ML20198R954

Summary of 971022 Meeting W/Util in Rockville,Md Re Licensee Corrective Action Issues & Status of Licensing Issues That Could Potentially Affect CR3 Restart Schedule.List of Attendees & Meeting Handouts Encl

ML20198R954
Person / Time
Site:	Crystal River
Issue date:	10/29/1997
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9711130405
Download: ML20198R954 (21)

Text

- _ . _ _.

October 29, 1997L

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LICENSEE: Florida Power Corporation FACILITY:- Crystal River Unit 3 (CR-3)

SUMMARY

OF MEETING ON OCTOBER 22, 1997 10 CFR 50.59 IMPLEMENTATION AND STATUS OF LICENSING ACTIVITIES' On October 22, 1997, representatives of the Florida Power Corporation, licensen_ for Crystal River Nuclear Plant, Unit 3 (CR3), met _ with staff. members of the U.S. Nuclear Regulatory Commission:(NRC or the staff) at their Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees.

Enclosure 2-is a copy of the handouts presented at the meeting.' '-

The purpose of the meeting.was-to discuss.the licensee's corrective action issues and status of-licensing issues that 'could potentially affect CR3's-restart schedule.

The licensee addressed the NRC staff's concern described =in a letter dated

-October 9, 1997 regarding 10 CFR 50.59 implementatien. Three specific examples of.10 CFR 50.59 implementation weaknesses'were discussed: use of ,

hotleg internal gap for baron precipitation prevention,-pressurizer surge line jet' impingement _ effects based on 20 instead of 30 cone angle, and lack of seismic qualification for waste disposal system. The licensee agreed to revise its unreviewed safety question (USQ) determination and make appropriate submittals to the staff. The licensee also agreed to implement corrective actions to ensure that'the use of NRC approved methodologies that are not in their current licensing basis, is properly addressed.

The staff discussed the status of licensing submittals. The staff expressed concerns regarding licenso's schedule slippage for several potential licensing submittals. For several other submittals, the licensee's response to the staff's reque:t for additional information is still awaited. The staff reiterated its previous concerns that the licensing submittals are in the critical path for restart.

original signed by L.Raghavan L. Raghavan, Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendees List W O\ , i

2. Meeting handout a cc w/ enclosures: .See next page Document Name: G:\ CRYSTAL \971022. SUM Office PM:PDII-3 LA:PDII-3 PD:PDII-3, i Name LRaghavan BClayton(8 FHebdos((h l Date 10/d/97 l.,,f - 10/dl/97 10/Mh7 Copy kNo f esl Yes/[No )

U . ~ '0FFICIAL RECORD COEV 9711130405 971029 a

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%g October 29, 1997 LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3

SUMMARY

OF MEETING ON OCTOBER 22, 1997 10 CFR 50.59 IMPLEMENTATION AND STATUS OF LICENSING ACTIVITIES On October 22, 1997, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3 (CR3), met with staff members of the U.S. Nuclear Regulatory Commission (NRC or the staff) at their Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees.

Enclosure 2 is a copy of the handouts presented at the meeting.

-The purpose of the meeting was to discuss the licensee's corrective action issues and status of licensing issues that could potentially affect CR3's restart schedule.

The licensee addressed the NRC staff's concern described in a letter dated October 9, 1997 regarding 10 CFR 50.59 implementation. Three specifi-examples of 10 CFR 50.59 implementation weaknesses were discussed: use af hotleg internal gap for boron precipitation prevention, pressurizer surge line jet impingement effects based on 20 instead of 30' cone angle, and lack of seismic qualification for waste disposal system. The licensee agreed to revise its unreviawed safety question (USQ) determination and make appropriate submittals to the staff. The licensee also agreed to implement corrective actions to ensure that the use of NRC approved methodologies that are not in their current licensing basis, is properly addressed.

