Exposure is within Limits Test Complete, Results in Review 10/31/97 25

(,_-

-=

Appendix R Modifications g%m9 %P 4-

.C 3

W ork FPC i

CR-3 D e s c rip tio n l Number Design ! Package Field Work ! Turnover

(

De g ra d e d S e a i M a te ria is j 9 7-06-0 7-01 W O R KIN G 11/17/97 R P Lube lie ctio n i 9 7-0S-16-01 10/30/97 CT S e conda ry P rote ction

{97-02-11-01

~

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l

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__... _ _.j 97-02-18-01 W O R KIN G.

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Em e rge ncy Lig hting W O R KIN G 11/28/97 FCN-1 (EDG A CCESS) 10/30/97, P ending i P endin g l'

~11/28/97 A HF-228, C, D Ca bles (EDG) { 97-05-19-01 W O R KIN G 11/17/97

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l 97-05-17-02 W O R KIN G 12/1/97 i

s

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97-05-17-01 W O R KIN G 11/12/97 i

10/31/97 26 l

e a

W Corrective Action Program DtkiR~

CARB Effectiveness FPc CR-3

- Ensuring Quality of Root Causes l

Reduction of CAP Open Items

- Decreasing Trend 3 Barriers of Defense in Depth for PCs Required for Restart

- PCs Screened as Restart Issues

- PCs Screened as System Readiness Review Issues 1

- Ali Corrective Actions Reviewed for Mode Restraint New CAP Information System Implemented 10/1/97

- Facilitates Tracking Mode Restraints at 10/31/97 Corrective Action I_evel 27 i

i I

DE 4

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N

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4 Status of License Amendment FPC and Tech Spec Submittals ca-3 l

Letter S ubmittal D escription Technical P repared D ate Input C om plete l

Appendix R - RCP Withdraw 10/31/97 10/31/97 11/3/97 11/7/97 Exemption Service Water Overheating 10/31/97 10/31/97 11/18/97 11/24/97 i

CCHE Test Results 10/31/97 10/31/97 11/4/97 11/7/97 l

l CCHE/CREVS Surveillance 10/31/97 11/6/97 11/18/97 11/24/97 i

f 10/31/97 10/31/97 11/4/97 11/7/97 e

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D escription Technical P repa red C om plete D ate Input 4

Reactor Coolant System Attached Com plete Com plete 10/30/97 10/31/97 Piping Fatigue Analysis f

Integrated Safety Assessment 11/26/97 11/27/97 11/28/97 12/1/97 Jet Impingement Supplement 11/4/97 11/5/97 11/7/97 11/10/97 I

Letdown Line Rupture - NRC RAI Complete 10/30/97 10/31/97 11/3/97 i

System Readiness Review 11/7/97 11/10/97 11/14/97 11/14/97 P rogram Summary Report NRC RAI-Emergency Diesel 10/31/97 11/3/97 11/5/97 11/7/97 e

Generator Protective Trips j

NRC RAI-Emergency Diesel 10/31/97 11/3/97 11/5/97 11/7/97 Generator Testing Restart Request Letter 11/21/97 11/21/97 12/1/97 12/1/97 10/31/97 FSAR Revision 24 11/21/97 11/21/97 12/3/97 12/4/97

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B. MCAP 11 Restart item Closure 0

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O. Self-identified Precursors 60 % or Greater December D. Self-identified Violations 33 % or Greater 35.7%

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61 December E. Systems Remaining to be 0

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9 Noseenber C. Total 1997 Commitments 0

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C. State & Federal Officials / Staff Meet Prior to Startup Complete Achiesed D. Opportunity to Tour Plant Elected Officiais and Staff Consplete Achieved Imited to Tour I

E. Open Communication Editorial Boards, Inteniews, and Complete Achiesed j

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52

Communications Readiness FPC 4

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Positive Community Meetings:

j

- Crystal River Held

- Inverness Held j

- Beverly Hills Held j

- Inglis/ Yankeetown Scheduled

- Crystal River Planned l

Local Civic Organization Briefings

- United Way, Kiwanis, Lions Club, Rotary Clubs i

l Improved Communication Effectiveness i

10/31/97 53

1 Communication Effectiveness Indicators

{

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j Area II - I understand critical restart issues.

Area III - I understand safety regulations and standards.

