ML17229A978

Informs That Fj Hebdon Will Retire,Effective 990101

ML17229A978
Person / Time
Site:	Saint Lucie
Issue date:	01/04/1999
From:	Gleaves W NRC (Affiliation Not Assigned)
To:	Weinkman E FLORIDA POWER & LIGHT CO.
References
NUDOCS 9901110302
Download: ML17229A978 (75)

Text

anaury 4, 1999 Mr. E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive'ensen Beach, Florida 34957

SUBJECT:

SITE ACCESS BADGE FOR FREDERICK J. HEBDON

Dear Mr. Weinkam:

As of January 1, 1998, Frederick J. Hebdon, currently the U.S. Nuclear Regulatory Commission (NRC) Project Director for Project Directorate II-3willbe retiring. Accordingly, by this letter Mr. Hebdon has discharged his duty to return his site access badge to Florida Power and Light Co., St. Lucie Plant.

Mr. Hebdon requested that I express for him, his congratulations on your record-breaking Unit 2 refueling outage, and his sincere best wishes for future success.

Sincerely,

/s/

William C. Gleaves, Project Manager Project Directorate Division of Reactor Projects-Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosure:

1. FPL picture badge for F. J. Hebdon

2. Access badge No. 2406 DISTRIBUTION:

FHebdon WGleaves JZwolinski St. Lucie R/F

Docket Fjles~

PUBLIC BClayton DOCUMENT NAME:

G:NSTLUCIENBADGE.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E"=Co with attachment/enclosure "N"= No co OFFICE NAME DATE P Dll-3/PM WGleaves:c CC PD II-3/LA BCla on 1

%/98 OFFICIALRECORD COPY

(

PDII-3/D FHebdon 12/ I/98 I>Q0"3 9'POiii0302 990i04 PDR ADQCK 05000335 P

PDR 7~&

I-LL!~

L M

A L

Oq Cy i~

0

. +~

~0~

++*++

0

~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 Vanuai.'y:: 4; l1999:

'Mr.

E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957

SUBJECT:

SITE ACCESS BADGE FOR FREDERICK J. HEBDON

Dear Mr. Weinkam:

As of January 1, 1998, Frederick J. Hebdon, currently the U.S. Nuclear Regulatory Commission (NRC) Project Director for Project Directorate II-3 willbe retiring. Accordingly, by this letter Mr. Hebdon has discharged his duty to return his site access badge to Florida Power and Light Co., St. Lucie Plant.

Mr. Hebdon requested that I express for him, his congratulations on your record-breaking Unit 2 refueling outage, and his sincere best wishes for future success.

Sincerely, William C. Gl aves, Project Manager Project Directorate Division of Reactor Projects-Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosure:

1

~ FPL picture badge for F. J. Hebdon

2. Access badge No. 2406

I V'

Distri10.txt Distribution Sheet Priority: Normal From:

Esperanza Lomosbog Action Recipients:

K Jabbour Copies:

1 Not Found Internal Recipients:

NRR/DIPM/EPHP IRO D Hagan 4vB 'CENT 1

1 '

Not Found Not Found Not Found x erna Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993620058 6

Subject:

Revised

EPIPs, including rev 5 to EPIP-12, "Maintaining Emergency Prep aredness Radiological Emergency Plan Training" 6 rev 15 to HP-200, "Health Physics Emergency Organization."

With 12/20/1999 letter.

Body:

PDR ADOCK 05000335 F

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A Page 1

0 C

Florida Power@ Light Company,6351 S. Ocean Drive, Jensen Beach, FL34957 December 20, 1999 L-99-276 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan Im lementin Procedures In accordance with 10 CFR 50 Appendix E, enclosed is a copy of a revised Emergency Plan Implementing Procedure (EPIP) and a procedure that implements the Emergency Plan as listed below.

Number EPIP-12 Title Maintaining Emergency Preparedness-Radiological Emergency Plan Training Revision Im lementation Date December 8, 1999 HP-200 Health Physics Emergency Organization, 15 December 13, 1999 EPIP-12 Revision 5 removed Protective Action Recommendation

(PAR) training from the requirements for the Technical Support Center (TSC) Dose Assessor position. HP-200 Revision 15 deleted low volume air sample from Operational Support Center (OSC) checklist and included checklist for Health Physics Network (HPN) Communicator.

Please contact us if there are any questions regarding these revised procedures.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/tlt Enclosures cc: Regional Administrator, Region II, USNRC (2 copies)

Senior Resident Inspector, USNRC, St. Lucie Plant (w/o)

@~~

Aocx,r c>a~ D~~

an FPL Group company

B

n Distri60.txt Distribution Sheet Priority: Normal From:

Esperanza Lomosbog Action Recipients:

K Jabbour Internal Recipients:

NRR/DIPM/EPHP IRO D Ha an F

ENTER Copies:

1 1

1 1

Not Found Not Found Not Found Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993610226

Subject:

Emergency Plan Implementing Procedures.

Body:

PDR ADOCK 05000335 F

Docket:

05000335, Notes:

N/A Docket:,05000389, Notes:

N/A Page 1

Florida Power 5 Light Company,6351 S. Ocean Drive, Jensen Beach. FL 34957 December 15, 1999 L-99-266 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan lm lementin Procedures In accordance with 10 CFR 50 Appendix E, enclosed is a copy of revised Emergency Plan Implementing Procedures (EPIPs) that implement the Emergency Plan as listed below.

Number Title Revision Im Iementation Date EPIP-04 EPIP-07 Activation and Operation of the Technical Support Center Conduct of Evacuations/Assembly 5

December 1, 1999 December 2, 1999 EPIP-04 Revision 5 changed Chemistry minimum staff position from Technical Support Center (TSC) Chemistry Supervisor to a TSC Dose Assessor; provided alternate notification methods, added instruction to produce list of Emergency Plan Implementing Procedures (EPIPs) with current revision numbers, and revised the re-entry worksheet.

In addition, EPIP-04 Revision 5 added instructions to create a conference bridge for Operations and made administrative and editorial changes.

EPIP-07 Revision 2 added a site assembly map and site evacuation routes.

Please contact us ifthere are any questions regarding these revised procedures.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/tlt Enclosures cc: Regional Administrator, Region II, USNRC (2 copies)

Senior Resident Inspector, USNRC, St. Lucie Plant (w/o) p~Mo~i~ DW~>>>>

an FPL Group company

Distri90.txt Distribution Sheet Priority: Normal From: Esperanza Lomosbog Action Recipients:

Int l Recipients:

IL CENTER Copies:

Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993550383

Subject:

GENERIC LETTER 97-01, "DEGRADATION OF CONTROL ROD DRIVE MECHANISM NOZZ LE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS":

REVIEW OF THE RESPONS ES FOR ST.

LUCIE UNITS 1 AND 2 (TAC NOS.

M98600 AND M98601)

Body:

PDR ADOCK 05000335 P

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A Page 1

I

gP,g RE00 g~e0 Cy 0O g

Cy Yr

~O

++*++

~

y~ 9>y pgy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Decerrber 13, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

GENERIC LETTER 97-01, "DEGRADATIONOF CONTROL ROD DRIVE MECHANISMNOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS": REVIEW OF THE RESPONSES FOR ST. LUCIE UNITS 1

'ND 2 (TAC NOS. M98600 AND M98601)

Dear Mr. Plunkett:

On April 1, 1997, the staff issued Generic Letter (GL) 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations," requesting that the industry provide a description of the plans to inspect the vessel head penetrations (VHPs) at their respective pressurized-water reactor (PWR) plants.

