Palo Verde Steam Generator Replacement

And Power Uprate Project

Presentation To The

Nuclear Regulatory Commission

February 21, 2001

Palo Verde Steam Generator Replacement And Power Uprate Project

Project Update

Carl Churchman SGR Project Director

v ý. I y

Agenda

Introduction Project status

Licensing activities

Safety analyses

Risk evaluation

CR habitability Modifications

Weld issues

Future activities

Carl Churchman

Carl Churchman

Dick Bernier

Paul Clifford

Gerry Sowers

Mo Karbassian

Mo Karbassian

Mo Karbassian

Carl Churchman4

"'t kl~

Objectives

+ Provide status of SG replacement and power uprate project

* Overview of RSG transportation

+ Overview of RSG installation

+ Discuss power uprate submittal

+ Proposed Technical Specification changes

ý- % I i'l

Objectives

+ Required plant modifications

+ Control room habitability + RCS piping weld issue

+ Provide an overview of upcoming activities

+ Discuss integrated schedule

j AOj

on L

r.

wI~II-iW~HiMilI 1inIRIiIu17LWFir~m I

711 rý-rrý

QIIIIMý

U

MUM-

RSG Transportation

+ Status of transportation plan

+ Status of permits

+ Status of infrastructure improvements

ý- i ,

Installation Activities

* U2R9 (fall 2000) (Complete) • Laser templating of piping in containment * Design walkdowns in containment

• Polar crane inspections

- No major rework required

* U2C10 (winter 2000 - spring 2002) * Personnel access and north side sally port

ý, I J,/

Installation Activities

* U2R10 (spring 2002) * Remove/relocate interfering commodities from

bioshield wall • Polar crane preparations (based on U2R9

inspection)

* SG2 auxiliary crane supports

,V0j

Installation Activities

SU2C11 (summer 2002 - fall 2003) • Craft access facility

* Outside lift system

• Haul route

e RSG preparations

* U2RII (fall 2003) * Bioshield wall modifications

o Replace steam generators

\1ji

YTFAU tiJFlrlDATi'0 OCDI Af"EiUEL a =• LIrl- -.. -I. -1- r.,ml I LJM

I IG REPLACEMENT CONTRACTOR PROCESSING, OFFICE & BREAK AREA FACILITY (EXISTING)

A 81G REPLACEMENT CONTRACTOR WAREHOUSE FACILITY (EXISTING)

5 REPLACEMENT SIG OFFLOADISTORAGE LOCATION

4 CONTAINMENT ACCESS, CRAFT ASSEMBLY AREA & PODIOUTAGE MANAGEMENT FACILITY

S OLD S/G STORAGE LOCATION

SIG CONTRACTOR SECURITY ACCESS FACILITY

EMERGENCY PERSONNEL HATCH)

® FAB SHOP, WELD TEST SHOP & MOCK-UP FACILITY (EXISTING)

LAYDOWN AREA

CONTRACTOR PARKING AREA

DECONTAMINATION FACILITY

May 9,20001. SECURITY GATE TO BE REWORKED

TO FACILITATE SO MOVEMENT INTO PROTECTED AREA.

2. CONTRACTOR TRUCKISMALL EQUIPMENT ACCESS TO PROTECTED AREA

ý' I I/

Licensing Activities

*Submittal is being reviewed by a crossdisciplinary team including members from another utility

* Final safety analysis results are within criteria defined at the outset of the project

ý k I--, /

Licensing Activities

+ APS will provide submittal to NRC in June 2001

* Request approval in June 2002

+ U2C12 fuel design to commence in September 2002 based on SER from NRC

'div

Technical Specification Changes

+ Definition of rated thermal power

* Low SG pressure reactor trip setpoint

* Low SG pressure MSIS setpoint

* Peak containment pressure

* Operating range for cold leg temperature at 100 percent power

* Allowable power vs. operable MSSVs

*\ kI ,

Safety Analyses

* UFSAR Chapter 15 Transient Analysis • CENTS code * Analytical limits • Methodology changes

• Sample from uprate submittal

Safety Analyses

* CENTS will replace CESEC-III as the primary tool for Chapter 15 non-LOCA transient analysis.

* Implementation of CENTS targeted for Unit 2 Cycle 11 in accordance with GL 83-11 Supplement I guidelines.

+ CENTS will be used to predict global changes in RCS pressure during the CEA ejection event. STRIKIN-II will continue to be used to predict local conditions (i.e. fuel enthalpy and DNBR).