The staff discussed the status of licensing submittalt The staff expressed concerns regarding licensee's schedule slippage for several potential licensing submittals. For several other submittals, the licensee's response to the staff's request for additional information is still awaited. The staff reiterated its previous concerns that the licensing submittals are in the critical path for restart.

L6 L. Raghavai, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendees List

2. Meeting handout cc w/ enclosures: See next page

4 . .

. Florida Power Corporation CRYSTAL RIVER UNIT N0. 3 GENERATING PLANT ,

cc:

Mr. R.-Alexander Glenn Mr. Robert E. Grazio, Director Corporate Counsel Nuclear Regulatory Affairs (SA2A)

Florida Power Corporation Florida Power Corporation MAC-A5A Crystal River Energy Complex P.O. Box 14042 .15760 W. Power Line Street St. Petersburg, Florida 33733-4042 Crystal River, Florida 34428-6708 Mr.- Charles Pardee, Director Senior Resident Inspector Nuclear Plant Operations (NA2C) Crystal River Unit 3 .

Florida Power Corporation U.S. Nuclear Regulatory Commission Crystal River Energy Complex 6745 N. Tallahassee Road 15760 W. Power Line Street Crystal River, Florida 34428 Crystal River, Florida 34428-6708 Mr. James S. Baumstark Mr. Bruce J. Hickle, Director Director, Quality Programs (SA2C)

Director, Restart (NA2C) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region II Mr. Robert B. Borsum U.S. Nuclear Regulatory' Commission Framatome Technologies Inc. 61 Forsyth Street, SW., Suite 23T85 1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 Rockville, Maryland 20852 Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production Office of Radiation Control (NA2E)

Department of Health and Florida Power Corporation Rehabilitative Services Crystal River Energy Complex 1317 Winewood Blvd. 15760 W. Power Line Street Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 Attorney General Mr. Roy A. Anderson Department of Legal Affairs Senior Vice President The Capitol Nuclear Operations

-Tallahassee, Florida 32304 Florida Power Corporation ATTN: Man;ge', Nuclear Licensing Mr. Joe Myers, Director Crystal River Energy Complex (SA2A)

Division of Emergency Preparedness 15760 W. Power Line Street Department of Community Affairs Crystal River, Florida 34428-6708 2740 Centerview Drive Tallahassee, Florida 32399-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street, SW., Suite 23T85 Board of County Commissioners Atlanta, GA 30303-3415 Citrus. County 110 North Apopka Avenue Iverness, Florida 34450-4245

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[ CRYSTAL-RIVER 3 MEETING 1 OCTOBER 22. 1997 Ham .Oraanization l L. Raghavan- NRC-NRR fred Hebdon NRC-NRR B.:Boger- NRC-NRR- .

- J. --Zwolinskii NRC-NRR W. Lyon NRC-NRR

10. Kunsemiller Florida Power Corp.

J. Holden- Florida Power Corp.

R. Grazio Florida Power Corp.

M. Rencheck Florida Power Corp.

r Enclosure 1

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CRYSTAL RIVER NUCLEAR PLANT NRC MEETING - OCTOBER 22,1997 FLORID A POWER CORPORATION Enclosure 2

"FPC-CR3 AGENDA 3

• ISSUES

• SW JET IMPINGEMENT

= BORON PRECIPITATION MITIGATION HOT LEG GAP e 10 CFR 50.59 PROGRAM IMPROVEMENT AND EFFECTIVENESS ASSESSMENTS

• RESULTS OF PROGRAM ASSESEMENTS

• CLOSING REMARKS

^

. '- "FPC-CR3 ,,

. ~

ISSUES

. TWO EXAMPLES STATED IN 10/09/97 LETTER OF POTENTIAL CONCERNS:

=> CHANGING THE JET IMPINGEMEilT CONE ANGLE FROM 30' TO 20'

=> CREDITING THE REACTOR COOLANT HOT LEG GAP METHOD FOR BORON PRECIPITATION MITIGATION

. LETTER FURTHER REQUESTED AN EXTENT OF CONDITION REVIEW

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! . FPC-CR3 - *

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" JET IMPINGEMENT ISSUE - .; .