In the discussion section of the GL, the staff indicated that it did not object to individual PWR licensees basing their inspection activities on an integrated, industry-wide inspection program.

The Combustion Engineering Owners Group (GEOG), in coordination with the efforts of the Nuclear Energy Institute (NEI), the Westinghouse Owners Group (WOG), and the Babcock and Wilcox Owners Group (BWOG), determined that it was appropriate for its members to develop a cooperative integrated inspection program in response to GL 97-01. The CEOG submitted that program in a topical report titled, CE NPSD-1085, "GEOG Response to NRC Generic Letter 97-01, Degradation of CEDM Nozzle and Other Vessel Closure Head Penetrations," on July 25, 1997.

In this report, a timing model (crack initiation and growth susceptibility model) was used to rank the VHPs of the participating plants in the GEOG. The GEOG later provided information to indicate that it was adopting the Electric Power Research Institute (EPRI) model as the basis for evaluating CE designed VHP nozzles.

F On December 11, 1998, NEI submitted a generic integrated response to the requests for additional information (RAls) on GL 97-01 on behalf of the utilitymembers in the GEOG, WOG, and BWOG. In the generic submittal, NEI informed the staff that it normalized the susceptibility rankings for the industry. The generic response to the RAls also provided sufficient information to answer the information requests in the RAls, and emphasized that the integrated program is an ongoing program that will be implemented in conjunction with the Electric Power Research Institute (EPRI), the participating utilities in the GEOG, WOG, and BWOG, and the Material Reliability Projects'ubcommittee on Alloy600.

By letter dated March 21, 1999, the staff informed NEI that the integrated program was an acceptable approach for addressing the potential for primary water stress corrosion cracking (PWSCC) in the VHPs of PWR-designed nuclear plants, and that licensees responding to the GL could refer to the integrated program as a basis for assessing the postulated occurrence of PWSCC.

T. F. Plunkett To date, all utilities have implemented VT-2 type visual examinations of their VHPs in compliance with the American Society of Mechanical Engineers'equirements specified in Table IWB-2500 for Category B-P components.

Most utilities, if not all, have also performed visual examinations as part of plant-specific boric acid wastage surveillance programs.

In addition, the following plants have completed voluntary, comprehensive augmented volumetric inspections (eddy current examinations or ultrasonic testing examinations) of their control rod drive mechanism (CRDM) nozzles:

1994-Point Beach Unit 1 (Westinghouse reactor design) 1994 - Oconee Unit 2 (Babcock &Wilcox (B&W)reactor design) 1994-D.C. Cook Unit 2 (Westinghouse reactor design) 1996-North Anna Unit 1 (Westinghouse reactor design) 1998 - Millstone Unit 2 (CE reactor design) 1999-Ginna (Westinghouse reactor design)

In addition, the following plants have completed voluntary, limited augmented volumetric inspections of their VHPs as well:

1995 - Palisades - eight instrument nozzles (CE reactor design) 1996 - Oconee Unit 2 - reinspection of two CRDM nozzles (B&Wreactor design) 1997 - Calvert Cliffs Unit 2 - vessel head vent pipe (CE reactor design)

The majority of these plants have been ranked as having the rrlore susceptible VHPs in the industry. Of these inspections, only the inspections at D.C. Cook Unit 2 have resulted in the identification of any domestic PWSCC type'flaw indications. The current program includes additional commitments to perform further volumetric inspections of the CRDM nozzles at Oconee, Unit 2 (a reinspection of 2-12 nozzles in 1999), Crystal River, Unit 3 (in 2001, a B&W reactor design), Diablo Canyon, Unit 2 (in 2001, a Westinghouse reactor design), Farley, Unit 2 (in 2001, a Westinghouse reactor design), and San Onofre, Unit 3 (in 2002-2008, a CE reactor design).

These plants are currently ranked in either the high or moderate susceptibility categories.

In your January 27, 1999, response, you endorsed the NEI submittal of December 11, 1998, and indicated that you were a participant in the NEI/GEOG integrated program.

Since the additional volumetric inspections performed to date have confirmed that PWSCC is not an immediate safety concern with respect to the structural integrity of VHPs in domestic PWRs, and since we have approved the integrated program for implementation, we conclude that the integrated program provides an acceptable basis for evaluating your VHPs. You may refer to the integrated program when submitting VHP-related licensing action submittals for the remainder of the current 40-year licensing period.

Furthermore, ifyou are considering applying for license renewal of your facilities, your application will need to address the following items:

(1) an assessment of the susceptibility of your VHPs to develop PWSCC during the extended license terms for the facilities; (2) a confirmation that the VHPs at your facilities are included under the scope of your boric acid corrosion inspection program; and (3) a summary of the results of any inspections that have been completed on your VHPs prior to the license renewal application.

T. F. Plunkett I)ecedxr 13, 1999 This completes the staffs effort on TAC Nos. M98600 and M98601. Thank you for your efforts in addressing this issue.

Sincerely, Docket Nos. 50-335 and 50-389 cc: See next page Origina1 sigmd by=

Kahtan N. Jabbour, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation h

ih i

l s

DISTRIBUTION'File Center i

PUBLIC St. Lucie R/F RCorreia BClayton KJabbour OGC t

ACRS LWert, Rll WBateman DOCUMENT NAME: G:hPDII-2(St. LucieWI98600gl97-01co. Itr¹2.wpd To recelhre e co of this document Indlcete In the born C

~ Co without ettechment/enclosure E

a Co with ettechment/enclosure N

rs No co OFFICE NAME PDII-2<PM KJabbour RCorreia gP' WBatem BCla ton PDII-2<LA, PDII-2<SC C

EMCBtiB DATE 12/499 12/4'99 12/~/99 12

/99 OFFICIALRECORD COPY 12/ /99

T. F. Plunkett This completes the staff's effort on TAC Nos. M98600 and M98601. Thank you for your efforts in addressing this issue.

Sincerely,

/QI'g-Q

./i-"(f~

Kahtan N. Jabbour, Sr. Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page

Mr. T. F. Plunkett Florida Power and Light Company ST. LUCIE PLANT CC:

Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. WilliamA. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin ¹C21 Tallahassee, Florida 32399-1741 J. A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. John Gianfrancesco Manager, Administrative Support and Special Projects P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997

Distribution Sheet Distri-8.txt Priority: Normal From: Elaine Walker Action Recipients:

K Jabbour Copies:

1, Not Found Internal Recipients:

NRR/DIPM/EPHP IRQ OH w

IL CENTER 01 Not Found Not Found Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item: ADAMSDocument Library: ML ADAMS"HQNTAD01, ID: 993620121

Subject:

Emergency Plan Exercise - February 16 2000 Body:

PDR ADOCK 05000335 F Docket: 05000335, Notes: N/A Docket: 05000389, Notes: N/A Page 1

Florida Power &light Company, 6501 South Ocean Drive, Jensen Beach, FL34957 December 13, 1999 L-99-272 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan Exercise Februa 16 2000 Florida Power &Light Company (FPL), in cooperation with the State ofFlorida, St.

Lucie County, and Martin County emergency response agencies, will conduct an exercise ofthe emergency plan for St. Lucie Plant on February 16, 2000. The exercise willinvolve participation by local emergency response agencies and State emergency response personnel and willbe evaluated by the Federal Emergency Management Agency.

As requested by NRC letter dated April3, 1987 (J.'"Nelson Grace to'C. O. Woody), the exercise scenario package is being forwarded only to Mr. Kenneth Barr, Branch Chief, Region II, "To be opened by addressee only."