\4j I ,

Safety Analyses

Initial conditions at full power Values Include appropriate uncertainties

Power Inlet temperature Pressurizer pressure RCS mass flow rate Pressurizer level

SG level Axial power distribution

MTC Primary to secondary leakage

= 4070 MWt (3990 + uncertainty) = 548 to 566*F

= 2100 to 2325 psia = 95% to 116% of design = 24% to 59%

= 4% to 92% NR = -0.20 to +0.20 ASI = -0.20 to -4.0 E-4 delta-rho/°F = 720 gpd I SG

,-. ý I "

Safety Analyses SMethodology changes

The following methods/assumptions changes will be applied to both the current plant configuration (Units 1/3) and Unit 2 RSG/uprate

- Dose calculations will assume a decontamination factor of 100 (partition factor of 0.01) for the intact SG

- Post-trip MSLB will employ a more detailed reactivity calculation, including moderator density feedback in the hot channel

Safety Analyses

* Methodology changes (cont.) - Single RCP sheared shaft with LOP will

assume that, at 90 minutes, the operator will re-establish level in the affected SG

- SGTR+LOP will credit EOP-based isolation of affected SG

Safety Analyses

SSample from uprate submittal • Outline and contents of the safety analysis

portion of the submittal is based on a composite of the PVNGS UFSAR and the Farley uprate submittal

Safety Analyses

SSample from uprate submittal (cont.) Inadvertent opening of a SGADV

- Identification of causes and event description

- Acceptance criteria

- Description of analysis

- Input parameters, initial conditions, and assumptions

- Results

- Conclusions

Safety Analyses Table 6.3-8: Sequence of Events for IOSGADV+LOP Event

Time (sec) Event Value

3876 3990 3876 3990 MWt MWt MWt MWt

0.00 0.00 Inadvertent opening of SG#1 ADV ......

0.00 0.00 Hot Channel Minimum DNBR 1.72 1.72

147.9 176.5 SG pressure reaches MSIS/Trip setpoint (psia) 850 915

149.1 177.7 Reactor/Turbine trip ......

Loss of Offsite Power

149.7 178.3 Scram CEAs begin falling ......

151.2 179.7 Minimum DNBR > SAFDL > SAFDL

153.5 182.1 MSIVs Closed ......

352.7 329.3 SG#2 MSSV Bank 1 Open (psia) 1303 1303

Begin Oscillating

463.9 428.3 RCS pressure reaches SIAS setpoint (psia) 1750 1750

919 1005 SG#1 Empties ......

1800 1800 Operators manually close SG#1 ADV ......

1800 1800 Operators initiate cooldown (min) 30 30

\. I ,

Safety Analyses- 3990 SMWt

- -- - - ý - 39.715 - -Lt

L20

T[r4E, seconds

- I - I - I

- I - I - I - I - I - I - I - I - I - I - I - I - I - I - I - I - I

- I - I - I - I

- I - I - I - I

- I'

L 200 1500 LStC

* .1.111.... 11.1....'.'

so

60

40

2 0

-� I I

20

00

\iJI

i . . - - - - . . . . . . . . . . . . . . . . . . . . . . . .

I I I I I

I I

Ow

Safety Analyses 3.10

-- 3990 MWt

2.80 3876 MWt

U

2.50 I

I

S2.20

- 1.90

- I

1.60

1.30

1.00 0 40 80 120 160 200

TIME, sec

ýt t i 'o,

RCS TEMPERATURES., degE

kA L

W In

CI)

Ld WCD

Safety Analyses.. . .. . .. . .. .. .I .. . . .. .

- I - I

- I - I - I - I

- I - I - I - I - I - I - I - I - I - I - I - I

- I - I - I - I- 9' - I - I

3976 IAWi

TKYU L

SCL,±zu

S.,,. SUISISI 55555111515511.1.... ii * a I*l1

SSSIII IS I

300~ 900~ T IPE., s coud s

L 200~

2

0

Sp

-2

4

-6

-S

-LtO

0

v t /

Safety Analyses _2750 . . . . ... . . ..... . . . . . . . . . . . . .1 .. . . . . . . .. I . . . . . . . . .

3990 lX, Wi

- -. . . . . .- .. 38.76 bAWIV L ,.•.." 2500

2250,

L750---------S/

LSOO S

L250 /

L250 . . . . ..l1 , , l 1 I . . . . . . . .. I. . .. . .. . ..

0 300 600O 900 L 200 L500 LSMD

T[ ME, s eonds

Safety Analyses L5.0 ......... .................. ............... ......... ..

Uhmf~ctud Sa

t 250,..,- " 1 p-I

- - 3976 MWtL

750

DI]

500~

250 16

Af.fvtr. dSG C!

