ML18054B588

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Summary of 900412 Meeting W/Util & Bechtel in Gaithersburg, MD Re Plant Steam Generator Replacement Project.List of Attendees Encl
ML18054B588
Person / Time
Site: Palisades 
Issue date: 05/07/1990
From: De Agazio A
Office of Nuclear Reactor Regulation
To: Diianni D
Office of Nuclear Reactor Regulation
References
TAC-76069, NUDOCS 9005110059
Download: ML18054B588 (65)
v • d • e


Text

Docket 50-255 MEMORANDUM FOR:

FROM:

~._LJ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May 7, 1990 Dominic D. Diianni, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Albert W. De Agazio, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects

SUBJECT:

SUMMARY

OF MEETING WITH CONSUMERS POWER COMPANY -

PALISADES STEAM GENERATOR REPLACEMENT PROJECT (TAC 76069)

A meeting was held in Gaithersburg, Maryland on April 12, 1990, at the offices of Bechtel Power Corporation to discuss certain aspects of the planned replacement of.the. Pa_lisades Plant steam generators.' *specifically, the meeting focused upon th~ ccnstr~ctioh*opening in the concrete, post-tensioned containment building. Enclosure 1 is the list ~f-attendees at the meeting.

ThE Palisades Plant steam generator repiacement project {SGRP) will be the first such replacement for a Combustion Engineering (C-E) designed plant.

Palisades was the first large C-E unit and initially used coordinated phosphate

  • s*econdary side chemistry.

In 1975, the chemistry was changed to all volatile treat111ent (AVT), but by then the early chemistry along with carbon steel tube shtel~ ~~d drilled tube supports led to severe tube denting an~ corrosion. The incidence of tube le~ks was significantly reduced following the change to AVT.

The replacement stear.i ger.erators we:re built in the late 1970s and are essentially the System-BO design except the feedwater does not enter at the bottom.

The containment opening will involve the detensioning and removal of 130 tendons.

Mockups of the containment wall will be used for development and training for cutting the opening, how_ever the actua 1 method to be used. for concrete cutting has not yet been selected. The opening *will be about 28-ft by 26-ft and will be above the original construction opening that was about 40-ft square. It is expected that the opening will exist for 35 - 40 days.

The construction of the retaining wall and roadway for the hoist area was discussed in detail along with the rigging concept for lifting and moving the steam generator both outside and inside the containment.

The r~sults of ccntainment structural analyses completed to date were presented and discussed.

The NRC staff expressed a desire to examine in detail the cortainment stress analytical results in the area of the construction opening at a later date wher; the analyses are completed. A structural* integrity test of the containme.nt will be conducted prior to restart of the unit. This.test will ~E run at 115% of the 55 psig design pressure.

- 9005110059 900507 PDR ADOCK 05000255 P

PDC

  • Qrol l \\t The ventilation concept to be used to contrril dust and contaminatio~was described, however much of the detail of ventilation and radiation control are not.scheduled for completion until about June 1990. contains copies of the visual aids used during the meeting. identifies the safety evaluations planned to support the determination that the SGRP can be done under 10 CFR 50.59{a)(l). identifies the load combinations considered in the containment structural analyses and identifies the concept for the structural integrity test of the containment.

.a/tu/-#1&-ik-*.

Albert ~

~gazio, Sr~,~:~:t Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

n

-....._. The ventil~iion concept to be used to control dust and contamin~tion was described, however much of the detail of ventilation and radiation control are not scheduled for completion until about June 1990. contains copies of the visual aids used during the meeting. identifies the safety evaluations planned to support the determination that the SGRP can be done under 10 CFR 50.59(a)(l). identifies the load combinations considered in the containment structural analyses and identifies the concept for the structural integrity test of the coritainment.