Ifthere are any questions or comments concerning'this exercise or the scenario, please contact Ms. Donna Calabrese at (561) 467-7185.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/tlt cc:

Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant Kenneth Barr, Branch Chief, USNRC, Region II,Plant Support Branch, w/encl 7DZ..~~It DQ~~ 55K an FPL Group company

0

@< r7reg I

Distribution Sheet Distri36.txt Priority: Normal from: Elaine Walker Action Recipients:

KJabbour Copies:

Not Found Internal Recipients:

NRR/DIPM/EPHP IRO D H~aan F LAMENTER01'ot Found Not Found Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTAD01, ID: 993350064

Subject:

Revised Emergency Plan Implementing Procedures EPIP-02 and HP-90.

Body:

PDR ADOCK 06000335 F Docket: 05000335, Notes: N/A Docket: 05000389, Notes: N/A Page 1

4

Florida Power 5 Light Company, 6501 South Ocean Drive, Jensen Beach, FL34957 November 22, 1999 L-99-248 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan Im lementin Procedures In accordance with 10 CFR 50 Appendix E, enclosed is a copy of the revised Emergency Plan Implementing Procedure (EPIP) and a revised procedure that implements the Emergency Plan as listed below listed below.

Number E PIP-02 Title Duties and Responsibilities of the Emergency Coordinator Revision Im lementation Date November 8, 1999 HP-90 Emergency Equipment 36 November 3, 1999 EPIP-02 Revision 4 clarified records required, revised Emergency Coordinator (EC) turnover process, changed "at the site" to "within the Owner Controlled Area," and clarified the use of field monitoring data for Protective Action Recommendations (PARs). EPIP-02 Revision 4 also added guidance for completing the Nuclear Regulatory Commission (NRC) notification form and made editorial changes.

HP-90 Revision 36 added check of fax machines, copy machines, and deleted unnecessary letter references to specific copies of the Emergency Response Directory (ERD).

Please contact us if there ar'e any questions regarding these revised procedures.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/tlt Enclosures cc: Regional Administrator, Region II, USNRC (2 copies)

Senior Resident Inspector, USNRC, St. Lucie Plant (w/o)

'04 Ao<<~~

an FPL Group company

/<~360~~

)

4 ll '4 j

Distri81.txt Distribution Sheet Priority: Normal From: Esperanza Lomosbog Action Recipients:

In LE CENTER 1

External Recipients:

NRC PDR NOAC Copies:

Not Found Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993320008 3

Subject:

ST LUCIE PLANT~ UNITS 1 AND 2 PROJECT MANAGER REASSIGNMENT Bo'dy:

PDR ADOCK 05000335 P

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A Page 1

l November 18, 1999 4

I Mr. T. F. Plunkett I

President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 1

SUBJECT:

ST. LUCIE PLANT, UNITS 1 AND 2 - PROJECT MANAGER REASSIGNMENT

Dear Mr. Plunkett:

This letter is to inform you that, effective December 1, 1999, in addition to his current position of Senior Project Manager for Turkey Point, Units 3 and 4, Mr. Kahtan Jabbour will be assigned as the Senior Project Manager for the St. Lucie Plant, Units 1 and 2. Mr. Jabbour may be reached at 301-41 5-1 496.

Sincerely, anginal signed by:

Herbert N. Berkow, Director Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page DISTRIBUTION:

LF I.C PUBLIC St. Lucie Reading OGC ACRS L. Wert, Rll M. Chancy KJabbour BClayton PDII-2 SC HBerkow eemm~~>>~

DOCUMENT NAME: P:>PM Reassignment-STL To receive a copy of this document, indicate in the box:

"C" - Copy without attachment/enclosure "E" - Copy with attachment/enclosure "N" - No copy OFFICE DATE PDII-2/PN KJabbour 11/

99 Q +~c l4 PDII-2/LA BClayton 11/ f'l /99 PDI I -2/SC OFFICIAL RECORD COPY

/99 9q3ggg00~

P I/

H erk 11/ / f/99

gy,R RECy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555<001 November 18, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNITS 1 AND2-PROJECT MANAGER REASSIGNMENT

Dear Mr. Plunkett:

This letter is to inform you that, effective December 1, 1999, in addition to his current position of Senior Project Manager for Turkey Point, Units 3 and 4, Mr. Kahtan Jabbour willbe assigned as the Senior Project Manager for the St. Lucie Plant, Units 1 and 2. Mr. Jabbour may be reached at 301-415-1496.

Sincerely, Docket Nos. 50-335 and 50-389 cc: See next page erbert N. Berkow, Director Project Directorate II Division of Licensing Project Management Office of'Nuclear Reactor Regulation

Mr. T. F. Plunkett Florida Power and Light Company ST. LUCIE PLANT CC:

Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin ffC21 Tallahassee, Florida 32399-1 741 J. A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. John Gianfrancesco Manager, Administrative Support and Special Projects P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power 8 Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997

Distri90.txt Distribution Sheet Priority: Normal From:

Esperanza Lomosbog Action Recipients:

W Gleaves Copies:

1 Not Found Internal Recipients:

OGC/RP OE NRR/DSSA/SPLB NRR/DLPM/LPD3 JSea LE CENTER 0

AC 1

1 1

1 1

1 1

Not Found Not Found Not Found Not Found Not Found Not Found Not Found External Recipients:

NRC PDR Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTADOl ID: 993310103

Subject:

Letter providing response to Generic Letter 99-02, "Laboratory Testing of Nuclear Grade Activated Charcoal."

Body:

PDR ADOCK 05000335 P

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A Page 1

c I

Florida Power 5 Light Company. 6351 S. Ocean Drive, Jensen Beach, FL 34957 November 16, 1999 L-99-232 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Generic Letter 99-02 Res onse The purpose of this letter is to provide the Florida Power &Light Company (FPL) response to Generic Letter (GL) 99-02, Laboratory Testing ofNuclear-Grade Activated Charcoal, for St.

Lucie Units 1 and 2. The 180-day response to GL 99-02 for St. Lucie Units 1 and 2 is attached.

FPL plans to submit the Technical Specification (TS) amendment requests to require charcoal testing to the ASTM D3803-1989 protocol by November 30, 1999.

On June 3, 1999, the NRC issued GL 99-02 to alert licensees that testing nuclear-grade activated charcoal to standards other than American Society for Testing an'd Materials (ASTM)

D3803-1989, Standard Test Method for Nuclear-Grade Activated Carbon,'ay not be conservative.

On August 23, 1999, the NRC issued an errata notice supplement to GL 99-02.

The NRC requested all licensees determine whether their TS reference ASTM D3803-1989 for charcoal filter laboratory testing.

Licensees, whose TS do not reference ASTM D3803-1989,

.were requested to either amend their TS to reference ASTM D3803-1989 or propose an alternative test protocol.

~

1 FPL plans to follow the recommendations of the GL. St. Lucie Units 1 and 2 meet the GL 99-02 definition of Group 2 plants.

For Group 2 plants, charcoal testing is in compliance with the current Technical Specifications that require charcoal tests using a test protocol other than ASTM D3803-1989.

For St. Lucie Unit 1, the last laboratory test of nuclear-grade activated charcoal filters was completed prior to August 2, 1999.

This testing was completed in compliance with the current TS. The next charcoal test is scheduled for the spring of 2001.

The next test willbe performed in accordance with ASTM D3803-1989 or the charcoal willbe replaced with charcoal tested in accordance with ASTM D3803-1989.

