ML070600521

ECR OC-06-00879-001, 10/24/2006; Drywell Floor/Trough/Drainage Inspections and Repairs

ML070600521
Person / Time
Site:	Oyster Creek
Issue date:	11/06/2006
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
A2152754, OC-06-00879 OC-06-00879-001
Download: ML070600521 (77)

Text

I PAGE 0001 - E c R Printout ECR NUMBER:

OC 06-00879 001 ECR 'TYPE: ASSIGNED ORG: OEDM ASSIGNED kNDV: MARKOS INITIATOR:

TAMBURRO REQUEST ORG: OED A/R NO: A21 527 54 PROJECT NO: PRINT DATE/TIME:

REQUIRED DATE: ECR STATUS:

STATUS DATE: INIT. DATE: A/R STATUS: I' DCP 11/06/06 07: 52 11/06/06 DISPON 11/05/06 10/24/0'6 ASIGND 6' I' A. IDENTIFICATION:

SYSTEM: ' COMP ID: OC 1 187 - F MISC 187 INIT OPER: y QA CLASS: -Q- POTL REPT: TECH SPEC: y REQD IN MODES: 1 2 3 PAGES ATTACHED:

y NO. OF PAGES: 38 ID/DATE: JDHl 11/03/06 PROBLEM DESCRIPTION and PROPOSED DISPOSITION:

DURING 1R21, WATER WAS DISCOVERED IN THE EXCAVATED TRENCH OF THE DRYWELL ELEVATION 10'-3" FLOOR. PROVIDE FOR INSPECTION AND REPAIR OF THE DRAINAGE PROVISIONS FOR THIS FLOOR, AS WELL AS PROTECTION OF THE DRYWELL SHELL. THIS ECR WILL IN PARTICULAR, THIS ECR ADDRESSES:

1- SUB-PILE ROOM TROUGH (CONCRETE AREA UNDER REACTOR VESSEL) INCLUDING THE ENTRANCE TO THE PIPE THAT DIRECTS THE DRAINS TO THE SUMP. 2- CLEANING AND INSPECTION OF THE DRYWELL SUMP. 3- CLEANING AND PREPARATION OF THE INTERFACE OF THE DRYWELL FLOOR AND DRYWELL SHELL, AND INSTALLATION OF A CAULKING MATERIAL INTENDED TO PREVENT WATER INFILTRATION 4- ADDITIONAL EXCAVATION OF THE TRENCH AT BAY 5, TO ALLOW FOR FURTHER UT EXAMINATION OF THE DRYWELL SHELL, FOLLOWED BY PARTIAL GROUTING OF THAT TRENCH TO OPTIMIZE ONGOING PROTECTION OF THE DRYWELL SHELL. CLEANING, INSPECTION AND REPAIR, AS NEEDED, OF THE !REV 1 !REV 1 NOTE: THIS ECR WAS CREATED AS A REPLACEMENT FOR ECR 06-00875, IN ORDER TO HAVE THE ECR UNDER THE APPROPRIATE A/R.

-r , PAGE 0002 E C R Printout ' I ECR NUMBER: OC 06-00879 001 ECR TYPE: DCP // B. EVALUATION:

50.59 REVIEW REQD: ORIG 50.59 REVIEW AFFECTED:

50.59 SE REQD: REPORTABLE:

N DATE/TIME:

STATION PROC/PROGRAM REVIEW COMPLT: - ' CAUSE: RE FINAL OPERABILITY:

SCHED CODE/WINDW: 1R21 187 CEGO 10/21/06 ADVANCED WORK AUTH: y FINAL DISP: RP INTERIM DISP: :. I COMP: ___ SYSTEM: - PLANT: - I SSV NAME: ssv DATE/TIME: APPROVED DISPOSITION:

REVISION 1 REV 1 INCLUDES MINOR REVISION PROVZDED BY PORC REVIEW OF REV 0 dF THIS ECR. PORC MEETING NO 06-18. I I THESE CHANGES ARE MINOR EDITORIAL CHANGES TO MAINTAIN CONSISTENCY WITH EXISTING STRUCTURAL MONINTORING COMMITMENTS. INSTEAD OF 4 YEARS. REFERENCE TO A FREQUENCY OF 2 YEARS I ,. I THIS REVISION REVISES: PAGE 1 OF THE ECR TO CLARIFY THAT CLEANING WAS NEEDED OF THE TROUGH. PAGE RESULTS OF THE GROUT TESTING 4 OF ATTACHMENT 1 IS REVISED TO CHANGE THE PAGE 9 OF ATTACHMEW 1 IS REVISED TO REFERENCE IR 00546049.

ATTACHMENT 10D IS REVISED TO CHANGE FREQUENCY OF CAULK PM FROM 4 YEARS TO 2 YEARS. OTHER MINOR EDITORIAL CHANGES AND ENHANCEMENTS THROUGHOUT THE DISPOSITION.

IhD OF REV 1 ..............................................

AWA FOR DRYWELL FLOOR REPAIRS: THE FOLLOWING ADVANCED WORK AUTHORIZATIONS ARE PREPARED IN ACCORDANCE WITH CC-AA-103.

THE WORK DESCRIBED BELOW DOES NOT AFFECT ANY IN-SERVICE EQUIPMENT. SPECIAL INSTRUCTIONS ARE AS DESCRIBED IN EACH SECTION THE SCOPE AND BELOW. iWA #1 - SUB-PILE ROOM (CONCRETE AREA UNDER REACTOR VESSEL) TROUGH CLEANING, INSPECTION AND PARIAL REPAIR: ________________------_--------------_------------------- ________________-------------_-------_---_-_-------------

THE TROUGH IS THE DRAINAGE TRENCH AT THE SUB-PILE L 1 *' PAGE 0003 E C R Printout ECR 'TYPE: DCP ECR NUMBER: OC 06-00879 001 APPROVED'DISPOSITION:

/ ROOM PERIMETER.

THE TROUGH MUST BE THOROUGHLY CLEANED AND INSPECTED, TO DETERMINE IF REPAIRS ARE REQUIRED.

STANDING WATER SHOULD BE REMOVED FROM THE TRENCH. ALL LOOSE MATERIAL (DEBRIS, LOOSE AGGREGATE, ETC.) MUST BE REMOVED. MATERIAL IN THE TROUGH, AROUND THE PIPES THAT CONNECT TO THE SUMP SHOULD BE REMOVED. TROUGH SHOULD BE QUANTIFIED.

TROUGH %LOOR ARE VISUALLY NOTICED, PLACE A 24" LONG STRAIGHT EDGE IN THE TROUGH AND MEASURE THE DEPTH OF THE DEPRESSION.

EXTENT, AND LOCATION OF ANY POCKETS OR DEPRESSIONS GREATER THAN SUMP, PROVIDE ENGINEERING WITH MEASUREMENTS OF DEPTH, WIDTH AND HEIGHT OF ANY CONCRETE DAMAGE.

AT THE FOUR PIPES THAT PASS WATER FROM OUTSIDE OF THE SUB-PILE ROOM, NOTE AND INFORM ENGINEERING OF THE BOTTOM ELEVATION OF THE PIPE RELATIVE TO THE BOTTOM SURFACE OF THE TROUGH (E.G. PIPE BOTTOM IS 3/8" LOWER THAN BOTTOM OF TROUGH). GROUT REPAIRS CAN BE PERFORMED TO THE AREA AROUND THE PIPES TO THE SUMP AND THE PIPES FROM OUTSIDE THE SUB-PILE ROOM TO INSIDE, AS NEEDED, IN ACCORDANCE WITH SPECIFICATION OCIS 551-81-6 (AS A STRUCTURAL REPAIR). "MASTERFLOW 713 PLUS" OR "MASTERFLOW 928" SHALL BE USED FOR THE REPAIRS (SAFETY RELATED MATERIAL), AND IT SHALL BE MIXED IN ACCORDANCE WITH THE MANUFACTURER'S INSTRUCTIONS RATHER THAN THOSE IN THE SPECIFICATION.

TEST CUBE SAMPLES DO NOT NEED TO BE TAKEN AS DIRECTED IN THE SPECIFICATION, SINCE THIS APPLICATION DOES NOT RELY ON THE STRENGTH OF THE CURED GROUT. BASED ON A PRELIMINARY INSPECTION BY SAM MARKOS, THE AREAS WHERE A GROUT REPAIR IS DEFINITELY REQUIRED AROUND THE DRAIN PIPE ARE: BOTH PIPES TO THE SUMP, AT THE POINT WHERE THEY EXIT THE TROUGH, AND THE INBOARD SIDE OF THE PIPE THROUGH THE PEDESTAL WALL, AT AZIMUTH 270. THESE THREE PIPES REQUIRE REMOVAL OF ALL LOOSE MATERIAL AROUND THE PIPE, DOWN TO CLEAN, SOLIDLY SECURED AGGREGATE.

THE STATION GROUTING PROCEDURE PRIOR TO GROUTING.

CARE MUST BE TAKEN NOT TO CREATE ANY BLOCKAGES TO FLOW THAT WOULD CREATE STANDING WATER IN THIS AREA. OTHER REPAIRS TO THE TRENCH WILL BE SPECIFIED BY ENGINEERING FOLLOWING REVIEW OF THE DATA PROVIDED.

ALL IN PARTICULAR, ALL LOOSE OR EASILY LOOSENED DAMAGE TO ANY'AREAS OF THE WHERE DEPRESSIONS IN THE NOTIFY ENGINEERING OF THE DEPTH, 1/4" DEEP. I AT THE DRAIN PIPES FROM THE TROUGH TO THE THE AREA MUST 3E PREPARED IN ACCORDANCE WITH THE ABOVE SCOPE OF WORK DOES NOT ALTER THE DESIGN OR FUNCTION OF ANY PLANT SSC. ROUTINE TASKS. AFFECTED SSC TO ITS INTENDED DESIGN CONDITION.

CLEANING AND INSPECTION ARE ANY GROUT REPAIRS SERVE TO RESTORE THE COORDINATION WITH THE OCC IS IMPERATIVE TO MAINTAIN THE TROUGH AREA DRY DURING THE REPAIR AND CURING PROCESSES. . . .. . . . . .

PAGE 0004 E C R Printout ' 11 I ECR NUMBER: OC 06-00879 001 ECR TYPE: DCP APPROVED DISPOSITION:

AWA #1 PREPARED BY: P. KESTER I' REVIEWED BY: DAN FIORELLO AUTHORIZATION FOR THIS SCOPE IS PROVIDED TO GEORGE SEVCIK

' (OWP) BY HOWIE RAY (SMDE DESIGNEE FOR S. ,HUTCHINS) (SMDE) ON 10/24/06, 12:OO. AWA #2 - DRYWELL SUMP CLEANING AND INSPECTION:

________________-----------------------------

_________________-_--------_----------_------ THE DRYWELL SUMP COULD BE A SOURCE OF WATER INFILTRA-TION INTO THE CONCRETE.

DRAINED AND CLEANED S0,THAT THE STAINLESS STEEL LINER UNTIL THE INSPECTION IS COMPLETE.

THE SUMP SHOULD BE CLEANED SUFFICIENTLY SUCH THAT A VT-1 INSPECTION OF THE INTERIOR SURFACES OF THE SUMP LINER CAN BE PERFORMED.

THE RESULTS OF THE INSPECTION SHOULD BE PROVIDED TO ENGINEERING.

IF ANY FLAWS ARE FOUND, REPAIRS WILL BE SPECIFIED ACCORDINGLY.

THE SUMP INTERIOR SHOULD BE CAN BE INSPECTED FOR FLAWS OR DAMAGE.' TEMPORARY DAMMING SHOULD BE PLACED'TO PREVENT WATER FROM ENTERING THE SUMP I!. .'. I' I THE ABOVE SCOPE OF WORK DOES NOT ALTER THE DESIGN OR FUNCTION OF ANY PLANT SSC. ROUTINE TASKS. AWA #2 PREPARED BY: P. KESTER REVIEWED BY: DAN FIORELLO AUTHORIZATION FOR THIS SCOPE IS PROVIDED TO GEORGE SEVCIK (OWP) BY HOWIE RAY (SMDE DESIGNEE FOR S. HUTCHINS) (SMDE) ON 10/24/06, 12:OO. CLEANING AND INSPECTION ARE AWA #3 - DRYWELL FLOOR-TO-SHELL INTERFACE CLEANING, PREP FOR CAULKING:

A BEAD OF CAULK WILL BE APPLIED TO THE DRYWELL SHELL WHERE IT MEETS THE CONCRETE STEPPED CURBING AROUND THE PERIMETER OF THE CONCRETE DRYWELL FLOOR SLAB AT ELEVATION 10'-3". AND PREPARATION OF THE CONCRETE AND STEEL SURFACES FOR CAULKING, BUT DOES NOT INCLUDE THE INSTALLATION OF THE CAULKING.

REMOVED FROM THE INTERFACE.

HAND TOOLS (DENTIST PICK, SHOULD BE USED. SUFFICIENTLY ROUGH FOR ADHESION OF THE CAULK, AND THEREFORE MAY NOT REQUIRE ROUGHENING.

ASSURED BY INSPECTION. CONCRETE ADJACENT TO THE DRYWELL SHELL SHOULD BE ASSURED TO HAVE A ROUGHNESS EQUIVALENT TO 60 GRIT SANDPAPER, OR ROUGHER. BAND OF AT LEAST 1" ADJACENT TO THE CONCRETE.

ANY LOOSE OR POORLY ADHERED MATERIAL SHOULD BE REMOVED USING HAND .........................................................

THE SCOPE OF THIS AWA IS THE CLEANING ALL DEBRIS AND LOOSE CONCRETE SHOULD BE SMALL WIRE BRUSH, CHIPPING HAMMER, ETC.) AND A VACUUM THE CONCRETE SURFACE IS REPORTED TO BE THIS SHOULD BE A BAND OF AT LEAST 1" WIDTH OF THE STEEL SURFACE SHOULD ALSO BE PREPARED FOR A PAGE 0005 E C R Printout ECR NUMBER: OC 06-00879 001 ECR'TYPE:

DCP APPROVED'DI

/ SPOSITION: TOOLS SUCH AS A STIFF BRUSH, A PUTTY KNIFE OR SCOTCH-BRITE TO SSPC-SP 2 STANDARD. WELL ADHERED COAT,INGS DO NOT NEED TO BE REMOVED. THE ABOVE SCOPE OF WORK DOES NOT ALTER THE DESIGN OR FUNCTION OF ANY PLANT SSC. ROUTINE TASKS.

CLEANING AND INSPECTION ARE I* D AWA #3 ,$REPARED BY: P. KESTER I REVIEWED BY: DAN FIORELLO AUTHORIZATION FOR THIS SCOPE IS PROVIDED TO GEORGE SEVCIK (OWP) (SMDE) ON 10/24/06, 12:OO. BY ,HOWIE RAY (SMDE DESIGNEE FOR S. HUTCHINS)

AWA #4 - EXCAVATE ADDITIONAL CONCRETE FROM'THE BAY #5 --__________________

TRENCH ________________--__-----_---------_

_______________-------_-----------_---__--_-------------

MORE OF THE DRYWELL SHELL MUST BE EXPOSED AT THE BOTTOM OF THE BAY #5 TRENCH TO FACILITATE ADDITIONAL DRYWELL SHELL UT MEASUREMENTS.

THE DRYWELL ELEV 10'-3" FLOOR SLAB, REGION, ADJACENT TO THE DRYWELL SHELL. THE BAY #5 TRENCH IS IN I IN THE BAY #5 CONCRETE AT THE BOTTOM OF THE BAY #5 TRENCH SHALL BE EXCAVATED AS REQUIRED TO EXPOSE AN ADDITIONAL 3 -1/2", ' (+/-) SHALL BE ACROSS THE ENTIRE WIDTH OF THE TRENCH. BAND OF THE DRYWELL SHELL. THE BAND EXTREME CARE SHALL BE EXERCISED TO AVOID DAMAGE (NICKS, CUTS, SCRAPES) TO THE DRYWELL SHELL. ALSO NOTE THAT A VERTICAL'STEEL PLATE STIFFENER (APPROX 1" THICK) BOTTOM OF THE BAY #5 TRENCH. PARALLEL TO THE DRYWELL SHELL AND APPROXIMATELY 7" FROM THE SHELL. EXPOSED IN THE EXISTING TRENCH EXCAVATION. CARE SHALL BE EXERCISED TO AVOID DAMAGE (NICKS, CUTS, SCRAPES) TO THIS STIFFENER PLATE. IS EMBEDDED IN THE CONCRETE AT THE THE STIFFENER PLATE IS A PORTION OF THE TOP EDGE OF THIS PLATE IS EXTREME ALL WORK SHALL BE DONE WITH HAND TOOLS. ALL MATERIAL REMOVED SHALL BE QUARANTINED FOR FURTHER 1 - INSPECTION/TESTING AS REQUIRED.

DOCUMENT THE FINAL CONFIGURATION OF THE TRENCH (DEPTH (ATTENTION:

AND WIDTH) AFTER THE EXCAVATION.

FORWARD THIS INFORMATION TO THE PROJECT ENGINEERING TEAM HOWIE RAY). DIGITAL PHOTOGRAPHS SHALL BE TAKEN OF THE NEWLY EXPOSED DRYWELL SHELL IMMEDIATELY AFTER EXCAVATION IS COMPLETE.

DIGITAL PHOTOGRAPHS SHALL ALSO BE TAKEN OF I ' ,' PAGE 0006 E C R Printout I I ECR NUMBER: - OC 06-00879 001 ECR TYPE: DCP APPROVED DISPOSITION:

THE SURFACE OF THE EXCAVATED CONCRETE THAT WAS ADJACENT TO THE DRYWELL SHELL. ALL DIGITAL PHOTOGRAPHS FILES SHALL BE TRANSMITTED TO THE PROJECT ENGINEERING TEAM (ATTENTION:

HOWIE RAY). I I THE SCOPE OF THIS AWA DOES NOT ALTER OR IMPACT THE FUNCTION OF ANY PLANT SSC'S. ,',

• AWA PREPARED BY: DP KNEPPER - PEDM AWA REVIEWED BY: DAN FIORELLO AUTHORIZATION FOR THIS SCOPE IS PROVIDED TO JIM HEARNS (OWP) BY HOWIE RAY CSMDE DESIGNEE FOR S. HUTCHINS) (SMDE) ON 10/24/d6, 18:OO. AWA #5 - CAULK DRYWELL SHELL-TO-CONCRETE FLOOR JOINT:

.....................................

AT THE OUTBOARD PERIMETER OF THE ELEV. 10'-3" DRYWELL FLOOR, THE CONCRETE SLAB MEETS THE DRYWELL SHELL. THIS INTERFACE HAS BEEN PREPARED FOR CAULKING UNDER AWA #3. THE CAULK WILL BE APPLIED TO THAT JOINT UNDER THIS AWA. THE CAULK SHALL LAP ONTO THE CONCRETE AND STEEL SURFACES BY 1/4" TO 3/4" ON EACH SURFACE. THE CAULK IS TO FOLLOW THE CURB ELEVATION (INCLUDING THE SIDES AND TOPS OF THE CURBS), AND THE DIPS INTO THE TWO TRENCHES.

TRENCH SHOULD NOT BE CAULKED UNTIL ALL NDE WORK IS COMPLETED, EVALUATION A2152754-5 IS BEING DEVELOPED TO DOCUMENT THE TECHNICAL BASIS FOR THIS AWA, AND PROVIDES A DETAILED SKETCH OF THE CAULK CONFIGURATION ALONG WITH MANUFACTURERS INSTRUCTIONS.

THE CAULKING MATERIAL SHALL BE THIOKOL 2235M BY POLYSPEC.

THE INSTALLATION OF THE CAULKING MATERIAL IS ACCEPTABLE PROVIDED THAT CAULKING MATERIAL IS QUALIFIED TO BE USED INSIDE THE DRYWELL AS AUGMENTED QUALIFY, QA CLASS "A" OR BETTER.

THE SURFACE PREPARATION SHALL BE AS DESCRIBED IN AWA #3 OF THIS ECR, AND INSTALLATION SHALL BE IAW THE MANUFACTURER'S INSTRUCTIONS (EXCEPT THAT PRIMER, BACKER ROD AND BOND BREAKER TAPE ARE NOT REQUIRED).

REQUIRED FOR PREPARATION (PER AWA #3 OF THIS ECR) AND INSTALLATION (MIXING, POT LIFE, APPLICATION).

QUALIFICATION OF THE CAULK IS BEING FINALIZED.

CONCRETE-TO-STEEL INTERFACE, FOLLOWING THE CHANGES IN THE BAY 5 BUT PRIOR TO RECOATING THE STEEL. TECHNICAL QV VERIFICATION IS DBA I I I .. ! WORK SCOPE: 1- ADDITIONAL EXCAVATION DESCRIBED IN AWA #4 HAS BEEN COMPLETED.

SECTION 3.2.6 OF SPECIFICATION IS-328227-004 REV. 13, BUT FOR THE NEWLY EXPOSED STEEL AREA IN THE TRENCH (REF. AWA PERFORM UT OF DRYWELL SHELL IN THE BAY 5 TRENCH AFTER UT SCOPE IS SIMILAR TO THAT DESCRIBED IN PAGE 0007 E C R Printout (( ECR 'TYPE: DCP APPROVE? DI SPOS ITION : #4). 2- CLEAN/PREP STEEL AND CONCRETE SURFACES FOR CAULKING I AS DESCRIBED IN AWA #3 SHOULD FORM A CONTINUOUS BARRIER AROUND THE CIRCUMFERENCE OF THE CONCRETE FLOOR, WHERE IT MEETS THE STEEL DRYWELL SHELL. VT3) OF,. THE FINAL CAULK CONFIGURATION IN ACCORDANCE WITH 5- AND BAY 17 TRENCHES AS DESCRIBED IN SECTION 3.2.2.4.3 OF SPECIFICATION IS-328227-004 REV. 13. 3- INSTALL CAULKING AS DESCRIBED ABOVE. FINISHED CAULK

/ 4- NDE SHALL PERFORM A PSI (PRE-SERVICE INSPECTION - ' ASME SECTION XI REPAIR/REPLACEMENT PROGRAM. RECOAT THE DRYWELL SHELL SURFACE IN BOTH THE BAY 5 i 8 THIS AWA DOES NOT AFFECT ANY IN-SERVICE EQUIPMENT.