0 F ......... I .. . . .I .I .I . . ...... I ........

0 300 60 900 L 200 L500 tLSW

T MIE s onds

Safety Analyses 24C oD . . . .. . . .. . . . . .. . . .. . . . . .. . . .. . . .. . . . I . . . . . . . .. I "T

3990 MW''

- -- - - - - - 3S76 MW-V'

200•00

L -----

-\ . . . . . . .----- -------\

L~IL

0 300 1200 LSOO

T[E MIE., seconds

0//

Safety Analyses

SSample from uprate submittal (cont.) Conclusion

For the IOSGADV+LOP event, all of the acceptance criteria are met. The peak primary and secondary pressures remain below 110 percent of design at all times, thus ensuring the integrity of the RCS and main steam systems. The minimum hot channel DNBR remains above the SAFDL, thus ensuring fuel cladding integrity. Offsite radiological consequences remain within a small fraction of 10 CFR 100 guidelines.

Risk Evaluation

* Submittal will not be made as a risk

informed licensing amendment

* Power uprate is not large and no substantial change in risk expected

* PRA will be updated to reflect changes due to uprate

-. 0

Control Room Habitability

* Revise design/licensing basis for allowable unfiltered in-leakage

+ Validate allowable in-leakage with baseline testing

+ Expect good results from testing due to CR ventilation system design and previous pressure testing

+ PVNGS will have contingency plan ready if test results are unsatisfactory

Required Plant Modifications

SSpray pond temperature monitoring equipment

SRemove containment spray flow orifices and install Annubar flow elements

SChange steam admission to HP turbine from partial arc to full arc

UI

RCS Piping Weld Issue

SPVNGS has reviewed construction records for RCS welds

* Records recovered to date indicate that welds were completed according to procedure

* Structural analysis for the RCS reflects those procedures

Future Activities

* RSG will be moved from Milan to Montfalcone for final welding later this year

* Meeting to discuss power uprate submittal a few weeks after receipt by NRC

* Point of contact for questions on submittal

PVNGS Unit 2 Steam Generator Replacement Project Integrated Level One Schedule for RSG & Power Up

119991997 18 192000 2001 2002_ 2003 12004MARO

Design & Document Phase

100W

Uprate 8a y 4/98 ame8

U2IA0

Falication of RSG's/Ansaldo Enerma smva. In Miln. Italy

Award Eng. Conýtrat/Obtain Infrastructure Pem*s

Finalize Transportatn Route Intervention Modiicalon

APS & CE RSO I Uprale ,Enneering Analysis

Complete NAC qnginering ~uMl

Transport to Shippng Port

Transport to PVNGS

RSG's Arrive At PVNGS #9102

9196 2101 � 9/ni

NRCeEvaluation o of S ittal

%SG& Power Upralie Modiiato EnglnerWng& InstallationIMS 12W0

cs rfif.acmtUprat.Mod Eng 2dJ0 1 7/01

Spray Pond Temp Transmitter Uprate Mod Eng

1/01ttJl•

Signed Installation Phase I Contract With Bechtel

3/99 ii!

CS orifie pe~apmment Uprate Mod Installation 30 5=V02MM 9 5 1203

SP Temp Transmitter Uprate Mod Instalation

Main Transformer Cooling Eng. Main Transformer Cooling Installation 1/0 t Ol M O 601 3WC2 102.. :: Coollng Tower Wind Vane Eng. M 1/0 :12/01,o+ :: MT Throttle Valve

Cooling Tower Wind Vane Installation MT Thottle Valve Mod Eng. Mod Installation 1/02. 51•029/ 2 1/030

Site Preparations for Installation" 9 12103

U2R8 -Laser Piping Templating .4 ::5 9

U2R9 - Design Verification Walkdowns U2R10 - BlO.11ield Wall Mods l9/o0 m11/O0 3 002

Prepare/issue U2R1O DCP's Prepare/issue U2R10 WP's SG Level Transmitter Installation

SG Level Transmltter Design Eng SG Level Transmitter Installation VW-0 MUOMM11101 3weno 5"0

Prepare/issue Const Proc.

2101 8A)1•o MW =, Install Protected Ama Access - North

U2R1 1 - Replace SG's 103 2/O03I

Prepare/issue U2R11 WP's W02 6W3

S1/01 2/0 Prepare/issue U2RI 1 DCP:s

Design/Construct 080 Storage/NSG Storage Facilities

North Anex Remodeling Install Downcomner Blowdown Electrical Modification S101 12 01. . _ 11flg

Contract Awarded To Ansetdo

12/07

u2RtI