For St. Lucie Unit 2, the next charcoal test is scheduled for the spring of 2000.

The testing will be performed in accordance with ASTM D3803-1989 or the charcoal will be replaced with charcoal tested in accordance with ASTM D3803-1989

~

an FPL Group company PQ@ 4~~ O5u353~

~ g r

tp Wl

. JO

'J

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-232 Page 2 This letter contains four new regulatory commitments.

FPL plans to submit the Technical Specification (TS) amendment requests to require charcoal testing to the ASTM D3803-1989 protocol by November 30, 1999.

The next St. Lucie Unit 2 charcoal test is scheduled for the spring of 2000.

The next charcoal test for St. Lucie Unit 1 is scheduled for the spring of 2001.

The above two and future tests willbe performed in accordance with the ASTM D3803-1989 test protocol or the charcoal will be replaced with charcoal tested in accordance with the ASTM D3803-1989 test protocol.

Please contact us ifthere are any questions about this submittal.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/GRM cc:

Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant

St. Lucie Units 1 and 2

Docket Nos. 50-335 and 50-389 L-99-232 Attachment Page 1

NRC Requested Action 1:

Within 180 days of the date of GL 99-02, submit a written response to the NRC describing your current TS requirements for the laboratory testing of charcoal samples for each ESF ventilation system including the specific test protocol, temperature, RH, charcoal bed thickness, total residence time per bed depth, and penetration at which the TS require the test to be performed. Ifyour current TS specifically require laboratory testing of charcoal samples in accordance with the ASTM D3803-1989 protocol at 30 'C [86 'Fj, and you have been testing in accordance with this standard, then you only need to address this requested action (i.e., no TS amendment or additional testing is required).

FPL Response I:

For St. Lucie Unit 1, the following are the safety-related ventilation systems with charcoal filters:

the shield building ventilation system (SBVS), emergency core cooling system (ECCS) area ventilation system, control room emergency ventilation system (CREVS), and the fuel handling building ventilation system (FHBVS). See Table 2 for the current St. Lucie Unit 1 TS requirements for the laboratory testing of charcoal samples for each ESF ventilation system.

For St. Lucie Unit 2, the following are the safety-related ventilation systems with charcoal filters:

the control room emergency air cleanup system (CREACS), the shield building ventilation system (SBVS), and the ECCS aiba ventilation system.

Emergency operation of the fuel handling building ventilation system is interconnected with the SBVS and uses the charcoal filters in the SBVS.

As discussed in UFSAR Section 9.4.3.2.4, no credit is taken for the ECCS area filtration and cleanup system in the accident analysis.

The current TS do not require charcoal testing of the ECCS area ventilation system filters.

See Table 3 for the current St. Lucie Unit 2 TS requirements for the laboratory testing of charcoal samples for each ESF ventilation system.

The assumed accident analysis penetration values for each ESF ventilation system, the GL 99-02 maximum allowable penetration based on a minimum safety factor value of 2, the current TS allowable penetration values and the TS allowable efficiencies are shown in Table 1. The values in the Table 1 were calculated using the followingformulas:

(Assr rnred Accident Analysis Penteralion) =(1 00% -MethylIodide EfficiencyCreditedin Accident Analysis)

(Assunred Accident Analysis Penetration)

I.99 -02 AllowablePenetration) 6 (Safety Factor = 2)

Current TS Allowable Penetration =(1 00% TS Allowable Efficiency)

K$

'i

$j

St. Lucie Units 1 and 2

Docket Nos. 50-335 and 50-389 L-99-232 Attachment Page 2 Table 1 Allowable Values ESF Ventilation System Unit 1 SBVS Unit 1 ECCS Area Ventilation S stem Unit 1 CREVS Unit 1 FHBVS Unit 2 SBVS Unit 2 CREACS Assumed Accident Analysis Penetration 30%

30%

30%

30%

50%

1%

GL 99-02 Maximum Allowable Penetration with SF = 2 15%

15%

15%

15%

25%

0.5%

Current TS Maximum Allowable Penetration 10%

10%

10%

30%

1 10%

1%

1 0.175%

Current TS Minimum Allowable Efficiency 90%

90%

90%

70%

1 90%

99%

1 99.825%

Note (1) - requirements specified for elemental iodine not methyl iodide.

Tables 2 and 3 include the specific test protocol, temperature, relative humidity (RH), charcoal bed thickness, total residence time per bed depth, and penetration at which the curry.nt TS require the test to be performed for the St. Lucie Units 1 and 2 systems.

NRC Requested Action 2 Ifyou choose to adopt the ASTM D3803-1989 protocol, submit a TS amendment request to require testing to this protocol within 180 days of the date ofthis generic letter.

The request should contain the test temperature, RH, and penetration at which the proposed TS will require the test to be performed and the basis for these values. Ifthe system has a face velocity greater than [1 10] (August 23, 1999 errata) percent of 0.203 m/s [40 ft/min], then the revised TS should specify the face velocity. Also, indicate when the next laboratory test is scheduled to be performed.

FPL Response 2 FPL plans to submit TS amendment requests to adopt charcoal testing using the ASTM D3803-1989 test protocol by November 30, 1999.

The proposed changes willbe only for those safety-related ESF systems with charcoal filters that currently have TS requirements to perform laboratory testing for iodine removal.

The proposed changes willalso retain the current TS surveillance intervals.

The request willcontain the test temperature, and RH at which the proposed TS willrequire the test to be performed.

The acceptance criteria willbe specified as minimum removal efficiency in lieu of the allowable penetration.

The license amendment request willinclude the basis for these values.

The applicable charcoal filter systems at St. Lucie do not have a face velocity greater than 110 percent of 40 fpm. The face velocity is calculated by dividing the flowrate (cfm) by the charcoal adsorber net free area (ft') in the equipment specification.

St. Lucie Units 1 and 2

-, Docket Nos. 50-335 and 50-389 L99-232 Attachment Page 3 For St. Lucie Unit 2, the next charcoal test is scheduled in the spring of 2000. For St. Lucie Unit 1, the next charcoal test is scheduled in the spring of 2001.

NRC Requested Action 3 Ifyou are proposing an alternate test protocol, address the attributes discussed below and submit a TS amendment request to require testing to this alternate protocol within 180 days of the date of this generic letter.

The request should contain the test temperature, RH, and penetration at which the proposed TS willrequire the test to be performed and the basis for these values. Ifthe system has a face velocity greater than [110] percent of 0.203 m/s [40 ft/min], then the revised TS should specify the face velocity.

Also, indicate when the next laboratory test is scheduled to be performed....

FPL Response 3 FPL is not proposing an alternate test protocol for use at St. Lucie.

NRC Requested Action 4 At the next required laboratory surveillance test of a charcoal sample that is 60 or more days after the date of this generic letter, test your charcoal samples in accordance with ASTM D3803-1989 or replace all of the charcoal with new charcoal that has been tested in accordance with ASTM D3803-1989. In all cases, the results should meet the acceptance criterion that is derived from applying a safety factor as low as 2 (see the note in Enclosure 2 of the GL) to the charcoal filter efficiency assumed in your design-basis dose analysis and the charcoal samples should continue to be tested in accordance with ASTM D3803-1989, in lieu of the current TS-required laboratory testing, until the TS amendment is approved by the NRC.

FPL Response 4 Allcharcoal media testing performed after August 2, 1999 willbe conducted in accordance with the ASTM D3803-1989 test protocol. Any new charcoal willbe procured to ASTM D3803-1989.

