ML20154P901
| ML20154P901 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/14/1998 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9810230098 | |
| Download: ML20154P901 (44) | |
Text
__
October 14, 1998 LICENSEE:
Florid: Pow;r Corporation FACILITY:
Crystal River, Unit 3
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 21,1998, CONCERNING CRYSTAL RIVER UNIT 3 EMERGENCY FEEDWATER SYSTEM AND HIGH PRESSURE INJECTION, SYSTEM MODIFICATIONS On September 21, b98, a meeting was held between staff of the U.S. Nuclear Regulatory Commission (NRC) and representatives of Flarida Power Corporation (FPC). The purpose of the meeting was to discuss FPC plans to modify the emergency feedwater system and the high pressure injection system to resolve previously identified design issues related to diesel generator loading and operator burden as a result of required manual actions for a small break loss of coolant accident. The presentation included tentative schedules for the submittal of necessary license amendment requests and the date by which approval of these amendments would be needed. Enclosure 1 is an attendance list for the meeting. Enclosure 2 includes copies of the meeting handouts.
The NRC staff indicated that the information presented by FPC at the meeting, as described in the enclosed handouts, was very useful in understanding the scope, schedule and potential impact on NRC resources of the projects. The NRC representatives indicated that is would be useful to include a discussion of risk reduction and risk insights in the license submittals. They also stated that a description of post-modification testing should be included in the submittals.
The NRC staff stressed the need for timely submittal of the license amendment requests to provide adequate time for review and processing. The meeting was adjourned after a brief question-and-answer session.
/s/
Leonard A. Wiens, Senior Project Manager Project Directorate u 3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
- 1. Attendance List
- 2. Handouts cc w/ enclosures: See next page DISTRIBUTION Hard Coov E-Mall l
6 Flie\\
SCollins/FMiraglia TMartin JTatum PUBLIC BBoger MTschiltz WLeFave
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Crystal r/f JZwolinski LPlisco, Rll JKnox LWiens FHebdon EWeiss Y
ACRS BClayton SSaba OGC W' P HLE CENTEa COPY J
DOCUMENT NAME: G:\\ CRYSTAL \\MEETGSUM.EFW To receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with ettschment/ enclosure "N"
- No copy 0FFICE P0ll 3/PM
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lC PO!! 3/LA l ) PDII 3/D i/
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NAME LWiens:cw M vW BClayton MM M FHebdon N DATE 10/p//98 '
10//4//98 10/ P4 /98 10/ /98 9810230098 981014 PDR ADOCK 05000302 P
PDR a
i
October 14, 1998 LICENSEE:
Florida Powtr Corporation FACILITY:
Crystal River, Unit 3
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 21,1998, CONCERNING i
CRYSTAL RIVER UNIT 3 EMERGENCY FEEDWATER SYSTEM AND HIGH PRESSURE INJECTION, SYSTEM MODIFICATIONS 4
On September 21,1998, a meeting was held between staff of the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power Corporation (FPC). The purpose of the meeting was to discuss FPC plans to modify the emergency feedwater system and the high pressure injection system to resolve previously identified design issues related to diesel i
generator loading and operator burden as a result of required manual actions for a small break loss of coolant accident. The presentation included tentative schedules for the submittal of necessary license amendment requests and the date by which approval of these amendments would be needed. Enclosure 1 is an attendance list for the meeting. Enclosure 2 includes copies of the meeting handouts.
4 The NRC staff indicated that the information presented by FPC at the meeting, as described in the enclosed handouts, was very usefulin understanding the scope, schedule and potential impact on NRC resources of the projects. The NRC representatives indicated that is would be useful to include a discussion of risk reduction and risk insights in the license submittals. They also stated that a description of post-modification testing should be included in the submittals.
The NRC staff stressed the need for timely submittal of the license amendment requests to provide adequate time for review and processing. The meeting was adjoumed after a brief question-and-answer session.