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l i

10/31/97 j

54 j

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Technical Issues Being Resolved i

Performance Indicators Show Improved Performance Organizations Understand Vision for 2000+

10/31/97 55

i i

"~' M Preparing for the Next i

! 38*5 Twenty Years e

i i

FPC

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Increasing Margin

Reducing Operamr Burden Resolving Long Term Issues

Improving Reliability i

Improving Performance

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10/31/97 56

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TOTAL POTENTIAL USQs 22 i

RESOLVED 13 1

SUBMITTED 5

1 1

l REMAINING 4

i i

w eavguso star es

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USQs m

~~

Status / Resolution Issue Resolution Status Boron Precipitation Mitigation - Hot Leg injection Potential USQ - implementation of Hot Leg injection (not a Open - due 11/7 g

restart requirement)

Seismic Qualification of Waste Gas / Liquid / Solid Pipe Potential USQ - quahfication of piping to meet the seismic Open - due 11/7 requirements is being reviewed Control Complex - Leak Test Results Potential USO - test methodology and dose calculation Open - due 11/7 currently under review RB Cooler /SW System Overheating Potential USQ - addressing the SW system temperature limit Open - due 11/24 and ultimate heat sink Boron Precipitation - Incorporation of Gaps (LAR 223)

USQ - credit for hot leg nozzle gaps as a passive method Submitted - 10/31 together with active methods and decision matrix for boron precipitation prevention EDG Fan Upgrade - fans under capacity (LAR 216)

USO - requires NRC review and approval prior to startup Submitted - 8/26 Letdown Line Rupture - manual operator action in place of USQ - requires NRC review and approval pricr to startup Submitted - 9/9 l automatic (LAR 218)

EDG Protective Trips - insta:lation of ove voltage trips could USQ - requires NRC review and approval prior to startup Submitted - 9/12 result in trip of EDG (LAR 219)

AHF-1C - this modification makes control logic changes to Not a USO for instartation, however, use of it will be due to Submitted - 10/4 FJ1ow use of AHF-1C by providing interlocks with its MCC-reliability of circuitry being modified and use of operator 3AB transfer switch (LAR 217) actions. Modification will be made but not tumed over until LAR approved.

EOP operator actions Not a USO - no new USQs were identified Resolved M OAvf 4J50 ptrv 03g

c-USQs Y EN_-.

=m-

~g Status / Resolution

%~nd V'.)

Issue Resolution Status HPI Cavitating Venturi Flow Test Not a USQ - FPC dete:Wned that attemate approach would be Resolved developed for insta!!at on in Refueling Outage 11 R Main Steam Line Break Not a USQ - reanalysis with original assumptions performed Resolved RWP Cyclone Separator Fouling - strainers instatied upstream Not a USO - new strainer tested and no clogging resulted Resolved might have clogged resulting in a loss of RWPs HPl Pump Recire. Line - MAR 96-11-02-01, proposes to instal!

Not a USO - actions idenbfied for operator action were Resolved an attemate manual recirculation line from HPI discharge header concluded to be equivaient to existing actions and the RB (operator action)

MUV-31 (Pressurizer Level Control Valve) control logic response Not a USQ - design change is like for like reciacement Resolved during transient conditions - replacement of some parts HPI Nozzle Cycles - planned change in methodology reflected in Not a USQ - change not implemented; submitted with FSAR R23 Resolved FSAR increated allowable thermal cycles from 11 to 80 letter, will correct FSAR back to 11 from 60 and maintain approved methodology AHFL - 1/2 testing not in compliance with FSAR Not a USO - FPC wdl comply with testing requirements Resolved MUV MAR 97-02-17-01 HPI autoclosure, add automatic Not a USQ - action is an aid to the operator, no credit for actions Resolved closure upon receipt of 1500* RCS low pressure signal in DBA analysis; this is reflected in SBLOCA submittal Remote shutdown panel fuses as originally intended to be Not a USO - revised design Resolved installed would not extinguish MCR lights on failure CT protectors addition could reduce availability of bus Not a USO - overall bus availability determined no discemible Resolved impact ADV capacity does riot meet FSAR values (301,000 lb/hr vs.

Not a USO - ADVs had overcapacity and can perform function Resolved 419,700 lb!hr) with existing intemals; action is to clarify FSAR information and resolve ambiguity regarding ADV actual capacity HPl isolation Criteria Not a USQ Resolved

NRC RESTART LICENSING SUBMITTALS 1030 97 l

4 1 sinc Submittal Date Restart License Amendments I.

Small llreak LOCA Analysis - TSCRN 210 Complete 6/14/97 a.

TSCRN 210 (SBLOCA)- Supplement I (Fuel Storage, Appendix D)

Complete 9/25/97(N)(R) 2.

Decay lleat - Flow Instrument Removal L4R 220 Complete 6/26/97 Supplemental Response (re: Boron Precipitation 9/12/97 fetter)

Complete 10/31/97 (NXR) a.

3.

Appendix R Thermo Lag Resolution Schedule (Letter to Address Complete 7/26/97 (N)

Exemption Request) 4.

Appendix R n.

(111.0 Reactor Coolant Pump Oil Cooling) Potential Exemption 11/7/97 (N)(R)

Withdrawal / Revision - When "A" Pump is in Compliance b.

