ML17055A898
| ML17055A898 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/02/1985 |
| From: | Hermann R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512110047 | |
| Download: ML17055A898 (92) | |
Text
December 2, 19 Docket No. 50-220 LICENSEE:
Niagara Mohawk Power Corporation FACILITY:
Nine Mile Point Nuclear Station Unit No.
1
SUBJECT:
I
SUMMARY
OF NOVEMBER 18, 1985 MEETING WITH NIAGRA MOHAWK POWER CORPORATION A meeting was held on November 18, 1985 in Bethesda, Maryland between representatives of Niagara Mohawk Power Corporation (NMPC), the licensee, and the NRC staff to discuss plans for inspection of an potential repair methods for furnace sensitized stub tubes.
A list of the attendees is attached as Enclosure 1.
A copy of the slides used by the as apart of its presentation is also attached as Enclosure 2.
Issues discussed included:
1.
The inspections and work performed at the 1984 refueling outage, development work and analysis, and experience gained from other Boiling Water Reactors.
2.
Inspection plans for the Spring 1986 refueling outage.
3.
Preparations for any repairs found necessary for any of the stub tubes at the Spring 1986 outage.
4.
The development of long-term repair methods for cracked stub tubes.
The licensee intends to formally submit their guidelines for the repair of leaking control rod drive penetrations for staff review and approval.
Enclosure:
As stated Original signed by Robert A. Hermann, Sr. Project Manager BWR Project Directorate ¹1 Division of BWR Licensing cc w/enclosure:
See next page DISTRIBUTION
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 2, 1985 Docket No. 50-220 LICENSEE:
FACILITY:
SUBJECT:
Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.
1
SUMMARY
OF NOVEMBER 18, 1985 MEETING WITH NIAGRA MOHAWK POWER CORPORATION A meeting was.held on November 18, 1985 in Bethesda, Maryland between representatives of Niagara Mohawk Power Corporation (NMPC), the licensee, and the NRC staff to discuss plans for inspection of an potential repair methods for furnace sensitized stub tubes.
A list of the attendees is attached as Enclosure 1.
A copy of the slides used by the as apart of its presentation is also attached as Enclosure 2.
Issues discussed included:
1.
The inspections and work performed at the 1984 refueling outage, development work and analysis, and experience gained from other Boiling Water Reactors.
2.
Inspection plans for the Spring 1986 refueling outage.
3.
Preparations for any repairs found necessary for any of the stub tubes at the Spring 1986 outage.
4.
The development of long-term repair methods for cracked stub tubes.
The licensee intends to formally submit their guidelines for the repair of leaking control rod drive penetrations for staff review and approval.
Enclosure:
As stated Robert A. Hermann, Sr. Project Manager BWR Project Directorate 0'1 Division of BWR Licensing cc w/enclosure:
See next page
I
CC:
Troy B. Conner, Jr., Esquire Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.
W.
Washington, D.
C.
20006 Frank R. Church, Supervisor Town of Scriba R.
D.
82
- Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:
Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I
U.
S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223
ATTENDANCE LIST - STUB TUBES Ray Pasterwak Brian Lipford William R. Schmidt Lee A. klosowski B.
D. Liaw C.
D. Seller R. A. Hermann W. A.
Koo D. B. Vassallo W. S. Hazelton NMPC MPR MPR NMPC NRC/DE NRC/DE/MTEB NRC/DBL/BWDtl NRC/DE/MTEB NRC/DL/ORBg2 NRC/DE/MTEB Sr.
Nuc.
Eng/Lead Licensing Eng.
P A
ON NE E PONT T
CONTROL ROD DRIVE PENETRATION REPAIR PRO RA NOVEISER 18, 1985
OUT N
OF P
SENTAT I ON NMP-CRD PENETRATION REPAIR PROGRAM I.
NTRODUCTION/BA GROUND A.
NMP-1 1980 SPRING OUTAGE ROLLED JOINT REPAIRS B.
COMPLETED EFFORTS IN SUPPORT OF ROLLED JOINT REPAIR METHOD
~
1.
MOCK-UP TESTS 2.
STRESS ANALYSIS LONG-TERN EFFECTIVENESS OF ROLLED JOINT 3.
EXPERIENCE AT OTHER BMRS EVALUATION OF COLD MORK/IGSCC RESISTANCE 5.
SAFETY EVALUATION OF ROLLED JOINT REPAIR-II.
NSPECT ON P
ANS 0
SP A.
HYDROTEST B.
VISUAL EXAMS C.
ULTRASONIC EXAMS TA E
] I/18/85
III.
PA S
A.
VERIFICATION OF ACCEPTABILITY OF ROLLING PROCESS-EPRI METALLURGICAL/MGCL2TESTS B.