The charcoal test results willmeet acceptance criterion that is derived from applying at least a safety factor of 2 to the charcoal filterefficiency assumed in the design basis dose analysis.

NRC Requested Action 5 Addressees who choose not to do the above actions are requested to notify the NRC in writing of their decision, as soon as a decision is reached but no later than 60 days from the date ofthis generic letter.

The 60 day written response should also discuss (1) addressee plans to pursue a proposed alternative course of action (including the basis for establishing its acceptability), (2) the schedule for submitting that proposal for NRC staff review (that proposal should be submitted to the NRC no later than 180 days from the date of this generic letter), and (3) the basis for continued operability of affected systems and components until such time that the proposed alternative course of action is

St. Lucie Units 1 and 2

, Docket Nos. 50-335 and 50-389 L-99-232 Attachment Page 4 approved by the NRC.

FPL Response 5 FPL plans to implement the recommendations of the GL 99-02, therefore no 60 day response was IeqU1ANI.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L99-232 Attachment Page 5 TABLE2 - ST. LUCIEUNIT..I-SAFETY.RELATEDHLTER SYSTKVS -'HARCOAL-":::TESTING S stem Descri tioii Existin -Test R uireiiieiits

,.Tech Spec (I) 4.6.6.1 4.7.8.1 4.7.7.1 4.9.12 Safety Related Ventilation System Service Shield Building Ventilation stem ECCS Area Ventilation S stem Control Room Emergency Ventilation S stem Fuel Handling Buildin Ventilation S stem Bed. --:-,:"--:-:'::: :---Test Thickness.'.,

Pr'otocol (5}

(1)

ANSI N510-1975 ANSI N510-1975 ANSI N510-1975 ANSI N510-1975 Test Temp

.::.:.(1)'30 deg C 130 deg C 130 deg C 130 deg C Test Relative-.

Residence Humidity::..:Time/ bed.

(1):::-::; ,'::='-:depth 2

95% R.H.

0.25 Sec 95% R.H.

0.25 Sec 95% R.H.

0.25 Sec 95% R.H.

0.25 Sec AHowab1e Penetratio'n (4) 10% for methyl iodide 10% for methyl iodide 10% for methyl iodide 30% for elemental iodide

--Pace Velocity

1. As specified in Technical Specifications 2.

Value per ANSI N509-1980, Paragraph 4.3 "normally 0.25 seconds per 2 inches of thickness" 3.

No TS Requirement for testing charcoal 4.

Calculated as 100 filterefficiency 5.

Values are based on charcoal adsorber net free area and system air flows from Equipment Specifications FLO-8770.776, FLO-8770.779, FLO-2998.776, FLO-2998.777, and FLO-2998.779

4 L

l

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-232 Attachment Page 6

- TABLE3 -'T.- LUCIEUNIT2'SAFETY RELATED FILTER-:.SYSTEMS CKARCOALTESTING S stem Descri tion Existin -Test R -iiirements Tech Spec (1),

Safety Related Vent>lation System Service

(I)

Thick'ness

,,(5)

Test Protocol (1)

Test Temp (I)

Test Relative

.Humidity Residence Time'I bed depth "2

Allowable Pe'netration

,::::::::::(4)

Face Velocity 4.6.6.1 4.7.7 Shield Building Ventilation System ECCS Area Ventilation stem Control Room Emergency Air Cleanu S stem ANSI N510-1980 ANSI N510-1980 130 deg C 95% R.H 130 deg C 95% R.H.

0.25 Sec 0.25 Sec 0.5 Sec 10% for methyl iodine & 1% for elemental iodine 0.175% for methyl iodine 40 m

40 fpm

1. As specified in Technical Specifications 2.

Value per ANSI N509-1980, Paragraph 4.3 "normally 0.25 seconds per 2 inches of thickness"

3. No TS Requirement for testing charcoal 4.

Calculated as 100 filterefficiency 5.

Values are based on charcoal adsorber net free aiea and system air flows from Equipment Specifications FLO-8770.776, FLO-8770.779, FLO-2998.776, FLO-2998.777, and FLO-2998.779

ly V

A, I

0

Cg'istribution Sheet Distri-7.txt Priority: Normal From: Stefanie Fountain Action Recipients:

W Gleaves Copies:

1 Not Found Internal Recipients:

NRR/DIPM/EPHP IRO D Ha an FIL'E PNTEfPN External Recipients:

NRC PDR NOAC Not Found Not Found Not Found Not Found Not Found Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 993240446

Subject:

Exercise of emergency plan for St Lucie Units 1 8 2 to be conducted on February 16,20 00 Body:

PDR ADOCK 05000335 F Docket: 05000335, Notes: N/A Docket: 05000389, Notes: N/A Page 1

w PPIL.

Florida Power 5 Light Company. 6351 S. Ocean Drive. Jensen Beach, FL 34957 p

November 10, 1999 L-99-245 10 CFR Part 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan Exercise-Februa 2000 Florida Power &Light Company (FPL'), in cooperation with th'e State ofFlorida and the St. Lucie County and Martin County emergency response agencies, willconduct an exercise ofthe emergency plan for St. Lucie Plant on February 16, 2000. The exercise will.involve participation by local emergency response agencies and the State ofFlorida emergency response personnel, and willbe evaluated by the Federal Emergency Management Agency.

Ifthere are any questions or comments concerning this exercise or the attached exercise r,.

I objectives which have been reviewed by our local agencies, please contact Ms. Donna Calabrese at (561) 467-7185.

g 7 Very truly yours, J. A. Stall Vice President St. Lucie Plant JAShlt Attachment cc:

Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Kenneth P. Barr, Emergency Preparedness Section Chief, Region II, USNRC

Attachment L-99-245 Page 1 of5 I'LORIDAPOWER AND LIGHTCOMPANY ST. LUCIEPLANT 2000 EME<RGE<NCY PRE<PAREDNE<SS EVALUATEDEXERCISE FEBRUARY 16, 2000 OBJECTIVES The St. Lucie Plant (PSL) 2000 Emergency Preparedness Exercise objectives are based upon Nuclear Regulatory Commission requirements provided in 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities and inspection criteria listed in the NRC Inspection Manual. Additional guidance provided in NUREG-0654, FEMA-REP-1, Revision 1, Criteriafor Preparation and Evaluation ofRadiological Emergency Response Plans and Preparedness in Support ofNuclear Power Plants, was utilized in developing the objectives.

The exercise willbe conducted and evaluated using a realistic basis for activities. Scenario events may escalate to a release ofradioactive material to the environment.

The following objectives for the exercise are consistent with the aforementioned documents:

A.

Accident Assessment and Classification 1.

Demonstrate the ability to assess accident conditions.

2.

Demonstrate the ability to identify initiating conditions, review conditions against the Emergency Action Levels (EALs), and correctly classify the emergency throughout the exercise.

Notification 1.

Demonstrate the ability to alert, notify and mobilize Florida Power and Light (FPL) emergency response personnel.

2.

Demonstrate the ability to alert and notify non-emergency response personnel.

3.

Demonstrate appropriate procedures for both initial and follow-up notifications.

4.

Demonstrate the capability to promptly notify the State ofFlorida and Local Authorities of an emergency declaration or change in emergency classification.

5.

Demonstrate the capability to promptly notify the U.S. Nuclear Regulatory Commission (NRC) of an emergency declaration or change in emergency classification.

6.

Demonstrate the ability to provide accurate and timely information to State, Local, and Federal Authorities concerning class of the emergency, plant status I conditions, and whether a radioactive release is in progress, as appropriate.