AWA #5 PREPARED BY: REVIEWED BY: DAN FIORELLO AUTHORIZATION FOR THIS SCOPE IS PROVIDED TO JOHN BURT (VENTURE)

BY F.H. RAY (SMDE DESIGNEE FOR S. HUTCHINS) (SMDE) ON 10/25/06, 13:30. NOTE REVISION OF THE ABOVE AWA #5: THE MAXIMUM LAP LENGTH OF THE CAULK ONTO THE CONCRETE AND STEEL HAS BEEN REDUCED FROM 1" TO 3/4" TO LIMIT THE AMOUNT OF MATERIAL' ADDED TO THE DRYWELL. P. KESTER AS REVIEWER OF THE ORIGINAL AWA, I HAVE REVIEWED AND AGREE WITH THE REVISED LAP LENGTH - DAN FIORELLO CHANGE APPROVED ON 10/26/06 AT 07:OO BY HOWIE RAY. JOHN BURT WAS NOTIFIED BY DAVE KNEPPER, AND A MARKED- UP SKETCH REFLECTING THE CHANGE WAS PROVIDED TO HIM. ~EVISION 2 TO THE AWA #5: iWA #5 AND ITS REVISION PROVIDE INSTRUCTIONS TO CAULK SURFACES BETWEEN THE DRYWELL VESSEL PLATE AND MASTERFLOW 928 GROUT MATERIAL.

THE SURFACES MUST BE DRY. THE BOTTOM OF THE TRENCH IN BAY 5 AND THE SEAM BETWEEN THE C0NCRETE.W STEEL ARE MOIST EVEN AFTER APPLYING MASTERFLOW 928. THEREFORE, THE CAULK CANNOT BE APPLIED. EXIST, PREPARE THE SURFACES AND INSTALL THE MINIMUM - _____ I IC, A1\m MBXTMr,M INCH OF THE CONCRETE IN THE TWO TRENCHES.

AWA #5 USED TO APPLY THE CAULK HOWEVER THE SURFACE AT IF THIS CONDITION CONTINUES TO 'I ALLOWED LAYEK J./A IIULLL ruvu Ay-a+----- - - GROUT IN ACCORDANCE WITH AWA #l. MATERIAL SHALL BE "747 RAPID- SETTING GROUT" MANUFACTURED BY BASF AND MIXING SHALL BE PLASTIC TO ACHIEVE A FINAL SETTING TIME OF 80 MINUTES. THE LAYER OF GROUT SHALL BE INSTALLED AT THE BOTTOM OF THE THE GROUTING PAGE 0008 E C R Printout ' #' I ECR NUMBER: APPROVE^

DISPOSITION:

I - OC 06-00879 001 ECR TYPE: DCP TRENCH AT MOIST SURFACES OVER EXISTING MASTERFLOW 928 HAVE BEEN PLACED WHERE CONCRETE MEETS THE DRYWELL VESSEL. OF 747 RAPID-SETTING GROUT IS TO COVER THE MOIST AREAS TO ALLOW PROPER APPLICATION OF THE CAULK. WAIT A MINIMUM OF 80 MINUTES FOR THE GROUT TO SET,BEFORE APPLYING ANY CAULK. ANY SAFETY RELATED FUNCTION.

THE REQUIRED STRENGTH IS MINImL AND IS PLACED TO FORM A SUITABLE SURFACE FOR CAULK.

BEFORE APPLICATION OF THE CAULK. THEREFORE, I THE MATERIAL MAY BE COMMERCIAL GRADE. THE PURPOSE OF THE ADDITIONAL LAYER THIS GROUT DOES NOT PERFQRM THE MATERIAL WILL BE CONFIRMED TO BE SET .I I. THIS AWA AND ITS'REVISIONS DO NOT AFFECT ANY IN SERVICE EQUIPMENT.

ROUTINE TASKS. CLEANING AND INSPECTION ARE iWA #5, REVISION 2 PREPARED BY: NIOGI, SUJIT (PIMS INPUT BY DJF) REVIEWED BY: DAN FIORELLO THIS AWA REVISION 2 IS APPROVED BY F. H. RAY FOR S. HUTCHINS (SMDE)

THIS AWA #5, REVISION 2 IS PROVIDED .TO DAVE RYAN AT 18:45 11/02/06 BY F.H. RAY I' I END OF AWA #5, REVISION 2 .........................................................

AWA #5 REVISION 3 BASED ON THE LATE DELIVERY OF THE 747 GROUT, IT IS PERMISSABLE TO USE THE BASF MASTERFLOW 928 GROUT. PER THE MANUFACTURE PRODUCT DATA SHEET, MASTERFLOW 928 WILL REACH A FINAL SET IN 4 HOURS. THE CONSISTANCY OF THE 928 SHOULD BE MIXED TO PLASTIC CONSISTANCY.

PER TELEPHONE WITH THE TECHNICAL REPRESENTATIVE OF POLYSPEC THE MANUFACTURER OF THIOKOL 2235M THE CAULK CAN BE APPLIED AFTER THE GROUT REACHES THE FINAL SET. AWA #5 AUTHORIZES THE USE OF MASTERFLOW 928. THE MINIMUM THINKNESS OF THE APPLICATION NEEDS TO BE CONSISTANT WITH THE EARLIER GUIDANCE FOR MASTERFLOW 928. REVISION 3 TO AWA #5 REVISION 3 PREPARED BY J. HALLENBECK REVIEWED BY:NIOGI, SUJIT THIS AWA REVISION 3 IS APPROVED BY:MAKAR, JOHN ;HIS AWA #5 REVISION 3 IS PROVIDED TO DAVE RYAN AT: 12:05 NOV 3, 2006 I I PAGE 0009 E c R Printout .I ECR NUMBER: OC 06-00879 001 ECR 'TYPE: DCP APPROVED'DI

/ SPO s ITION: END OF AWA #5 REVISION 3 AWA'#6 - USE OF BACKER ROD BEHIND CAULK JOINT: ........................................................

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0' SCOPE OF AUTHORIZED WORK: I BASED Old THE SIZE OF THE GAP BETWEEN THE DRYWELL CONCRETE FLOOR SLAB AND THE STEEL DRYWELL SHELL, IT IS DESIRED TO INSTALL BACKER ROD IN SOME AREAS TO MINIMIZE THE AMOUlyT OF CAULK NEEDED. THE BACKER ROD IS A POLYETHYLENE MATERIAL (204-07780)

THAT WILL BE COVERED BY THE CAULK, AND THEREFORE WILL NOT BE EXPOSED. THE INSTALLER ESTIMATES THAT 10' OF PERIMETER WILL REQUIRE ITS USE. THIS AMOUNT OF ROD WEIGHS ON THE ORDER OF A FEW OUNCES.

RELATIVE TO THE MATERIAL WEIGHTS IN THE SUCTION STRAINER CLOGGING CALCULATION, THE WEIGHT IS INSIGNIFICANT COMPARED TO THE CALCULATION WEIGHTS OF 150 POUNDS FOR DUST, DIRT AND CONCRETE, AND 25 POUNDS FOR MISCELLANEOUS ADDITIONAL DEBRIS. IN ADDITION, THE BACKER ROD WILL EITHER FLOAT , OR MELT AND FLOWN DOWN THROUGH THE GAP BETWEEN THE CONCRETE AND THE STEEL SHELL IF EXPOSED TO EXTREME TEMPERATURE.

THEREFORE, THE BACKER ROD WILL NOT GET TO THE SUCTION STRAINERS TO CONTRIBUTE PRIMARILY, THOUGH, THE BACKER ROD WILL BE WEDGED INTO THE GAP BETWEEN THE SHELL AND THE CONCRETE, AND IS THEREFORE VERY UNLIKELY TO BE DISLODGED BY ANY DBA IN THE DRYWELL. THEIR ,CLOGGING.

MARK CARLSON AND TIM TRETTEL WERE CONSULTED FOR FIRE THE AMOUNT AND THE LOCATION, USE OF THE BACKER ROD IS ACCEPTABLE WITH REGARD TO FIRE LOADING ADDED TO THE DRYWELL. THEREFORE AUTHORIZATION IS GIVEN TO UTILIZE BACKER ROD IN THIS APPLICATION. PROTECTION CONCERNS, AND THEY INDICATED THAT BASED ON PREPARED BY: P. KESTER CHANGES TO THE ABOVE AWA WERE MADE BY THE REVIEWER BASED ON THE PREPARER INPUT. AS STATED IN CC-AA-103, THIS WORK IS BEING PERFORMED AT RISK AND DOES NOT AFFECT ANY THIS AUTHORIZATION IS GIVING TO TOM BADDERS, VENTURE PLANNING.

INDEPENDENTLY REVIEWED BY S. MARKOS THIS AWA HAS BEEN REVIEWED AND APPROVED BY THE OC SDEM S. HUTCHINS, ON 10/26/06 8 20:27 IN SERVICE EQUIPMENT:

PAGE E c R Printout ' I' I ECR TYPE: DCP I. APPROVED DISPOSITION: END OF AWA

1. 6 AWA #7 - REPAIR OF VOID IN THE TROUGH ADJACENT TO SUMP *****************************************

I 11 1 I' 1-8: SCOPE OF WORK: II, 1, ~ALK DOWN BY WILLIAMS COATING INC. REVEALED T~TAT APPROXIMATELY 4 INCH WIDE VOID EXIST IN THE TROUGH ADJACENT TO THE SUMP 1-8. FOREIGN GLASS OBJECT IS LODGED IN TO THE VOID. MUCH AS POSSIBLE BY,BREAKING IT IN*TO SMALL PIECES AND REMOVING THE BROKEN GLASS PIECES THE VOID SPACE SHALL BE\' FILLED WITH GROUT WITH "MASTERFLOW 713 PLUS" OR IIMASTERFLOW 928". APPLICATION IN THE DRYWELL PER AWA #1. I' ALSO IT APPEARS THAT A I I I' THE, OBJECT SHALL BE 'REMOVED AS I I VACUUM CLEANING *HE BROKEN GLASS PIECES. ALL, PIECES I ' SHALL BE RETAINED FOR LATER EVALUATION. AFTER THIS HAS BEEN APPROVED FOR SPECIAL INSTRUCTIONS:

ALL THE STEPS FOR CLEANING, SURFACE PREPARATION, MIXING AND PLACEMENT OF GROUT SHALL BE AS DELINEATED IN AWA #1 AND MANUFACTURER INSTRUCTIONS SHALL BE FOLLOWED.

IF THE VOID IS MORE THAN 2" WIDE, 33% BY WEIGHT OF CLEAN, DAMP 3/8" PEA GRAVEL MEETING THE REQUIREMENTS OF ASTM C33 MAY BE ADDED TO THE MIXTURE. SEVENTEEN POUNDS OF PEA GRAVEL SHALL BE ADDED TO EVERY 50 POUNDS OF GROUT. GROUT AND PEA GRAVEL SHALL BE AT ROOM TEMPERATURE (APPROXIMATELY 70 DEGREES F). THE GROUT MIXTURE SHALL BE COMPACTED WITH A STEEL ROD OR SIMILAR DEVICE TO ELIMINATE VOIDS AND CONSOLIDATE THE GROUT MIXTURE AS IT BEING PLACED IN THE VOID. I THE AWA DOES NOT AFFECT ANY IN SERVICE EQUIPMENT.

CLEANING AND INSPECTION ARE ROUTINE TASKS. REPAIRS SERVE TO RESTORE THE AFFECTED SSC TO ITS INTENDED DESIGN CONDITION.

ANY GROUT iWA #7 PREPARED BY S. NIOGI. REVIEWED BY: P. TAMBURRO AND DAN FIORELLO THIS AWA IS APPROVED BY F.H. RAY FOR S, HUTCHINS (SMDE) THIS AWA IS PROVIDED TO G. SEVCIK AND B. MAZE AT 1930 ON 10/28/06 BY F.H. RAY. 0010 ENSURE ALL DEBRIS REMOVED FROM THE VOID IN THE CONCRETE TROUGH IS RETAINED FOR LATER EVALUATION. NOTE REVISION OF THE AWA #7: IF THE WIDTH OF THE VOID **+**++***+********REVISION 1 TO AWA #?***************e

~ PAGE 0011 E C R Printout I' ECR NUMBER: OC 06-00879 001 ECR'TYPE:

DCP APPROVE,D DISPOSITION

IS 2 INCHES OR SMALLER PEA GRAVEL IS NOT REQUIRED TO BE ADDED TO THE GROUT MIXTURE. I' ~EVISION 1 TO AWA #7 IS PREPARED BY SUJIT NIOGI REVISION 1 TO AWA #7 WAS REVIEWED BY DAN FIORELLO (I I I ; AWA 7, REVISION 1 AUTHORIZATION:

AND I RROVIDED TO D. RYAN AND J. BURT AT 1100 THIS AWA IS APPROVED BY F.H. RAY FOR S. HUTCHINS (SMDE) i', I I ' ON 10/30/06 BY F.H. RAY. I' (I ....................................................

/ iWA #8 SgALING TRENCH IN BAY 5 ,I SCOPE OF WORK AWA #5 PROVIDES INSTRUCTIONS TO CAULK SURFACES BETWEEN THE DRYWELL VESSEL PLATE AND THE CONCRETE IN THE TWO TRENCHES.

TO APPLY THE CAULK THE SURFACES MUST BE DRY. HOWEVER THE SURFACE AT THE BOTTOM OF THE TRENCH IN BAY 5 AND THE SEAM BETWEEN THE CONCRETE AND STEEL ARE MOIST. THEREFORE THE CAULK CANNOT BE APPLIED. IF THIS CONDITION CONTINUES TO EXIST, PREPARE THE SURFACES AND INSTALL THE MINIMUM ALLOWED LAYER (1 INCH) OF GROUT IN ACCORDANCE WITH AWA #l. THE LAYER OF GROUT SHALL BE INSTALLED AT THE BOTTOM OF THE TRENCH AT MOIST SURFACES WHERE EXISTING CONCRETE MEETS THE DRYWELL VESSEL. THE PURPOSE OF THE LAYER OF GROUT IS TO COVER THE MOIST AREAS TO ALLOW PROPER APPLICATION OF THE CAULK. WAIT A MINIMUM OF 24 HOURS FOR THE GROUT TO CURE. iPPLY THE CAULK ON DRY SURFACES BETWEEN THE GROUT AND THE STEEL VESSEL AND OVER LAP THE AREAS WHERE OTHER CAULKING HAS ENDED. THE AWA DOES NOT AFFECT ANY IN SERVICE EQUIPMENT CLEANING AND INSPECTION ARE ROUTINE TASKS. REPAIRS SERVE TO RESTORE THE AFFECTED SSC TO ITS INTENDED CONFIGURATION.

ANY GROUT AWA #8 PREPARED BY P,. REVIEWED BY: DAN FIORELLO THIS AWA IS APPROVED BY F.H. RAY FOR S. HUTCHINS ( SMDE THIS AWA IS PROVIDED TO DAVE RYAN AT 1600 10/30/06 BY F.H. RAY. TAMBURRO ..

PAGE 0012 E C R Printout . ECR NUMBER: OC 06-00879 001 I .I ECR TYPE: DCP APPROVED' DISPOSITION: END OF AWA 8 ' .....................................................

AWA #9 - LEAK TEST OF TROUGH INSIDE THE PEDESTAL, EL.10'-9" UNDER VESSEL SCOPE OF WORK THE TROUGH IS APPROXIMATELY 8" DEEP AND LOCATED THERE ARE FOUR 4" DIAMETER PIPE SLEEVES AT 90 DEGREES APART THROUGH THE 4 FEET REACTOR PEDESTAL WALL FOR DRAINING WATER FROM

'DRYWELL FLOOR &L.' 10 I - 3" TO THE SLEEVE IS 10'-3". 1-8 BY TWO 2" DIAMETER PIPE SLEEVES. ELEVATION OF THE 2" DIAMETER PIPE SLEEVE IS 10'-1 1/48'. THIS AWA #9 PROVIDES THE INSTRUCTIONS TO PLUG THESE SIX SLEEVES (FOUR 4" DIAMETER AND TWO 2" DIAMETER).

INSIDE THE REACTOR SUPPORT PEDESTAL AT EL.10'-9".

TROUGH. THE INVERT ELEVATION OF THE 411 DIAMETER PIPE THE TROUGH IS CONNECTED TO THE SUMP THE INVERT THE SLEEVES CAN BE PLUGGED USING TAPERED SILICONE RUBBER PLUGS, MCMASTER-CARR CATALOG PART NO. 9277K75 FOR 4" DIAMETER PIPE SLEEVES (FOUR REQUIRED)

AND MCMASTER-CARR CATALOG PART NO. 9277K79 FOR 2 DIAMETER PIPE SLEEVES (TWO REQUIRED).

THESE PLUGS SHALL BE INSERTED FROM INSIDE THE PEDESTAL IN TO THE PIPE SLEEVES. AFTER THE PLUGS ARE INSERTED IN TO THE SLEEVES THE SURFACE AROUND THE PLUGS BETWEEN THE PIPE SLEEVE AND THE PLUG SHALL BE COVERED WITH DUCT TAPE OR EQUAL AS APPROVED BY THE CHEMISTRY AND OPERATION DEPARTMENT.

BEFORE THE TAPE IS APPLIED. THE SURFACES MUST BE DRY ALTERNATE TYPE PLUGS AS APPROVED BY ENGINEERING MAY BE UTILIZED IF REQUIRED.

BEFORE FILLING THE TROUGH WITH WATER, USING A THIN STEEL NARROW RULER OR THIS NARROW FLAT BAR (OR EQUIVALENT) TO VERIFY THAT NO ADDITIONAL VOIDS EXIST IN THE TROUGH THAT COULD ADD TO THIS LEAKAGE PATH. IF SIGNFICANT VOIDS ARE DISCOVERED, REPAIR USING GROUT. REPAIR STEPS FOR CLEANING, SURFACE PREPARATION, MIXING AND PLACEMENT OF GROUT SHALL BE AS DELINEATED IN AWA #1 AND MANUFACTURER INSTRUCTIONS SHALL BE FOLLOWED.

IF REPAIR BY GROUT IS PERFORMED, ALLOW 24 HRS FOR CURING PRIOR TO PLUGGING THE DRAIN HOLES OR PERFOMING THIS PMT TEST OF THE SUBJECT TROUGH.

WATER IN BAYS 5 ANTI 17 TRENCHES SHOULD BE VACUUMED OUT. FILL THE TROUGH WITH WATER AT LEAST 7" DEEP AND MONITOR THE HEIGHT OF THE WATER FOR TWO HOURS AND CAREFULLY RECORD THE DEPTH. WATER TO 7" HEIGHT IF ANY WATER IS LOST DURING THE FIRST TWO HOURS. HEIGHT OF WATER EVERY ONE HOUR FOR NEXT FOUR HOURS.

REFILL THE TROUGH WITH AFTER THE TROUGH IS REFILLED, MEASURE THE I I I I t. 4 ..

PAGE 0013 E C R Printout ECR NUMBER: OC 06-00879 001 APPROVED DISPOSITION:

I. ECR'TYPE:

DCP I I DISTANCES APART USING THE EXACT LOCATIONS EACH TIME. I: ACCEPTANCE CRITERIA - THE LEVEL AFTER 4 HOURS SHALL N,OT I HAVE DROPPED MORE THAN 1/4 INCH WITH A MEASURING ,I I THE HEIGHT OF WATER SHALL BE MEASURED AT 90 DEGREE I \ I 'I ACCURACY OF 1/16 INCH THE AWA DOES NOT AFFECT ANY IN SERVICE. EQUIPMENT.

CLEANING AND AND THE TAPE SHALL BE REMOVED AFTER TPE LEAK TEST AND THE AFFECTED AREA OF,, THE SSC SHALL:BE RESTORED TO ITS INTENDED CONFIGURATION.

THIS AUTHORIZATION IS GIVEN TO TOM BADDER OF SENTIJRE 'I 1. ' INSPECTION ARE ROUTINE TASKS. ALL PLUGS 'I I I I I I PLANNING.

AWA #9 PREPARED BY NIOGI, SUJIT 'I REVIEWED BY: PI TAMBURRO THIS AWA IS APPROVED BY SP HUTCHINS (SMDE) THIS AWA IS PROVIDED TO DAVE RYAN AT 1600 11/01/06 BY. F.H. RAY REVISION 1 TO AWA 9 NOTE THAT REVISION 1 TO AWA 9 CHANGED THE ACCEPTANCE CRITERIA TO A DROP IN WATER LEVEL OF 1/4 INCH WITH A MEASURING ACCURACY OF 1/16 INCH. THE PURPOSE OF THE TEST IS CHECK FOR ANY GROSS LEAKAGE FROM THE TROUGH THROUGH CRACKS AND VOIDS.

THERE WILL BE SOME LOSS OF WATER THROUGH EVAPORATION.

ALSO SINCE CONCRETE IS PERMEABLE, THERE WILL BE SOME LOSS OF WATER THROUGH SEEPAGE INTO THE SOUND CONCRETE.

I I REVISION 1 TO AWA 9 PREPARED BY: DAN FIORELLO ~EVISWION 1 TO AWA 9 REVIEWED BY PETE TAMBURRO THIS AWA REVISION HAS BEEN PROVIDED TO DAVE RYAN AND JOHN BURT AT 15:OO ON 11/2/2006 BY F.H. RAY. ~EVISION 1 TO AWA 9 APPROVED BY: F.H. RAY FOR s. HUTCHINS AS SMDE. END OF AWA #9 &ISON z TO AWA #9 FOR BETTER ALARA PRACTICE:

WATER LEVEL IN THE TROUGH AT 7" WILL BE MARKED ON THE REACTOR PEDESTAL WALL AT ONE LOCATION.

A CAMERA WILL BE FIXED ON THE MARK TO PAGE 0014 , E C R Printout ' ECR NUMBER:

OC 06-00879 001 I I ECR TYPE: DCP APPROVED DISPOSITION:

FACILITATE MONITORING OF THE TROUGH WATER LEVEL WITH RESPECT TO THE LEVEL MARK ON THE PEDESTAL WALL. FINAL AND DEPTH. RESULTS OF THE FIELD TEST WILL BE DOCUMENTED IN THE W.O. I FIELD VERIFICATIONS WILL BE PERFORMED FOR,,WATER LEVEL *I 'I CREM FOR ACCEPTANCE.

I , +HIS REVISION OF THIS AWA DOES NOT AFFECT ANY,TN SERVICE EQUIPMENT.

THIS AWA IS GIVEN TO TOM BADDER OF VENTURE.