Aug.11,19953 Feb.26,1996 April 10,1997 June 5,1997 '

NRC Letter- FPC letter-I W NRC insp. Report IFl 95-15-02

, 9 Licensing Basis for Dynamic Protodion A0ainst Dynamic Effeds -

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g 993 ~

. LOCA Effects of LOCA .  ;

- Pmvided results of walkdowns

- FPC reiterates LBB as licensing - NRC concurs that CR-3 is LBB (GL87-11, GL88-11) '

-NRC requested FPC to . . basis except for RCS branch lines -

provide eh that there - Declared pipe whip not a

- Ongsnal FSAR der'gn criteria - Requests FPC to submit problem was design features provided not clearly documented results of field inspection to! - Commated to provide jet

• to protect agamst dynamic  : - Identified potential undesirable determine if there is any .f effects Get W. pipe interaction between pressurizer undesirable interaction W 6 by '

whip)- nr2tw97 surge line and Sw between the pressunzer surge line and the SW piping.

(Identified by FPC in IR 95-15 .

as a potential concem) k Acrorvrri LBB ~ eak Before Break) i 4

1

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

FPC - CR3  :

JET IMPINGEMENT ISSUE ,

9/10/97 Sep.29,1997 October 9,1997 l

NRC Letter-Proledion agahst FPC letter- Jet Dynamic Effeds FPC 1oCFR5059 impingement ,1 of LOCA-EVAWADOt! -

g gy adddional information

- Presented results of FPC's jet impingement st@ NRC comment-

- Conduded that neither a circumferential or longitudinal pipe Do not agree with FPC USO rupture would adversely affed the SW system piping determination-

- Stated the FSAR would be revtsed to state the fluid jet created - Use of SRP not acceptable by a circumfere.itial rupture is limited to 205 induded angle '" * #8#

consistent with SRP 3.6.21ANS 58.2 .

V

- FDC 10CFR50.59 determination condtaded the following:

• The change in the pressurizer surge line break analysis described in the 50.59 preserves the assumptions made in FSAP. accident analysis

• Does not result in a physical plant change and could not affed a design basis accident t

• Adivity ensures the integrity of the containment barrier thereby the consequences of an accident are not increased

• The change to the shape does not result in impingement on new targets.

• The physical barriers are not affeded therefore no inciease in consequences of malfunction

• No accidents are created

• Adivity docs not introduce any credible failure modes

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JET IMPINGEMENT

= PRESENTATION OF BASIS FOR THE USQD WAS NOT CLEAR AND COMPLETE.

• INDUSTRY METHODS (i.e. ANSIIANS 58.2 AND SRP) WERE NOT THE PRIMARY BASIS FOR "NO USQ" DETERMINATION.

• ORIGINAL LICENSING BASIS DID NOT DEFINE ALL NEEDED -

ANALYTICAL INPUTS.

. USE OF 20' CONE ANGLE IS A TECHNICALLY CORRECT METHOD WITH A DEFINED CRITERIA.

• FPC BELIEVF.D THIS WAS AN APPROVED AND CORRECT METHODOLOGY.

. FURTHER EVALUATION IS UNDERWAY AND RESULTS WILL BE REFLECTED IN THE RESPONSE.

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FPC-CR3 . .

l BORON PRECIPITATION - HOT LEG NOZZLE GAPS - -

3 12/30/76 11/7/91 12/4/91- 3/9/93 '12/2/94 B&Wletter to ..