/s/
Leonard A. Wiens, Senior Project Manager Project Directorate ll-3 Division of Reactor Projects - 1/11 q
j,
Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
- 1. Attendance List
- 2. Handouts 1
ec w/ enclosures: See next page t
DISTRIBUTION'
- ~
Hard Cooy E-MAIL Docket File SCollins/FMiraglia TMartin JTatum j
PUBLIC BBoger MTschiltz WLeFave Crystal r/f JZwolinski LPlisco, Rll JKnox LWiens FHebdon EWeiss ACRS BClayton SSaba OGC DOCUMENT NAME: G:\\ CRYSTAL \\MEETGSUM.EFW To recsive a copy of this document, Indicate in the box:
"C" a copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PDil 3/PM
)
lC PD!l 3/LA l I Poll 3/0 i) lC I
NAME LWiens: cud 7 V W 8Clayton 4/L U FNebdon N DATE 10//4//98 '
10/ I/~/98 10/ H /98 10/ /98 0FFICIAL RECORD COPY
l l
Mn UNITED STATES i
j NUCLEAR REGULATORY COMMISSION
=
t WASHINGTON, D.C. 30006 4001
'+,.....,o October 14, 1998 LICENSEE:
Florida Power Corporation l
FACILITY:
Crystal River, Unit 3 L
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 21,1998, CONCERNING CRYSTAL RIVER UNIT 3 EMERGENCY FEEDWATER SYSTEM AND l
HIGH PRESSURE INJECTION SYSTEM MODIFICATIONS On September 21,1998, a meeting was held between staff of the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power Ccrporation (FPC). The purpose of the meeting was to discuss FPC plans to modify the emergency feedwater system and the high pressure injection system to resolve previously identified design issues related to diesel generator loading and operator burden as a result of required manual actions for a small break l
loss of coolant accident. The presentation included tentative schedules for the submittal of necessary license amendment requests and the date by which approval of these amendments would be needed. Enclosure 1 is an attendance list for the meeting. Enclosure 2 includes copies of the meeting handouts.
l The NRC staff indicated that the information presented by FPC at the meeting, as described in the enclosed handouts, was very useful in understanding the scope, schedule and potential impact on NRC resources of the projects. The NRC representatives indicated that is would be I
useful to include a discussion of risk reduction and risk insights in the license submittals. They also stated that a description of post modification testing should be included in the submittals.
The NRC staff stressed the need for timely submittal of the license amendment requests to provide adequate time for review and processing. The meeting was adjourned after a brief question-and answer session.
ll l
Leonard A. Wien, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/II t
Office of Nuclear Reactor Regulation i
Docket No. 50-302 l
j
Enclosures:
- 1. Attendance List L
- 2. Handouts cc w/ enclosures: See next page L
l i
t
l' a
l l
L
- Florida Power Corporation CRYSTAL RIVER UNIT NO. 3 GENERATING PLANT -
cc:
Mr. John Paul Cowan, Vice President Chairman j
Nuclear Operations (SA2A)
Board of County Commissioners i
ATTN: Manager Nuclear Licensing Citrus County I
Florida Power Corporation 110 North Apopka Avenue r
Crystal River Energy Complex invemess, Florida 34450-4245
.15760 W. Power Line Street i
' Crystal River, Florida 34428-6708 Mr. Robert E. Grazio, Director Nuclear Regulatory Affairs (SA2A)
Mr, R. Alexander Glenn Florida Power Corporation Corporate Counsel Crystal River Energy Complex Florida Power Corporation 15760 W. Power Line Street MAC-ASA Crystal River, Florida 34428-6708 P.O. Box 14042 St. Petersburg, Florida 33733-4042 Senior Resident inspector Crystal River Unit 3 Mr. Charles G. Pardee, Director U.S. Nuclear Regulatory Commission Nuclear Plant Operations (NA2C) 6745 N. Tallahasrae Road Florida Power Corporation Crystal River, Fionda 34428 Crystal River Energy Complex 15760 W. Power Line Street
'Mr. Gregory H. Halnon Crystal River, Florida 34428-6708
_ Director, Quality Programs (SA2C)
Florida Power Corporation Mr. Robert B. Borsum Crystal River Energy Complex Framatome Technologies Inc.