,/: PREPARED BY S. MARKOS REVIEWED BY: JOHN A. CAMIRE I' .A 1, APPROVED BY SMDE : S .,( HUTCHINS I8 ,I ' I I L I I I I I OF AWA #9, REV. 2 .......................................................... - 1.1 PROBLEM DEFINITION: DURING 11R, TWO TRENCHES WERE CUT FROM THE CONCRETE FLOOR WHERE IT MEETS THE DRYWELL SHELL TO EVALUATE SHELL THICKNESS AND TO REMOVE PLUG SAMPLES IN BAYS 5 AND 17. AFTER EVALUATION AND REPAIR, THE SHELL WAS SPRAY COATED IN THE TRENCH AREAS, FILLED UP WITH DOW CORNING 3-6548 SILICONE RTV FOAM AND SEALED AT THE TOP BY POURING A PROTECTIVE SEALING LAYER OF PROMATEC LOW DENSITY SILICONE ELASTOMER.

IT WAS EVIDENT AFTER A 12R INSPECTION OF THE AREA, THAT WATER WAS SEEPING INTO THE TRENCHES.

PROBABLE SOURCES OF WATER MAY BE VARIOUS COMPONENT (E.G. VALVE) LEAKAGES, FROM DRAIN TANKS, AND (C): EXCESS WATER FROM OUTAGE ACTIVITIES (E.G. CRD CHANGES).

TRENCH AREAS WERE VISUALLY INSPECTED AGAIN (WITHOUT REMOVING THE FOAM COVER)

WALKDOWN WAS CONDUCTED DURING A FORCED OUTAGE. THE AREAS WERE FOUm, DRY. STRUCTURAL MONITORING INSPECTIONS NO SIGNS OF CORROSION OF THE INNER SURFACE OF EXPOSED STEEL SHELL IN THE TRENCHES WAS FOUND. THE PRESENCE OF WATER IN THE TRENCHES WAS OBSERVED IN 16R REFUELING OUTAGE IN 1997. IN THE 17R REFUELING OUTAGE, NO SIGN OF WATER WAS OBSERVED IN THE TRENCHES.

IN THE 18R REFUELING OUTAGE DRYWELL INSPECTION THERE IS NO MENTION OF WATER PRESENCE IN THE TRENCHES. (A): (B): SPILLS IN APRIL 1994, THE WHEN A DURING THE 1995 I I ,t I I I DURING 1R21, AFTER THE REMOVAL OF THE FOAM COVER, WATER WAS DISCOVERED IN THE THIS WATER WAS VACUUMED OUT, BUT THE TRENCH SOON REFILLED INDICATING THAT WATER WAS CONTAINED IN OR AROUND THE SLAB. I TRENCH IN BAY 5. THE FLOOR SLAB IS POURED AGAINST THE PAGE 0015 *. E c R Printout . ECR NUMBER: OC 06-00879 001 APPROVED DISPOSITION:

\ I ECR TYPE: DCP BOTTOM OF THE 'DRYWELL SHELL. WATER SAMPLES SHOWED THAT THE WATER IS NEUTRAL TO WEAK BASIC. INERTED WITH NITROGEN.

WEAK BASIC WATER DO NOT FORM AN AGGRESSIVE ENVIRONMENT THAT COULD LEAD TO CORROSION OF THE DRYWELL STEEL SHELL. THIS HAS BEEN CONFIRMED WITH VISUAL IVSPECTION OF THE INNER SURFACE OF THE DRYWELL EXPOSED SHELL IN INDICATES THAT (A): PROMATEC LDSE IS NO LONGER ACTING AS A SEAL TO PREVENT INTRUSION OF SURFACE WATER, AND (B): DOW CORNING RTV FOAM IS RETAINIIdG THE WATER REACHING THE TRENCHES; THE POTENTIAL SOURCES OF THE WATER ARE DIRECT LEAKAGE INTO THE FLOOR-TO-SHELL GAP DUE TO STANDING WATER ON THE FLOOR OR WATER RUNNING DOWN THE INTERIOR OF THE DRYWELL SHELL. IN ADDITION THE WATER COULD ALSO BE TRAVELING THROUGH CRACKS OR CONSTRUCTION JOINTS IN THE CONCRETE SLAB, COMING FROM THE TROUGH AROUND THE INNER FACE OF THE REACTOR PEDESTAL, HOLES EXIST IN THE SUMP LINER. CHEMICAL ANALYSIS OF WHEN THE PLANT IS AT POWER THE DRYWELL IS LACK OF OXYGEN AND NEUTRAL TO I' THE AREA OF THE TRENCHES.

THE ABOVE OBSERVATION .I OR FROM THE 1-8 SUMP IF INSPECTION OF THE SUMP LINER SHOWS THAT IT IS IN GOOD CONDITION WITH NO HOLES. THEREFORE THE SUMP IS NO LONGER'CONSIDERED AS A POSSIBLE SOURCE FOR THE WATER. AFTER REMOVING DEBRIS FROM TROUGH AROUND THE INNER FACE OF THE REACTOR PEDESTAL (PER AWA #1) A VOID WAS FOUND IN CONCRETE IN THE BOTTOM OF THE TROUGH IT IS POSSIBLE THAT THIS VOID ALLOWS WATER TO BYPASS THE TROUGH ROUTING ARRANGEMENT TO THE 1-SUMP AND ALLOWS WATER TO ENTER THE CONCRETE FLOOR AND MIGRATE THROUGH CRACKS OR CONSTRUCTION JOINTS TO THE TRENCH IN BAY 5. AS A RESULT AWA # 7 WAS ISSUED TO THE FIELD TO REPAIR THIS VOID AND ELIMINATE THIS LEAKAGE SOURCE INTO THE CONCRETE FLOOR. (IR 00550437).

1.2-SCOPE:

THIS ECR THEREFORE ADDRESSES SEVERAL TOPICS: 1.2.1-THE GAP BETWEEN THE DRYWELL SHELL AND THE CONCRETE FLOOR SHALL BE CAULKED AT THE INTERFACE.

i .2.2 -THE GAP BETWEEN THE DRYWELL SHELL AND THE TRENCH i.2.3-THE EXISTING TRENCH IN BAY 5 IS EXCAVATED FURTHER SIDES SHALL BE CAULKED AT THE INTERFACE.

TO DETERMINE THE CONDITION OF THE DRYWELL SHELL IN THAT AREA. ACTIONS ARE SPECIFIED FOR FINISHING THE TRENCH SURFACES AFTER THE UT INSPECTIONS ARE COMPLETED.

' I '. I I I I ..

PAGE 0016 'I E C R Printout I ECR NUMBER: OC 06-00879 001 ECR 'TYPE: DCP , APPROVED / DISPOSITION:

1.2.4- INSTRUCTIONS FOR CLEANING AND INSPECTION OF THE DRYWELL SUMP WERE PROVIDED UNDER AWA #2 TO DETERMINE IF ANY REPAIRS ARE REQUIRED.

RESULTS WILL BE FORWARDED TO ENGINEERING FOR EVALUATION UNDER THE STRUCTURAL MONITORING THE , 1' PROGRAM. 1.2.5-THE TROUGH INSIDE OF THE SUB-PILE ROOM (THE AREA INSIDE OF THE PEDESTAL AT ELEVATION 10'-3) AND THE PIPES THAT CONNECT IT TO THE AREAItOUTSIDE OF THE PEDESTAL AND THE,,SUMP WERE 1NSP.ECTED UNDER REPAIRS ARE NEEDED AROUND THE PIPES CONNECTING SUB-PILE ROOM, AND THE VOID IN THE TROUGH. THEREFORE THESE REPAIRS ARE ADDRESSED IN THIS ECR . 1.2.6-THE TROUGH INSPECTION ALSO IDENTIFIED LOW POINTS IN THE TROUGH. WITHOUT ACTION Is JUSTIFIED IN THIS ECR. AWA #I. THE TROUGH TO THE SUMP, THE AREA OUTSIDE OF THE THE RESULTS I~ICATED THAT CONCRETE ACCEPTANCE OF THESE LOW POINTS 1.2.7-INSPECTIONS IN THE SUB-PILE ROOM REVEALED THAT THE RAISED FLOOR SLAB IS DEGRADED, WITH EXPOSED AGGREGATE.

THIS CONDITION IS ADDRESSED IN THIS ECR, INCLUDING JUSTIFICATION FOR CONTINUED OPERATION UNTIL REPAIRS ARE DETERMINED AND IMPLEMENTED DURING A FUTURE REFUELING OUTAGE, IF DESIRED (SEE ATTACHED DESIGN ATTRIBUTES AND IR 54604 9) I .I I I I' \ I I I 1.3 ECR TYPE AND CLASSIFICATION:

BASED ON "NO" ANSWERS TO SOME OF THE SCREENING QUESTIONS OF CC-AA-103 ATTACHMENTS F AND G, THIS ECR IS CLASSIFIED AS A DESIGN CHANGE PACKAGE.

SSC'S ARE AFFECTED. SAFETY RELATED i .4 A TECHNICAL TASK RIGOR/RISK ASSESSMENT WAS PERFORMED TECHNICAL TASK RIGOR/RISK ASSESSMENT:

PER HU-AA-1212.

CONDUCTED ON 10/18/06.

FOR THE TASK OF DETERMINING THE SOURCE AND CONSEQUENCES OF THE WATER (ADDRESSED IN A2152754 E06, NOT IN SCOPE OF THIS ECR), A RISK RANK OF 2 WAS DETERMINED. AN EVALUATION TEAM OF MULTIPLE SME'S WAS ASSEMBLED, AND IT WAS DETERMINED THAT AN INDEPENDENT THIRD PARTY REVIEW WAS REQUIRED.

THE SCOPE OF THIS ECR IS TO IMPLEMENT THE RESOLUTIONS OF THAT TECHNICAL TASK. A RISK RANK OF 3 WAS DETERMINED.

ON-SITE INDEPENDENT THIRD PARTY REVIEW. THE INITIAL BRIEF FOR THIS TASK WAS FOR THE SCOPE OF THIS ECR, THEREFORE THIS ECR REQUIRES AN

i. 0 SOLUTION / TECHNICAL EVALUATION:

E C R Printout ECR NUMBER:

OC 06-00879 001 ECR'TYPE:

DCP 4, I APPROVED DISPOSITION:

/ _______________--------_--

________________----------

2.1 DESIGN CHANGE ATTRIBUTES:

11 DESIGN CHANGE ATTRIBUTES AND INPUTS HAVE BEEN REVIEWED I' PER'ATTACHMENT IA OF CC-AA-102, AND ADDITIONAL GUIDANCE PROVIDED IN ATTACHMENT 1 OF CC-MA-102-1001.

It THIS REVIEW IS PROVIDED IN ATTACHMENT 1 OF THIS ECR. I 4 I* 2.2 CONFIGURATION ACTIVITIES IMPACT REVIEW: CONFIGURATION CONTROL ACTIVITIES HAVE BEEN REVIEWED IN ACCORDANCE WITH THE REQUIREMENTS OF ATTACHMENT 7 OF CC- AA-102 AND ADDITIONAL GUTDANCE PROVIDED IN ATTACHMENT 7A OF CC-MA-102-1001,8 ATTACHMENTS a 1 ANDl'2 OF THIS ECR.

' REVIEW IS D'OCUMENTED IN 4 I' I' 2.3 PROGRAM IMPACT REVIEW PROGRAM ACTIVITIES HAVE BEEN REVIEWED IN ACCORDANCE WITH THE REQUIREMENTS OF ATTACHMENT 8 OF CC-AA-102 AND ADDITIONAL GUIDANCE PROVIDED IN ATTACHMENT 8A OF CC-MA- 102-1001.

THIS REVIEW IS DOCUMENTED IN ATTACHMENTS 1 AND 2 OF THIS ECR. I1 2.4 SOLUTION:

THE REPAIRS SPECIFIED UNDER THIS ECR ARE INTENDED TO CONTROL WATER FLOW IN THE BOTTOM OF THE DRYWELL. ALTHOUGH DETERMINED TO BE ACCEPTABLE IN A2152754 E06*, IT IS ,DESIRABLE TO MINIMIZE THE AMOUNT OF WATER IN THE PORES AND SMALL SPACES IN AND AROUND THE DRYWELL CONCRETE FLOOR SLAB AT ELEVATION 10'-3". THE SUMP HAS BEEN INSPECTED AS DIRECTED IN AWA #2 TO MINIMIZE ITS POTENTIAL AS A SOURCE OF LEAKAGE INTO THE SLAB. STAINLESS STEEL LINER IS IN GOOD CONDITIONS AND HAS NO HOLES. THEREFORE THIS SOURCE OF THE LEAKAGE IS ELIMINATED AS A LEAKAGE SOURCE, (A2152754-13).

TO DO THIS, VT-1 INSPECTION OF THE SUMP SHOWS THAT THE ;HE TROUGH AREA HAS ALSO BEEN INSPECTED, AND WILL BE REPAIRED AS REQUIRED TO DIRECT FLOW TO THE SUMP (BY REPAIRING THE CONCRETE AROUND THE PIPES). REMOVING DEBRIS FROM TROUGH AROUND THE INNER FACE OF THE REACTOR PEDESTAL (PER AWA #1) A VOID WAS FOUND IN THE CONCRETE IN THE BOTTOM OF THE TROUGH (IR 00550437).

THIS VOID MAY ALLOW WATER TO BYPASS THE TROUGH ROUTING ARRANGEMENT TO THE 1-8 AND ALLOWS WATER TO THOUGH CRACKS AND CONSTRUCTION JOINTS IN THE FLOOR TO THE TRENCH IN BAY 5. AS A RESULT AWA # 7 WAS ISSUED TO REPAIR THIS VOID AND ELIMINATE THIS LEAKAGE SOURCE INTO THE CONCRETE FLOOR. ELIMINATE THE LEAKAGE SOURCE, WHICH CONTINUES TO FILL THE BAY 5 TRENCH. AFTER ENTER THE'CONCRETE FLOOR, WHICH ALLOWS WATER TO MIGRATE THE REPAIR OF THE TROUGH SHOULD I' . I ENGINEERING

& FIELD PERSONNEL ALSO PERFORMED ADDITIONAL I

PAGE 0018 I ,I E C R Printout ' I ECR NUMBER: 00879 001 ECR TYPE: DCP APPROVED'DISPOSITION:

INSPECTIONS OF THE FULL PERIMETER SURFACE OF THE TROUGH I TO ENSURE NO OTHER VOIDS EXIST. ONLY MINOR SUPERFICIAL I DEFECTS WERE IDENTIFIED AND DETERMINED NOT TO NEED I I I* I REPAIRS. I IN ADDITION, THE PERIMETER OF THE SLAB WILL BE CAULKED TO THE STEEL VESSEL TO PREVENT WATER FROM ENTERING THE GAP AT THIS INTERFACE. THESE REPAIRS SHOULD ELIMINATE I' THE PRI~Y~ARY FLOW PATH INTO THE SLAB AREA. I THE TRENCH AT BAY 5 WILL BE EXCAVATED SEVERAL INCHES DRYWELL SHELL. STEEL SHELL WILL'BE GROUTED, CAULKED AND THE STEEL DEEPER TO ALLOW FOR FURTHER UT INSPECTION OF THE THEN THE NEW CONCRETE' EDGES AGAINST THE SHELL EXPOSED AREA WILL BE COATED. OF THE RAISED SLAB IN THE SUB-PILE ROOM, AND THE LOW POINTS IN THE TROUGH DO NOT SIGNIFICANTLY AFFECT THE CONTROL OF WATER IN THIS AREA. THEREFORE NO REPAIRS ARE REQUIRED FOR THESE CONDITIONS AT THIS TIME. THIS CONCLUSION WAS DOCUMENTED AS PART OF THE STRUCTURE MONITORING PROGRAM ER-OC-450 (REF. R2091380-01

& 02) - THE DEGRADATION 2.5 TECHNICAL EVALUATION:

THE DESIGN SOLUTIONS ARE EXPLAINED HERE, AND SUPPORTED BY THE ATTACHED DESIGN ATTRIBUTES.

WATER HAS BEEN FOUND IN THE TRENCHES OF THE 10'-3" DRYWELL FLOOR SLAB DURING SEVERAL PAST INSPECTIONS.

JUSTIFIED IN IR 546049-02* (SEE NOTE AT END OF DAR). AS I I I I THE PRESENCE OF THIS WATER IS NOT DETRIMENTAL TO THE STEEL DRYWELL SHELL. HOWEVER, CAULK WILL BE INSTALLED AT THE INTERFACE BETWEEN THE CONCRETE AND THE DRYWELL SHELL TO MINIMIZE THE AMOUNT OF WATER ENTERING THE GAP BETWEEN THE CONCRETE SLAB AND THE SHELL. THE CAULK WILL FOLLOW THE CONTOUR OF THE EDGE OF THE CONCRETE ALONG THE STEEL SHELL, GOING UP AND DOWN THE CHANGES IN CURB ELEVATION AND INTO THE DEPRESSIONS OF THE TRENCHES. MATERIAL POTENTIALLY FOULING THE SUCTION STRAINERS BECAUSE A GREATER AMOUNT OF MATERIAL (SILICONE FOAM AND ELASTOMER)

WAS REMOVED FROM THE TRENCHES AND IS NOT BEING REPLACED, REFER TO TECHNICAL EVALUATION A2152754-05 FOR ASSESSMENT OF THE IMPACT ON THE SUCTION STRAINERS THE CAULK DOES NOT INCREASE THE AMOUNT OF ;HE TRENCH IN BAY 5 WAS EXCAVATED APPROXIMATELY 311 DEEPER TO EXPOSE THE DRYWELL SHELL FOR ACCESS FOR UT MEASUREMENTS. THE MINOR AMOUNT OF CONCRETE REMOVED HAS NO IMPACT ON THE STRUCTURAL INTEGRITY OF THE SLAB SINCE THE SLAB IS PRINCIPALLY A FILL LAYER TO PROVIDE A LEVEL FLOOR (EXCEPT FOR BEARING DIRECTLY UNDER THE PEDESTAL).

I

'I PAGE 0019 E C R Printout I ECR NUMBER: OC 06-00879 001 ECR 'TYPE: DCP I I APPROVE? DISPOSITION: THE CONCRETE REMOVED IS A PORTION OF THE REMAINING THIN WEDGE AT THE BOTTOM OF THE TRENCH, BETWEEN THE (RELATIVELY)

FLAT BOTTOM OF THE TRENCH AND THE SLOPED SHELL SURFACE. NO REINFORCING OR STRUCTURAL STEEL IS AFFECTED. CONTAINMENT BOUNDARY.

THE NEWI+Y EXPOSED DRYWELL VESSEL, WHICH DEMONSTRATED NOMINAL THICKNESS.

THE STEEL SHELL REMAINS INTACT AS THE UT EXAMINATIONS WERB PERFORMED ON THAT THE VESSEL THICKNESS WAS ESSENTIALLY UNCHANGED FROM THE NEW EDGE OF THE CONCRETE WILL BE CAULKED TO THE STEEL SHELL,' TO MAINTAIN COATED WITH GREASE AS DESCRIBED IN SECTION 3.2.2.4.3 OF SPECIFICATION IS-328227-004 REV. 13, TO PREVENT CORROSION OF ANY AREAS THAT ARE NOT COATED WITH THE NORMAL ZINC BASED COATING. REMOVAL OF THE SILICONE FOAM AND ELASTOMER FROM THE TRENCHES HAS NO IMPACT ON THE FLOOR SLAB OR THE STEEL SHELL. THE TRENCHES UNDER THE SILICONE MATERIAL, SO THEY ARE NOT EFFECTIVE AS A WATER SEAL IN THIS APPLICATION.

WATER COLLECTING IN THE TRENCHES WILL NOT AFFECT THE STEEL DUE TO THE GREASE APPLIED, AND THE CONCRETE IS NOT DET,RIMENTALLY IMPACTED BY CONTACT WITH THE WATER. THE CONTIN~ITY OF THE CAULK BARRIER. THE STEEL WILL BE WATER WAS FOUND IN ANY ,I IN THE TROUGH AREA, THE CONCRETE WAS FOUND TO BE DEGRADED AROUND SEVERAL PIPES. THE TWO PIPES TO THE SUMP WERE FOUND TO HAVE VOIDS AND LOOSE MATERIAL UNDER THEM ON THE TROUGH SIDE, AS WAS THE AZIMUTH 270 PIPE FROM OUTSIDE OF THE SUB-PILE ROOM TO THE TROUGH. THREE AREAS WILL BE RESTORED TO THEIR ORIGINAL CONFIGURATION USING SAFETY RELATED MASTERFLOW 928 GROUT, WHICH IS AS STRONG OR STRONGER THAN THE ORIGINAL I THESE CONCRETE.

IN ADDITION, AFTER REMOVING DEBRIS FROM TROUGH AROUND THE INNER FACE OF THE REACTORtPEDESTAL (PER AWA #1) A VOID WAS FOUND IN CONCRETE IN THE BOTTOM OF THE TROUGH (IR 00550437).

MOST LIKELY THIS VOID ALLOWS WATER TO BYPASS THE TROUGH GOING TO THE 1-8 SUMP AND ALLOWS WATER TO ENTER THE CONCRETE FLOOR, WHICH ALLOWS WATER TO MIGRATE THOUGH FLOOR TO THE TRENCH IN BAY 5. AS A RESULT AWA # 7 WAS ISSUED TO THE FIELD TO REPAIR THIS VOID AND ELIMINATE THIS LEAKAGE SOURCE INTO THE CONCRETE FLOOR. ELIMINATE THE PRIMARY LEAKAGE SOURCE, WHICH CONTINUES TO FILL THE BAY 5 TRENCH. THE REPAIR OF THE TROUGH SHOULD THE DEPTH OF THE TROUGH WAS MEASURED RELATIVE TO STANDING WATER IN THE TROUGH TO DETERMINE IF THE FLOOR OF THE TROUGH WAS SLOPED TO THE SUMP AREA. IT WAS I PAGE 0020 E C R Printout ' I I ECR NUMBER: OC 06-00879 001 ECR TYPE: DCP APPROVED DISPOSITION:

FOUND THAT, GENERALLY, THE LOW POINT OF THE TROUGH IS AT THE SUMP (0 DEGREES) AND THE HIGH POINT IS OPPOSITE THE SUMP (180 DEGREES). THE TROUGH IS RELATIVELY FLAT FROM 270 DEGREES TO 0 DEGREES, HAVING ONLiY A 1/8" DIFFERENCE IN WATER DEPTH. THE FLOOR AND WALLS OF THE TROUGH WERE FOUND TO BE IN GOOD CONDITION, HAVING NO SIGNIFICANT CRACKS OR PATHS OF LEAKAGE INTO TYE SLAB INTERIOR. BASED ON THIS INFORMATION, IT WAS DETERMINED THAT THERE WAS LITTLE BENEFIT TO RESURFACING THE TROUGH FLOOR TO PROVIDE A CONTINUOUS PITCH TO THE SUMP. STANDING WATER IN THE TROUGH DOES NOT AFFECT THE CONCRETE.