DISTRIBUTION

DOCKET FILE:;

NRC & LOCAL PDRs PD31 R/F PSHUTTLEWORTH ADEAGAZIO OGC EJORDAN ACRS GBAGCHI WLIU EMURPHY RPIERSON ESWANSON CTAN NWAGNER KWICHMAN PM/PD31:~

ADEAGAZIO 4~790 (A~oo ~~ ~

DDl)tm-;~SP 4/~-{/90 Original signed hy Albert W. De Agazio, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

ENCLOSURE 1 MEETING ATTENDEES Docket # dt!J -J-;;--.}-

Accession# 9120.:J-/ lo 11;;~9 Date o /7 l9t2 of Ltr Regulatory Docket File

MEETING ATTENDANCE DATE:

April 12, 1990 PLACE:

Bechtel Power Corp., Gaithersburg, Maryland UTILITY AND DOCKET NO:

Consumers Power Co. (Palisades Plant)

Docket No. 50-255

SUBJECT:

Containment issues related to the Palisades Steam.

Generator Replacement Project.

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ENCLOSURE 2 VISUAL AIDS USED WITH DISCUSSIONS

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. I NRCJCPCo/BPC MEETING PALISADES STEAM GENERATOR REPLACEMENT PROJECT CONTAINMENT CONSTRUCTION OPENING GAITHERSBURG, MARYLAND APRIL 12, 1990

9:00 9:15 9:30 io:oo 11:00 Lunch 1:00 2:00 2:30 3:00 Palisades SGRP NRC/CPCo/BPC Meeting 9:00 A.M *. April 12, 1990 Bechtel Offices, Gaithersburg, Maryland CONTAINMENT CONSTRUCTION OPENING Agenda Opening Remarks SGRP Video Presentation Licensing/Safety Evaluation Containment Opening.Construction Reinforced Earth Retaining Wall Containment Wall/Liner Plate Opening S/G Rigging Containment Wall/Liner Plate Replacement Containment Opening Structural Analysis Design Criteria Analyses structural Integrity Test Temporary Ventilation summary Safety Evaluation Schedule Closing Remarks Adjourn I). Joos (CPCo)

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L~ Morris (BPC)

E. Thomas (BPC)

B. Seam (BPC)

T. Tai (BPC)

R. Beck (BPC)

D. Joos (CPCo)

l OUTLINE OF NUCLEAR PRESENTATION 0

CONSTRUCTION OPENING 0

GENERAL WORK ACTIVITIES 0

50.59 ISSUES 0

PRECAUTIONS TO BE CONSIDERED

CONSTRUCTION OPENING PURPOSE: EQUIPMENT RIGGING LOCATION: SE QUADRANT OF CONTAINMENT HEIGHT:

28 FT (EL. 651'*0" TO 679'*0")

WIDTH:

26 FT CENTERLINE: 120° AZIMUTH

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  • GENERAL WORK ACTIVITIES o

DETENSION/REMOVE TENDONS AND TENDON GREASE o

CUT/REMOVE CONCRETE WALL o CONCRETE o REINFORCING STEEL o TENDON SHEATHING o LINER PLATE o

INSTALL TEMPORARY CLOSURENENTILAT/ON.

SYSTEM o

COMPLETE STEAM GENERATOR REPLACEMENT o

REPLACE CONCRETE WALL o LINER PLATE o TENDON SHEATHING o REINFORCING STEEL o CONCRETE o

REINSTALL/RETENSION TENDONS AND TENDON GREASE o

PERFORM SIT

ISSUES TO BE ADDRESSED IN 50.59 EVALUATION o

CONTAINMENT STRUCTURAL ADEQUACY.

o DESIGN PARAMETERS/FSAR COMMITMENTS o

MATERIALS (CONCRETE, REINFORCING,.

TENDONS, LINER PLATE) o PERFORMANCE TEST (SIT)*

o MAINTAIN CORE COOLING CAPABILITY DURING CONSTRUCTION o

PROTECT SAFETY-RELATED EQUIPMENT/

STRUCTURES DURING CONSTRUCTION o

RADIATION PROTECT/ON/RADIOLOGICAL RELEASE CONTROL o

WASTE DISPOSAL o

VENTILATION CONTROL

ISSUES TO BE ADDRESSED IN 50.59 EVALUATION (CONT) o PROCEDURAL CONTROLS o CONTAINMENT ACCESS o SECURITY o OTHER OPERATIONS o