15760 W. Power Line Street 1700 Rockville Pike, Suite 525 -
Crystal River, Florida 34428-6708 Rockville, Maryland 20852 Regional Administrator, Regica il Mr. William A. Passetti, Chief U.S. Nuclear Regulatory Commission Debrtment of Health 61 Forsyth' Street, SW., Suite 23T85
- Bareau of Radiation Control Atlanta, GA 30303-3415 2020 Capital Circle, SE, Bin #C21
- Tctlahassee, Florida 32399-1741 Mr. Leonard D. Wert U.S. Nuclear. Regulatory Commission Attomey General-61 Forsyth Street, SW., Suite 23T85 Department of Legal Affairs Atlanta, GA 30303-3415 The Capitol
- Tallahassee, Florida 32304 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 i
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ATTENDEES SEPTEMBER 21.1998 MEETING l
i CRYSTAL RIVER l
HIGH PRESSURE INJECTION AND EMERGENCY FEEDWATER l
Name Affiliation Scot Greenlee FPC Craig Miller FPC Tim Stack FPC/Framatome Technologies l
Sherry Bemhoft FPC Cecil T. Gurganus FPC l
Paul V Fleming FPC Eric Weiss NRC/SRXB S.N.Saba NRC/EELB Jim Tatum NRC/SPLB -
Bill LeFave NRG/SPLB John Knox NRC/EELB l
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Presentation to the
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Nuclear Regulatory Commission Diesel Driven Emergency Feedwater Pump and l
HPI Upgrade Projects l
September 21,1998
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> Introduction - Scot Greenlee
> Diesel Driven Emergency Feedwater Pump j
> System Operation - Paul Fleming
> Project Details - Craig Miller
> HPI Upgrade Project
> System Operation - Paul Fleming
> Project Details - Craig Miller i
> Conclusion - Scot Greenlee
> Questions and Answers - Open Format j
09/21/98 2
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DieselDriven Emergency Feedwater Pump gh and
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m Introduction
> Purpose
> Scope and Schedule for Projects
> NRC Resource impacts
> Background
> Design Outage issues
> FPC Commitments
> Modification Overview j
> EFW System Upgrade
> HPI System Upgrade I
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> License Amendment No.163 t
> SBLOCA
> Spectrum Requiring Use of OTSG Cooling / Emergency Feedwater
> Operator Actions Required to Mitigate Design Basis Accidents j
> EDG Load Management.
> EFW Configuration Management i
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> EFP-1 Starts
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Nkk DieselDriven Emergency Feedwater Pump l
V N
m Design Alternatives l
> Detailed Study
> Replace or Upgrade Both EDGs
> Replace Single EDG
> Add Third EDG l
> Add Diesel Driven EFP
> Third Party Evaluation i
j i
1 1
09/2188 14
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j wm u Design Features
> New Safety Related Emergency Feedwater Pump (EFP-3)
> New Safety Related Diesel Engine
> Independent Class 1 Building i
i
> Fuel Oi! Supply Allows 7 Day Operation Plus Testmg j
> All Required Indication and Control Power for Diesel i
Provided by Dedicated Class 1E Batteries Located in New Building
> AC-independent Design Enhances SBO Coping Strategy
> Applicable Codes and Standards Building - NUREG 0800. Standard Review Plan Equipment - Current Approved Codes and Standards (e.g., B31.1,1967) i o,mm is 1
l
9 DieselDriven Emergency Feedwater Pump MP
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a Design Features (continued)
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> Pump Location Allows Suction from All Water Sources '
Except Condenser Hotwell.. Administratively Controlled Inventory Exceeds the Requirement for Natural Circulation Cooldown j
> EFP-1, EFP-2, FWP-7 can Transfer Water from the j
Hotwell to the Emergency Feedwater Tank / Condensate j
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DieselDriven Emergency Feedwater Pump YP m -- m _ ___ m ^ c ~. a Design Features (continued) > Disposition of EFP-1 > Actuation Logic will be Transferred from EFP-1 to EFP-3 Logic Prevents Concurrent Operation of EFP-3 and EFP-1 > EFP-1 will be Capable of Being Manually Selected > EFP-1 can be Loaded on the "A" Diesel Generator When Capacity Allows EFP 1 will be Credited for Post-Seismic Cooldown > Remove Auto-Open Signal from ASV-204 emm is