Exemption Request fbr Lube Oil Remote Fill Line Complete 9/5/97 (N) 5.

Low Temp Over Pressurization (LTOPs)- Code Case N 514 Exemption Complete 4/7/97 6.

LTOPs TSCRN 213 a.

15 Efrective Full Power Years (EFPY) License Amendment Complete 7/18/97 b.

30 EFPY License Amendment (not needed until cycle 12)

Resolved (N) c.

Supplemental Infbrmation Complete 9/12/97 (N) d.

RAI Complete 9/5/97 (N) e.

Revision 1 (including response to RAI dated 10/7/97)

Complete 10/25/9?(NXR) 7.

Letdown Rupture Line (USQ)- L4R 2/8 Complete 9/9/97 (R) 8.

Integrated Leak Rate Test, Appendix J Option B - 7NCRN J/2 Con.p[ete 2/1/97 9.

Integrated Leak Rate Test Appendix J. Option B, Rev. I Complete 5/1/97 4

10. Appendix J. Option B - Additional Information Complete 8/l1/97 (N)

11. System Readiness Review (Potential License Amendment)

Resolved

12. License Condition Amendment (if needed)

Resolved Items 13 32. Potential USQ Submittals

13. Emergency Diesel Generator Protective Trips During Engineered Safety Complete 9/12/97 (R)

Actuation and Loss of Offsite Power - L4R 219

14. IIPI Analysis (Without Cavitating Venturis)

Resolved 6/14/97

15. IIP! Pump Recire Resolved Page1

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16. liigh Pressure injection Nozzle Cycles (Contained in the FSAR R.23 Resolved 7/3/97 Letter, and not a USQ)

17. Air llandling Filter l/2 Testing Requirements Resolved l

18. hiakeup Supply Valve (h1UV 27)- Add Automatic Closure upon Receipt Complete 6/14/97 of #1500 Signal

19. liDG Fan Upgrade - L4R 2/6 Complete 8/26/97 (N)

20. Atmospheric Dump Valve (ADV) Design Capacity Resolved' (N)

21. Operator Actions for EOPs and APs Complete 10/3/97 (R)

22. Remote Shutdown Panel Added Components Resolved" (N)

23. RW Cyclone Separator I ouling Resolved

24. h1UV-31 Control Logic Resolved

25. CT Protectors Resolved'(N)

26. htSL11 Resolved (N)

27. IIPI Cavitating Venturis Special Test Resolved' (N)

28. AliF-1C Fan Auto Transfer - L4R 2/7 Complete 10/4/97 (N) 29 lloron Precipitation Mitigation - 110t Leg injection a.

Incorporation of Gaps as Passive Method - L4R 223 Complete 10/31/97 (N)(R) b.

Ilot Leg injection - L4R 225 110/97 (N)(R)

30. CCllE Leakage / Dose Methodology 11/7/97 (R)

31. SW Cooling (Potential USQ or i FS Change) 11/24/97 (N)

32. WDTs Piping Seismic Qualification TIlD (N)

' fi. Once Through Steam Generator (OTSG) License Amendment 211, R1 Complete 3/27/97 a.

OTSG, License Amendment 211, Resubmit Sholly Notice Complete 5/1/97 (N) b.

OTSG Response to Additional Infom1ation Request from NRC Complete 8/19/97 (N) c.

Revision 1 to License Amendment 211 Complete 8/20/97 (N)

34. OTSG License Amendment -IGA Growth Tube Plugging Information Complete 10/1/97 (N)

(Submit Prior to Restart)- L4R 22/

' information lener to NRC 90 (C)

Information lener to NRC 8'19 (C)

' informanon lener to NRC 9/17 (C)

Page 2

i lung bubmittal Date

35. PAhi Table Revision, 'l SCRN 209. RG 1.97 (EDO kW hieters)

Complete 7/29/97

)

36. ECCS hiode 4 Tech Spec Change - MR 2/4 Complete 10/31/97 (NXR) j

37. CCilE Surveillance TS (Submit Prior to Restart). MR 222 11/24/97 6

h

38. EDO Surveillance Testing - Exigent License Amendment TSCRN 215 Completc 8/4/97 (N) i a.

TSCRN 215. Revision 1 Complete 8/16/97 (N)

39. 500 kV ilackfeed Tech Spec Change (not needed before restart)

Resolved (N)

Licensing Restart Submittals (Non-License Amendments) 1.

13oron Precipitation Letter Compicte 9/12/97 2

Appendix R lssues a.

Independent Assessment Summary Complete 7/3/97 b.

Appendix R - Revise Response to Address 72 hr. Cold Shutdown Complete 8/29/97 (N) t (NRC RAI 7/7/97) c.

Appendix R - Thermo Lag Ampacity (NRC RAI)

Complete 7/3/97 (N) d.