-NRC FPC letterto NRC  :

NRC SER Prefirrhry . LER ,

NRC (Thadspi) - - 10CFR50.59 g, 2 SUPPL 3 Safety 91-011 letter to B&WOG -

report - FSAR ' -

Concem "

R21 1g (PSC) y

-Responded to B&WOG 10CFR50.59 conclusions:

- Analysisindicated height of -Identified gereeric B&W presentaiion on GAPS

• GAPS is the first and preferred i- two phase mixture may not te issue that RVVVs would method and dropline as the -

sufficient to provide flow of not be effective in alg - Recognized GAPS

. liquid through Reactor Vessel cases methodology AS backup to secondary method ~

Vent valves pnmary recire. now path and concludes B&W PSC issue resolved '

- Poses no immediale safety V concem i

ORIGINAL CR-3 LICENSING BASIS

' ~ FPC methodology allows adequate dilution of boron during long term cooling which ceivG , with sin 0le failure criterion.

-Reactor Vessel Vent Valves (RVVV) > 40 DAYS Fonowed by-

• Aux. Pressurizer Spray (Long term)

-Initista active method within 24 HRS:

• Dropline to sump

'

• Hot leg injection with Aux. pressurizer spray ,

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FPC-CR3 M BORON PRECIP!TATION - HOT LEG NOZZLE GAPS -

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6/17/96 7/26/96 8/23/96 NRC letter to FPC FPC response to R 10CFR SO.54(f) .

50.54(f) -cet URI 9644-01 NRC concern- -NRC queshons the adequacy - FPC is adively addressm0 the .Pntrwnenary safety h EDBD and FSAR appears of 10CFR50.59 for Rev. 21 genenc boron precepitation of 50.54(f) response

- to be incornastent with

• Use of GAPS as a Twst and controlissue with B&M deterreined that CR-3 safe to provissons of NRC position preferred method over an - N'e= man of applicahon of operate untilissue resolved regarding prirnary adive method B&WOG reports for CR ,

required flow path

• Compliance with the - Response to specife GAPS licensmg basis for CR-3 questions

• Specife GAPS questions s

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l ' FPC-CR3 :

L: BORON PRECIPITATION - HOT LEG NOZZLE GAPS

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l 3/12/97 3/27/97 11/18/96 B&WOG Letter to NRC Enf

- F%R Rev. 23 Action -

comund t

-GAP method changed to

- 10CFR50.59 for FSAR R21 ' - Analysis of GAP flow for '

passive, backup method was inadequate for B&W plants:.

demonstrating a USQ did -Condudes GAP flowis not exist adequate boron dilution . -

- FSAR and EDBDs change method for SBLOCA &

inappropriate ' .

LBLOCA

- Departure from the licensing .

basis

- Flow through reador vessel intemal gaps has been

, identified as acceptable to the NRC (letter dated 3&l93) only as a backup method and not as the primary method i

F

. -~ .

FPC-CR3  :

BORON PRECIPITATION - HOT LEG NOZZLE GAPS- -

..~

4/11/97 7/21/97.

6/16/97 9/12/97 FPC Letter to p NRC FPC/NRC Post LOCT roton

', Technical Meeting precipitation mitigation plan '

4 Corrective actions:

- FSAR revised in R23 to make ~

GAPS backup method Boron precipitation sut$ect topic-

- B&WOG moving forward on - Identified active methods as dropline . t long term resolution and hot leg injection -

- License change request will be - Passive method is hot leg nozzle gaps submitted to revise License Condition i

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FPC-CR3 BORON PRECIPITATION MITIGATION - HOT LEG NOZZLE GAP

. NRC LETTER TO B&WOG WAS NOT THE PRIMARY BASIS FOR DECISION TO CREDIT GAPS IN REV. 23 OF FSAR.

. KEY INPUTS TO FSAR REV. 23:

=> ENFORCEMENT ACTION

=> 50.54(F) LETTER

=> FPC RESPONSE

=> IPAP

• CREDITING GAPS FOR BORON MITIGATION AT CR-3 IS SIMILAR TO OTHER B&W PLANTS

. WILL UPDATE BORON MITIGATION STRATEGY IN UPCOMING SUBMITTAL.

. PARTICIPATING WITH THE B&WOG FOR LONG TERM RESOLUTION OF THE ISSUE.