TECHNICAL SPECIFICATION REQUIREMENTS o

FSAR COMMITMENTS

PRECAUTIONS -TO BE CONSIDERED I

o DETENSION OF TENDONS WILL NOT START UNTIL AFTER:

o FULL WATER INVENTORY IN REFUELING POOL o

PRIMARY SYSTEM TEMPERATURE

< 120 F, AND o

PRIMARY SYSTEM BORON CONCENTRATION~ 1720 PPM o

CONTAINMENT LINER WILL NOT BE BREACHED UNTIL REACTOR IS DEFUELED o

MAINTAIN REQUIREMENTS IN GOP-14, "SHUTDOWN COOLING OPERATIONS" o

INVOKE HEAW LOAD PROCEDURES FHS*M-23 AND FHS*M-24 o

CONCRETE CHIPPING INSIDE LOCAL ENCLOSURES o

MAINTAIN AIR FLOW INTO THE CONTAINMENT

PRECAUTIONS TO BE CONSIDERED (CONJ]

o LOCATE RADIATION MONITOR AT THE EXHAUST OF THE TEMPORARY VENTILATION SYSTEM o

TEMPORARY ENCLOSURE FOR CONTAINMENT OPENING o

PERIODIC RADIOLOGICAL SURVEILLANCE OUTSIDE THE CONTAINMENT o

INVOKE ONP-11.2, "FUEL HANDLING ACCIDENT' TO CONTROL EQUIPMENT HATCH

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BASIS OF THE EVALUATION

  • TO SATISFY ALL COMMITMENTS IN THE FSAR

PRIMARY PARAMETERS AFFECTING BEHAVIOR OF CONTAINMENT DUE TO STEAM GENERATOR REPLACEMENT ACTIVITIES

  • POTENTIAL DIFFERENCE IN CONCRETE PROPERTIES

-STRENGTH

- LONG TERM CREEP

- SHRINKAGE

  • POTENTIAL DIFFERENCE IN PRESTRESS LEVEL

OUTLINE OF THE PRESENTATION

  • DESCRIPTION OF PALISADES CONTAINMENT
  • DESIGN CRITERIA
  • STRUCTURAL (FINITE ELEMENT)

MODEL

  • ANALYSIS APPROACH
  • MATERIAL PROPERTIES
  • RESULTS OF THE ANALYSIS
  • REPLACEMENT CONCRETE
  • STRUCTURAL INTEGRITY TEST

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SECTION CONFIGURATION OF DOME TENDONS POST TENSION/NG DETAILS

TENDON SYSTEM NO. OF TENDONS DESIGN PRESTRESS LEVEL SHELL:

552 HOOP TENDONS 665 KIP/FT 180 VERTICAL TENDONS 290 KIP/FT DOME:

165 TENDONS 370 KIP/FT (ARRANGED IN THREE SETS).

- TENDONS ARE UNBONDED

  • PROTECTED AGAINST CORROSION BY GREASE FILLER

- LOCAL LOAD VARIATION IN CONTAINMENT HAS INSIGNIFICANT EFFECT ON TENDON PERFORMANCE

BASIC FEATURES OF THE CONTAINMENT

  • POST-TENSIONING IMPOSES A CONSTANT

. INWARD LOAD ON THE CONTAINMENT

- ACCIDENT PRESSURE RELIEVES THE POST-TENSIONING LOAD AND.

UNLOADS THE CONTAINMENT

  • POST TENSIONING SYSTEM IS PASSIVE

- NO CHANGE-OF-STATE REQUIRED TO RESIST ACCIDENT LOADS

BASIC FEATURES OF "THE CONTAINMENT (CONTINUED)

  • SUBSTANTIAL MARGINS EXIST IN THE PALISADES DESIGN

- DESIGN PRESSURE:

55 PSI

- TESTED TO:

63 PSI

- POST TENSION PRESS. 78 PSI (EFFECTIVE PRESTRESS = 1.5 X DESIGN PRESSURE - NOMINAL)

- SURVEILLANCE RESULTS INDICATE THAT POST*

TENSIONING MAY BE APPROXIMATELY 5%

GREATER THAN DESIGN END-OF-PLANT LIFE PREDICTION

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. DESIGN CRITERIA

  • EXACTLY THE SAME AS ORIGINAL DESIGN
  • AC/ 318-63 WITH ENHANCEMENTS IDENTIFIED IN FSAR
  • BOTH WORKING STRESS AND ULTIMATE STRESS ANALYSIS PERFORMED (AS SPECIFIED IN FSAR)