AiiAclllllclli I 99-245 Page 20f5 7.

Demonstrate the ability to provide periodic plant status updates to State, Local, and Federal Authorities.

C.

Communications 1.

Demonstrate the availability and operability of emergency communications equipment for notification of State, Local, and Federal Authorities.

2.

Demonstrate the means to provide follow-up information to State, Local, and Federal Authorities.

3.

Demonstrate the availability and operability of communications equipment in the Emergency Response Facilities (ERFs) for interfacility communications.

4.

Demonstrate the availability and operability of emergency communications equipment necessary for off-site monitoring activities.

5.

Demonstrate the means to acquire meteorological data necessary for emergency response.

D.

Emergency Response 1.

Demonstrate staffing of Emergency Response Facilities (ERFs).

2.

Demonstrate planning for 24-hour per day emergency response capabilities.

3.

Demonstrate the activation of the Technical Support Center (TSC) and Operational Support Center (OSC).

4.

Demonstrate the activation of the Emergency Operations Facility (EOF).

5.

Demonstrate the functional and operational adequacy of the Emergency Response Facilities: TSC, OSC, and EOF.

6.

Demonstrate the ability of each Emergency Response Facility Manager to maintain command and control over the emergency response activities conducted within the facility throughout the exercise.

7.

Demonstrate the ability of each facilitymanager to periodically inform facility personnel of the status of the emergency situation and plant conditions.

Attachtncnt L-99-245 Pagc30f5 Demonstrate the transfer of Emergency Coordinator (EC) function from the Nuclear Plant Supervisor (NPS) to designated senior plant management and transfer of Emergency Coordinator responsibilities: (1) off-site notification to the State and Local Authorities and (2) recommending protective actions to the Recovery Manager (RM).

9.

Demonstrate the ability to promptly and accurately transfer information between Emergency Response Facilities (ERFs).

10.

Demonstrate the ability of the TSC to request and prioritized Emergency Response Teams (ERTs) in a timely manner.

11.

Demonstrate the ability of the OSC to assemble, dispatch, and control ERTs in a timely manner.

/

12.

Demonstrate the capability for development of the appropriate Protective Action Recommendations (PARs) for the general public within the 10-Mile Emergency Planning Zone (EPZ).

13.

Demonstrate that the appropriate PARs can be communicated to State and Local Authorities within the regulatory time constraints.

14.

Demonstrate the activation, staffing, and control of the Emergency News Center (ENC).

E<.

Radiological Assessment and Control 1.

Demonstrate the capability to provide radiological monitoring for people evacuated from the site.

2.

Demonstrate the coordinated gathering ofradiological data necessary for emergency response, including collection and analysis of in-plant surveys and samples, as applicable.

3.

Demonstrate the capability to calculate radiological release dose projections and perform timely and accurate dose assessment, as appropriate.

4.

Demonstrate the ability to compare on-site and off-site dose projections to the EPA protective action guidelines and determine and recommend the appropriate protective actions.

Attachment L-99-245 Page 4 of5 5.

Demonstrate the ability to provide dosimetry to emer'gency response personnel as required and adequately track personnel exposure.

6.

Demonstrate the capability to confirm and periodically assess the habitability of the on-site Emergency Response Facilities (ERFs).

7.

Demonstrate the capability for on-site contamination control.

8.

Demonstrate the ability to adequately control radiation exposure to on-site emergency workers, as appropriate, to radiological conditions.

9.

Demonstrate the decision making process for authorizing emergency workers to receive radiation doses in excess of 10 CFR Part 20 limits, as appropriate.

10.

Demonstrate the ability to control and coordinate the flowof information regarding off-site radiological consequences between radiological assessment personnel in the TSC and EOF.

11.

Demonstrate the ability of field monitoring teams to respond to and analyze an airborne radiological release through direct radiation measurements in the environment, as appropriate.

12.

Demonstrate the means to determine the necessity of and the capability for decontamination.

13.

Demonstrate the ability to assemble and dispatch field monitoring teams.

14.

Demonstrate the collection and analysis of air samples and provisions for effective communications and recordkeeping, as appropriate.

15.

Demonstrate the ability to control and coordinate the flow of information regarding off-site radiological consequences with State radiological assessment personnel in the EOF.

F.

Public Information Program 1.

Demonstrate the timely and accurate response to news inquiries.

2.

Demonstrate the ability to brief the media in a clear, accurate, and timely manner.

3.

Demonstrate the ability to coordinate the preparation, review, and release of public information with State and Local Government Agencies, as appropriate.

Attachment L-99-245 Page 5 of5 G.

Medical Emergency 1.

Demonstrate the ability to respond to a radiation medical emergency in a timely manner.

2.

Demonstrate the capability of the First Aid and Personnel Decontamination Team to respond to a medical emergency, administer first aid, and survey for contamination on a simulated contaminated injured individual.

H.

Evaluation 1.

Demonstrate the ability to conduct a post-exercise critique to determine areas requiring corrective action or improvement.

I.

Clarifications/C<xemptions Areas of the PSL Emergency Plan that willNOT be demonstrated during this exercise include:

1.

(E.1) Actual radiological monitoring of evacuated personnel (off-site HP monitoring resources willbe identified and allocated to the off-site Assembly Area).

2.

(E.9) Credit willbe taken for discussion of the decision-making process during evaluation of the need for dose extension(s).

3.

Site evacuation of non-essential personnel.

4.

On-site personnel accountability.

5.

Availabilityand operability of backup communications equipment.

Distribution Sheet Distri76.txt Priority: Normal From: Stefanie Fountain Action Recipients:

In naW~i'am~

ILE CENTE 01 Copies:

Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 993190249

Subject:

COMPLETON OF LICENSNG ACTION FOR GENERIC LETTER 98-01 AND SUPPLEMENT 1 - ST LUCIE PLANT, UNITS 1 AND 2 (TAC NOS. MA1892 AND MA1893)

Body:

Docket: 05000335, Notes: N/A Docket: 05000389, Notes: N/A Page 1

gpit RE00 0

o Q

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 November 2, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENEFflC LE%i ER 98-01 AND SUPPLEMENT 1 - ST. LUCIE PLANT, UNITS 1 AND 2 (TAC NOS. MA1892 AND MA1893)

Dear Mr. Plunkett:

On May 11, 1998, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 98-01, "Year 2000 Readiness of Computer Systems at Nuclear Power Plants," to all holders of operating licenses for nuclear power plants, except those who have permanently c..ased operations and have certified that fuel has been permanently removed from the reactor vessel.

The NRC issued GL 98-01 to ensure that licensees were adequately addressing potential date-related errors with computer systems, embedded software devices, and software applications sufficiently in advance of the Year 2000 (Y2K) rollover date to ensure that nuclear power plants will be in a stable, safe condition during the Y2K transition. ~

Subsequent to the issuance of GL 98-01, increased public awareness and government attention to the Y2K issue resulted in concern over, not only public health and safety of nuclear power plants, but also the ability of nuclear power plants to continue to provide power to the national electric power grid. Therefore, on January 14, 1999, the staff issued Supplement 1 to GL 98-01 to provide addressees with a voluntary, alternative response to that required in Item (2) of GL 98-01.

In responding to Supplement 1, addressees were asked to confirm Y2K readiness of the facilitywith regard to those systems within the scope of the license and NRC regulations, as well as those systems required for continued operation of the facility after January 1, 2000.

Addressees were permitted to voluntarily respond to Supplement 1 to GL 98-01 on or before July 1, 1999, in lieu of Item (2) of GL 98-01.