ALSO, RAI,SING THE FLOOR.OF'THE TROUGH IN THE 270 DEGREE REGION, COULD CAUSE WATEg TO COLLECT OUTSIDE OF THE PEDESTAL fN THAT AREA, OR EVEN FLOW OUT OF THE THE TWO AREAS. TANGIBLE BENEFIT AND POTENTIAL NEGATIVE CONSEQUENCES, NO REPAIRS ARE SPECIFIED FOR THE TROUGH FLOOR OR WALLS. ANY TROUGH TO THE OUTER AREA THROUGH THE PIPE THA'T CONNECTS THEREFORE, BASED ON THERE BEING NO I I, I I I I THE RAISED SLAB IN THE CENTER OF THE SUB-PILE ROOM HAS EXPOSED AND LOOSE AGGREGATE, AND SPALLING ALONG THE EDGE IN A FEW PLACES. FROM THE CENTER POINT IN ORDER TO SHED WATER INTO THE TROUGH. PORTION OF THE SLAB OTHER THAN TO PROVIDE A WORKING SURFACE FOR UNDER VESSEL WORK. THE DISLODGED AND LOOSE AGGREGATE AND DEBRIS HAS BEEN REMOVED, SO THERE IS NO CURRENT CONCERN WITH THE CONDITION AND IT SHOULD NOT BE A SOURCE FOR WATER TO ENTER THE CONCRETE SLAB AT ELEVATION 10'-3". RESURFACING OF THIS SURFACE SHOULD BE CONSIDERED TO PREVENT ADDITIONAL DETERIORATON AND CREATION OF DEBRIS. THEREFORE THE DEGRADED CONDITION OF THE SLAB IS ACCEPTABLE AT THIS TIME, AND NO REPAIRS ARE SPECIFIED. (REFERENCE IR 546049-10)

THIS SLAB IS PITCHED DOWNWARD THERE IS NO STRUCTURAL FUNCTION OF THE RAISED .- I I I I I ;I 11 I 3.0 10CFR50.59 REVIEW: (4 __________-__-----

____________-__---

AS SUCH, A 50.59 REVIEW IS REQUIRED.

OC-2006-S-0379 HAS BEEN PERFORMED PER LS-AA-104 FOR THIS CONFIGURATION CHANGE. THE 50.59 SCREENING CONCLUDES THAT A 50.59 REVIEW IS NOT REQUIRED AND THAT PRIOR NRC APPROVAL IS NOT REQUIRED TO IMPLEMENT THIS CONFIGURATION CHANGE. THIS ECR IS DETERMINED TO BE A DCP-TYPE PER CC-AA-103.

50.59 SCREENING 4.0 PLANNING, INSTALLATION AND TESTING INSTRUCTIONS:

...................................................

4.1 PLANT MODE (S) APPLICABILITY:

THIS DESIGN CHANGE PACKAGE REQUIRES INSTALLATION OF MATERIALS IN THE DRYWELL. MUST BE INSTALLED AND INSPECTED DURING THE 1R21 OUTAGE. THEREFORE THIS MODIFICATION I' PAGE 0021 E C R Printout ECR NUMBER: OC 06-00879 001 ECR ' TYPE : DCP APPROVE@ / DI S POS ITION : 4.2 INSTALLATION REQUIREMENTS:

4.2 .'l GENERAL 4.2.1.1 ALARA PLAN MUST BE DEVELOPED FOR THE REQUIRED WORK ACTIVITIFS.

4.2.1.2 ACCORDANCE WITH 2400-SMM-3150.16 AND THE MANUFACTURER'S INSTRUCTTONS.

THE MIXXNG I AND PLACEMENT OF THE GROUT. WORK WILL BE IN A POSTED HIGH RAD AREA. AN I THE MIXING AND PLACEMENT OF GROUT SHALL BE IN A QV QUALIFIED INSPECTOR MUST WITNESS 4.2.1.3 THE MIXING OF THE CAULKING MATERIALS AND . PLACEMENT MUST BE IN ACCORDANCE WITH THE MANUFACTURER'S INSTRUCTIONS AND THIS ECR, AND BE WITNESSED BY QV QUALIFIED INSPECTOR-4.2.2 REPAIRS IN SUB-PILE ROOM (AREA INSIDE OF THE PEDESTAL)

.. .. 4.2.2.1 SHOULD BE REMOVED FROM THE TROUGH AND THE RAISED FLOOR SLAB. LOOSE DEBRIS AND EASILY DISLODGED AGGREGATE IN . 4.2.2.2 THE TROUGH TO THE SUMP, AND AT THE AZIMUTH 270 PIPE THROUGH THE PEDESTAL WALL TO THE TROUGH, AS DESCRIBED IN AWA #1. IN ADDITION THE VOID SHALL BE REPAIRED PER GROUT REPAIR IS REQUIRED AT THE TWO PIPES FROM AWA #7. 4.2.2.3 CLEAN AGGREGATE IS EXPOSED PRIOR TO INSTALLATION OF THE REPAIR GROUT, IN ACCORDANCE WITH PROCEDURE 2400-SMM-ENSURE THAT LOOSE MATERIAL IS REMOVED AND 3150.16. 4.2.2.4 INSPECTED AS DESCRIBED IN AWA #2, WITH ANY UNSATISFACTORY RESULTS BEING REPORTED TO ENGINEERING FOR CONSIDERATION OF REPAIRS AND BEING TRACKED UNDER THE DRYWELL SUMP LINER SHOULD BE CLEANED AND A2152754 -13.

1. 4.2.3 CAULKING THE ELEVATION IO I - 3 81 SLAB PERIMETER 4.2.3.1 PREPARED AS DESCRIBED IN AWA #3. DEBRIS AND CONTAMINANTS MUST BE REMOVED PRIOR TO CAULKING. SURFACE CONDITIONS SHOULD MEET MANUFACTURERS INSTRUCTIONS FOR CAULK PLACEMENT.

THE STEEL AND CONCRETE SURFACES SHOULD BE LOOSE COATINGS, DIRT, .. 4.2.3.2 CAULK SHALL BE APPLIED TO THE FULL PERIMETER PAGE 0022 E C R Printout ' I' I ECR NUMBER: OC 06-00879 001 ECR TYPE:

DCP APPROVED' DISPOSITION:

OF THE SLAB, AT ITS INTERFACE WITH THE STEEL SHELL, AS DESCRIBED IN AWA #5 AND MODIFIED BY AWA #6 FOR USE OF BACKER ROD. 4.2.3.3 AND THE REVISION TO AWA #5 REDUCING THE MAXIMUM LAP OF NOTE THE QV INSPECTIONS REQUIRED BY THE AWA,, THE CAULK ONTO THE STEEL AND CONCRETE TO 3/4y 4.2.4 TRENCH EXCAVATION AND RESTORATION I 4.2.4.1 THE TRENCH IN BAY 5 SHALL BE I FURTHER EXCAVATED AS DESCRTBED I , IN AWA #4., .a 1, 4.2.4.2 AFTER C~MPLETION OF UT EXAMINATIONS, CAULK CAN BE APPLIED AT THE INTERFACE WITH THE STEEL SHELL AND THE CONCRETE PER SECTION 4.2.3. REMOVE ALL STANDING WATER FROM THE TRENCH AND ALLOW THE SURFACES TO DRY SUFFICIENTLY TO ALLOW THE APPLICATION OF THE GROUT. CONDITIONS MAY NOT ALLOW FOR A COMPLETE DEWATERING OF THE TRENCH AND DRYING OF ALL SURFACES.

IN THIS CASE APPLY A MINIMUM APPLICATION OF GROUT TO THESE SURFACES AND ALLOW 8 HOURS FOR IT TO DRY. ONCE DRY APPLY THE CAULK. 4.2.4.3, BAY 5 l!.ND BAY 17 TRENCHES AS DESCRIBED IN SECTION 3.2.2.4.3 OF SPECIFICATION 18-328227-004 REV. 13. RECOAT THE DRYWELL SHELL SURFACE IN BOTH THE 4.2.4.4 ELASTOMER TOPPING IN THE TWO TRENCHES.

4.3 ACCEPTANCE TESTING: DO NOT REINSTALL THE SILICONE FOAM OR 4.3.1 GROUT REPAIRS - LEAK TEST WILL BE PERFORMED TO ENSURE ADEQUATE REPAIRS AS DETAILED IN AWA #9. THE LEAK TEST IS USED AS A POST MAINTENANCE VERIFICATION.

4.3.2 WILL BE PERFORMED ON THE CAULK. OF THIS VISUAL EXAMINATION PROVIDES SATISFACTORY ACCEPTANCE TESTING FOR THIS INSTALLATION.

CAULKING - AN IS1 PRE-SERVICE INSPECTION (PSI) SUCCESSFUL COMPLETION i .3.3 TRENCH EXCAVATION/RESTORATION - ACCEPTANCE TESTING FOR THIS PORTION OF THE WORK IS A VISUAL VERIFICATION BY THE WORK GROUP THAT ALL STEEL SHELL SURFACE AREA IN THE TRENCHES IS COATED, EITHER WITH THE ORIGINAL ZINC BASED COATING OR THE GREASE SPECIFIED IN I I # I I I THIS ECR. 4.4 MATERIALS

3.04 -04825 MASTERFLOW 928 GROUT (PC1) --- - 204-07780 BACKER ROD

' PAGE 0023 E C R Printout ECR NUMBER: OC 06-00879 001 ECR 'TYPE: DCP APPROVED DISPOSITION:

I POLYSPEC THIOKOL 2235M CAULK

5.0 REFERENCES

=

l.-A2152754 E05, GENERATION 2.-A2152754 E06, DRYWELL 3.-50.59 SCREENING OC-2006-S-0379 4.-CALCULATION C-1302-241-E610-081

5. A2152754 EO9, EVALUATION OF UT DATF (THIS WAS TRANSFERRED TO IR 54,6049 -07) TECHNICAL BASIS FOR CAULK DEBRIS IN BOTTOM OF EVALUATION OF WATER (THIS WAS TRANSFERRED TO IR 546049-02)

I " I I 1.-DESIGN ATTRIBUTE REVIEW, 9 PAGES 2.-IMPACT REVIEWS (ATTACHMENT IO'S OF CC-AA-102), 7 PAGES 3.-EP-O11 QUALITY CLASSIFICATION FORM, 4.-MARKUP TO DWG BR 4070, 1 PAGE 5.-KOREA ATOMIC ENERGY RESEARCH INSTITUTE RADIATION TEST REPORT (CAULK), 17 PAGES 6.-COPY OF C-1302-241-E3610-081, 3 PAGES REV 2A MINOR -. ~ REVISION, 1 PAGE. IND. D,ESIGN REVIEW COMMENTS:

STRUCTURAL TECHNICAL REVIEW WAS PERFORMED BY DAN FIORELLO I PERFORMED A REVIEW OF THE WORD DOCUMENT CONTAINING THE EVALUATION OF THE DESIGN CHANGE AND AM IN AGREEMENT WITH THE CHANGES. ATTACHMENT

1. MY COMMENTS WERE MINOR AND WERE INCOPORATED INTO THE DOCUMENT PROBLEM RESOLUTION, I REVIEWED THE AWAS AND THE TECHNICAL I ALSO REVIEWED THE DESIGN ATTRIBUTES IN . INDEPENDENT REVIEW BY PETE TAMBURRO I HAVE REVIEWED THE ATTACHED ECR IN ACCORDANCE WITH CC-AA-103 ATTACHMENT D. THE ECR DESIGN INPUTS ARE CORRECT. ALL ASSUMPTIONS ARE REASONABLE.

THE APPROPRAITE QUALITY ASSURANCE REQUIREMENTS HAVE BEEN SPECIFIED.

ALL DESIGN HAS BEEN QUALIFIED. ADEQUATE MAINTENANCE AND INSPECTION FEATURES HAVE BEEN ADDRESSED.

RADIATION EXPOSURE HAS BEEN CONSIDERED.

ALL RECORD RETENTION AND APPROVAL REQUIREMENTS HAVE BEEN ADDRESSED.

THEREFORE I RECOMMEND APPROVAL OF THIS ECR. ALL COMMENTS RECEIVED FOR THE THIRD REVIEWER HAS BEEN SATISFACTORY RESOLVED AS DOCUMENTED IN EMAIL DATED 10/ INTERFACE REQURIEMEN+S ARE MET. THE INSTALLED CAULK ....................................

28. . s. I1 I' I PAGE 0024 . E c R Printout . ECR NUMBER: OC 06-00879 001 IND. DESZGN REVIEW COMMENTS:

I I' ECR TYPE: DCP SIGNED FOR ELDRIDGE, SHARON DUE TO PIMS INACCESSIBILITY.

...............................

~WA 1 THROUGH 9 INCLUDING REVISIONS WHICH'WERE DISPOSITION AND ALL REVIEWER COMMENTS REMAIN VALID. THIRD PARTY REVIEW BY MPR ASSOCIATES AND WAS FOUND REQUIRED TO IMPLEMENT AND CORRECT THE IDENTIFIED DISCREPANCIES HAVE BEEN REVIEWED AGAINST THE FINAL THIS PACKAGE ALSO RECIEVED A FINAL INDEPENDENT ACCEPTABLE WITHOUT REVISION.

• • • • I I. '0 I ., ' I I MANAGERS COMMENTS . '0 THIS DCP IS APPROVED' FOR USE. THIS 'M~DIFICATION WILL IMPROVED THE HEALTH OF THE DRYWELL AND CONCRETE TO I 4 1 ENSURE THAT THE PHYSICAL PLANT IS KEPT HEALTHY THROUGH LIFE EXTENSION.

THE SUBJECT ECR REVISION HAS BEEN INDEPENDENTLY REVIEWED IAW PROCEDURE CC-AA-103 AND FOUND TO BE ACCEPTABLE.

THIS DESIGN REVIEW ONLY COVERS THE REVISION 1 CHANGES. ............................

• • • • • I I REVISION 1 MANAGER COMMENTS:

THE PERSONNEL WHO PERFORMED THIS DISPOSITION WERE QUALIFIED AND THE CHANGES HAVE RECEIVED A RIGOROUS CHALLENGE THROUGH THE PROJECT TEAM ALONG WITH IN HOUSE ININDEPENDENT THIRD PARTY REVIEWER (ITPR)

AND AN OVERALL ITPR PERFORMED BY MPR (J. NESTELL) AS PART TO THE DRYWELL WATER ISSUE EVALUATIONS COVERED UNDER IR 546049. I MADE NUMEROUS EDITORIAL AND ADMINISTRATIVE CHANGES WITHIN THE DISPOSITION TO IMPROVE THE WORDING AND ADDRESS SEVERAL QUESTIONS DISCUSSED AT PORC PORC MEETING 06-18. (SI ELDRIDGE)

I I ;HE HU-AA-1212 PRE-JOB BRIEF AND RISK SCREENING WAS INCLUDED AS PART OF THE OVERALL TASK OF EVALUATING THE EFFECTS OF WATER FOUND IN THE DRYWELL PER IR 0546049, WHICH WAS GIVEN A RISK RANK OF 2. THESE REVIEWS HAVE BEEN COMPLETED AND COMMENTS RESOLVED.

I PAGE 0025 ' . ,' E C R Printout ' ECR NUMBER: OC 06-00879 001 ECR TYPE: DCP C. DOCUMENT CHANGES: DOC CHANGES REQUIRED:

y .DOC SCREEN STATUS:

8 I I AFFECTED DOCUMENTS:

F Type Document ID Sheet As-Built ,Incorp Dwg Inc 'Inc Resp I Type Cat Due Date ., qate Rev Orgn 1.02 D OED 1 OC DWG BR 4070 OC DWG GU 3B-153-34-1000 N/A 6.01 I F I OED 1 .I I I D. E. APPROVALS: , Name User ID Date INTERFACING GROUPS:

CAQ: - ISSUE NBR: RESP ENGINEER: TAMBURRO, PETE PXTO 11/05/06 IND REVIEWER:

NIOGI, SUJI SNNl 11/05/106 MANAGER : RAY, F.H. FHRl 11/06/06 ECR WORK COMPLETION NOTIFICATION:

WORK REQUIRED:

y AUTO CLOSE: c_ N PRKl FILM ID: BLIP NBR: BOX NBR: C2013725 01. 2 COMPLT 20061024 DESC: 187 MOBILIZE WORK AREA C2013725 02 1 COMPLT 20061025 DESC: 187 DOP TEST HEPA UNIT I C2013725 03 1 COMPLT 2 00 6 1024 DESC: 187 CLEAN TROUGH C2013725 04 1 HOLD 20061024 DESC: 187 MATERIALS

/ PARTS WORK ORDER PAGE E C R Printout ECR NUMBER:

OC 06-00879 001 ECR'TYPE:

I E. ECR WORk COMPLETION NOTIFICATION:

WORK REQUIRED:

y AUTO ' CLOSE : - N PRKl I DCP BLIP NBR: BOX NBR: FILM ID: 2 0 061 024 C2013725 05 1 INPROG I DESC: ,.'187 PERFORM CLEANLINESS INSPECTION C2013725 06 1 COMPLT 20061030 QUANTIFY EXTENT OF REPAIRS I DESC: ,1871 C2013725 07 1 COMPLT 20061101 DESC: 187 REPAIR PER AWA #1 C2013725 08 1 READY 20061030 DESC: 187 ENGINEERING INSPECTION C2013325 09 1 READY 20061025 DESC: 187 ENGINEERING ECR/MOD ACCEPTANCE C2013725 .a 1 COMPLT 20061102 DESC: 187 GROUT REPAIR PER AWA

1. 7 (22013725

-11 1 COMPLT 20061103 DESC: 187 MOBILIZE CHECK FOR VOIDS C2013725 2 1 COMPLT 20061103 DESC: 187 INSTALL PLUGS C2013725 13 1 COMPLT 20061103 DESC: 187 FILL TROUGH AND VERIFY NO LEAK C2013725 14 1 COMPLT 20061103 DESC: 187 "TROUGH LEAK TEST" 0026 I

-_ I PAGE 0027 E C R Printout ' ECR NUMBER: OC 06-00879 001 E. ECR WORK COMPLETION NOTIFICATION:

WORK REQUIRED:

y AUTO CLOSE: - N PRKl ECR TYPE: 1 I DCP I, '11 I BLIP NBR: BOX NBR:

FILM ID: I. C2013725 15 1 COMPLT 20061103 ,I, DESC: 187 GROUT REPAIR (CONTINGENT)

I B I C2013725 16 I, , G' COMPLT 2'0061104

! I I DEMOBILIZ~

' I DESC: 187 t I I

• 2'0061104 B --_-- ! I I DEMOBILIZ~

' I I t I C2013726 01 1 COMPLT 20061029 , DESC: 187 REMOVE CONCRETE IN BkY #5 C2013726 02 1 READY 20061025 DESC: 187 ENGINEERING ECR/AWA ACCEPTANCE C2013726 03 1, COMPLT 20061104 DESC: BAY 5 & 17 COAT PREP AREAS WITH VERSILUBE C2013726 04 1 COMPLT 2 0061104 DESC: 187 VACUUM WATER FROM BAY #5 C2013726 05 1 COMPLT 20061102 DESC: 187 GROUT REPAIR BAY #5 TRENCH C2013726 06 1 COMPLT 20061101 DESC: 187 REMOVE WATER FROM BAY 17 C2013726 07 1 COMPLT 2 0061 104 DESC: 187 PROVIDE ENGINEERING SUPPORT I, I I, I C2013729 01 1 COMPLT 20061029 DESC: 187 CLEAN OUT PERIMETER CREVICE PAGE 0028 E C R Printout ECR NUMBER: OC 06-00879 001 . // E. ECR WORk COMPLETION NOTIFICATION:

ECR 'TYPE: DCP WORK REQUIRED:

y AUTO,' CLOSE

- N PRKl BLIP NBR: BOX NBR: FILM ID: I C2013729 02 1 COMPLT 20061029 I' DESC: ,,'187 CAULK PERIMETER CREVICE C2013729 03 1 READY 20061027 DESC: 01 87 ENGINEERING INSPECTION C2013729 03 1 READY 20061027 DESC: 01 87 ENGINEERING INSPECTION C2013729 04 1, READY 20061027 DESC: 187 ENGINEERING ECR/MOD ACCEPTANCE C2013729 05 1 COMPLT 2 00611 04 DESC: 187 CONDITIONAL RELEASE OF MATERIAL C2013729 06 1 COMPLT 2 00611 04 DESC: 187 VERIFY MATERIALS HAVE BEEN 4, I C2013729 07 1 COMPLT 20061029 DESC: 187 CLEAN GREASE FROM GALVANIZE C2013729 08 1 COMPLT 20061103 DESC: 187 COMPLETE CAULKING C2013732 01 1 COMPLT 20061029 DESC: 187 CLEAN OUT DRYWELL SUMP C2013732 02 1 COMPLT 20061028 DESC: 187 PROVIDE SUPPORT FOR DRYWELL SU C2013732 03 1; COMPLT 20061030 DESC: 187 ENGINEERING INSPECTION PAGE 0029 E C R Printout . ECR NUMBER:

OC 06-00879 001 ECR TYPE: E. ECR WORK COMPLETION NOTIFICATION:

WORK REQUIRED:

1 AUTO CLOSE: N PRKl 0. - I' DCP I BLIP NBR:

BOX NBR: FILM ID: I +, C2013732 04 1 COMPLT 20061029 1. DESC: 187 DWlO ROV REMOTE VT EXAMS DRYWELL SUMP I' I1 C2013732 05 11 , 1' COMPLT *' 2'0061029 DESC: 187 It I , REMOVE COVERS FROM DW SUMP I I C2013732 06 1 COMPLT 20061029 DESC: SUB PILE ROOM C6-1568 INSTALL GRATING C2013732 07 1 COMPLT 20061030 DESC: GRATING C6-1568 REMOVE GRATING SCHED 20061103 C2013732 08, 1 DESC: 187 PERFORM PMT C2013732 09 1 COMPLT 20061031 DESC: 187 REINSTALL COVERS FROM DW SUMP C2013732 10 1 COMPLT 20061030 DESC: 187 TO BE CLOSED NO WORK PERFORMED C2013732 11 1 COMPLT 20061030 DESC: 187 OPS SUPPORT TO EMPTY SUMP COMPLT 20061030 C2013732 12 1 DESC: 187 TO BE CLOSED OUT C2013732 13 1 COMPLT 20061029 DESC: 187 POWERWASH DRYWELL SUMP I(: I/ 'I I I I PAGE 0030 E C R Printout 11 ECR NUMBER: OC 06-00879 001 ECR 'TYPE: DCP E, ECR WOR'k COMPLETION NOTIFICATION:

WORK REQUIRED:

y N PRKl AUTO CLOSE: - I I BLIP NBR: BOX NBR: FILM ID: C2013732 .* 1 COMPLT 20061029 DESC: 187 HYDROLAZE DRYWELL SUMP I I' I C2013732 15 ,, " COMPLT .n20061029 I I DESC: 1187 I MECHANICALLY CLEAN 1-8 SUMP C2013732 18 1 COMPLT 20061029 DESC: 187 REMOVE TENT (CONTINGENT)

C2013732 17 1 COMPLT 20061029 DESC: 187 ERECT TENT (CONTINGENT)

C2013732 19 - 1 COMPLT 20061031 DESC: 187 PERMITS PERMITS C2013732 20 1 COMPLT 20061030 DESC: 187 PERFORM WELD REPAIR AWA XXX COMPLT 20061103 C2013732 21~ 2 DEMOBILIZE DESC: 187 COMPLT 20061031 PERFORM STATIC TEST C2013732 22. 1 DESC: 187 C2013727 01 1 COMPLT 20061026 DESC: 187 DWlO PREP DW SHELL FOR UT INSPECTION A2152754 05 COMPLT 11/04/06 DESC: TECHNICAL BASIS FOR AWA FOR ECR 06-00879 PAGE 0031 E C R Printout . I I ECR NUMBER: OC 06-00879 001 ECR TYPE: DCP / E. ECR WORK COMPLETION NOTIFICATION:

WORK REQUIRED:

2 AUT0,CLOSE:

N PRKl I FILM ID: BLIP NBR:

BOX NBR: - I 1 A2152754 06 RETURN 11/04/06 ' .I. I' DESC: 'EVALUATE IMPACT OF WATER IN BAY 5 & 17 TRENCHES A2152754 12 , COMPLT '1 1 / 0 5 /O 6 DESC: ENSURE DRYWELL CAULK PASSES dUALIFICATION TESTING I a 8 1 A2152754 13 COMPLT 11/03/06 DESC: ENSURE DRYWELL SUMP LINER PASSES VT-1 INSPECTION F. COMPONENT CHANGE REQUESTS:

Affected Component List .. CCR Revw Prop User Rev Flag Stat ID Date JDAO 10 /27 /06 Y F OC 1 1-87 M MISC NROl\MBOOl-INT 000 - -

,I PAGE 0032 ,I E C R Printout I1 COMPONENT CHANGE REQUEST I 40 MECHANICAL MISCELLANEOUS

OMP ID : o'c 1 187 M MISC NROI\MBOOI-INT ECR/NCR ID: E 06-00879 001 :CR REV : 000 ,AST UPD : 10/31/06 PXTO REV1 EWED : y,, ~ROPOSD CRL STATUS: F CCR STATUS: APPVD REVIEWED BY : PXTO REVIEW DATE : 10/31/06 :Mp DESCRIPT,, : :MP DESCRIPT : I LANUFACTURER 1: - [FGR STYLE : ' OM NUMBER : - IODEL NUMBER : THIOKOL 2235M IFG TYPE ERIAL NUMBER: I 10 CAT ION : LOC: DW 10 IAA DRYWELL INTERIOR MOISTURE BARRIER '3 CONCRETE FLOOR ELEV 10-3 WHERE DW FLOOR MEETS DW SHELL I 0 !I *" I' ,' - COMPUTER ADDRESS:

LOC : iBL FOOTNOTES

__________________------

______________

CODES AND CLASSIFICATIONS

...........................

e--

• A SEIS CAT -- z SSEL/SQUG 9 -- M EQPT .-- ENV QUAL - -- E INTERFACE

- - REG.GDE. 1.23 : N REG-GDE. 1.26 -- EG.GDE. 1.155 : -- N ATWS --- --- N 10CFR73.55 - -- N SWP/RWP - -- N EB 79-18 e-- N IEB 80 -- N EMER HT SNK -- M CM 0-v SET POINT CLASS: X IS1 CLASS -- RES BND INSTR : - - N MRULE/EPIX

-- e-- N LR -- TECH SPEC 9 -- THER RR --- Y TMI-2 PDMS --- BORON -- N N N W N N N FIRE PROTECTION

!A CLASS EG.GDE. 1.97' : - - N REG-GDE. 1.143 : IRE SSD SME SEC XI ISI: - - Y ASME SEC XI IST: N ASME REPR/REPL

N SA CLASS RAM 0- ITE PIPE CD : - IVOR REQ : ' 9 -- N A4 SCOPE - ASIC REFERENCE DOCUMENT:

BR 4070 - EFS/OTHER COMMITMENTS

THE AMOUNT OF POTENTIAL DRYWELL DEBRIS THAT COULD ENTER THE ECCS SUCTION STRAINERS IS EVALUATED IN CALCULATION C-1302-241-E610-081.

I. ' . PAGE 00'33 1 E C R Printout COMPONENT CHANGE REQUEST MECHANICAL MISCELLANEOUS I 3MP ID : OC 1 187.. M MISC NROl\MBOOl-INT ECR/NCR ID: ZR REV : 000 I1 I E 06-00879 001.. I I , '. VALVE SIZE : INE NUMBER : 3MP SUB -TYPE: I I , LOW RATING ZSIGN TEMP PEED RATING LWR PRES RT 'IIVER SPEED %SIGN PRESS ILUME [MENSIONS IRSEPOWER SPACITY $TED SPEED WTOFF HEAD JBE PRESS 3LIEF PRESS 3MP CORRECT II I - SHELL PRESS: h I 4CKPRES S COR : SNCH TEST PR: 3RVICE FLUID:

J SERVICE DATE: 3NDOR CODE 10/27/06 PO NO: 'EC NBR $SIGN CODE . : ITEM NBR: )NSTR CODE ISTALL CODE : .. .

PAGE 0034 8, 1. E C R Printout COMPONENT CHANGE REQUEST 11 MECHANICAL MISCELLANEOUS

// :OMP ID : dc 1 187 M MISC NROI\MBOOI-INT ECR/NCR ID: E 06-00879 001 :CR REV : 000 *Y ,AST UPD : 10/31/06 PXTO REV1 EWED 9- 'ROPOSD CRL STATUS: F CCR STATUS: APPVD REVIEWED BY : PXTO REVIEW DATE : 10/31/06 COMMENTS ========================

ID == DATE = .___________________------------

.___________________------------

PRKl 10/27/06 PRKl 10/27/06 PRKl 10/27/06 NOTE: THIS IS THE CAULK JOINT AROUND THE PERIMETER OF THE ORYWELL CO~CRETE FLOOR AT ELEVATION 10'311, WHERE IT MEETS 'THE STEEL DRYWELL SHELL. , I, LAX DESIGN STRO~E TIME POSITION OPEN: P+ID COORD: ACT'TYPE : NORMAL : CLOSED: APP.

J TYPE C : G.L. 89-10 : SAFE : VALVE CAT

SIZE: 0.00 0.00 FAIL : PENETRATION/COMMODITY EN SIZE : EN CONFIG: OMMODITY SIZE OMMODITY MATERIAL:

IPING: MAX MVMT LECTRICAL

NEW CABLE LOADING: -~~ (% FILL) AXIAL LATERAL MAX PIPE TEMP: AD A/BA RATIO: (ACTUAL) ATER PENETRATION SEAL A SIDE B SIDE ETAIL: I EQUIV FT OF CONC. REQD PSIG(MAX FLD HT. - MIN PEN. ELEV X 0.43) ******************************************************************************~

• ...............................................................................

• • END - OF - CCR PAGE 0035

• I' E C R Printout COMPONENT CHANGE REQUEST e MECHANICAL MISCELLANEOUS

// OMP ID dc 1 187 M MISC NROI\MBOOI-INT ECR/NCR ID: E 0'6-00879 001 CR REV : 000 *Y AST UPD :' 10/31/06 PXTO REVIEWED 0- ROPOSD CRL STATUS:

CCR STATUS: APPVD REVIEWED BY : PXTO REVIEW DATE : 10/31/06 ................................................................................

• ................................................................................

• *' END,."OF ECR - ALL ASSOCIATED CCR"S PRINTED I' I' ECR 06-00879 rev. 0 Attachment 1 , page 1 of 9 ECR 06-00879 Rev. 0 I' Attachment 1 - Design Attribute Review , I DESIGN ATTRIBUTES (Numbers correspond to CC-AA-102 rev 13, Att. 1 list items) 4.1.4.1 IDENTXFY BASIC SSC FUNCTIONS:

I 11 I( The Containment is an enclosure for the reactor vessel, the Reactor Coolant Recirculation System, and other branch connections of the Reactor Coolant System.

Per UFSAR section 6.2.1, the design criteria for the Containhent are as follows: I . To withstand the peak transient pressure (coincident with an edrthquake) which could occur due to the postulated break of any pipe inside the drywell. To channel the flaws fkom postulated pipe breaks to the torus. To withstand the force caused b> the impingement of the fluid from a break,in the largest IO'C~I pipe or connection, without containment failure.

To limit primary containment leakage rate dmbg and following a postulated break in the primary system to substantially less than that which would result in offsite doses approaching the limiting values in 1 OCFRl 00. To include provisions for leak rate tests. a. b. c. d. I I' I e. I1 The concrete floor slab at the base of the drywell provides a foundation for the RPV support pedestal, as well as a level support surface for personnel and equipment.

The slab internal to the pedestal has an additional 6"slab on top, and is therefore at a higher elevation than the slab outboard of the pedestal, with the exception of the 6" wide trough just inboard of the pedestal. Drains external to the pedestal can reach the trough (and sump) via four pipes in the base of the pedestal that connect the inboard and outboard areas. The higher slab inside of the pedestal is sloped downward from the center to shed water to the trough. 4.1.4.2 IDENTIFY SAFETY CLASSIFICATION OF CONFIGURATION CHANGE: The structural support fbnction of the concrete slab is safety related, in that it provides structural integrity for the reactor vessel and its supporting equipment.

The steel drywell containment vessel is also safety related, providing the containment integrity.

The concrete slab is not required to be impregnable to water? as justified in tech eval A21 52754 E06*. Therefore any coatings and caulks are not safety related, and ody provide the desired effect of minimizing water infiltration into the concretelsteel shell interface.

This ECR is classified as safety related, however, because the added materials come into contact with the safety related steel and concrete, and could potentially have an adverse effect on them. Accordingly, the caulking material is Augmented, "A" Qualifty.

i.1.4.3 IDENTIFY SEISMIC CLASSIFICATION OF SSC : The steel drywell vessel and the concrete floor slab are Seismic Category I structures. Any added coatings or caulks do not affect these seismic capabilities. Therefore there are no seismic qualification requirements for added coatings or caulks. The concretehteel shell interface is not considered a seismic gap.

.I ECR 06-00879 rev. 0 . Attachment 1, page 2 of 9 1 i.l.5 IDENTIFY PERFORMANCE REQUIREMENTS:

Coatings and caulk shall not degrade or alter the strength and integrity of the steel cohtainment vessel and the concrete floor slab. Cementitious grout has a cured , " compressive strength as high, or typically higher than concrete, so it will behave in the same manner as the concrete to which it is applied. This prevents the need for consideration of any new failure effects for the grout.

The caulk shall be qualified to remain adhered under all potential drywell conditions identified in procedure ES-027, with the exception ofjet impingement.

4.1.6 DESIGN REQUIREMENTS FOR SURVEILANCE AND ACCEPTANCE TFSTING: ASME Section XI program. 4.1 :7 SPECIFICATIONS, CODES, STANDARDS, OR REGULATORY i The design allows for future inspections of the installed caulk as required under the REQUIREMENTS: Containment Vessel Thickness Examinations". Specification IS-328227-004 Rev 13, "Function Requirements for Drywell OC Station Procedure No. 2400-SMM-3 150.1 6, "Mixing and Placement of Grouts". GE NEDO-32686, Rev 0, "Utility Resolution Guidance for ECCS Suction Strainer EP-057, "Component Record List Control".

EP-011 , "Methodology for Assigning and Maintaining the Quality Classification of ES-027, "Environmental Parameters - Oyster Creek NGS". B 1 o ckage". Components". .I 4.1.8 PWR SUMP PROGRAM IMPACTS FOR BRAIDWOOD, BYRON AND TMI: Not applicable.

4.1.9 CALCULATIONS OR DESIGN ANALYSES AFFECTED:

The effect of the missing curb will not have a significant effect on the Design Basis Accident analysis of the Containment Shell For the following reasons: The finite element models used in the GE analysis of the containment shell has fixed boundary conditions at the base where it is supported by the concrete foundation.

With the sand bed removed, this interface is modeled at the base of the sand bed region (El 8' 31 7B") The concrete floor inside the drywell at El 10'-3" extends up to an elevation of 12' -3". The concrete floor and curbs above the bottom of the sand pocket region were not considered to provide &y support to the Drywell shell. The thermal analysis considered that the temperatures of the shell behind the curb were lower than that of the shell exposed to the drywell atmosphere. There are two portions of the curb that have been removed, each being approximately 16 inches wide. Cutting this small portion of the curb will expose a portion of the shell to higher temperatures. This will have a negligible affect on the shell thermal distribution and the ECR 06-00879 rev. 0 Attachment 1 , page 3 of 9 thermal analysis stresses.

A review of the GE stress report indicated that in the sandbed region the highest stress (primary & secondary) is due to load Case VI (Post -Accident condition) - Gravity, Flooded Seismic) which is a primary stress check and does not included the DBA accident temperature load. The load condition that includes the DBA accident temperature is Load Case V-1. This load case has a maximum primary plus secondary stress in the sandbed region, which is approximately 73 percent of the allowable stress. The Load Case V-1 includes the pressure, gravity, unflooded seismic, seismic relative support displacement and temperatufe gradient during DBA loads.

The ' load case would conservatively determine combined stresses because the pressure and thermal stress will not maximize simulataneously. The,local change in the shell temperature where the curb has been removed will increase the thermal stress in a localized area but this increase is judged not to be significant. The stresses ar&secondary and localized. The event is a one time loading that has no affect on metal fatigue.

Any localized change in the thermal stress can be accommodated by the existing margin to the I I allowable stress. .I '8 I I As documented in Technical Evaluations A2 152754-05, the amount of potential drywell debris that could enter the ECCS suction strainers is evaluated in calculation C-1302-241-E61 0-081. The grout behaves as the concrete already present in the drywell, and therefore does not contribute to the potential debris.

No additional debris will be created by its presence, since it provides the same surface area available for abrasion or spalling during the DBA as the concrete, and has equal or better strength than the concrete.

I The caulk can become dislodged by a water jet, and therefore must be addressed as potential additional debris.

However, the amount of caulk added is less than the amount of silicone foam and elastomer removed from either one of the two trenches, and the silicone material was removed from both trenches. Therefore there is no net increase in mass that could clog the suction strainers.

The calculation does not specifically address the silicone foam in the trenches, but rather genm'cally includes dust, dirt, concrete and debris in typical amounts for nuclear plants.

The amounts are not based on the drywell inventory specific to Oyster Creek (except for insulation), but are numbers utilized by the industry as typical. Since the caulk being added is typically installed in nuclear plants, it can reasonably be considered to be captured in the generic debris amounts utilized in the calculation.

Thus, fi-om a practical perspective, there is no net increase in the mass of material in the drywell.

And fiom a configuration control perspective, the caulk being installed is represented in the existing mass values used in the calculation. Therefore it is not necessary to revise the numerical values of the calculation, and the calculation remains accurate to the same degree as when it was originally created.

However, text is added to alert calculation users of this issue, and that the mass values are considered to include the caulk installed by this ECR. There are additional facts that reduce the threat of suction strainer clogging fiom the caulk. The caulk is at the lowest level of the drywell, installed in a comer joint. The position of the recirc pumps and piping are such that a break would impinge on the caulk in a direction that would push it into the corner rather than in a direction that would tear it fiom the comer. If it were to be dislodged, its position is below the downcomers such that it would have to travel upward in the drywell to reach the torus. In most line breaks, I ECR 06-00879 revJ Attachment 1, page 4 of 9 flow in the drywell is downward to the downcomers, making it unlikely that the caulk strip would be washed upward.

The cured caulk has a density roughly 1.5 times that of water, making it likely that it will remain at the bottom of the drywell and not reach the torus. and the steel shell, to reduce the amount of caulk needed.

The backer rod is a negligible contribution to debris. The installer estimates that 10' of perimeter will require its use. This amount of rod weighs on the order of a few ounces, which is insignificant compard to the calculation weights of 150 pounds for dust, dirt and concrete, and 25 pounds for miscellaneous additional debris. In addition, the backs rod will float, and therefore will not get to the suction strainers to contribute to their cloggink. However, it is very unlikely that the backer rod will dislodge at all. It is a high fiction, compresdible material that will be wedged into the gap between the steel shell and the concrete.

Any water jet or other DBA will not penetrate into this gap with any significant force, so the rod is expected to remain in its installed location under all conditions.

Therefor?

use of , the'backer rod is acceptable, and no calculation changes are required to reflect its use. In some areas, backer rod will need to be installed in the gap between the concrete slab ' I 4.1.10 REDUNDANCY, DIVERSITY AND SEPARATION REQUIREMENTS:

I Not applicable to this modification.

4.1.1 1 FAILURE EFFECTS REQUIREMENTS

I As discussed above, the grout is no different than the concrete floor slab already present, $0 its presence does not add any new potential failure effects. It is used to restore the contour to the trough in the sub-pile room. The grout will be placed in accordance with Procedure 2400-SMM-3150.16 with adequate controls to ensure that the grout will not experience bonding failure to the existing concrete.

However, if it became delaminated from the concrete substrate, it would result in localized ponding in the trough, and could potentially reach the sump. Localized ponding in the trough is not a concern, since it would not damage the remaining concrete and would allow-a negligible volume of water to remain in the drywell.

Any grout that reached the sump would remain on the bottom of the sump, and would not affect the operation of the sump pump. Procedure ES-027 for the DBLOCA defines the environmental parameters inside the drywell. The caulking matm'als will survive the DBLOCA environmental parameters with exception of the impingement zone of influence caused by the recirculation piping in close proximity to the caulked joints. Failure of the caulk bond could result in water infiltrating the crevice between the concrete drywell floor and the steel drywell vessel. This is acceptable, as determined in A2152754 E06*. The caulk could become dislodged and travel through the.

downcomers to the torus. This has been addressed in the debris analysis as discussed above. The caulk is sufficiently flexible to accommodate any movement of the drywell vessel relative to its concrete floor slab, and will not restrict this movement. The caulk remains flexible and will remain adhered under the expected range of relative motion, having an elongation capability of greater than 400% (reference Rev. 1 a, ECR 06-00879 rev. 0 Attachment 1 , page 5 of 9 A21 52754-05).

The caulk material used has also been successfully tested to the radiation dose associated with plant life service plus accident conditions (see ECR attachments).

4.1.12 USE ATTACHMENT z TO IDENTIFY FIRE PROTECTION AND APPE~IX R SAFE SHUTDOWN REQUIREMENTS:

All screening questions of CC-AA-102 Att. 2 are answered "no". Therefore a formal fire protection review is not required.

In particular, question 1 is answered "no" based on the following reasons: The grout material is essentially concrete, and is not flammable. The MSDS for the caulk indicates that the material has an NFPA flammability rating of zero, and that it is not a fire hazard. Review by the fire protection program manager indicates that there is no impact to the fire protection and Appendix R safe shutdown.

requirements and that the amount of polyethylene backer rod material is insighificant, the material is not exposed, there is no fire source in the area, and the environment is inerted. 4.1.1 3 MATERIAL AND MATERIAL SUIT4BILITY REQUIREMENTS:

l%e cementitious bout used is compatib'le with the wet environment of the d3ywell . and the concrete floor slab to which it is bonded, and is not adversely affected by the radiation levels present. The caulk material is designed fo; this type of application and has been qualified to perform satisfactorily under drywell design basis accident conditions.

Furthermore? the caulking material is compatible with the DW steel shell structure and concrete structure and will not result in harmll chemical reactions to any of these structures.

The backer rod is also compatible with the drywell environment, and will not react with the steel, concrete, or drywell atmosphere.

4.1.14 ENVIRONMENTAL CONDITIONS AND IMPACTS:

provided in procedure ES-027. The materials are essentially inert once cured, and will have no effect on the drywell environment. They are not flammable and do not generate any flammable gases, with the exception of the small amount of backer rod added, which has been accepted in the fire protection review. This modification does not affect the temperature, pressure or humidity of the drywell environment.

4.1.15 EQUIPMENT ENVIRONMENTAL QUALIFICATION:

qualification?

and do not affect the EQ of any existing equipment.

h. 1.16 OPERATING EXPERIENCE: These repairs are based, in part, on the past findings documented in the structural monitoring program, as discussed in the ECR introduction.

The caulk applied to the drywell floor joint is the same material used successfUlly in this application at Peach Bottom, Turkey Point, St. Lucie, Oconee, Catawba, McGuire, and Wolsong, per the coatings consultant on site for the outage (Jon Cavallo, VP of Corrosion Control Consultants and Labs, Inc.). 4.1.17 EPIX DATABASE IMPACTS:

I I I ' I The installed materials are rated for the drywell normal and accident conditions I These modifications do not install any equipment requiring environmental None.

.I I IS ECR 06-00879 rev$ f %\ob Attachment 1, page 6 of 9 ,Ab ,I 4.1.1 8 PRA IMPACTS:

Although the Level 2 PRA took some credit for the curb probabilistically, the minor daunt of concrete removed fiom the trench in Bay 5 is not significant enough to markedly change LERF or the co&sions of the SAh4A analysis, (Ref. IR 55002i). The failure probabilities for the OC h due to core material impingement are not significantly different than those for other Mark I containments where the concrete curb does not exist. Therefore there are no impacts to the PRA analysis.

' 4.1.19 SYSTEM OPERATIONAL REQUIREMENTS;:

The ECCS suction strainers must not become clogged to the point that they affect the I operability of the ECCS systems.

