ML20148U441

Summary of 970624 Meeting W/Util in Rockville,Md Re Proposed License Amend Relating to High Pressure Injection,Emergency Feedwater & Emergency Diesel Generator Sys.List of Attendees & Handouts Encl

ML20148U441
Person / Time
Site:	Crystal River
Issue date:	07/07/1997
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9707100179
Download: ML20148U441 (46)

Text

- _ - _ ._ - . - .. - _ _ _ . _ _ .

I g$  % UNITED STATES

, jo

,j

'f NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066Hoo1 1

..... Ouly b 1997 I I

LICENSEE: Florida Power Corporation  !

l FACILITY: Crystal River Unit 3

SUMMARY

OF MEETING ON JUNE 24, 1997, REGARDING PROPOSED LICENSE I AMENDMENT RELATING TO HIGH PRESSURE INJECTION, EMERGENCY FEEDWATER {

AND EMERGENCY DIESEL GENERATOR SYSTEMS On June 24, 1997, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3 (CR3) met with mer.bers of the staff at i the U.S. Nuclear Regulatory Commission (NRC)-Headquarters in Rockville, -- - i Maryland. The licensee presented an overview of its June 14, 1997 license amendment request relating to the CR3's potential success path for emergency feedwater (EFW) flow and emergency diesel generator (EDG) loading concerns during a small break loss of coolant accident (SBLOCA) design basis scenario.

Enclosure 1 is a list of attendees. Enclosure 2 contains copies of handouts l

distributed at the meeting.

The licensee discussed the design basis accident scenario affecting the EFW and EDG operation, SBLOCA, loss of offsite power (LOOP) and three limiting single failures and potential success paths. The licensee presented details ,

of plant modifications, design reanalyses, and technical specification changes I that would be necessary to meet its established success path. The licensee indicated that the EDG calculations for determining the maximum expected accident loads, design of plant modifications, and emergency and other operating procedure changes are currently in progress.

The NRC staff expressed concern regarding its review of the proposed license  !

amendment with pending supporting details and its impact on staff resources especially considering the licensee's request for an expedited review of the amendment by November 1997. The licensee indicated that it recognizes the staff concern and stated that based on its detailed conceptual knowledge and thorough review by safety review committees and other in-house organizations, it is confident that its current ongoing efforts would not involve any unreviewed safety questions and would not adversely affect its June 14, 1997 '

license amendment request. The licensee stated that it will complete these ongoing efforts, and provide necessary details to the staff well before November 1997.

[f The NRC staff specifically requested the licensee to submit its proposed emergency and other operating procedure changes as soon as possible, and the i i final version by September 1997. The staff briefly discussed the Institute 1 of Electrical and Electronics Engineers (IEEE) Standards, and other industry and regulatory guidelines relating to EDG modifications, design and requalification considerations including the rationale for establishing the predicted accident loads. The staff requested the licensee to provide details 9707100179 970707 PDR ADOCK 05000302 e "a

"""'" NRC. RLE CENTER COPY '

1111lIllli!1IIBl!Illill

to demonstrate meeting these industry and regulatory guidelines. The licensee agreed to provide the requested information.

F yu . . I' Y 7.d L. Raghavan, P ject Manager

' Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

I. Attendance List

2. Meeting Handout

~ ~~ ~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ " ^ ' - ~ " " '

Ec w/EnclosuresI See next page

t to demonstrate meeting these industry and regulatory guidelines. The licensee L agreed to provide the requested information. .

Original signed by Frederick J. Hebdon for  :

L. Raghavan, Project Manager '

Project Directorate 11-3 i Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302 l

Enclosures:

1. Attendance List  !

2. Meeting Handout ,

3

e t

4 1

i

i DOCUMENT NAME: G:\ CRYSTAL \970624. SUM To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy

, 0FFICE PDII-3/PM l PDII-3/LA , w

~

PDII-3/D ,) c NAME LRaghavan BClayton Af W FHebdon M-

,l DATE 07/ /97 07/ d /97 07/ 7 /97

' 0FFICIAL RECORD COPY

- - . . ~ ~ . - - -

1

)

Florida Power Corporation CRYSTAL RIVER UNIT NO. 3  !