In response to GL 98-01, you provided a letter dated November 22, 1998, for St. Lucie Plant, Units 1 and 2. This submittal provided the information requested by the GL. The staff has reviewed your response and has concluded that all requested information has been provided.

Therefore, we consider GL 98-01 to be closed for.St. Lucie Plant, Units 1 and 2.

NRC document, NUREG-1706, "Year 2000 Readiness in U.S. Nuclear Power Plants," provides a status of nuclear power plant Year 2000 readiness as of September 1, 1999, and a description of NRC actions to determine Y2K readiness in operating U.S. reactors.

The staff assessment of Y2K readiness consisted of independently evaluating nuclear power plant licensee Y2K readiness program processes, reviewing licensee responses to NRC requests for reporting Y2K readiness (i.e., GL 98-01 and Supplement 1), and combining the results on these

~peslm'~

q<r/7~2 41 peal

T. Plunkett assessments to achieve a high level of assurance that each facilitywilloperate safely during

'the transition from 1999 to 2000 and on other Y2Ksensitive dates.

NUREG-1706 is linked to the NRC home page (http://www.nrc.gov/NRC/NEWS/year2000.html).

We would like to acknowledge the effort Florida Power and Light has put forth in preparing St. Lucie, Units 1 and 2, for the Y2K transition and appreciate your continued cooperation on this important issue.

If you have any questions regarding this matter, please contact me at (301) 415-1479.

Sincerely, t0. C~

William C. Glea es, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page

1 If

Mr. T. F. Plunkett Florida Power and Light Company ST. LUCIE PLANT CC:

Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. WilliamA. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin ¹C21 Tallahassee, Florida 32399-1741 J. A. Stall, Site Vice President St. Lucie Nuclear Plant

, 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. John Gianfrancesco Manager, Administrative Support and Special Projects P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997

i..

~

T. Plunkett November 2, 1999 assessments to achieve a high level of assurance that each facilitywilloperate safely during the transition from 1999 to 2000 and on other Y2Ksensitive dates.

NUREG-1706 is linked to the NRC home page (http://www.nrc.gov/NRC/NEWS/year2000.html).

We would like to acknowledge the effort Florida Power and Light has put forth in preparing St. Lucie, Units 1 and 2, for the Y2Ktransition and appreciate your continued cooperation on this important issue.

If you have any questions regarding this matter, please contact me at (301) 415-1479.

Sincerely, Docket Nos. 50-335 and 50-389 cc: See next page Original signed, by:

William C. Gleaves, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Distribution i¹ile Center>

PDII-2 Reading File HBerkow OGC AHansen, Lead PM

, JCalvo PUBLIC JZwolinski/S Black Acting SC PDII-2 ACRS LWert, Rll WGleaves BClayton DOCUMENT NAME: G:EPDII-2>St. Lucie)MA1892GL98-01co.wpd Indicate in the box: "c" = co without enclosures "e" = co with enclosures "n" = no co OFFICE NAME DATE PM:PDII-2 WgleCves 4C/ZC

/99 SC: PDII-2 (A LA:PDII-2 BCIaylon~

14/ 02. /99 10/ ~'1

/99 OFFICIALRECORD COPY

iv i

J r

I

'I l

l

Distri40.txt Distribution Sheet

(((r (ff Priority: 'Normal From: Linda Eusebio Action Recipients:

W Gleaves Copies:

1 Not Found Internal Recipients:

NRR/DIPM/EPHP IRO D Ha an F

CENTER Not Found Not Found Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993140309

Subject:

Revision 4 to EPIP-05, "Activation and Operation of the Operational Su pport Center."

Body:

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A

)at~g,

/( gQ fff (E/'f Page 1

Florida Power 5 Light Company, 6501 South Ocean Drive, Jensen Beach, FL34957 PPK November 1, 1999 L-99-233 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emer enc Plan lm lementin Procedure In accordance with 10 CFR 50 Appendix E, enclosed is a copy of the revised Emergency Plan Implementing Procedure (EPIP) listed below.

Number Title Revision Im lementation Date EPIP-05 Activation and Operation of the 4

Operational Support Center October 9, 1999 EPIP-05 Revision 4 clarified the role of the Operations (OPS) re-entry supervisor, added guidelines for Operational Support Center (OSC) command and control assistance, provided instructions for emergency access to restricted areas, and revised minimum staff position in Chemistry to the OSC Chemist.

EPIP-05 Revision 4 also clarified facility sign-in and accountability instructions,'einforced instructions for the development of a contingency team, and made editorial changes.

Please contact us if there are any questions regarding this revised procedure.

Very truly yours, Vice President St. Lucie Plant JAS/tlt Enclosure cc: Regional Administrator, Region II, USNRC (2 copies)

Senior Resident Inspector, USNRC, St. Lucie Plant (w/o) an FPL Group company

S+>>

V>>

'd f

Distr>.35.txt Distribution Sheet Priority: Normal From: Linda Eusebio Action Recipients':

W Gleaves NRR/DLPM/LPD2-2 B Clayton Internal Recipients:

RidsManager OGC/RP NRR/DSSA/SRXB N P;/~DSSA/C PLB~

Fi e Cente 0

ACRS Copies:

1 1

1 Not Found Not Found Not Found OK Not Found Not Found Not Found Not Found Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library:

ML ADAMS"HQNTAD01 ID: 993140283

Subject:

Letter submitting LBLOCA Evaluation Model 30-day 10CFR50.46 rept regar ding significant change to calulated peak cladding temp for limiting l oss of coolant accident evaluated for St. Lucie, Unit l.

Body:

Docket:

05000335, Notes:

N/A Page 1

0 Florida Power 5 Light Company. 6351 S. Ocean Drive, Jensen Beach, FL 34957 October 29, 1999 L-99-236 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket 50-335 LBLOCAEvaluation Model 30-Da 10 CFR 50 46 Re ort The attached report is submitted pursuant to 10 CFR 50.46(a)(3)(ii) to provide notification of a significant change to the calculated peak cladding temperature for the limiting loss of coolant accident evaluated for St. Lucie Unit 1.

Please contact us ifyou have any questions about this matter.

Very truly yours, J. A. Stall Vice President S

. Lucie Plant S/RLD Attachment CC:

Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant QD an FPL Group company p r.qrr3 A'0 J Z3

e r

St. Lucie Unit 1 Docket No. 50-335 LBLOCAEvaluation Model 30-Da 10CFR50.46Re ort L-99-236 Attachment Page 1 of2 Siemens Power Corporation (SPC) is the current fuel vendor for St. Lucie Unit 1, and performs the calculations to demonstrate that the Unit 1 emergency core cooling system (ECCS) performance conforms to 10 CFR 50.46.

SPC employs an acceptable evaluation model consistent with 10 CFR 50, Appendix K.

Re-analysis of the large break loss of coolant accident (LBLOCA) has resulted in a significant reduction in the calculated peak cladding temperature (PCT), and is hereby reported pursuant to 10 CFR 50.46(a)(3)(ii).

Nature of the Model Chan e and Corrective Action Certain non-physical behavior associated with reflood heat transfer coefficients used in SPC's LBLOCA evaluation model was identified by the NRC staff and is discussed in Reference

1. Compensatory measures taken by FPL at that time included an analysis of the LBLOCA by SPC using a modified 1986 methodology described in Reference 2.

Based on that analysis, the calculated PCT for the limiting ECCS analysis of record was 2027'F (DECLG with 0.8 discharge coefficient).