The amount of installed material that could become dislodged and reach the suction strainers has been analyzed and found to be within the available margin for continued operability of ECCS systems. Also, materials installed will not affect the operation of the drywell sump pumps. 4.1.20 HUMAN FACTORS REQUIREMENTS:

I( It I IC Not applicable to this ECR. 4.1.21 USE ATTACHMENT 9 TO IDENTIFY PROCEDURE CHANGES: The requirement to inspect the caulk will be added to procedure ER-OC-330-1006 for the Containment IS1 program inspections IAW ASME Section XI program and is tracked under A2 152754-1 1. Based on review of attachment 9 and the impact review performed, there are no other procedure impacts.

4.1.22 TRAINING REQUIREMENTS: , , $None required.

4.1.23 SYSTEM INTERFACE REQUIREMENTS:

'4 . This activity will leave the two trenches that were previously filed with a foam material empty. This empty space may slightly delay the measurement of unidentified leak rate which is measured by the 1-8 sump. The open trenches may collect unidentified leakage and temporarily prevent the leakage from reaching 1-8 sump. However this delay is conservatively estimated to be no more than a 30 minutes. The total empty volume of the both trench is estimated to be approximately 50 gallons. Tech. Spec.

3.3.D.1 requires that reactor coolant shall be limited to a 2 gpm increase in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Assuming a 2 gpm leak were to instantaneously develop and leak into both trenches at the same time, it would take about 30 minutes for the trenches to fill and overflow at which point the leakage would enter the 1-8 sump. The installed matenals,are primarily structural and cosmetic repairs, and do not interface with any other plant systems.

ECR 06-00879 rev. 0 Attachment 1, page 7 of 9 ' II' 4.1.24 LAYOUT AND ARRANGEMENT REQUIREMENTS:

There are no special requirements for these modifications. h.l.25 USE ATTACHMENT 5 TO DETERMINE RADIATION PROTECTION

/ ALARA APPLIcABILI?"y:

1 Based on the responses to the attachment 5 questions, an ALARA review is r'equired II (I for this scope of work. 1 4.1.26 WALKDOWNS: Several walkdowns and inspections were performed by ehgineering, planning and the work group to determine the best course of action and the preferred design solktion.

The walkdowns established the existing field conditions, and the installability of @e intended I design solutions.

8 I1 II i 4.1 27 ACCESS.,FOR'MAINTENANCE, REPAIR, ISI, OR IST: The design allows for fbture inspections of the installed caulk as required under the ASME Section XI program, and for fiture inspections of &e trenches to determine if they contain water. The installed caulk and grout does not impede access to any plant equipment.

I 4.1.28 HANDLING, STORAGE, CLEANING, SHIPPING AND TRANSPORTING

~ REQUIREMENTS:

specified in AWA #3 of this ECR. Cleaning requirements in preparation for application of the caulking material are 4.1.29 EMERGENCY PLAN IMPACT: . i.1.30 INDUSTRIAL SAFETY REQUIREMENTS:

determine the applicable hazards and precautions.

None for this modification.

The MSDS for all materials should be obtained by the work group, and reviewed to h.1.31 USE ATTACHMENT 6 TO DETERMINE IMPACT ON NUCLEAR FUEL, CORE COMPONENTS, CORE DESIGN, REACTIVITY MANAGEMENT; CRITICALITY CONTROL AND ACCOUNTABILITY OF NUCLEAR MATERIALS, AND TRANSIENT AND ACCIDENT ANALYSES: There are no impacts. The materials used are qualified for the drywell environment. Potential creation of debris under DBA conditions has been evaluated and determined to be bounded by the existing conditions and analyses.

4.1.32 LOAD PATH REQUIREMENTS:

modifications.

s.1.33 MECHANICAL SYSTEM DESIGN LIMITS:

There are no special handling requirements for the materials used for these I' ECR 06-00879 rev. 0 . ' Attachment 1 , page 8 of 9 None applicable.

'I I 4.1.34 IDENTIFY CHEMISTRY REQUIREMENTS:

Leachable contaminants are within the limits of this environment. /Chemistry has approved the materials applied by this ECR for use in the drywell: , 4.1.35 ELECTRICAL REQUIREMENTS:

Not applicable.

I I 4.1.36 INSTRUMENT AND CONTROL REQUIREMENTS:

4.1.37 SECURITY REQUIREMENTS:

h.l:38 JDENTIFY CIhL / STRUCTURAL REQUIREMENTS: The repairs do not perform a structural function, but,only serve to direct water to the drywell sump. The materials utilized are compatible with, and do not affect the structural integrity of the existing structural elements.

4.1.39 IDENTIFY SEISMIC / DYNAMIC QUALIFICATION REQUIREMENTS:

requirements, and do not impact the seismic capabilities of existing SSC's. 4.1.40 PERSONNEL REQUIREMENTS: , I ', Not applicable. , Not applicable.

I I IC I u I Similar to the above item, the installed materials do not have a seismic hnction or Personnel shall be qualified for installation of the materials specified.

t' 4.1.4 1 SPECIAL PROCEDURES OR SPECIAL INSTALLATION SPECIFICATIONS:

The applicable portions of Specification IS-328227-004 rev. 13 are referred to in the work instructions of AWA #5. Unless directed otherwise within this ECR, all materials shall be installed in accordance with the manufacturer's instructions.

Grout is to be insta3Ied in'accordance with Specification IS-551 6 as directed in AWA #l. 4.1.42 IDENTIFY / OBTAIN INTERFACING DEPARTMENT REVIEWS: Interface reviews have been performed by the work group (Dave Ryan), the Venture planner (John Burt), Operations (Robin Brown), the structural monitorhg program owner (Sugit Niogi), the system manager (Sylvain Schwartz), the fire protection program manager (Mark Carlson) and the IS1 program manager (Greg Harttrafi).

The completed reviews are attached to this ECR. All identified impacts have been addressed, or have a tracking mechanism to ensure their completion.

4.1.43 USE ATTACHMENT 11 TO DETERMINE POTENTIAL IMPACT ON LICENSE RENEWAL: A2 152754-1 3, which will satisfy the structural monitoring requirement for license renewal and tracked under A21 52754-13. All of the questions of attachment 11 are This ECR directs a VT inspection of the drywell 1-8 sump pit liner and tracked under ECR 06-00879 rev.# ' Fq!& /I document. A2152754 E06 has been transferred to IR 00546049 A02. The conclusion this Tech Eva1 does not change disposition or repairs made by this ECR. ' Attachment 1, page 9 of9 Rev. 1 answered "no". The SSC's involved are not affected, and the materials installed do not perform any of the roles or functions addressed by the screening'questions.

4.k.44 NEIL REQUIREMENTS:

None. .

5- -. CC-AA-I 02 Revision 13 [ . Page 61 of 77 ., ., '. . . -> ECR 06-00879, Iikv. 0 A?TACHMENT

$J . PAGE( OF V tl I ATTACHMENT

'lOA Operations Department (including Radwaste) Configuration Change Review Checklist Page 1 of I Configuration Change Document No.: @M 06 00 87 9 h. 0 This Attachment is a sample of a format that can be used to obtain InterDepartmental approvals of a Configuration Change.

The content of the Attachment is the required level of questions that each department is expected to answer and provide concurrence before Engineering issues the Configuration Change. As long as the content of the Attachment is being addressed, there is no requirement to use this particular format.1 This review covers activities performed during the design phase of a Configuration Change, including initial theetings, walkdowns, detailed design development, and identification of impacts on other station programs and areas of responsibility.

1. The impact on the station equipment, changes in equipment responses, and changes in operator response for different scenarios have been discussed.

As the representative of the Operations Department, I fully understand the impaqt,, including training needs, upon my department and concur that my 'concerns have b.een adequately addressed.

2. I have confirmed the 'identified Programs, Procedures and Training requirements are complete, or initiated tracking for completion, for my department in accordance with CC-AA- 102 attachments listed below: I , Review Reauirements

@l',, InitiallDate c *I I d@& ,/O-27-% ' I* 0 Attachment 7 - Configuration Activities (List Tracking &/Q-t746 I NO. /I/u,+' 1 1 /O 06 m/b27106 'I 0 Attachment 8 - Programs (Tracking No. h ~3 Attachment 9 - Procedures and Training (Tracking I No. &,Jn4 1 3. Acceptance

$riteria for Post Maintenance Testing and any special tests required to adequately demonstrate system operability following implementation of a Configuration Change have been specified.

4. AURA for operation has been considered in th 5. 6. The Configuration Change does not interfere with operation of existing nearby equipment.

Jd 10-27-k! lh.3 70-276 1!%-+5?d Appropriate component labeling is used in the design package, including drawings.

-#Y /o-z7-i% 7. There are no operating procedure changes required by this Configuration Change that introduce new susceptibility to water hammer or hydraulic transients that might result in impacting plant operation.

8. The design can be implemented within constraints of plant operatiodmode. This includes an operation assessment of all affected systems and interfacing structures, systems and components during the mode(s) in which the design change is being implemented.

9. The configuration change has been reviewed and will not introduce a new single point of vulnerability and there are no existing SPVs (unless approved by Site Engineering Director)

10. Impact of this configuration change on Operator Aids has been reviewed and appropriate actions have been or will be taken (refer to OP-AA-115-101 and the Operator Aid Log) pGde 11. The configuration change has been reviewed and impacts on margin are understoo&The 10-27-lV design summary adequately addresses known margin impacts. (refer to ER-AA-2007)

12. Changes impacting the Clearance and Tagging Program have been identified and are being & /0-27-06 tracked. My department has reviewed the Configuration Change Document (or appropriate contents) and understands the impact regarding my department's operations, procedures, and programs.

All Configuration Change support been identified.

Date: f 0 -2? 7% OpGatZns Department Representative Return the completed form to the Configuration Change Preparer I

• I ECR 06-00879, REV. 8 8. New components are classified per MA-AA-716-210 in the PCM web-based tool, appropriate revisions in the PCM web-based tool for existing components have been made, or additions and #A- changes are being tracked to assure timely completion. (Action Tracking No. ) Nuclear Fuels Dept. design authority, if affected, have been discussed with NF and addressed if req'd. 9. Design conditions, inputs, and assumptions used in processes, designs or analyses subject to 10. The configuration change has been reviewed and will not introduce a new single point of & cc-AA-102 Revision 13 I Page 62 of 77 I' ATTACHMENT IOB *' Plant Engineering Configuration Change Review Checklist Page 1 of 1 Configuration Change Document No.: 06 -00 8 79 Rk- / This Attachment is a sample of a format that can be used to obtain InterDepartment approvals of a Configuration Change. The content of the Attachment is the required level of questions that each department is expected to ans'wer and provide concurrence before Engineering issues the Configuration Change. As long as the content of the Attachment is being addressed, there is no requirement to use this particular format. This review mvers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development, and identification of impacts on other station programs and areas of responsibility.

Review Reauirements

1. My department has participated as required, and concurred with the proposed Configuration Change; and fully understands the Configuration Change implications for my department.

Included in this review is verification that restoration activities will not result in hydraulic transients that could result in water hammer or affect the continued operation of the unit initiated tracking for completion, for my department in accordance with CC-AA-102 attachments listed below I InitiallDate 1, I 4 /cr/z7/pc

1. ,o/z7/Q # A4 7/1& 4/yi Je4 --#I+ $!A 2. I have confir;med the identified Programs, Procedures and Training requirements are complete,'

or Attachment 7 - Configuration Activities (Tracking No. A- Z/r27 C4 ) Attachment 8 - Programs (Tracking No. ) Attachment 9 - Procedures and Training (Tracking No. ) EC& 06-,0087' 40 3. Acceptance criteria for DCP Testing and any special tests required to adequately demonstrate system operability following Configuration Change implementation have been specified.

4. Parameters for performance monitoring and trending are adequately instrumented.

.. NA-' ! &/04 5. If applicable, changes to system descriptions in UFSAR and DBDs have been reviewed and are CoTect. 6. Existing Surveillance Procedures are adequate for monitoring system performance or revision are being tracked to assure timely completion. (Action Tracking No. )

8, I ECR 06-00879, REV. 0 ATTACHMENT 2 PAGE 30~ 7 cc-AA-102 Revision 11 I Page 57 of 63 . ATACHMENT IOC Engineering Programs Configuration Change Review Checklist . Page I of 1 // CONFIGURATION CHANGE DOCUMENT NO.: This Attachment is a sample of a format that can be used to obtain InterDepartmental approvals of a Configuration Change. The content of the Attachment is the required level of questions that each department is expected to answer and provide concurrence before Engineering issues the Configuration Change. As long as the content of the Attachment is being addressed, there is no requirement to use this particular format. This review covers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development, and identification of impacts on other station programs and areas of responsibility.

8' Review Requirements InitiallDate

/rlk /0/27& fl& lo)&7hb ) * /aJL7IQL N14C /djZ7/0L 1. My department has participated as required, and concurred with the proposed Configuration Change; and fully understands the Configuration Change implications for my department, 2. I have confirmed the identified Programs, Procedures and Training requirements are complete, or initiated tracking for completion, for my department in accordance with CC-AA- 102 attachments listed below: AttachmegIA- Configuration Activities (Action Tracking flk fohh 1 Attachment 8 - Programs (Action Tracking No. Nh' Attachme t 9 - Procedures and Training (Action Tracking No. e?b ) fiw /0)27b6 3. DkP Testing has been specified to adequately demonstrate program compliance for components. These tests have been reviewed to assure that there is no likelihood of initiating a water hammer event.

4. Changes to system descriptions in UFSAR and component DBDs have been reviewed and

/uAc t?0b7hb are correct. 5. Existing Surveillance Procedures are adequate for monitoring system performance r W /Jbbb 6. The configuration change has been reviewed and impacts on margin are understood.

The Wd7k b revisions are being tracked to assure timely completion. (Action Tracking No. Mh 1 design summary adequately addresses known margin impacts. (refer to ER-AA-2007)

My department has reviewed the Configuration Change Document (or appropriate contents) and understands the impact regarding my department's operations, procedures, and programs.

All Configuration Change support h7l474.A t have been identified. Engineering Programs Representative Date Return the completed foim to the Configuration Change Preparer or Sign Electronically in PlMS or Pass P o rt ECR 06-00879, REV. 0 ATTACHMENT%

PAGE@F 7 cc-AA-102 , Revision 11 I Page 57 of 63 I( ATTACHMENT 1OC Engineering Programs Configuration Change Review'Checklist Page 1 of 1 CONFIGURATION CHANGE DOCUMENT NO.: e I?. 0 6 - O 9 7 9 , &c,u.D This Attachment is a sample of a format that can be used to obtain InterDepartmental approvals of a Configuration Change.

The content of the Attachment is the required level of questions that each department is expected to answer and provide concurrence before Engineering issues the Configuration Change. As long as the content of the Attachment is being addressed, there is no requirement to use this particular format. This review covers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development, and identification of impacts on other station progtams and areas of responsibility.

I Review Reouirements InitiallUate 4" ' 1. My department has garticipated as required, and concurred with the proposed Configuration

2. I have confirmed the identified Programs, Procedures and Training requirements are complete, or initiated tracking for completion, for my department in accordance with CC-AA- 102 attachments listed below: Change; and fully understands the Configuration Change implications for my department.

I f&Jd/2,/&

JAy ,b)%&, Attachment 7 - Configuration Activities (Action Tracking <&/a 7;/6 4 No. Y /A 1 f. . Attachment 8 - Programs (Action Tracking No. rJ /A- Attachment 9 - Procedures and Training (Action Tracking No. fJ iff 3. DCP Testing has been specified to adequately demonstrate program compliance for components. These tests have been reviewed to assure that there is no likelihood of 4. Changes to system descriptions in UFSAR and component QBQs have been reviewed and ark correct. initiating a water hammer event. Id /A / A 5. Existing Surveillance Procedures are adequate for monitoring system performance or , ' iJ /A revisions are being tracked to assure timely completion. (Action Tracking No. 6. The configuration change has been reviewed and impacts on margin are understood. The L-' f design summary adequately addresses known margin impacts. (refer to ER-AA-2007)

My department has reviewed the Configuration Change Document (or appropriate contents) and understands the bJ ( A 1 ocedures, and programs.

All Configuration Change support Date Return the completed form to the Configuration Change Preparer or Sign Electronically in PlMS or Passport

.. cc-AA-102 . Revision 13 I .?; Page63of77

' , . #I ECR 06-00879, REV. 0 . ATTACHMENTV " . PAGESOF 7 .. ATTACHMENT IOC . Engineering P tog rams Configuration Change Review Checklist I / Page 1 of 1 CONFIGURATION CHANGE DOCUMENT NO.: he 06 -0087 9 PW.0 _, This Attachment is a sample of a format that can be used to obtain InterDepartmental approyak of a Configuration Change. The content of the Attachment is the required level of questions that each depa'rtment is expected to answer and provide concurrence before Engineering issues the Configuration Change. *'long as the content of the Attachment is being addressed, there is no requirement to use this particular format. This review covers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development, and identification of impacts, on other station pyrams t IO and areas of ' . responsibilHy.

'. Review Reauiremenb InitialFate I' 1. My department has participated' as required, and concurred with the proposed Configuratipn Change; and fully understands the Configuration Ch'ange implications for my departmentr

2. 1 have confirmed the identified Programs, Procedures and Training requirements am complete, or initiated tracking for completion, for my department in accordance with CC-M- 102 attachments listed below: Attachment 7 - Configuration Activities (Tracking No. ) Attachment 8 - Programs (Tracking No. AV52754 Et1 0 Attachment 9 - Procedures and Training (Tracking No. ) 3. DCP Testing has been specified to adequately demonstrate program compliance for components.

These tests have been reviewed to assure that there is no likelihood of initiating a water hammer event. 4. Changes to system descriptions in UFSAR and component DBDs have been reviewed and are correct. revisions are being tracked to assure timely completion. (Action Tracking No. ) 5. Existing Surveillance Procedures are adequate for monitoring system performance or 6. The configuration change has been reviewed and impacts on margin are understood, The L L design summary adequately addresses known margin impacts. (refer to ER-AA-2007)

My department has reviewed the Configuration Change Dowment (or appropriate contents) and understands the impact regarding my department's operations, procedures, and programs.

All Configuration Change support department have been identified.

Engpring Prbbms Representative Return the completed form to the Configuration Change Preparer or Sign Electronically in PlMS or PassPort cc-AA-I02 Revision 13 I , Page 64 of 77 ECR 06-bo379, REV. o PAGE 6 OF 7 ATI'ACHMENT 2/ ATTACHMENT 10D ' I Maintenance Department Configuration Change Review Checklist 6@ ob-obB3 #!fl d / Page 1 of 1 I Configuration Change Document No.: This Attachment is a sample of a format that can be used to obtain InterDepartmental approvals of a Configuration Change. The content of the Attachment is the required level of questions that *each department is expected to answer and provide concurrence before Engineering issues the Configuration Change.

Ap long as the content of the Attachment is being addressed, there is no requirement to use this particular format. I This review covers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development, and identification of impacts on other station programs and arZas of responsibility.

', Review Reauiremene 1 InitiallDate

1. My department has participated as required and concuked with the proposed 'Configuration Change; and fully understands the Configuration Change implications for my department.

J 2. I have confirmed the identified Programs, Procedures and Training requirements are complete, or initiated tracking for completion, for my department in accordanp with CC-AA-102 attachments listed below: -4 M 4. Demolition and removal boundaries have been clearly specified.

5. Equipment layout allows maintenance space for newly installed components and does not interfere with maintenance of existing equipment. -q 6. Items not in inventory, long lead time items, and required spare parts have C. been identified. (Tracking Number: ) 7. Acceptance criteria for maintenance testing has been specified as required.

-- ble contents) and understands the Configuration Change support ATTACHMENT 10F Configuration Change Review Checklist for Use by Other Departments , - Page 1 of 1 Department dz- /z# &i?& CONFIGURATION CHANGE DOCUMENT NO.:& -0 879 l I This Attachment is a sample of a format that can be used to obtain InterDepartmental approvals of a Configuration Change. The content of the Attachment is the required level of questions that each department is expected to answer and provide concurrence before Engineering issues the Configuration Change. As long as the content of the Attachment is being addressed, there is no requirement to use this particular format. This review covers activities performed during the design phase of a Configuration Change, including initial meetings, walkdowns, detailed design development,.and identification of impacts on other station programs and areas of I i InitiallDhte responsibility.

I I , Review Resuirements'

1. 2. My department has participated in the Configuration Change process (sCope meetings, walkdowns, impact review, etc.) as required, and concurred with the proposed Configuration Change; and fully understands the Configuration Change implications for my department.

I have confirmed the identified Programs, Procedures and Training requirements are complete, or initiated tracking for completion, for my department in accordance with CC-AA-102 attachments listed below: 0 Attachment 8 - Programs (Action Tracking No. ) A, 0 Attachment 9 - Procedures and Training (Action Tracking No. ) 3. Other Considerations required to be completed in support of the Configuration Change: A/A /A/ I 4. The configuration change has been reviewed and impacts on margin are understood.

The design summary adequately addresses known margin impacts. (refer to ER-AA-2007)

My department has reviewed the Configuration Change document (or applicable contents) and understands the impact regarding my department's operations, procedures, and programs, All Configuration Change support actiyities required of my department have been identified.

1 Uected Plant Department Representative (See EC Milestone for Dept Review signature authentication)

Return the completed form to the Configuration Change Preparer or Sign Electronically in PlMS or PassPort I ECR 06-00879, REV 0, ATTACHMENT 3, PAGE 1 OF 3 Procedure EP-011 Rev. 11 AmerGen, Exhibit 2A An ElebnlBmrh CMrgy COrnFany QUALITY CLASSIFICATION EVALUATION FORM (Typical)

EP-Oil I ECR NO: 06-00879 REV: 0 , PAGE LOF- 1. Component Information

' NEW COMPONENT REVISION CI INITIAL CLASSIFICATION , Faciliv. a Unit1 Category:

M Type: MlSC CRL Component No.: NROl\MB001-INT.

Host System No.: -187 Host ComponenVDescription:

DRMELL I I System Classification:

ElQ CIA* , I7N Host Component Classification:

lXlQ OA ON 1, 811. Evaluation

1. What are the safety functions of the host system and the host component?

If both the host system and host component do not perform a safety function, mark this question and question 2 as "NIA" and continue to question 3. Host Svstem: Host System: I ,I 0, I , The Containment is an enclosure for the reactor vessel, the Reactor Coolant Recirculation System, and other branch connections of the Reactor Coolant System. per uFsAR section 6.2.1, the design criteria for the Containment are as follows: a. TO withstand the peak transient pressure (coincident with an earthquake) which could occur due to the postulated break of any pipe inside the drywell. I b. To channel the flows from postulated pipe breaks to the torus. C. To withstand the force caused by the impingement of the fluid from a break in the largest local pipe or connection, without containment failure.

d. To limit primary containment leakage rate during and following a postulated break in the primary system to substantially less than that which would result in offsite doses approaching the limiting values in 10CFR100. , e. To include provisions for leak rate tests. Host Component:

The concrete floor slab at the base of the drywell provides a foundation for the RPV support pedestal, as well as a level support surface for personnel and equipment

2. Does the item play a role In accomplishing the host system or host component's safety function?

If "NO", go to Question 3. If "YES" mark questions 3 and 4 as "WA" and go to section 111. In either case, explain your answer. 3. Does the item serve as an isolation device between a safety related and non-safety related interface with regard to fluid systems, electrical circuits, primary containment or effluent control? If "YES, explain your answer. If "NO", mark this question "NO" and go to Question 4. 4. Are there any credible faiture mechanismdmodes of the item that would prevent its host system or host component from performing its safety function?