GENERATING PLANT i i

cc: i Mr. R. Alexander Glenn Senior Resident Inspector l Corporate Counsel Crystal River Unit 3  :

Florida Power Corporation U.S. Nuclear Regulatory Commission MAC-A5A 6745 N. Tallahassee Road P.O. Box 14042 Crystal River, Florida 34428 l St. Petersburg, Florida 33733-4042 l Mr. James S. Baumstark  !

Mr. Bruce J. Hickle, Director Director, Quality Programs (SA2C) ,

Nuclear Plant Operations (NA20) Florida Power Corporation. l Florida Power Corporation Crystal River Energy Complex  ;

Crystal River Energy Complex 15760 W. Power Line Street I

- 15760-W. ~ Power Line- Street- - Crystal River, Florida 34428-6708- ~ ~l Crystal River, Florida 34428-6708 . . .

._ j Regional Administrator, Region 11 Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission B&W Nuclear Technologies 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 1 Tallahassee, Florida 32304 Florida Power Corporation ATTN: Manager, 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 1 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 Mr. Robert E. Grazio, Director i Nuclear Regulatory Affairs (SA2A) '

Florida Power Corporation Crystal River Energy Complex .

15760 W. Power Line Street Crystal River, Florida 34428-6708 l

J

. -.= . - _ .. - - _ _ . . - . . .

l'

SUMMARY

OF MEETING ON JUNE 24, 1997, REGARDING PROPOSED LICENSE AMENDMENT RELATING TO HIGH PRESSURE INJECTION, EMERGENCY FEEDWATER AND EMERGENCY DIESEL GENERATOR SYSTEMS 1

Distribution:

HARD COPY w/ Enclosures 1 and 2

'~

. Docket File.

PUBLIC L. Raghavan Crystal River Reading OGC ACRS-

' E-Mail w/ Enclosure 1 i S. Collins /F. Miraglia (SJC1,FJM) __

J ^ -

~~ ~~-~

R. Zimmerman (RPZ)

' J. Zwolinski (A)(JAZ)(2) -.

F. Hebdon (FJH) i B. Clayton (BAC2)

D. Ross (SAM)

J. Jaudon (JPJ)

H. Cristensen (H0C)

W. Rogers (WGRI)

F. Orr (FR0) l G. Hubbard (GTH) l W. LeFave (WTL1) ,

M. Pratt (MPP)  !

S. Sanchez (SPS)

D. Thatcher (DFT)

S. Saba (SNSI)

C. Liang (CYL)

G. Tracy (GMT)

S. Cahill (SJC2)

J. Johnson (JRJ)

J. Bongarra (JXB) i S.V. Athavale (EVA1) I 1

I

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

(

CRYSTAL RIVER 3 MEETING JUNE 24. 1997 Hamt Oraanization L

L. Raghavan NRR K. Landis NRC-RII i

John P. Jaudon NRC-RII l F. J. Hebdon NRC-PDII-3 i H. Cristensen NRC-RII i

! Frank Orr NRC/SRXB Bill LeFave NRR/DSSA/SPLB 1 Paul V. Fleming Florida Power Corp. '

John J. Holden Florida Power Corp.

Mark Pratt NRC/EELB ,

Dale Thatcher "

NRC/NRR\EELB Saba Saba ~

~' ~

~

NRC/NRR/EELB Mark Van Sicklen -

Florida Power Corp. -

Chu Liang NRR/SRXB S.V. Athavale NRR/HICB J. Bongarra NRR/HHFB S. Katradis NUS Information Services M. Lalon Florida Power Corp.