~ ALL LOAD CASES IDENTIFIED IN FSAR WERE EVALUATED

ADDITIONAL DESIGN CONSIDERATIONS

  • DETENSIONED CONTAINMENT WITH/WITHOUT OPENING

- EXTREME WIND

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  • CRANE LOAD (PER REQUEST OF REGION Ill)

FINITE ELEM MODEL

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  • 30 ANALYSIS
  • REPRESENTS SHELL AND DOME
  • FIXED BOUNDARY CONDITION AT BASEMAT
  • 1400 PLATE/SHELL ELEMENTS
  • .ELEMENT SIZE LESS THAN 2.6 X WALL THICKNESS.

- AREA AROUND OPENING; ELEMENT SIZE IS LESS THAN 1.29 X WALL THICKNESS

  • USED BSAP CODE

- WELL VERIFIED & FAMILIAR TO NRC

LOADS ON SHEL E TO PRESSURE RESULTS OF ORIGINAL ANALYSIS (AS SHOWN IN FSAR)

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ANALYSIS APPROACH

  • CONSIDERED 5 STAGES (1) EXISTING. STRUCTURE (2) STRUCTURE DETENSIONED (2 DETENSIONING SCHEMES)

(3) STRUCTURE DETENSIONED, WITH OPENING (4) STRUCTURE WITH REPLACED CONCRETE RETENSIONED (IMMEDIATELYAFTER *..

RETENSION/NG) *

. (5) STRUCTURE WITH REPLACED CONCRETE RETENSIONED (AT END OF LIFE)**

  • STRESSES IN.RETENSIONED STRUCTURE STAGE (4) IS COMBINATION OF THOSE FROM STAGE (3) +ADDITIONAL STRESSES CREATED BY RETENSIONING AND OPERATING/ACCIDENT LOADS
    • STRESSES IN STAGE 5 STRUCTURE OBTAINED SIMILAR TO THAT IN STAGE 4 EXCEPT THAT MODULUS WAS CORRECTED IN STAGE 5 ANALYSIS TO ACCOUNT FOR LONG TERM CREEP EFFECTS

ZONE OF VERTICAL DETENSIONI NG*

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MATERIAL PROPERTIES

  • EXISTING CONCRETE
  • USED SAME VALUES AS ORIGINAL ANALYSIS AND AS PRESENTED IN THE FSAR
  • REPLACEMENT CONCRETE

~TO ESTIMATE PROPERTIES OF REPLACEMENT CONCRETE BOTH AT INITIAL PRESTRESSING AND AT END OF PLANT LIFE THE FOLLOWING BASE DATA WAS CONSIDERED:*

- ORIGINAL LABORATORY TEST DATA

  • ORIGINAL ANALYSIS DATA (MORE CONSERVATIVE THAN LAB TEST DATA)

- ESTIMATE OF OPTIMAL MIX RESULTS

  • ESTIMATE OF STIFFNESS (MODULUS OF ELASTICITY) AT 7 DAYS

-. STIFFNESS: 0. 78 TO.92 X DESIGN VALUE

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MATERIAL PROPERTIES (CONTINUED)

  • CREEP EFFECTS WERE ACCOUNTED FOR*BY AN EFFECTIVE MODULUS OF ELASTICITY
  • AC/ 209R (CONSIDERING BVZANT'S AGING FACTOR)
  • AC/ SP-76 (BASED ON ACTUAL CREEP TESTS RESULTS FOR SEVERAL CONTAINMENTS***

STRUCTURES)

  • LONG TERM STRENGTH AND STIFFNESS

- STRENGTH: 1.16 TO 1.74 X ORIGINAL DESIGN VALUE (ACTUALLY USED 1.0)

- STIFFNESS:.64 TO.78 X ORIGINAL DESIGN VALUE (BEST ESTIMATE:.69 ORIGINAL)

~--~-----~-

MATERIAL PROPERTIES (CONTINUED)