Explain. The amount of potential dwell debris that could enter the ECCS suction strainers is evaluated in calculation C-l302-241-E610-081.

111. Component Classification If the answer to question 2,3 or 4 is YES, classify the item as Safety Related (a). If the item is not Q, is it required to meet any of the commitments or requirements of Exhibit 3 in EP-0117 If YES, identify those commitmentdrequirements on Exhibit 28 and classify the item as Augmented Quality (A); otherwise, classify the item as "Not Safety Related" (N). IV. Revisions NO NO Q (Safety Related)

A (Augmented Quality)

N (Not Safety Related) 17 UPGRADES - Operability Review/CAP Initiated DOWNGRADES - 1 OCFR50.59 Previous Report number: (Required for EDMS) CAP No. SE No.: MAINT. RULE COORD. NOTIFIED OF CLASSIFICATION REVISION:

PREPARER'S INITIALS:

SM (EP-O11/S6)

E2- 1 DATE: 10/27/06

. ECR NO: 06-00879 ECR 06-00879, REV 0, ATTACHMENT 3 PAGE 3 OF 3 RevNo.: 0 Date: 10/27/06 Quality Class: A 1 EQ (10 CFR 50.49): ECR 06-00879, REV 0, ATTACHMENT 3 PAGE 2 OF 3 ' QC Evaluation (Typical)

Facility:

E Cmp Nbr: NROl\MB001-INT Unit: 1 system : 187 Category:

M Type: - Functions: (include Safetv Function for Safetv Related items) NONE. INSTALLED TO MINIMIZE WATER INTRUSION INTO CONCRETE FLOOR. ALL ITEMS ARE TO BE EVALUATED REGULATORY COMMITMENTS [Blank indicates "N". X indicates

'Y) 0 R.G. 1.23 (Meteorological Monitoring) 0 10 CFR 50.62 (ATWS) R.G. 1.26 (Quality Group Classification) 0 R.G. 1.143 (Radwaste Management Systems) 0 R.G. 1.155 (Station Blackout) 0 R.G. 1.97 CAT 1 required to be classified "Q" 0 IEB 79-18 (Plant Paging) 0 R.G. 1.97 CAT 2 0 IEB 80-1 1 (Block Walls) 0 R.G. 1.97 CAT 3 0 10 CFR 73.55 (Security)

"'(Note l),., R.G. 1.97: Check one Box only Seismic Cateaow: Check one Box only 0 W - (Seismic Class 1 -Operable During & After SSE) 0 X - (Seismic Class 1 - Operable After SSE) 0 Y - (R.G. 1.29 Anti Fall-down)

Z - (No Seismic Class applies)

SSEUSQUG:

Check One Box Only 0 1. (Host Component SQUG Eval- Active SSEL.) 0 2. ("Rule Of Box" SQUG Eva1 - Active SSEL) 0 3. (Essential Relay - Active SSEL) .- 0 4. (Operator Action Relay - Active SSEL) 0 5. (Host Component SQUG Eval- Inactive SSEL.) 0 6. ("Rule Of Box" SQUG Eva1 - Inactive SSEL) 0 7. (SQUG Qualified Component Not On SSEL) M-RULEEPIWPSA 1 M-RULE (R / Y / N) 0 A4 SCOPE (Y / N) 0 PSACLASS(Y/N) - ORAM (0 / S / B/ N) 10 CFR 50 APP. WBTP APP. A (FHARl 0 FSSD(N/1/2) 0 FlREPROTC(/N)

~ OTHER CLASSIFICATION REQUIREMENTS (Blank indicates "N", X indicates "Y") 1E Interface Emer Ht Sink 0 Press Boundary Inst. License Renewal ASME REQUIREMENTS (Blank indicates "N". X indicates

Y'*) - IS1 CLASS(A/C/N/M/1/2/3)

IxI SECXI IS1 0 SEC XI IST 0 ASME REPAIWREPLACE 0 RefsDther Commitments:

Comments:

MUST MEET ENVIRONETAL CONDITIONS OF DBLOCA FOR SUCTION STRAINERS CLOGING.

References:

C-1302-241 -E61 0-081, Rev. 0 Reason for Revision: - -

ECR 06-00879, REV 0, ATTACHMENT 3 PAGE 3 OF 3 Note 1 : "Y" Rewires the following Soecial Text Entrv in PIMS: "***SECURITY REQUIRED PRIOR TO WORK ON THIS COMPONENT***" CMP NBR - 5 0 Exhibit 2C - EP-011 CATG TYPE FUNCTION (Include Safety Function for "Q" components)

QC Evaluation (Typical)

Multiple Component Sheet For ECR#

EL. 0'- I I - 114" ECR 06-00879 1 -ECR 06-00873 ATTACHMENT 4 PAGE I OF I - BY:D.ABBRJJSCATO DATE: I 1105106

- 7 m,. x. 1997 1 88pM NORTON SCP WOODSTOCK ( E151 3375261 NO.827 P.4/16 'r .+ C Korea Atomic Energy Research Institute P. 0. BOX 7. DAEDUK-~ANJI.

TAEJdN. 3O5a. KOREA :i '*, .- SMLE CERTIFICATE OF RADIATION PROCESSING DOSIMElza DOSE I I MwsuRE TIME 466hr 1994. 6. .- 26. 14:66 - 7. 7. 06:s 1 mssrI!!E:54~

.. Head, Radiation Processins Proie i 00.27.1997 1 : 09PN MORTON SCP WOODSTOCK ( E15 1 3375261 9, I.. No.827 P.Wl6 . I, I I.: 0 c* XT, 27.1997 1 : 09PM MORTON SCP WOODSTOCK c e15 13375261 . NO.827 P.Wl.6 .. . 0 c. :..-

_. .. OCT. E. 1997 1

B9PM MORTON SCP WOODSTOCK ( 81 5 I 33'!5261 NO.827 P.746 .**. " 1- - LP" II 5/69 TD-569N i POLYSULFIDE POLYMER I *e RADIATION RESISTAhkE OF LP@ LIQUID POLYSULFIDE POLYMER BASED COMPOUNDS , 1 II INTRODUCTION I I Several independent test laboratory studies hav,e been conducted on the radiation resistance bf Lp@ liquid polysulfide based compounds.

In one study, an LP liquid polysulfide based compound withstood gamma radiation doses up to Si6 x lo7 roentgens, for a period of seven days, with little degradation to physical properties.

In a second study, specially formulated LP liquid polysulfide based compounds immersed in JP-4 jet fuel withstood as much as 1.7 x IO8 roentgens, with only a small loss in physical properties.

BoTh srudies showed that commercially available LP liquid polysulfide polyrher base aircraft sealants formulated io meet Federal Specifications MIL-S-7502C and MI L-S-8802C had the best resistance to radiation.

I DISCUSSION Of RADIATION RESISTANCE DATA FROM OTHER REPORTS One report which contains radiation data is entitled, "Research on Elastomeric and Compliant Materials for Aerospace Sealants", Technical Documentary Report No. ASD-TDR-62-709.

In this study, eight different polymer based sealants, which were all proprietary sealants, were evaluated and compared.

Of those sealants tested, rhe LP liquid polysulfide based sealants gave the best resistance to gamma radiation, In testing The LP liquid polysulfide based sealant compounds for radiation resistance, three different curing agents were used, The best radiation and heat resistance results obtained were on those LP polysulfide polymer compounds which used either the chromate*

or MnO, cure as compared to the PW1 cum. The best results obtained in this study were on an LP liquid polysulfide polymer based compound that withstood gamma radiation doses of 6.4 x lo6 roentgens at temperatures of 190°F for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. After 7 00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at 25OoF, this compound was stili serviceable although some degradation was evident. A second repoR that contains considerable radialion data on various sealant systems is entltled, 'The Effects of Reactor Radiation on Elastomers and Sealants4 I I", by L. L. Morgan. This is Document No. NARF-60-37T, and Is also lined as ASTIA No, 256,689. In rhis study, a number of proprietary compounds, as well as compounds prepared by Thiokol, were evaluated againn a number of combined environments.

The maximum gamma dosage which LP' liquid polysulfide based sealants withrtood, when exposed in alr at 9@F, was 7.7 x lo8 roenrgens.

After this rnaximqm Karnrna radiation exposure, the samples stilf exhibited tensile propercies of 400 psi and elongation values of 265%. - /CHEMICAL DIVISION 930 Lower Ferry Poad P.O. Box 1296 OTrenton, N. J. 08607 0 (609) 396-4001 0 Reglotarad trademark of TClclrd Carporolfan.

The InformalIan in thle b~llatlf~

I$ drrfvod ham Ihs bast waltabie IOU~CBB snd 18 b~~lfivaa Io DB accLnaIe.

Clovwor no euarente8 k.elpreassd of Impllad rosardtng tho ~CEU~~C~ of lhcie d81q 01 tho VDO of thlr DroUuEI. nor aro any aleternant8 In INa bulletln tnlanded Io lnfrlnge on on; pBIanL 4 * ~, 0cT.S. 1997 1: 18pM NORTON SCP WOODSTOCK(E15)3375261 . N0.027 P.Wl6 - '. y",' in another rea, cured tensile specimen samples of seyeral LP liquid polysulfide polymer based sealant compounds were Immersed in JP-4 fuel for seven days. Next, the samples recdived a gamma dose of 1.7 x IOB roentgens, after which they were leh immersed in the'JP-4 fuel for thiny more days, After complerion of the exposure tests, the samples still exhibited a tensile'strength of 350 psi and an elohgation of 125%. The LP liquid polysulfide polymer based cornDounds used in these exposure tests were based on a chromate and MnO, cure system. Refer to Table I for typicat LP liquid polysulfide polymer based formulations and the Fhysical and heat resistant properties of the cured compounds.

Then, refer to Tables I1 and 111 for a summary of results on five cure systems and their correlation between radiation and beat resistance.

All data in rhe following Tables was compiled from tests conducted by Convalr, a division of General Dynamics, Fort Worth, Texas, Convair conducted all the hadlalion studies on the test sample?, which were prepared ' and supplied by Thiokol Chemical Corporation.

Among the sealants formulated by Thiokol, It was established thar cure systems ex hibiting the best heat resistance also exhibited the best radiation resistance.

Exposure to higher temperatures during irradiation indicated that heat alone can cause L. .I I I degradation.

0, 0 I t TABLEI 'E PHYSICAL PROPERTIES OF COMPOUNDS BASED ON THIOKOL'S LP-32 POLYMER / / Compound (pbwl A B C 0 i! LP-32 Polymer Titenox RA-50 25% Maleic Anhydride in Ourer 10694 SRF 43 M90 Sutfur Srearic Acid Cumene Hydroperoxide 5096 TeOl in Diburyl Phthalate 43% Ammonium Chronwre Cabosil M-6 Sodium Stearate MnOz ."D" Grade EH-330 Cyclohexanone 50% PbOa VI TP-680 Soluxion in Hz 0 1 00 0 t 100 50 - I ' loo 100 I 1.2 2 i 3P 0 I I- c -*' 20 Original Physical Propetth Tensile, psl 300% Modulus, psi ElorigarTon, % Hardness, Shore A 390 240 500 50 310 780 530 33 43s 130 910 46 ,-:- 800 810 590 61 Physical Fropenies After One Week at 1!S0F. Tensile, psi 3gp% Modulus. pi Elongation.

96 Hardness.

Shore A 550 300 540 ' 53 520 1 65 830 40 360 150 630 50 910 610 490 62 Physical Properties After One Week at 212'F. Tenslls, psi 710 420 870 950 780 300% Moddur, psi 380 1 40 290 680 290 Elongation.

38 440 350 740 460 710 Hardness, Shore P 57 49 57 64 48 .L Physical Properties After One Week at 250'F. Tensile, psi 540 380 800 710 1 430 Y- 300% Modulbs, psi 120 460 510 160 Elongatlon, 96 190 BSO 460 420 750 Hardness.

Shore A Y. 64 48 58 67 43 if 3

. ~ -0~1 .ZY. IrJI 1: llpM NORTON SCP WOODSTOCK(E15)~EZ61 , NO. 827 P. 18/16 II '?. -3% 01 *. b / TABLE II I I PHYSICAL PROPERTIES OF EXPERIMENTAL SEALANTS, BASED 1 . ON THIOKOL'S LP-32 POLYMER, AFTER IRRADIATION IN AIR AT 90°F.' 1.5 I 10.1 ..- I 0 1 10,l 8.4 17.4 :i ^I Neutron %IOu ' 0 y; c .4 a 7 0 7.3 a 7 0 1,3 7.1 7 ,o 1.3 7 7 0 1.3 7 480 460 300 250 \ 420 260 170 820 580 420 400 1230 1140 650 C' 480' 280 250 -,- -, \ Elongarion, 96 Si26 , 490 210 166 700 720 200 200 '( 670 - -. 560 320 260 " 570 440 210 160 5% " 450 2511 21 0 Gamma irradiation in Roentgens.

but originallv expressed as ergslgrrr. (Cl Neutron lrradiation In n/cd where E>0.33 MEV I h T?

OCT. zi!. 194 1 : 1 1PM MORTON SCP WOODSTOCK ( E15 13375261 .NO.627 P.1146 P t.* - V *. 'I '9. . I ... I / TABLE 111 PHYSICAL PROPERTIES OF EXPERlMENfAL SEALANTS BASED ON THIOKOL'S LP-32 POLYMER, AFTER IRRAD1ATION AND IMMERSION IN JET FUEL *I LIST OF BRAND NAME COMPOUNDING INGREDlENV Material Trade Name Chemical Composition Manufacturer TP@ -680 Polymeric Thio kol/Chemica I Division Dura 10694 Phenolic resin Hooker Chemical Corp. MnO? - "D" grade Manganese dioxide, special Manganese Chemical - Titanox RA-50 Tiraniurn dioxide Titanium Pigments 0 Cabosil M-5 Fumed sifica Cabot Corporation Catalyst, tertiary amine Thiokol Chem. Corp. grade MnO, Corporation Corporation

/ I' , Q 1 : 11PH MORTON SCP WOODSTOCK C C15l3375261 NO.827 P.lW16 DlVlSl ON HEADOUARTE RS P. 0. Box 1286 Trenton, New Jersey 08607 (609) 3964001 SALES OFFICES 4 Suite 521 One Oxford Valiey Langhorne, Pennsylvania 19047 1 (21 5) 752-5355 6272 Oakton Street Morron Grove, Illinois 60053 (312) 583-2900 1 2631 Michelle Drive Tustin, Callforqia 92680 (714) 832-3560 IN CANADA: Thiokol Canada Limited 75 Homer Avenue Toronto, Ontario, Canada M8Z 4x5 (416) 259-1141 IN ENGLAND: .. c Thiokol Chemicals Llmited Station Tower, Statton Square Coventry CVl2GH, England Telephde:

2-1 213 CH EM1 CAL DIVISION

• A DIVISION OF THIOKOL CORPORATION TRENTON, NEW JERSEY 08607 Y I .!% ,' e:. ,. . ' ... *:. 'Engineering Paper NO. , 893 t TIE E*FECT OF NUCLEAR I1ADYITION ON S*XLABT$, I c , I) I' * . I1 ,, I 'i . .' 'by I I I Raymond A. Siebert Process Engineer Materials Research 6 PrPcess;,Epgineeriag Douglas Afrcraft Company, Inc, . c

• c Tbis papet to be presented at the Society of Aircraft Haterials and Process Engineers, Sppcsbnn on Sealats ad Scaling Aircraft, Missiles, and Electrical Components, October 28, 1959, in the fnstitutc of Aeronautical Sciences, 7660 W. 3everly Blvd., Los Angcles, Califomfa i;

, NO.827 P.14116 c 0 In additfon to the obvious rhmnaf end mtchantcal effects,'of an atomic exploshn, additional, effects nay result from exposure to high intensitp nuclear radiation.

and shock wave of an atomic detonation could ionceivably become disabled because of radiation effects on components of aa essential system such as hydraulic controls or power plant. had the opportunity to investigate the effects of nuclear fadfation from an atomic explosion on various process materials used in the construction of aircraft and missiles.

sealants which were selected because of their general usage in the air- frame and iss silt industry,

• 4 An aircraft or missile which might survive the hear I Recently, Douglas Aircraft Company 'Ilncluded in the test materials we= vaiibus -.I 1, Raterial A is a polysulfide based H2L-S-8502 typk jet fuel resistant integral fuel tank sealant which employs a chromate based accelerator.

I Hatpriai B is a black, polysulfide based MIL-S-7502 type l*ntegral fuel tank sealant vhich uril5zes a lead perox'ide based accelerator.

Material C is a polysulfide based Ma-S-8516 type electrical p.qttlng compound which utilizes a lead pemxide based accelerator.

Haterial D is a room temperature curing silkone based sealant. HaterialE is a heat curing silicone based sealantvh%ch is puttp-like in consistency before cure. I 2. ' I 3. , I - , 4 4. 5. ' , b. I Specimen Prepara tiou Test spechens were prepared from 118 inch thick sheets of cured sealanc vhich had been milled to r~ovea entrapped air immediately after addltion of the accelerator.

After the sbeets had cured 7 days at 77

• 2%., dab- bell specheas uere cut using the die described in ASM D-412-SlT 8s Die D. The resulting specbeas measured 4 inches in lagth with a .maxburu width of 5/8 of an hch and a throat width of 1/8 of an inch. Since Haterial E, the heat: turfng silicone, vas too viscous foz air-free mailling, 112 by 4 inch rectangular specbe- vete cut fm a 118 inch thick sheet vhich had been pressed from a portion of the uncured cOmp0-d. Each specimen was then weighed to the oeasest milligram and enclosed in ;B piece of 1100 aldm (2s) tubing with an imide diameter of 3f4 of an inch and a lengrh of 5 %aches. The ads of the tubes were trjmptd closed and the sealants allowed to cure an additional 37 d8p at 77* 203, The specimens were then divide'd into 5 groups,vith each graup SonsrLsting of 3 specimens of each sealant, 4 control group, was encased in a 6 inch aluminum sphere having a wall thickness of 1-112 inches in order to protect the spechens from thermal and mechanical damage. These spercs vere shipped to the test site vhere they were placed at varying distances from ground zero- The control specbens were maintained at 77

• 29. for the duration of the test, - Each group, vith the exceptton of the

~ ~ 0~~.2T.1997 1:lZpM MORTON SCP WOODSTOCK(E1513375261 N0.027 P.lW16 --- *i *I -*I h z.

• C" Eighteen days after the detonetiop, The test spedmens vere removed from the almninum tubes and checked for induced radioactivity.

// sulfide specimens - Msterlals A, B snd C - uhtck had been exposed at Positfons 1 and 2 exhiblted any measurable induced radioactivtty, as shown in che Table of Results. reveighed and per cent changes in veight calculated.

significant trends apparent in the welght changes except, perhaps, in Haterial E which will be discussed later. Only .the poly- All specimens including the controls were There were no cur; of 62 di~ys, were tested for n properties at 77

• 29. using a e 2-1 clamps and operating at a* minute. All specimens of )laterial , there was no consist&&

pattern Fn or elongation of the exposed specheas ttd specbeas of fuel tank sealants, ght Sncrease in ultimate tensile opostional to the amouat of radiation nly consistent changes vere observed eclmens o* Haterial E, vhere a increasing proximity to ground Rex Durometer, Node1 A. zero was noted. .. The changes tn weight and hardness exhibited bp the wposed specimens of Katcrlal E Yere possibly caused by Jncreased temperatures as the specimens vere s5lxatid closer to ground zero. which normally requires 5 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 250OP., the specimens of .Haterial?

A, B a08 C at this position should have exhibited detectable signs of heat exposure, such as increased tensile strength ox reduced elongation.

exhibited by Haterfal E vere probably a result of bombardment by thermal neutrons whose energy effects may have been sufficient to polpcrtze the relatively 10u molecular weight silicone compdnd. Generally, the sealants tested did not experience sufficient damage to impair their serviceability at the levels of radiatlon invdved S.a this test. from an atomic explosion would probably be destroyed or disabled by the hear os ahock vave, any effects on sealsnt materials at these levels vould appear to be of secondary interest.

0 However, if the temperature at 5'~ 11 Position 1 was sufficient to cure Haterial E to a hardness of 45-50, 0; 2 - ', Crc 8 3 du 8 3 pc Since there appeared to be no other ev*deace of beat effects, the chmges - Since an aircraft:

or missile exposed to hCgher levels of zadiatioa U 'I L

PULYSPEC PAGE 81 NSF Xafernationd . I NOV 20, 1997 Ann Arbor, MI Sacr;mtnto, CA Washinglon, D.C. Bru~se16, Belgium QD .. 1 '. f .I .. I I I' Send To 32300*IM' Plant 32301 MORTON INTERNATIONAG, IUCd 100 NORTH RWERSIDE PUZA: Attn: MR. MARK NOWAK I CRICAM, IL 60606-1598 . ' MO~TON' INTERNATIONAL, mc. 812 4 ELDER FERRY ROAD ' I4095 POINT, MS 39581 Attnz MIL HAL MC LAUGIlLXts I. I I *a I 4, I 8. Tbank'you for having youz product tested by NSF: The enclosed report details the rersulte af the feaf'ing performed on yovz pX&VCr. y?W program representative wi11 be contactlng you in the near future if there are any remaining Yaaues concrrnihg the statue of this product. Plaaae do nat hesitate toicontact VB If you have any immediate questions pertaining to your product. ' .. I I. *. 0 a ,!F97 11 2 0 54 0 5 Report for Job 955316 Page 1 of 6 I. Thi8 report shall not be reproduced, sxcrpt ir\ ita entirety, vithouf thm written approval of NSF. This report not represent USF Csxtifios@Zen 9Y aurhbulaatien

+e YOQ tho WSF Mark. hutheritation Co uoo tho NE?? Hark io Lh to product8 appearing b the Companyrs Official NSP LiJtlng Boek ez NSFpe Internet Product Ccxtifisation Direi P.O. Box 130140 Ann Atbor. Michigan 481 13.0140 USA 313-749-8010 1-800-NSF-MARK Fax 3 13-769-0109 E-Mail: info@nsf.org Web:http://www.nsf.b%

I. POLYSPEC Tracking ID: 'IA01875 Re ion:.-04 caqlectioa Date: IO-APR-19:96 OO:OO:OO,OO

// .