Pending further evaluation and long-term correction of LBLOCA model deficiencies, Reference 3 concluded that the modified 1986 model was acceptable for determining that St. Lucie Unit 1 meets the acceptance criteria of 10 CFR 50.46.

Additional PCT adjustments based on the estimated impact from other model anomalies discovered since the last acceptable model are documented in References 4, 5, and 6.

The St. Lucie Unit 1 ECCS cooling performance has been analyzed for operating cycle-16 using the LBLOCAevaluation model identified in SPC Report EMF-2087(P)(A). This revised model resolves the identified deficiencies and incorporates other improvements, and is approved by the NRC staff as an acceptable ECCS evaluation model (Reference 7).

Im actof the Model Chan e

Reanalysis with the revised LBLOCA model results in a PCT -98'F from the value of 2027'F calculated previously with the modified 1986 model.

The new LBLOCA PCT is 1929'F (DECLG with 1.0 discharge coefficient), and is the limiting PCT of record for St. Lucie Unit 1.

References 1.

NRC Letter, Brian E. Sheron (NRC) to T.F. Plunkett (FPL), 10 CFR 50.46 LARGE BREAK LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL FOR ST.

LUCIE PLANT, UNIT 1 (TAC NO. M96335); October 11, 1996.

FPL Letter L-96-295, J.A. Stall (FPL) to NRC (DCD), Docket 50-335, LBLOCNECCS Revised Analysis, 30 Da 10 CFR 50.46 Re ort; November 7, 1996.

NRC Letter, Leonard A. Wiens (NRC) to Thomas F. Plunkett (FPL), 10 CFR 50.46 LARGE BREAK LOSS OF COOLANT ACCIDENT EVALUATION MODEL FOR ST.

LUCIE PLANT UNIT 1 (TAC M96355); December 6, 1996.

2

St. Lucie Unit 1 Docket No. 50-335 LBLOCAEvaluation Model 30-Da 10CFR50.46Re ort L-99-236 Attachment Page 2 of 2 4.

FPL Letter, L-97-034, J.A. Stall (FPL) to NRC (DCD), Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Reactors:

10 CFR 50.46 Annual Re ort; March 6, 1997.

5.

FPL Letter, L-98-057, J.A. Stall (FPL) to NRC (DCD), Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Reactors:

10 CFR 50.46 Annual Re ort; March 4, 1998.

6.

FPL Letter, L-99-049, J.A. Stall (FPL) to NRC (DCD), Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency, Core Cooling Systems for Light Water Reactors:

10 CFR 50.46 Annual Re ort; March 1, 1999.

7.

NRC Letter, Cynthia A. Carpenter (NRC) to J.F. Mallay (SPC), ACCEPTANCE FOR REFERENCING OF THE TOPICAL REPORT EMF-2087(P),

"SEM/PWR-98: ECCS EVALUATIONMODEL FOR PWR LBLOCAAPPLICATIONS" (TAC NO. MA3457); June 15, 1999.

SOY p 5 ]ggp r

Distri74.txt Distribution Sheet Priority: Normal From:

Esperanza Lomosbog Action Recipients:

Inte 1 Recipients:

ENTER 0

Copies:

Not Found External Recipients:

NRC PDR NOAC Not Found Not Found Total Copies:

Item:

ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 993190315

Subject:

ST LUCIE g UNlT 1 ~

CLARiFICATION OF SAFETY EVALUATION FOR CLOSEOUT OF G

ENERIC LETTER 95 07 ~

PRESSURE LOCKING AND THERMAL BINDING OF RELATED POWER-OPERATED GATE VALVES."

Body:

pdr adock 05000335 p

Docket:

05000335, Notes:

N/A Docket:

05000389, Notes:

N/A Page 1

oR RE'Cc 0

A.

ClO IVl0 Cp

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 October 28, 1999

~

Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE, UNIT 1, CLARIFICATIONOF SAFETY EVALUATIONFOR CLOSEOUT OF GENERIC LETTER 95-07, "PRESSURE LOCKINGAND THERMALBINDINGOF SAFETY-RELATED POWER-OPERATED GATE VALVES,"(TAC NO. MA6919)

Dear Mr. Plunkett:

On August 17, 1995, the U.S. Nuclear Reactor Commission (NRC) issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," and requested that licensees take action to ensure those safety-'related power-operated gate valves that are susceptible to pressure locking or thermal binding are~capable of performing their safety functions.

In a letter dated February 13, 1996, Florida Power 8 Light Company submitted its 180-day response to the GL for St. Lucie, Unit 1. The NRC staff reviewed the licensee's submittal and requested additional information in a letter dated June 26, 1996.

In a "L-96-191, Responds to RAI Concerning GL 95-07, Pressure Locking & [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. of SR Power Operated Gate Valves. Summary of Requested Calculation Encl|letter dated July 31, 1996]], the licensee provided the additional information. The NRC staff performed an inspection to review specific aspects of information summarized in the licensee's response to GL 95-07. This inspection is documented in NRC Inspection Report 50-335, 389/97-11, dated November 10, 1997. The licensee provided additional information in a letter dated May 20, 1999, in response to a staff request.

The NRC staff reviewed the licensee's submittals and found that the licensee adequately addressed the actions requested in GL 95-07 for St. Lucie, Unit 1.

In a safety evaluation (SE) dated July 15, 1999, the NRC staff described the licensee's corrective actions to ensure that valves in the scope of GL 95-07 are capable of performing their intended safety functions.

In Section 3.2.a of the SE, it stated that the actuators for the shutdown cooling hot leg suction valves, V-3481, V-3651, and V-3652, were scheduled to be modified to increase actuator capability during the fall 1999 refueling outage.

On September 8, 1999, the licensee clarified that the modification involved installation of a bypass line across the reactor coolant side of

%Bi.

Chil,lm* gIFj~~g/7$ ij',IIP%

P(3lfoflg

A.

p

~

T.F. Plunkett each valve seat in lieu of modifying the actuator for each valve. The NRC staff finds that this modification is an effective corrective action that wilt eliminate the potential for pressure locking in hot leg suction valves V-3481, V-3651, and V-3652, and therefore is acceptable.

This completes the staff's effort on TAC No. MA6919.

Sincerely, William C. Gl ves, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page

Mr. T. F. Plunkett Florida Power and Light Company ST. LUCIE PLANT CC:

Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P..O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. WilliamA. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin ¹C21 Tallahassee, Florida 32399-1741 J. A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. John Gianfrancesco Manager, Administrative Support and Special Projects P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President-Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997

1 h

October 28, 1999 T.F. Plunkett 2

I each valve seat in lieu of modifying the actuator for each valve., The NRC staff finds that this modification is an effective corrective action that willeliminate the potential for pressure locking in hot leg suction valves V-3481, V-3651, and V-3652, and therefore is acceptable.

Sincerely, Docket Nos. 50-335 and 50-389 cc: See next page Origjmd. signed by:

William C. Gleaves, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation DISTRIBUTION:

<File, Center~

PUBLIC St. Lucie R/F KJabbour (Acting SC)

BClayton WGleaves OGC ACRS LWert, Rll DOCUMENTNAME: G:1PDII-21St. LucleUMA6919gl9507coltr¹2.wpd To receive e co of this document lndlcete In the bout "C" a Co without ettechmengfenctoeute "E" a Co with ettechmenO'endoeute "N" a No co OFFICE NAME PDII-21PM 9

PDII-21LA

~

PDII-2LSC A WGI ves MC4 BCla on A~M KJabbour DATE 108 99 10/v 99 10/

99 OFFICIALRECORD COPY 10/ /99 10/ /99