  • NEW ANALYSIS BASED ON THE FOLLOWING:
  • CONCRETE STRENGTH OF 5000 PSI (SAME AS ORIGINAL ANALYSIS) FOR BOTH-OLD AND REPACEMENT CONCRETE
  • FOUR DIFFERENT STIFFNESS VALUES

_ (MODULUS OF ELASTICITY) FOR REPLACEMENT CONCRETE (BASED ON LOADING AT AGE OF 7 DAYS)

  • 1.2 X ORIGINAL DESIGN VALUE
  • . 77 X ORIGINAL DESIGN VALUE
  • .69 X ORIGINAL DESIGN VALUE
  • .63 X ORIGINAL DESIGN VALUE

MATERIAL PROPERTIES (CONTINUED)

  • CONCRETE MIX DESIGNED TO MINIMIZE SHRINKAGE
  • FOR DESIGN - USE AC/ 209R TO DETERMINE AMOUNT OF SHRINKAGE

- EVALUATE MICROCRACKING

~SIZE

- DISTRIBUTION

  • RESULTING STRESS IN CONCRETE
  • APPROXIMATELY 2 1/2 KIP/FT

- ACCEPTABLE PER AC/ 224R-80

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RESULTS OF ANALYSIS

  • DEPENDENT UPON FOLLOWING TWO PARAMETERS:

- AMOUNT OF DETENSIONING (PRIMARY)

- AMOUNT OF LONG TERM CREEP (SECONDARY).

  • EFFECTS OF BOTH PARAMATERS OF LIMITED TO THE AREA IMMEDIATELY SURROUND/NG THE OPENING

- HOOP DIRECTION:

  • AVERAGE HOOP PRESTRESS MEETS ORIGINAL DESIGN REQUIREMENT

- VERTICAL DIRECTION

  • AVERAGE VERTICAL PRESTRESS MEETS ORIGINAL DESIGN REQUIREMENT

- REBAR AND CONCRETE STRESSES STILL UNDER EVALUATION

- RESULTS WILL SHOW THAT ORIGINAL DESIGN CRITERIA IS SATISIFIED

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REPLACEMENT CONCRETE

  • DESIGN MIX BEING DEVELOPED AT UNIV. OF ILLINOIS

. - OBJECTIVE:

- MAXIMIZE STRENGTH

- MINIMIZE SHRINKAGE & LONG TERM CREEP

-APPROACH

- USE HIGH DENSITY, LOW ABSORPTION AGGREGRATE

- POSSIBLE GAP GRADING OF AGGREGATE

- MIMINIZE MORTAR-TO-AGGREGATE RATIO

- MINIMIZE WATER-TO-CEMENT RATIO

- LOW HEAT OF HYDRATION CEMENT (TYPE II)

- MINIMIZE CEMENT FACTOR

ACTIVITIES. AT UNIV. OF ILL

  • PREPARATION OF PRELIMINARY TRIAL BATCHES
  • PREPARATION OF FINAL TRIAL BATCHES
  • SELECTION OF A FINAL MIX TO OPTIMIZE THE FOLLOWING:

- LOW MORTAR TO AGGREGATE RATIO

- LOW WATER-TO-CEMENT RATIO

- LOW CEMENT FACTOR

- SUFFICIENT WORKABILITY AND PUMPABILITY

- MINIMUM DOSAGE OF ADMIXTURES

  • ACHIEVE HIGH EARLY STRENGTH.
  • PERFORM CREEP TEST

- TESTS SETS TO BE LOADED AT 7 AND 28 DAYS

- STORE AT 70 DEGREES AND 110 DEGREES

- OBTAIN: -

- COMPRESSIVE STRENGTH

- MODULUS OF ELASTICITY

- POISSON'S RATIO

- SPECIFIC CREEP

- TEST DURATION: 6 MONTHS

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

STRUCTURAL INTEGRITY TEST (SIT)

  • A SIT JS PLANNED

- SUGGESTED TEST PROCEDURE JJF.5/G#

- PRESSURIZE TO 1.15 x Ae~T PRESSURE

  • MEASURE RADIAL DISPLACEMENT OF SHELL AT OPENING AND IN AN ORTHOGONAL DIRECTION

- MEASURE VERTICAL DISPLACEMENT OF SPRINGLINE DIRECTLY ABOVE OPENING

- PERFORM CRACK MAPPING AT CENTER AND AT ONE TOP CORNER OF REPLACED CONCRETE

Objective:

  • Mitigate Potential Airborne Radioactive Particle Release Through Construction
Opening,
  • Accomplish By Creating a Negative Pressure Differential Across Construction Opening To Prevent Air From Flowing Out of Containment.