3.;

FPC-CR3 ,

-50.59 PROCESS IMPROVEMENTS & EFFECTIVENESS ASSESSMENTS -....

L _ -

, Jan - March March May MC971357 FPC 50.59 improvemert QA survestlance performed of ADDRESS 50.59 program:  : new 50.59 process -

FINDINGS FROM Cont.

- N .s SSMENT

- New 50.59 process centralized and rewritten Ash Ms: Compiled 50.59 concems 8

- Formaltramm0 program developed - MCAP related actions -

g

-Independent revew group formed ~

- Other utility processes reviewed and -Mmorweaknessesidentified ~ ~

incorporated '

• Improve procedural tie to -

FSAR- -

- WC WW N aM

• Improve availability of SERs actions incorporated

• Improve procedural references

• Define SAG program requirements 1

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FPC-CR3 ,.'

50.59 PROCESS IMPROVEMENTS & EFFECTIVENESS ASSESSMENTS - I

'i 8/11/97 July-August September October l

NRC team Restart self-l inspedion of Supplementallessons QA surveillance of assessments 50.59 program leamed training and 50.59 program 50.59 procedure revised implementation Third party (IR 97-08) assessment

- Review of organizations and Resu".s of inspection: Results include:

Further guidance included: processes for readiness for

- Management oversight (Good) - Program is adequale

- Manual operator actions restart (included sample

- Engineering effectiveness (Good) - Minor improvements identified

- Margin of Safety reviews of 10CFR50.59

- Knowledge of design basis (Good)

• References to include

-Increase in consequences products-FPC procedure

- Compliance with regulations (Good) revision number

- Compensatory measures Al-256)

• Performance goals set for

- Review of 12 signif*mant FPC review group 10CFR50.59 reviews by a third

• Defined closure tracking party method I

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.- )

RESULTS OF PROGRAM ASSESSMENTS

• PROGRAM HAS BEEN IMPROVED -

=> NEW PROGRAM PROCEDURE

=> FORMALIZED TRAINING

=> INDEPENDENT REVIEW GROUP

=> FPC ACTIVELY PARTICIPATING IN INDUSTRY 50.59 WORKING GROUPS

=> LESSONS LEARNED FEEDBACK INTO PROGRAM THROUGH

TRAINING-

!

• PROGRAM EXTENSIVELY REVIEWED

=> QA

=> SELF ASSESSMENT

=> 3rd PARTY REVIEW

=> NRC INSPECTIONS

• RESULTS OF PERFORMANCE REVIEWS INDICATE PROGRAM iS FUNCTIONING EFFECTIVELY AND MEETS CURRENT REGULATORY REQUIREMENTS.

1

_ - _ . _ _ . _ _ _ _ ___ __ m - . - - - . . . - - - . - - , - - - .- - . - , . . . - - ,

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• * ~-

, "FPC CR3 CLOSING REMARKS

• 10 CFR 50.59 PROGRAM IS " SOUND AND EFFECTIVE".

. CORRECTIVE ACTION DOCUMENT WRITTEN TO ADDRESS EXTENT OF CONDITION.

. PRESENTATION OF THE ISSUE IN THE CORRESPONDENCE WAS NOT CLEAR.

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$UBJECT:

SUMMARY

OF MEETING ON OCTOBER 22.-1997 10 CFR 50.59 IMPLEMENTATION AND STATUS OF LICENSING--

ACTIVJTIES Distribution HARD COPJ

' Docket File-

'PUBLIC Crystal River Reading OGC

- ACRS L. Raghavan J. Johnson, RII E-Mail S. Collins /F. Miraglia (SJC1.FJM)

R. Zimmerman (RPZ)

B. Boger (BAB2.RCN)

J. Zwolinski (JAZ)

K. Landis (KDL)

'F. Hebdon (FJH)

B. Clayton J. Joudan. RII T. Martin (e-mail to SLM3)

L.~Trocine, 100 (LXT)

W.Lyon (WCL)

-