Appendix R - NRC Information Notice 9218 (!!ot Shorts)

Complete 9/l8/97 (N)(R) e.

Appendix R - Submit Description of hsues Related to Restan Issue Complete 9/25/97 (N)

D ll to Support NRC Plans for Close-out (NRC RAI 7/7/97)

~

3.

System ReMiness Review - Summary Report l1/5/97 l

2 4.

Generic Letter 96 Summary Report Complete 9/5/97 5.

FSAR Revision 23 - USQ Review Complete 7/3/97 i

6.

Generic Letter 96 Summary Report Complete 10!!7/97 (R) 7.

Tendon Surveillance Report (if needed) 11/1/97 (R) 8.

hiaintenance Rule Structural 13aseline - Walkdown Summary Report Resolved (R)

(combine w/ ltem 3) 9.-

Integrated Safety Assessment of Current Outage hiodifications -

1I/29/97 (R)

- Summary Report

10. FSAR Rev. 24 Upgrade 12/4/97

11. Restan Request Letter 12/1/97

12. RCS Attached Piping - Respond to NRC 4/7/97 Letter Complete 10/30/97 (NXR) a.-

Program Plan for Fatigue Analysis

13. Loss of DC Power, Failure h1 odes and Effects Analysis - Summary Complete 9/24/97 (R)

Report I-Page 3

.n-W w-m-,v e me.

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-mm

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,,--g

-~s-w o w y,n e---g,

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Issue Submittal Datt

14. FSAR Rev. 24/25 Upgrade Program Description Complete 7/17/97 (N)

15. 50.54(0 Letter to Address Discrepancies (if needed)

Resolved (N)

16. Review of implementation of Liceme Conditions Complete 5/20/97 a.

Supplement to Address Additional Condition - Closed (IR 97-08)

Resolved (N)

17. Submittals to Support SBLOCA TSCRN 210:

a.

Letter to Confirm Calculations (EDG Loading,13 lock Valve Complete 9/25/97(N)(R)"

Cycling)

I b.

Letter to Confirm EOPs do not Result in a USQ Complete 9/25/97(N)(R)"

c.

Submit Draft EOPs 3 and 8, AP 770 Complete 8/4/97 (N)

- RAI for EOPs 3,8 and AP 770 Complete 9/17/97 (N) d.

Submit Proprietary and Non-proprietary Version of LilLOCA Complete 9/2/97 (N)

Analysis of Record C mplete 9/25/97(N)(R)"

e.

EDO Testing Plan

18. 1.icensing liasis for Dynamic Loads Initial Response (Pipe Whip) to NRC 4/10/97 Letter Complete 6/5/97 (N) a.

b.

Supplemental Response (re: Jet Impingement)

Complete 9/29/97 (N) c.

NRC RAI re: Jet Impingement (10/9/97) 11/10/97 (N)(R)

19. Low Pressure injection - hiission Time Complete 5/15/97

20. Appendix R - Atmospheric Dump Valve 30 Day Response Complete 4/30/97

21. System Readiness Review Plan Complete 3/27/97

22. EUP/AP Operator Action Commitment Date Change Complete 3/25/97

23. GL 96-06 Letter regarding Service Water Fittings Complete 4/30/97

24. ash 1E Section XI - Code Case Relief Request Complete 3/24/97

25. h1 CAP ll, Rev. 2 Complete 4/25/97

26. ITS Bases Submittal Complete 4/18/97

27. Letter on Pressure Locking re: EFV-12,-32,-33 (Supports SER for GL 95-Complete (N) 8/l1/97 07)

28. Resolution of A-46 SQUG Walkdown issues (NRC RAI 5/27/97)

Complete (N) 8/1/97 29 Temporary Waiver of Compliance for CCllE hiodifications (FSAR Resolved (N)

Requirement)

30. Submit FPC Plan for llPI Nozzle Oconee issue Complete 10/30/97 (N)(R)

31. IWE/lWL Supplemental Response Requested by the NRC Complete 10/30/97 (N)(R)

Page 4

r litus Submittal Date

32. PILR Revision Complete 10/11/97 (N)

33. PAM RAI (re: 'l SCRN 209)

Complete 10/29/97 (N yl'.)

34. Letdown Line Rupture. RAI 11/5/97 (NXR) 35, NRC RAI EDO Trips not flypassed IsfR 2/9 11/5/97 (N)

36. NRC - RAI EDO Testing Results 11/7/97 (N)

(N) New (R) Revised

" Consolidated with TSCRN 210 Supplement Complete 9/25/97 0

l H CA%T'31'DM RV 04 Page5

-

ML20202C923

Contents

Text

SUBJECT:

SUMMARY

Dear Mr. Anderson:

Enclosures:

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ML20202C923

Text

SUBJECT:

SUMMARY

Dear Mr. Anderson:

Enclosures:

Navigation menu

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