CONTAINMENT VENTl,LATION SYSTEM CONSTRUCTION OPENING~

HEPA PREF.

REDUNDANT FANS 401000 CFM EACH RADIATION MONITOR 40,000 CFM

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CONTAINMENT EQUIPMENT~

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TEMPORARY CONTAINMENT VENTILATION SYSTEM CONSTRUCTION OPENING~

HEPA PREF.

REDUNDANT FANS 401000 CFM EACH RADIATION MONITOR

TEMPORARY CONTAINMENT.VENTILATION SYSTEM PLAN VIEW.

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CONSIDERATIONS 0

KEEP TEMPORARY CLOSURE DOOR CLOSED EXCEPT DURING RIGGING OPERATION 0

DURING RIGGING OPERATION, IN ADDITION TO TEMPORARY VENTILATION SYSTEM, FB EXHAUST SYSTEM WILL INDUCE AIR FLOW FROM

_ CONTAINMENT TO FB 0

ABILITY TO CLOSE EQUIPMENT HATCH, AS REQUIRED, IN THE EVENT OF FHA 0

FUEL BUILDING EXHAUST SYSTEM THROUGH CHARCOAL ADSORBERS WILL BE OPERABLE AT ALL TIMES 0

FAN FAILURE/DIRTY FILTER/RADIATION ANNUNCIATION WILL BE ALARMED IN THE VICINITY OF 24-HOUR MANNED STATION 0

  • CAM WILL BE IN THE VICINITY OF CONSTRUCTION OPENING

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===========================*===============================================~=======c===========================~====*======c=m=**=c**=**===*==s*=**a*s*RB******a*an*=~=*~

PRJ NAME PALISADES SGR SUBJECT CTHT CONSTRUCTION OPENING PRJ LOCAT COVERT, HI RPT DATE 11-Apr-90 REVISION 0

RESPONS.

DESCRIPTION START 01-Sep~90 UEEKS 22

  • END 02-Feb-91 START DAYS DOES SCHEDULE INCLUDE YIN SATURDAYS Y

SUNDAYS Y

END

==~==a===~===================================================~======~

START OF OUTAGE 01-Sep-90 1 01-Sep-90 FUEL OFF-LOAD 18-Sep-90 9 26-Sep-90 TENDON DETENSION/REHOVAL 16-Sep-90 15 30-Sep-90 CTHT UALL CONCRETE CUTTING 26-Sep-90 5 30-Sep-90 RPV COMPLETELY DE-FUELED 26-Sep-90 83 17-Dec-90 REMOVE CTHT UALL PLUG 30-Sep-90 1 30-Sep-90 CT"T OPENING EXISTS 30-Sep-90 39 07-Nov-90 INSTALL LINER PLATE 07-Nov-90 24 30-Nov-90 INSTALL TENDON DUCT/REBAR 09-Nov-90 9 17-Nov-90 INSTALL FORHUORK 13-Nov-90 15 27~Nov-90 CONCRETE PLACEMENT 01*Dec-90 3 03-Dec-90 CONCRETE CURE 03-Dec-90 21 23-Dec-90 REINSTALL TENDONS 06-Dec-90 10 15-Dec-90 TENSION/GREAS~ TENDONS 23-Dec-90 18 Q9-Jan-91 RE-LOAD FUEL 17-Dec-90 10 26-Dec-90 SIT 22-Jan-91 3 24-Jan-91 2

3 4. 5 6

7 8

9 10. 11 12 13 14 15 16 17 18 19 20 21. 22 ' 23.

90 90* 90 90 90 90 90 90 90 90 90* 90 90 90 90 90 90 91 91 91 91 91 91 SEP SEP SEP.SEP OCT OCJ OCT OCJ NOV NOV NOV NOV NOV DEC DEC DEC DEC JAN JAN JAN JAN FEB FEB 1 14 21 28 5 12 19 26 2

9 16 23 30 7 14 21 28 4 11 18 25 1

8

~-~--------1-----------*****l*---~~---*****--*l*******-~---**-*l************-****I***

I START OF OUTAGE

~*. "* :.