R. D. deMontfort Florida Power Corp ,

D. Kunsemiller Florida Power Corp.

G. Hubbard NRR/SPLB

-a h

t i

i i

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

l .

i

,n i

! JD!s5h

'-- --. . ._ _i s' .

l i

..3'.18

"'2 A SOLUTION SET -

FLOW PATH S

-+ LOB A -+

COPE)m0NS Loss of "A" Battery U i C

RX TRIP ODE l --> SBLOCA + & -> FAI URES LOOP Lossor s sattery E

l S

% EFP-2 --> i S '

l -

i i

1 6/24/97

. .O 24 AGENDA e ..

• Introduction - Dave Kunsemiller

• Modifications - John Holden

• S.BLOCA Solution Sets - Mark Van Sicklen

• ITS Submittal - Paul Fleming

• Operations Perspective - Dave de Montfort

• Engineering Summary - John Holden 4

• Conclusions - Dave Kunsemiller i t

Purpose of ITS Submittal f  :

.l License CR-3 for Startup and Operation during Cycle 11 with:

> Cross Train Dependencies

> EDG Load Management

> Mitigation Strategies Involving Operator Actions i

I t

t

._4

1. 4 q) Contents of Submittal i a

• Cover Letter

• Safety Assessment

• ITS Changes

• Framatome Analysis

• Supporting Information

! > Operator Actions -

3

> Mods / FSAR Changes

> USQ Resolution l

1 l

Dj MODIFICATIONS EFW / FWP-7 Mods i

i

> EFW Cavitating Venturis l

> Diesel Power Supply for FWP-7

> EFV-12 Motor Operator ,

=

7

_ g ,

24 MODIFICATIONS EDG Load Capability

> Load Capacity Increase  ;

Engine Modifications (150 kW) kW Meters

> Load Management P-T-L Control Handles EFP-1 Trip Defeat Switch

> Load Removal / Reduction

.q f

249 Diesel Generator Load ,

a  :

Sept '96 June '97 Old EDG Ratinas _

New EDG Ratinas _

30 Min 3500 kW 30 Min 3500 kW 200 Hr 3250 kW 200 Hr 3400 kW 2000 Hr 3000 kW 2000 Hr 3200 kW Contin. 2850 kW Contin. 2850 kW Auto . Connect Load Auto Connect Load 1 ';. QO 9. ... w.

s.g s Ff.5 ; c. s .a,/

.a\

I . .

24 STARTUP TEAM 9

l

• First Team Identified EDG Margin Concerns

> On December 18d' Recommended 3 Options

• Second Team Identified Concerns with Startup

> Complexity of TS Changes

> Cross-Train Dependencies

> Importance of EFW for SBLOCA

> Impact of 3 Limiting Single Failures t

l

_ - - _ _ - - _ - - _ - - - _ _ - _ -_ _ _ ___. -_]

I 24 LIMITING ACCIDENTS i

~ s l THE TEAM REVIEWED FSAR CHAPTER 14 ACCIDENTS.

THE LIMITING TRANSIENTS AFFECTING THE EMERGENCY DIESEL GENERATOR LOADING AND EMERGENCY FEEDWATER WERE IDENTIFIED AS:

i SBLOCA & LOOP AND LIMITING SINGLE FAILURES

o 25 LIMITING SINGLE FAILURES LOBA or LOBB - Loss of a Battery

' i

> Disables ONE Emergency Diesel Generator

> Disables ONE Train of Emergency Core Cooling

> Disables ONE Train of DC Control Power EFP-2 The Motor Driven Emergency Feedwater Pump (EFP-1) is designed to be load shed (during the accident) to protect the ' A'  !'