.n i . t N$ DieselDriven Emergency Feedwater Pump N _M ._m = u Industry Experience > Diesel Driven Safety Related Emergency / Auxiliary Feedwater Pumps l t > Byron Units 1 and 2 t i > Braidwood Units 1 and 2 > Fort Calhoun > Other Diesel Driven Safety Related Pumps { > Byron Units 1 and 2 (Emergency Service. Water) i l > Braidwood Units 1 and 2 (Emergency Service Water) j > Surry Unit 1 (Emergency Service Water) l l > Prairie Island Units 1 and 2 (Nuclear Service Water? 99/21/98 39 l )
n i W$ Diesel Driven Emergency Feedwater Pump \\ l l l m j i n Overall Safety Benefits l l > Multiple, Diverse Emergency Feedwater Pumps l > EFP-2 is Steam Driven Technical Specification l Required Pump > EFP-3 is Diesel Driven Technical Specification Required Pump I > EFP-1 is Motor Driven Safety Grade Manual Pump p l > FWP-7 is Defense-in-Depth > Reduce EDG Load Management in EOPs { > Reduce "A" EDG Auto-Connected Load l \\ l l 3 o,mm 3,
t $k DieselDriven Emergency Feedwater Pump i WP r = g-- m ~ I a Overall Safety Benefits (continued) t > Operator Actions Eliminated i > Need to Cross-Tie EFP-2 to "A" Train (EFV-12) - [OA9]i > Need to Place SWP-1A and RWP-2A in Pull-to-Lock and EFP-1 in Trip Defeat -[OA11]1 > Need to Place EFP-1 in Trip Defeat Prior to LPl/EFP-1 interlock (500 psig)-[OA15]1 > Need to Manage Overfill Protection on Loss of"B" i Battery 1 Operator Actions were Identified in the NRC Safety Evaluation Report for License Amendment No.163. wmm n i
{ = i L s . i l $$b DieselDriven Emergency Feedwater Pump MP l mus - a Required Technical Specification Revisions > Removal of License Amendment No.163 Cycle 11 l Specific Limitations > Removal of Technical Specifications for EFP-1 j > New Technical Specifications for New Equipment i i i l I i i l 09/2138 22 i
r 1 i 1 s 4 t 8 $. Diesel Driven Emergency Feedwater Pump $$5 i j 1 w -. 1 g-- m. l ~ i a Project Schedule t 1998 1999 l J F M A M J J A S O N D J F M A M J J A S O N D l Design l l l mml l l l l l ; ; ; l Design Review Board I I I I I al l l i I I I l l I l I i l l I I i l I I I I I I I I I I I I I I I I I I I I l l Design Review Board
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j Licensing Submittal i I I I I I I I I IW I I I i l l l l l l l t I lI l l, l l, lum I I I I I Construction aun num a '30Ps Revised l l l l l l [ l pumuuspeusl l l l l l l l l l l j Simulator Modified I I I I I I I I I A I l l I I I I I I I I ] I l 1 i i l I I I I I I I I I I I I I I l l EOP Validation l ; l l l l l j ; ; i ampumuspi ; ; ; ; ; ; ; l EOP Training (First Cycle) I i l i i l i l I i i i l i I humiin i I I l l I I J Requested NRC Review & Approval nummmmmmummmmmmmmmma , y ; EOP Training (Second Cycle) l I I I I I I I I I i l i i I I I semml l I I I I I I I I I I I I I I I I I I I I I LI I outage 11R Degins I I I I I I I I I I I I I I I I I I I i 1 I l i g /21/98 G9 1 23 i
.. m s-e s m i ,s R-$ HPIl& grade Project l l 1 7 mumm-w: = u HPI Configurations and Operation l I > License Amendment No.163 j i i > SBLOCA l > Spectrum that Requires l OTSG Cooling / Emergency Feedwater > Operator Actions Required to Mitigate Accident > Elevated Peak Clad Temperature (PCT) for Cold Leg Pump Discharge (CLPD) Break l l l l I i i 1 09/21/98 24 j i 4
s s* % ~ f4 '- M-t t M$1 HPIl& grade Project l WP M-M l l l m Operator Actions > Trip RCPs j > Ensure all 4 HPI Valves Open > Includes Power Transfer > lsolate Normal Makeup i t > Includes Power Transfer j > lsolate Broken HPI Line i > Initial Evaluation > Monitor HPI Flow > Subsequent Evaluation if OTSG Heat Transfer Upset i > lsolate RCP Sealiniection > Raise OTSG Level to 95% i o, nim 25
^ rs r, W g RCS Cold Leg A g q_q Y a N -7< A i 24f N r RCS Cold Leg x_ c_ Nonnd i y; j)y x
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s ~ T RCS Cold Leg iT \\ 25g q_q \\ .. k "a.na Mkb 26 ,Nggj!f![k [ 58 _y p RCS Cold Leg \\ p _ fCurrent HPI Confinurationi w = ES Standby / Normal Operation x-x - m-26 e