I FUEL OFF-LOAD JENDON DETENSION/REHOVAL CTHT UALL CONCREJE CUTTING RPV COMPLETELY DE*FUELED REMOVE CTHT UALL PLUG

.CTHT OPENING EXISTS I.

INSTALL LINER PLATE INSTALL TENDON DUCT/REBAR INSTALL FOR~RK CONCRETE PLACEMENT CONCRETE CURE REINSTALL TENDONS TENSION/GREASE TENDONS RE*LOAD FUEL

  • --~-*

SIT

===============================================================
  • -************---1------------~---1-----------------1----------~-----1--------------*---1---

PREL~MINARV

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ENCLOSURE 3 PLANNED SAFETY EVALUATIONS TO SUPPORT NO UNREVIEWED SAFETY QUESTIONS DETERMINATIONS I,.

L

l FC Interim Old SG Storage Facility FC Containment Construction Opening FC Rigging Installation in Spring Outage Rigging FC Fe FC FC FC FC FC FC FC Haul Routes and Transportation Retaining Wall Outside Containment Steam Generator Replacement PCS Piping Main Steam Piping Emergency Feedwater Piping SG Blowdown Piping - Spring outage SG Blowdown Piping SG Recirculation Piping - Spring outage SG Recirculation Piping

. FC SG Sample System FC Wide Range Level Instrumentation Temporary Removal of Commodities

ENCLOSURE 4 CONTAINMENT LOAD COMBINATIONS STRUCTURAL INTEGRITY TEST

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LOAD COMBINATIONS CONSIDERED IN THE ANALYSIS

  • SAME.AS IDENTIFIED IN THE FSAR
  • WORKING STRESS CONDITION
1. D + Ff + L + To
2. D + Ff + L + P + Ta
3. D + Ff + L + P' WHERE D = DEAD LOADS L = LIVE LOADS.

Ff = FINAL PRESTRESS LOADS To = THERMAL LOADS DUE TO OPERATING TEMPERATURE Ta = THERMAL LOADS DUE TO DBA :

TEMPERATURE P = DESIGN PRESSURE P' = TEST PRESSURE (1.15 X DBA PRESSURE)

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LOAD COMBINATIONS (CONTINUED)

- YIELD STRENGTH CONDITION

1. Y = 1/</J(1.05D + 1.5P + 1.0Ta + 1.0 Ff)
2. Y = 1/</J(1.05D + 1.25P + 1.0Ta + 1.25H + 1.25E

+ 1.0 Ff)

5. Y = 1/</J (1.0D + 1.0P + 1.0 Ta*+ 1.0E' +* 1.0 Ff)

WHERE: Y = REQUIRED YIELD STRENGTH OF THE STRUCTURE

</J = YIELD CAPACITY REDUCTION FACTOR D = DEAD LOAD P = DBA PRESSURE LOAD Ff = FINAL PRESTRESS H = FORCE ON STRUCTURE DUE TO THERMAL EXPANSION OF PIPES To =THERMAL LOADS DUE TO OPERATING TEMPERATURE Ta* = THERMAL LOADS DUE TO DBA.

TEMPERATURE E = OBE LOADS FOR GROUND ACCELERATION OF 0.1g E' = SSE LOADS FOR GROUND ACCELERATION OF 0.2g

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STRUCTURAL INTEGRITY TEST (SIT)

  • A SIT IS-PLANNED *
  • SUGGESTED TEST PROCEDURE
  • PRESSURIZE TO 1.15 X DESIGN*PRESSURE
  • MEASURE RADIAL DISPLACEMENT OF SHELL AT OPENING AND IN AN ORTHOGONAL DIRECTION
  • MEASURE VERTICAL DISPLACEMENT OF SPRINGLl.NE DIRECTLY ABOVE OPENING
  • PERFORM CRACK MAPPING AT CENTER AND AT
  • ONE TOP CORNER OF REPLACED CONCRETE
  • AN ILRT WILL ALSO BE PERFORMED

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