Description:

Thiokol 2235-M Sampled: XPR;10, 1996 Re c e ived : Lab Number: 560502730

~l'as 3 ~unct i on : JASM/G'SK Tracking ID: IA01875 . Listed. el; Fetest: AI Normalization Voluma (Field) : 1 Normalization Factor - @2: 0 Testigg Standara:

61 Normalization Ambunt (Field): 7.75 11 PAGE 82: 3996 P ar wt b r - . Result un t er c.d I I' qescxiption:

Th5okol 2235-M, 'sample exposed at ~OC and p~ 5 ' Lab Number: S61003055 sampled:.

MR IO,, i996 Pmer I - Redeived:

APR 16, 1996 Additives sample preparation:

informattan , bate exposure completed 10-30-96 ' . Sampler 11-OCT-ISS6 00 :DO 0 d 8 . Conirol: 11-OCT-1996 OOk 00 surface area expoaed (All . Final volume of solution (91) Length of axpowre . (T1) Arsenic, Cadmilurn , Lead CI PHercury .. .. in2 10-30-96 liters 10 96 10-3 0- 96 ug/L 11 96 21-0 8- 96 11-08-96 mg/G 10-17-96 hour# ug/L ug/L ,

Description:

Thipkol 2235-M, Sample exposed at 30C.and pH 0 Lab Number: S61003056 Sampled: ~PR 50, 1996 Received:

APR 16; 1996 1. Pweter : Y C&#? f! Additives sample preparation:

infomation Date exposure completed . 10-'30-96 . Sampler 1%-OCT-1996 00:OO cpnkol: 11-OCT-1996 OOb 00 Surfrac urea txpoatd (Al) 12 6 1 28 . in2 Zength of. sxpooura (Tl) liter. a Rinal volume of solution (91) 7.30 7.60 24.00 24 -00 hourn 0.032 ND (0.001) mg/L 2-Mercaptoethanol , ND (50) ND (50) ug/L Bia (2-Ethylhcxyl)

Phthalate ND (1) ND (1) ug/L 'Dukyl Benzyl Phthalate 3 ND (1) US/L Phena 1 hca Phthalates, in Water, Scan, 6 compounda, 625 10-30-9 6 10-30-96 10-30-96 10- 15-9 6 11-0 5-9 6 11-18-96 11-18-96 . ND Indicates Not Derqcted.

F9711205405 Report fox Job 955316 . Page 2 Qr.6

~ 10/25/2886 11: 49 2813976512 POLYSPEC '" S61003056 Continued I I Pwer, S ample a1 qn4ta Phthdlates, in Water, Scan, 6 colnpsunbs, 625 Continued Di-n-Butyl Phthalate

<I 1 uu/L Diethyl Phthalate 5 <l ug/L Dimethyl Phthalate ND(10) ND (10) ug/L 8 ,' Di-n-Qctyl Phthalate ND (1) ND (1) ug/L Note:. Also found approximately:

8.2 ug/L AS 1 Benzensmetganal 3.3 ug/L ASt 1-Phenyl ethanoae I 3.9 ug/L AS: 2-Phcnyly2ipropanol

• I' External 10 linaaj Phthalatee, in Water, Scan, 6 compounda, 623 7 ug/L LP: TetramethyL urea 6 ug/L LP: Mix of oxygen containing, HW 89 and oxathiolane and ethyl 6 I ug/k LP: 'Nlt~ogen.cqntainlng, MOQ>114 9 ' ug(L ZIP: (PropenyloAy) benzene 10 ug/L LP: Trimethyl gentanediol 3 ug/L LP.r (Propenyl) phenol 3 ug/L LP: Oxygen contiaining, W=>.l44 ,7 uq/L 'LP: Tetramethyl thiourea 3 ug/L LP: Nitrogen, dxygen containing, &>a57 . 20 ug/L Le: Oxygen aengaining, MW->142 10 ug/L Yip: Oxygen csncaining, MW>159 46 ug/L Lgr Oxygen contieining, EpQ>173 900 ug/L LP: Mix.of nitdogen containing, MW=>199 and surrogate standard 20 ug/L LP: Aromatic v$ygan containing, MV?=>162 3.00 ug/L LPt Aromatic OXygen containing, MW=3164, 81 30 uq/L LPt Aromatic njitrogen, oxygen containing, MW3178 0 1QQ ug/L ZIP: Aromatic oqygen containing, MW~>l.64, #2 4, ug/L LIP: Mix of oxyden containing, MoJ=>lBO and ditert butyl rnethbxy ug/L LP3 Oxygen cent~ainina, MW=>202 . 0.61 US/& AS: Bia (2-ch1ok:oethoxy)merhane I .I 20, ug/L LP: Oxygen contiaining, m>103 hesanol I

• 200 ug/L LP: Mix of Diodathiocane and aurragat;e etandard d5-nltrabenzene dt3- fluorobqphsnyl

.. phenol ug/L LB: Nitrogen cdntaining, Me176 ~ 0 8 8 o, w Ll- oxygen containigg, MW=>206 . 0 4% $ 5 $ uq/L LP: Mix of nitdogen .containing, MW>198 and oxygen containing, U& 'ug/L W=>2 0 4 LP: M%, two oqygen cantaining, MWm>lB6 and MW>16s and aromatic LPi Aromacle o*ygen containing, m->204, fl

• ug/L LP: Aromatic olygen containing, MW=>204, #2 ug/L LPI Nitrdgen cqnt&ining, MW>ZOO 1W ug/L LB: Nitrogen cdntainhg, m>OL2, #l 1.0 ug/L LP: Nitrogen cqntaining hydrocarbonl Nw?192 3 ug/L LP; Aromatic alygen containing, Mp9->236 4 ug/L LP: Aromatic qygen conta.ining, m=>204, 113 30 ug/L LP: Aromatic!

o@gen containing, MD1->192 50 ug/L LP: Aromatic ox&gan containing, MW=>194 6 . ug/L LP: (Methyl phenyl ethyl) phenol 8 ug/L LP! Nltrogen caxttaining, MPp>246 7 ug/L LP: Unknown hydrocarbon, MW>209 .. 6 : ug/L LP: Nittogen cdntalning, Mw)212, 92

• 6 ug/L LP: Mix 9f nitrogen cantaining, MW>230 and axygen containing, W->226 PAGE 83 -.J&=xL 1 1-1 8 - 9 6 11 9 6 11-1 B - 9 6 I 11-18-96 I ID ladk4tc~ Not Detected.

b F9711205405 Report for Job 955316 Page 3 of 6 I. I fhie report shall not be reproduced, except in it8 entirety, without the Written approval of NSF, This &rt not reprosent NSF Ccrt!ficatien or authcrixation to UBQ the NS? Mark. Authorisation CO uae the N6F Mark 3.. Ilm EO products appearing In the Company'e 00ficSal NSF Lisrinp Book or NSF's Internet Produat Cextification Diroc

., h8/25/2086 11: 49 2613976512

.- POLYSPEC PAGE 04 11 S61003056 Continued I ssmolp con- Units T!t%t- Phthalates, in Water, Scan, 6 ccmpounde, 625 Continued 3 ug/L LP: Nitrogen cdntainlng, @a44 80 ag/L LP: Nitrogen cdntalning, Mw=>257 8 ug/k LP: Oxygen contatning, m->166 10 ug/L LPs Nitrogen cubtainlng, MW260 10 ug/t LP: Nitregen c trining, MW=s2P9 30 ug/L LP: Unknown hydrocarban, ?49=>312 20 ug/L LP: Mix of nitrlogen containing, WC-328 and oxygen contaiqbng, 2 ug/L LPr Oxygen contkiking, MW->390 100 ug/L LP:.Nltrogen cwltaining hydrocarbon, MW>270 11 40 ug/L LPx Nitrogen cqntaining, MW>286 ' ' I1 4' 100 ug/L LP: Unknown by 2 ocarbon, MW=>300 ug/~ 1.2:. Unknown hyd, E ocarban, m>2Sf MHm>310 . '. . 200 uq/L. LP: NAtXOgen COptalning hydrocarbon, MW=>3316 3 A0 ug/L LP: N+txo$en 'cahtalnlng hydrocarbon, MW->379 I' 10. ug/L LPt .Unknown hyd ocarbon, MW>344, . .I I' -0 Volatilesr Onregulate4 VoC'o. Comment Dichlorodifluo~ametbane ND(0.5) ' Chloromethane ND ( 0.5) Bromomethane ND(0.5) Chloroathane ND (0.5) ~ricblozofluoro~thane , NP (0.5) Trichlarotrifluoroe~han~

NPiO.5) Methylene Chloride ND(0.2) trane-1,Z-Dichlorosthylena ND(0.S) 1, 1-Dichloroithane ND(0.5) ND (0.5) Chloro *om Bromochloromethane . ND(0.5)' ND (0.5) 0 1,l-Dichl oropropene Carbon Tetrachloride

' L, 1,P-Dfichloropropane ND (0.51 ND (0 - 5) ND(0.5) Bromodichloromethane D&ram*methana 2-ChloroethyLvinyl Ether ND(0.5) ND ( 0.5) ' 8 cis-l,3-bichloropropene 8 trana-l,3-Dichloropropens ND(0.5) d A 1,1,2-Trich2oroet*hane ND10.5) 4 @ 1,3-Pichloroprapana Na(0.5) w 4 Chlorodibromomethane

' ND(Qi5) Bromof 09 ND(0.5) lI3-Pichlorobenzen+ .ND(0.8) ND (0.5) ND(0.5) 1, +Dichlorobenzene 2,2-Dichlorobenzene Methyl-terC-Butyl Ether ND(0.5,) ND (51 ND (5) Methyl Isobutyl Petone Methyl Ethyl .Ketone Sample: Aslo had 520 ugi/L carbon disulfide.

• ." 2 , 2-Dichl oropropane

• ND(0.S) cis-1, O-~icbL~roethylens ND (0.51 1.2 . 'I 8 2 TeCrachloroethylcnc rja(0.5) ch 1 osoben zem ND(O.5) 1,1,1,5-Tetrachloroethane NP(U.5) I, 1,2,2-Tetrachloroathane ND(0.5) 1, 2,3-Trichloropropane

• 0.5 N .A. ND (0 -5) ND (0.5) Nb (0.5f ND(b.51 ND(0.S). ND(O.5) ND (0.2) ND (0.5) ND (0 .SI MD (0.5) ND (0 .SI AD(0.5) ND (0.5) ND(0.5,) ND (0 e5.1 . ND (0.5) ND (0.5) ND (0.5) dD (0.5) ND(0.5) NP (0.5) Nt, (0.6 1 ND (0.5) ND(O.5) ND(0.5) ND (0 .J) ND (0.5) ND (0.5) ND (0.5) ND (0.5) ND(0.5) ND(O.5) ~~(0.5) ND(0*5) ND (51 ND(5) ' 10-18-96 , 10 9 6 10-18796 10 96 10 96 10-18-96 I 1O-l8-Q6 ' 10 96 307 18-96 10-10-96 10-18-96 lO-l8$96 10-18-96 10-18 -9 6 10-18-9 6 10-18-96 10-18-96 10-18-96 IO 9 6 10-18-96 10-18-96 10-1s-96 10-18-96 10-18-96 10- 18-96 10- 18-96 10-18-96 lO-18-9L 10-18-96 10-18-9 6 10-18-96 10 96 10-la-96 10-3.8- 9 6 io-la-94 io-18-36 IO-I~-D~ ND indicates Not Detected.

E9711205465 Report fox Yob 9S5316 Patre 4 of 6 This repart ehalS not be reproducedi' e%ce t in Ate entirety, without the written approval of WSP. Thin report not represent NSF tbrtlfbaticn er autHcxfzafton fo uao tho NSP Mark. Authorizattlaa to uae the NSF Mark ir 1I to products appearing An the Cempany'a Official NBF Listing Book or NSF,'n Xntetntt Produot Certification Dirr

, .. .I t 50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 2 Page 1 of 1 Station/Unit(s): Ovster Creek Unit 1 t' I Activity/Document Number: ECR 06-00879 Revision Number:

1 Tide: NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial,summary report Drywell FIoor/Trouf&Drahage Inspection and Repairs submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

s I' II' Description of Activity:

I (Provide a brief, concise description of what the proposed activity involves.)

ECR 06-00879 specifies repairs to the lower drywell elevation. The joint at the perimeter of the concrete floor slab is caulked tc the steel shell of the drywell. Degraded concrete around the pipes to and from $e drain trough is repaifed wit$ grout. The existing trench into the concrete slab, in bay 5, is being excavated slightly deeper. The worn concretq'surface of the raised slab in the sub-pile room is accepted as-is. The non-uniform slope of the sub-pile room drain trough is also accepted as-is. 1 I Reason for Activity: .I I' 11 @iscuss why the proposed activ& is being performed.)

• ' .I Water was found in one of the 2 trenches in the drywell concrete floor slab. Extensive study (ref.

Passport IR 00546049-02 an 07) was performed to evaluate thepotential causes and effects.

ECR 06-00879 was created to implement repairs to limit the amount of water that would bypass the intended drainage path and enter the floor slab crevices.

Effect of Activity:

@iscuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.) method of operation, design basis or safety analysis descnied in the UFSAR. The repairs will help to ensure that the drywell drainage paths function as originally intended and designed The specified repairs do not impact plant operations or operability. There is no deviation fiom any descnid system function, I , Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential hguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

conditions of the UFSAR regarding plant SSC condition, operation or reason for acceptance, but rather serve to restore the intended design function of the drywell drahage system. Based on the assessment and screening responses, a 50.59 evaluation is not required, and the activity can proceed without prior NRC approval.

A 50.59 screening was prepared, and all five questions are answered "no". The repairs do not invalidate any stated or implied Attachments:

Attach all 50.59 Review forms completed, as appropriate. (NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

Forms Attached: (Check all that apply.) Applicability Review 50.59 Screening 50.59 Screening No. OC-2006-S-0379 Rev. 1 w 50.59 Evaluation 50.59 Evaluation No. Rev. I 50.59 SCREEMNG FORM LS-AA-104-1003 Revision 1 Page 1 of3 50.59 Screening No. OC-2006-S-0379 Rev.No. 1 I Activity/Document Number: ECR 06-00879 Revision Number:-l

// I. 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question)(See Section 5 of the Resource Manual (RM) for additional guidance):

I 1. 2. 3. 4. 5. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR described design function? (See Section 5.2.2.1 of the RM) Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design hnctions are performed or controlled? (See Section 5.2.2.2 of the RM) .I, Does the proposed Activity involve an adverse change to an element of a UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used & ' establishing the design bases or used in the safety analytjes? (See Section 5.2.2.3 of the RM) - YJ5S AN0 I - YES XNO - YES XNO I I Does the proposed Activky hvolve a test or experiment not descnied in the UFSAR, where an ' SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the - YES XNO RM) License? (See Section 5.2.2.5 of the RM) Does the proposed Activity require a change in the Technical Specifications or Operating - YES AN0 I n. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question). , See below. m. Select the appropriate conditions:

NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure.

If question 1,2,3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed, If questions 1,2,3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementation of the Activity.

If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity.

In addition, if question 1,2,3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Activity.

Sign: /5%75- Date:-- (Signature)

&v I V. Screening Signoffs:

50.59 Screener: (Print name) 5 3 5 \T ho L\ Date:\' I gl Ob 50.59 Reviewer: (Print name) (S ignatur 50.59 SCREEMNG FORM LS-AA- 104- 100 Revision Page 2 of 50.59 Screening NO. OC-2006-S-0379 Rev. No. 1 I Activity/Document Number: ECR 06-00879 Revision Number: 1 / / Expanded Responses:

1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR descnibed design function?

I No. The UFSAR contains extensive discussion on the concrete outside of, and beneath, the steel drywell dell, including the gap between the two. That is because that concrete provides important shielding and support functions, and the gap is essential to these functions. However, there is very little mention of the concrete floor slab inside of the drywell.

Section 3.8.3.1.1, "Fill Slab", states that the concrete provides a wbrkini surface and transfenLthe loads of the drywell internal structures to the shell through direct bearing. Design functions of the fill slab are not mpacted by the repairs performed under ECR 06-00879.

The caulk installation serves to prevent water from entering any gaps between the slab and shell, and has no impact on the load transfer or support functions.

Inspection of the caulk will be performed, every two years under the structural monitoring program to ensure that it does not degrade. The drywell sump's purpose is to collect all leakage in the drywell so that it can be monitored and quantified,, as well as appropriately discharged.

The trough and its supply and discharge paths direct the drains to the sump. The concrete repairs specified serve to restore the full capability of these fbnctions by preventing any unintended diversion of the water fiom these pathways. The conditions of the raised floor slab section and the trough slope were determined to have no impact on the drainage hnction or the structural function of the concrete.

This activity will leave the two trenches empty. This empty space may slightly delay the measurement of unidentified leak rate, which is measured by the 1-8' sump. The open trenches may collect unidentified leakage and temporarily prevent the leakage from reaching 1-8 sump. This delay has been evaluated in the ECR attachment 1 and is concluded to be minor. Tech. Spec. 3.3.D.1 requires that , reactor coolant shall be limited to a 2 gpm increase in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Assuming a 2 gpm leak were to instantaneously develop and leak into both trenches at the same time, it would take about 30 minutes for the trenches to fill and overflow at which point the leakage would enter the 1-8 sump. In addition the Tech Spec. requires that reactor coolant shall be limited to 5 gpm. Increases over 5 gpm over a short time frame are bounded by the tech spec requirement for the 2 gpm increase over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Assuming a 5 gpm leak were to instantaneously develop and leak into both trenches at the same time, it would take about 12 minutes for the trenches to fd and overflow at which point the leakage would enter the 1-8 sump. The torus suction strainers serve the hction of preventing debris fiom damaging the ECCS pumps.

The UFSAR section 6.3.2.2.3 descnies the design analysis which ensures that excessive debris is not created such that the suction strainers could become too clogged by debris to allow sufficient flow to the pumps. That analysis was reviewed.

The , result of the materials (that could generate clogging debris) added and removed from the drywell by the subject ECR is a net reduction in these materials. Therefore there is no adverse effect on the analysis.

The 1986 removal of concrete from the floor and curb, that formed the trenches in Bay 5 and 17, does not affect any safety related design functions.

A review of the Design Basis Accidents documented in chapter 15 of the UFSAR shows that the floor and curb are not credited for mitigation of design accidents.

In addition it does not adversely affect the design inputs, assumptions or conclusions of the GE Design Bases Analysis of the Drywell Vessel (reference GE Report "An ASME Section Vm Evaluation of Oyster Creek Drywell for Without Sand Case Part I Stress Analysis -Index 9.3" dated Feb 1991). The effects of the missing curb will not have a significant effect on the Design Basis Accident Analysis of the Containment Shell as discussed in attachment 1 section 4.1.9 of the ECR. The curb feature (which is unique to Oyster Creek) has been credited in some Severe Accident Mitigation Events.

However the overall benefit of the curb is marginal.

The PRA implications of the curb removal were not specifically addressed at the time the PRA was developed, which was after 1986. IR 550022 has been issued to address this omission.

An initial review has been completed and the results demonstrate a less than significant impact on LERF and no impact on CDF. ' The minor amount of concrete removed from the existing trench in bay 5 is in an area where it also has no impact on these functions. Therefore the scope of ECR 06-00879 does not adversely affect any design function that is descnied, implied or referred to in the UFSAR.

.. .. 50.59 SCREENING FORM LS-AA- 104- 100 Revision Page 3 of 50.59 Screening No. Rev. No. 1 -0C-2006-S-0379 I ActivityDocument Number:

ECR 06-00879 I Revision Number: 1 / 2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled?

4. II No. All of the changes made by the subject ECR are passive in nature, and do not affect the performance 0; control of any plant operations or evolutjons.

The repairs do not impact operdtion of the drywell sump, drywell structures or equipment or ECCS systems. No plant processes or procedures are affqcted by the changes. Therefore the scope of ' ECR 06-00879 does not adversely affect the performance or control of any UFSAR descnied besign fbnction.

,' .. 3. Does the proposed Activity involve an adverse change to an eIement of a UFSAR described evaluation methodoldgy, or use of an alternative evaluation pethodology, that is usdd in establishing the design bases or used,in the safety analyses?

No. The design antilysis for suction strainer clogging described in the UFSAR was reviewed with regard to the materials added by the subject ECR. The net change in debris generating materials was evaluated using the existing methodolorn ofthe design analysis to establish its acceptability. There are no other evaluation methodologies involved with this activity.

Therefore the evaluation methodology used within ECR 06-00879 does not deviate fiom those descriied in the UFSAR .I '4 I I I I 4. Does the proposed Activity involve a test or experiment not descnied in the UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses of descriptions in the UFSAR? No. The purpose of the repairs is to direct drywell drains to the sump, as described in the UFSAR. The caulk and grbut serve to restore this function. The addition of the materials has been evaluated in accordance with existing analyses and' processes, and was found to be acceptable. The scope of ECR 06-00879 does not affect the use or cohtrol of any plant SSC. Therefore this activity does not involve any test or experiment that is not bounded by the UFSAR. 5. Does the proposed Activity require a change in the Technical Specifications or Operating License?

No. The repairs in ECR 06-00879 are passive in nature and do not affect the operational parameters or operability of any plant SSC. As discussed under question 1, the potential for water retention by the concrete and trenches not reaching the sump is minima1 and the changes implemented per this ECR would not require a technical specification change. However this issue is being further addressed by Licensing under IR 00546049 assignment

09. Therefore none of the required actions or limits for operation of the Technical Specification or Operating License are impacted by the rep&. Therefore no changes are required to the Technical Specifications or Operating License.

Documents Reviewed:

WSm. Overview of entire document, plus detailed review of sections 1.2, 1.9,3.8.2,3.8.3,5.2.5,6.2,6.3,9.3,11.2. Tech Spec: Overview of entire document, plus detailed review of sections 3.4,3.5,4.4,4.5,5.2.

Operating License DPR-16: Entire Document

References:

1. IR 546049, Water Observed Coming Into The Trench In Bay 5 Of Drywell