y m M r, RCS Cold Leg - -N s N ~f A 24 r ~~ l RCS Cold Leg v: N B l b T X. 3.,y. 25 ^: \\ \\ >N C 26 58 / RCS Cold Leg 77 l~ Current HPI Configuration 7 - N 4 Post Actuation =- y N 27 09/11/98
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~ l RCS Cold Leg s x ~ r m RCS Cold Leg ~ u*ur B N-W $ $ 'e ~ S o XA T 9 RCS Cold Leg xK z e j k N% / RCS Cold Leg JE Curreht HPl C6nfiaurationi [ ~ LOBA; \\ \\
m A ~ = m RCS Cold Leg g 73 -R N A I Q -N ( X-X-\\-\\ j r RCS Cold Leg L-L2 gg, N -X k_ B T T 1 dg$ggtjg _y W 1{yg~g S _y cq T ,,, g }j 7 RCS Cold Leg ( N t s M i g y ~ ~ ~ _y p RCS Cold Leg 4 5 New NPI C$nfEbur$ tion ' E a Standby - 29
..l -7 RCS Cold Leg g --l_ [ -- 73 7< (-) A l A 'r ~~ ~ l RCS Cold Leg umkeup B-N i 3 r w r w W s S '3 'B' _ q/? g 'Y [)g T s. RCS Cold Leg p Zr L _X ( y_X_N_% \\ ?' (3< C B v' x x-x-N-N a RCS Cold Leg K '~ ~ - -I L# MeWMPI CSn6 duration 1 ~ m. y ~ Post Actuation - - 7 30
.~ ew RCS Cold Leg }p A-I N -V< _K wc m; \\ ( g-- N e 3 a RCS Cold Leg M v a B i x -K g I n m W .ggN$y 7 7 S k 0-37, gpy [ R@ s nn,ason RCS Cold Leg g [ !( w h C 1 B I / N RCS Cold Leg 3/g i New HPI Configuration \\
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~ e... 1 I N$ HPI Upgrade Project 4 05 t i-- M m l m Design Alternatwes I > Detailed Evaluation of Alternatives a Design Features l > Cross-tie Lines Between HPl Lines to Ensure Flow in All Four l Injection Lines > lsolation Valves in Cross-tie Lines to Limit Thermal Fatigue Cycles > Throttle Valves Downstream of Cross-ties to Balance injection Line Flow and Limit Flow During a Postulated HPl Line Break > Auto-Isolation of Normal Makeup and Seal Injection Flow > Increased ES Actuation Setpoint > Currently 1500 psig (nominal) > Will be ~1600 psig > Other Setpoints (RCS Trip and Bypass, ES Bypass) Adjusted Accordingly \\ ~ emm n 1
r ^ .M... 1 HPI Upgrade Project = 1 m i i l m Required Technical Specification Revisions ~ > Add Surveillance Requirements for New Configuration ' > Revise Reactor Protection System and Engineered Safeguards Setpoints I I t I i i I l l i 09/2188 33 ' t i i
~ ~ - ?"* s p 1 N$d HPI Upgrade Project $9 l m Overall Safety Benefits l > Reduced PCT (RELAP5) ~ 3 > Reduced Operator Actions Eliminate Need to Open All 4 HPI Valves [OA3]1 Eliminate Need to isolate RCP Seal Injection [OA4]1 l Eliminate Need to isolate Normal Makeup i Eliminate Need to isolate Broken HPl Line [OA5]1 Eliminate Need to Periodically Evaluate HPl Line Break Criteria on Repressurization [OA17]1 1 i 1 Operator Actions were Identihd in the NRC Safety Evaluation Report for License Amendment No.163. 1 i 09 mas u
r..., t $D HPI Upgrade Project 4$5 1m m Overall Safety Benefits (continued) > Brings CR-3 in Line with Other B&W Plants t Peak Clad Temperature (PCT;i j Setpoints l 3 Design ? l I I i i l l 09at/9s 35 l I i
$ $a HPI Upgrade Project j m Project Schedule t i 1998 1999 j J F M A M J J A S O N D J F M A M J J A S O N D l Design i I i mimmum i i i l l l 1 l l I I f - I I I I I I I I I I Design Review Board Licensing Submittal l l l l l l l l l lq l l l l l l l l l l l Construction l I I I I I I I l iI I I I I Ml I I I I I I I I I I I I I I I I I I I I I I I E0Ps Revised l ; ; ; ; ; g ya; ; g g ; ; ; j Simulator Modified i I I I i l i l I luma'umu i i l l I I I I I i ! I I I I I I ll I I E0P Validation mssummer EOP Training (First Cycle) l I I i l l l l l l l l l l l pimps I l 1 l l I I I I I I I I I I E I I I I I Requested NRC Review & Approval I i i i l I i l i I I I I I I I I I I I I I E0P Training (Second Cycle) [ [ l [ [ l l l l l l l l l l l l meml l [ l Outage llR Degins l I l l I I I I I I I I I I I I I I I la l I ! I t I if I I i 1 l l 1 I i l i i i ! i 1 09/2138 36
Diesel Driven Emergency Feedwater Pump
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4gs HPI Lpgrade Projects j ~ e i s Conclusion > Net Safety Benefits ~ i >. Reduces Operator Burden in EOPs > Reduces Worst Case SBLOCA PCT e > Increases EFW Redundancy / Diversity i > Eliminates EDG Load Management Requirements l > Eliminates EFW Cross-train Relationships j > Meets NRC Commitments j > Schedule Considerations s I i 09/21/98 37 1 .}}