Emergency Diesel Generator from an overload condition

1

,at 2n

, LOCA SIZES

. _ _ , _ , _ _ _ _ . . , _ _ _ _ _ - - . . . . . - - ' - - ' ' - - - - ' - - - - - - - ^ ^ ' '

36" Inside Diameter (7.07 ft2)

LBLOCA DOES NOT REQUIRE HPI

\

DOES NOT REQUIRE EFW 9.6" inside Diameter (0.5 ft2) l' SBLOCA HPIIS REQUIRED

• DOES NOT REQUIRE EFW

<1" Inside Diameter % 3

(.015 ft2) l With 2 HPl Pumps 's LMIE TIME 2.7" inside Diameter (0.04 ft2) i With 1 HPI Pump EFW IS REQUIRED t

l O,

g I

RCS PRESSURE TRACE

' i t

i i

RCS PRESSURE RESPONSE TO A SMALL BREAK LOC A 3000 l t

2500 -- .- .

'. i

.- '. l 2000.. ,

i m *

$ ,e '.'

M = ,

0. ,-

W .- ~

g 1500. - '.'

D }

m ,

i 50 W I E

1000-,

500 --

I 0

TIM E I

Startup Team Solution Set

• Address Each Single Failure Scenario Separately

• Identify Design Basis Success Path

• Identify Challenges l

• Identify Defense In Depth

• Identify Needs ,

> Modifications

> Procedures

> Licensing Actions

> Training t

I4 Startup Team Solution Set

'^  ;

r ,

LIMITING SINGLE FAILURES

LOBA -

Loss of "A" Battery INITIAL CONDITIONS

, , r , r , r ,

MODE

+ SBLOCA + & +

I F 1 UR S LOOP Loss of "B" Battery

, 2 < > < > '

E

= .2 =

S S

e a

. .D I4 LOSS OF BATTERY "A" 49 I"

MUP-1B or MUP-1C UMP S

U MfTIGATION STRATEGY LOBA + '

FRAMATOME 1 HPI PUMP g  : EFP-2  :

EFW , 6

ADMIN -> AND +

EFW FLOW '

ANALYSIS < >

C u

EFW ' E FLOW S

r , FWP-7 ' DEFENSE IN DEPTH

--+ FWP-7 -+ DIESEL w ' M@ ,

• S SUCCESS PATH v CHALLENGES DEFENSE IN DEPTH

_ _ _ _ _ _ _..oj i,

24 FWP-7 e

e INCREASE DEFENSE-IN-DEPTH e MAXIMIZE FWP-7 INDEPENDENCE e MINIMIZE OPERATOR BURDEN

i D:

^

g l

'A' 6900 VOLT BUS i -m uLL JJJJ rTTrTrn 4160 RX AUX BUS --

(( (SPARE) (( (SPARE)

T T . .... . ...... .... .. . ........ .......... .....  :

taaa t a a a i 4160/480 f CH LLER t r t r I

r v t v i Transformer f

I[ NEW I DIESEL POWER t

i  : Dist.  :

t  : Panel

I  :

26 hp Air Compressor -

i .

24 vdc Power Supply Control {

4 I Power -

FWP-7 Control Valve Power j i

{

!  : - - - Isoiation MOVs t... .......... .. ............. ............. ......

f

_ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ - _ _ _ __ ___J

i

.D- ,

d 2^/ *mb LOSS OF BATTERY "B" "D ~

PUM  :( MUP-1 A or MUP-1B ) -

u m INSUFFICIENT OPERATIONAL

-> EFP-1y EDG ->

UMITATION

~~~~~'

I CAPACITY

.. ............. i S '

- CONTROL COMPLEX

• Ig ho COOUNG [-1.0 hr)

P gg MITIGATION * . g WE DEPENDENCY -EIEE ,  %#

STRATEGY .....a I o LOBB., - 500 PSIG 1 HPI PUMP '

(Operator CooMown) .

I a a  ;

. . . . . . . . . . . . . . . i 1 8

C EFW FLOW ,

I o l N .

i FRAMATOME '

i C

E - + EFP-2 -> CROSSTIE EFW TRAINS -* EFW --+ ADMIN + AND +

FLOW l

' > W ANALYSIS ,

' > E S

S

, , FWP-7 DEFENSE IN DEPTH

- -

• FWP-7  : DIESEL SUCCESS PATH ' '

MOD CHALLENGES v I

DEFENSE IN DEPTH

, - D 24 LOSS OF EFP-2 M

2HPl . HPI FLOW PUMPS ANALYSIS a

MfTIGATION u

STRATEGY FRAMATOME TIME EFP-2-+ 2 HPl PUMPS * -

C ANALYSIS EFW FLOW  ;

OPERATIONAL LOAD EFP-1 TRIP F- m C

-+ + LIMITATION MANAGEMENT +

EFP-1 "* DEFEAT --* AND + ADMIN ->

' SWi1CH '  ;  ;

, , w , , < ,

EFW -

- smac== L.Oo E -

FLOW -- BWsT DEPLETION L MOD (PTL)

- 500 Psig (Operator Cooldown)

S

' ' I DEFENSE IN DEPTH  !

-> FWP-7 --> DIESEL

' " MOD SUCCESS PATH < ,

CHALLENGES l DEFENSE IN DEPTH v  :

i  :

-,- , , g:l 1

r ADMINISTRATIVE ITEMS 4*4 i

4 LIMITING SINGLE FAILURES o

, , O l t

l U

LOBA  :

ADMIN  :

C Loss of "A" Battery i

LOBB  : SAFETY C

ASSESSMENT i Loss of "B" Battery i  : EOPIAP REVISIONS i EFP-2  : ITS SUBMITTAL S

FSARIEDBD REVISIONS < >

i I

.o 249 SAFETY ASSESSMENT

• Describes the Success path for each SBLOCA Scenario

> Includes Defense-In-Depth

• Addresses Associated Modifications

• Addresses Operator Actions

• Focus on Safety Significance and Plant Operations

] .

Dj 249 SAFETY ASSESSMENT i

Conclusion:

• These SBLOCAs can be mitigated using a combination of Plant Modifications and 4

l Operator Actions.

• Provides Defense In Depth-r

,..Ol Framatome Analysis Resolves Solution Set Challenges

• EFW Requirements (OTSG Cooling)

> Mission Time

> EFP-2 Operation

• HPI Line Break Isolation Criterion

> 1 and 2 HPI Pump Operation

O' 1 1 .

@gh Framatome Analysis 1

Conclusion:

• Current SBLOCA Analysis Remains Bounding

• Specific SBLOCA Analyses Demonstrate the I

Core Remains Covered at all Times t l

• Validates the SBLOCA Solution Sets

. .E 28.gs OPERATOR ACTIONS

~ ~

• Actions < 2 Mintites

> Trip RCPs

• Actions < 10 Minutes

> Initiate HPI All 4 HPI lines (Transfer Power)

> Initiate Reactor Building Isolation &

Cooling Actuation

,.g!

4

[,

1. 5 sOPERATOR ACTIONS

• Actions < 20 Minutes

> Isolate RCP SealInjection l

> Isolate Normal Makeup

> Isolate Broken HPI Line

> Ensure EFW Flow l

ga

_m NEW OPERATOR ACTIONS d

@ (> 20 Minutes) l

• Cross-tie EFW (LOBB)

> EFP-2 through 'A' train flow path

> Secure EFP-1

• Periodic HPI Line Monitoring

• Manage EFP-2 Operation

!

• EDG-1 A Load Management

> SWP-1 A & RWP-2A in PTL

> Defeat EFP-1 Trip

..sl 25% EOP / AP REVISIONS t

• Will incorporate required actions from Solution Sets in appropriate procedures.

i

• Will be Verified and Validated including Plant Walkdowns, Table Top Discussions and Simulator Scenarios. i l

!! f

Il!l!ll!l ll

!!!:ll B

. n 2 i o

t 1

u s e l o

e l

c s e

y g c r o

n t m

r a i r

o t e

g h r p n o

C n w d l

o a t S d r t e

a e

u E

ht i p d c s S

i _

e Y w i t

n g A e -

n L b a a N

s B Ot o

t e

g h

c n

s n e -

/ 1 e e a s l g s b n h S

1 n

a a c e i s

e h s T

I l

c C y

mo r N s

a e P s

o _

e > >

C > P R f.4

. .D ITS Change Package Package Segregated into

• Part 1 - SBLOCA Mitigation

• Part 2- EDG Upgrade

• Part 3 - EDG Load Rejection and Steady State Loads

t 25 SBLOCA Mitigation I System Cross Train Dependencies

~

Column A Column B Train "B": . EFP-2 (ASV-204)

. EDG . Cross tie ability (EFV-12, EFV-13)

. AC Electrical i Power Subsystem

. AC Vital Bus

Subsystem EFP-2 . Both Trains of  ;

HPl(ECCS)

EDGs Decay Heat Seawater DC AC ElectricalPower DistrSubsys AC Vital Bus Subsystem

. SWP-1B  !

. Train "B" of Nuclear Services Seawater

. CHHE-1B and CHP-1B of Control Complex Cooling t

i

' f

y;a Configuration Document

1. Integration Program

• Project input information from:

i > SRR, PCs, prs, Docket Review, Independent FSAR Review, Mods, Analysis

• Consolidate information into specific plant

, System Information Sets

• Resolve open items

• Update the plant documents

> FSAR, EDED, ITS Bases, ABD

i

%f Operations Perspective

• Operations Involvement i

> Startup Team

> EOP Team

> Independent Reviews

> Validation Team Review

• SRO Validation ,

> End User Review (SSOD)

• PRC Review and Approval

• NGRC Review and Approval

i _____..D .

y=;;a Operations Perspect.ive 9

Continuing Operations Involvement

• EOP Verification and Validation

• Operator Training i

> SBLOCA Solution Sets

> Safety Assessment i

> ITS Changes

> EOP Training i

• Operational Readiness Assessment

. . .y t

==3CA --

• ?d5 Conclusion

• It is a Safe Solution for Restart of the Plant

• Reasonable Engineering Approach to Address Issue on Interim Basis

• We will continue to have Technical Meetings with the NRC

• Supports December Restart

_ _ _ _ - _ _ _ - _ _ _ _ _ _ - _ _ - _ _ _l

)

I4 Outstanding Actions e

• Prior to Approval

> Calculations EDG Loads (confirmation)

EFW Block Valve Cycling Control Complex Cooling i

> Modifications i 50.59s approved  !

> Procedures

! 50.59s approved i l

' '- ,.Oi

1. 7 4 Outstanding Actions

• Prior to Restart

> FSAR Updated

! > FWP-7 Availability and Reliability

> EDG Load Testing and Calculations

> Modifications

> Procedures

, , D

%f Outstanding Actions l

i

• Prior to Cycle 12

> EDG Long Term Resolution

> Remove interim ITS Changes i

__________._..________..____._______________________.______~!

l

24e HPI -

LPI COMPOSITE DHP-1A

• -e MUP-1A a I

~I ST Mu MUP-1B b h MUP-1C DHP-1B h  !

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

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

1

)

25 EFW - AUX FEEDWATER e ..

~

OTSG l Stoem Supply .

~

ASV-204 ASV-6 A$ Steam Driven h

i EFP-2 EFV-12 sr L, ~ m Non-Safety FWP-7 X

u b j Motor Driven Joa--

EFP-1 .

t

.---.--.-_w___ _ . - - - - . _ - _ - . _ - - - - - - - _ - - - - - - _ . . _ _ _ . - _ _ _ . - - - . . - _ - _ - - - . . . . _ . - _ - . _ . - . - _ - - - _ . - - - --. ---