DEVELOPMENT OF ROLL REPAIR IMPROVEMENTS I.
PROCUREMENT OF IMPROVED ROLLING EQUIPMENT, MOCK UPS 2.
MOCK-UP TESTS OF METHODS FOR RE-ROLLING PREVIOUSLY ROLLED HOUSINGS I
3.
EVALUATION OF CRD THERMAL SLEEVE EFFECTIVENESS JUSTIFICATION FOR SECURING COOLING C.
GUIDELINES FOR THE REPAIR OF LEAKING PENETRATIONS IV.
EVE OP ENT OF ON THO S
A.
REVIEM OF DEVELOPMENT MORK BY OTHERS BE NMP-I SEAL ASSEMBLY DESIGN CONCEPT 1.
CRD HOUSING IS RETAINED 2.
CRD HOUSING IS REPLACED 11/18/85
CD NMP-1 SEAL ASSEMBLY DEVELOPMENT 1.
DEMONSTRATION OF STUB TUBE AND HOUSING MACHINING PCI 2.
MECHANICAL SEAL ASSEMBLY DESIGN 3.
INSTALLATION TOOL DESIGN SEAL ASSEMBLY STRESS ANALYSIS 5.
SEAL ASSEMBLY PROTOTYPE DEVELOPMENT TESTING 6.
CONTINGENCY PLANNING FOR IMPLEMENTATION OF LONG-TERN REPAIR D.
SAFETY ANALYSIS OF NMP-1 SEAL ASSEMBLY AND VESSEL MODIFICATION.
ll/18/85
ST B
0 YE PENETRA 0
PA P
0 A
0 U T ON A.
SPRING 1980 OUTAGE 1.
INSPECTION A.
CRD PENETRATION 06-27 FOUND LEAKING AT 15. DROPS PER MINUTE B
CRD PENETRATION 10-11 SHOWED SIGNS OF WETNESS c.
SEVEN ADDITIONAL HOUSINGS SHOWED POSSIBLE EVIDENCE OF PRIOR LEAKAGE o.
CLOSED CIRCUIT TV INSPECTION OF 12 PENETRATIONS REVEALED SIGNIFICANT.
CRACKING OF S IX STUB TUBES 11/18/85
2.
REPAIR INITIALLY, NINE CRD HOUSINGS WERE ROLL EXPANDED TO SUBSTANTIALLY REDUCE LEAKAGE (I)
PENETRATIONS WHICH LEAKED OR EXHIBITED POSSIBLE SIGNS OF PREVIOUS LEAKAGE (2)
ONE PENETRATION WITH OBSERVED STUB TUBE CRACKING, BUT NO S IGNS OF LEAKAGE, WAS NOT REPAIRED (31-10)
B DURING ISI HYDROTEST, AN ADDITIONAL PENETRATION (50-19)
MAS FOUND LEAKING AND MAS SUCCESSFULLY REPAIRED BY ROLLING c.
TOTAL OF TEN PENETRATIONS REPAIRED BY ROLLING OF CRD HOUSING 11/18/85
D ~
REPAIR SEQUENCE (1)
PERFORN.U'T.
INSPECTION TO VERIFY:
INTEGRITY OF STUB TUBE-TO-CRD HOUSING J-MELD INTEGRITY OF CRD HOUSING NATERIAL IN THE AREA TO BE ROLLED (2)
ROLL EXPAND CRD HOUSING INTO TIGHT CONTACT WITH VESSEL WALL TO L I NIT LEAKAGE ACHIEVE 3-0X MALL THINNING OF CRD HOUSING ROLL BAND 3" LONG 11/18/85
INSPECTlON RESULTS 51 47 43'9
'5 31.
27 23 19 15 07 03 Legend:
Inspected By CCTV Possible Evidence Of Prior Leak Visible Leak 02 06 10 14 18 22 26 30 34 38 42 46 50 Rolled After Post Repair Hydrostatic Test Crack Visible By CCTV
MPA A660CIATK8 F-88-45-40 3/66/85 304SS Weld 1.12 to 4.93" W\\Wl,w l%'Aq
'Lie
~
%%%,1AI A%
304SS Stub Tube (Furnace Sensitized) 304SS Cladding 1/2" Inconel Weld 3 II, Rolled Location 1/2 II 304SS CRD Housing Alloy Carbon Steel Vessel ROLLED AREA OF NMP-I CRD HOUSING
0 P TESTS:
QUALIFICATION PROCEDURES-TWO MOCK-UP TYPES TESTED; TYPE A AND TYPE B
10 MOCK-UPS ROLLED:
0 MOCK-UPS WERE ROLLED TO DEVELOP AND QUALIFY ROLLING EQUIPMENT AND PROCEDURES, 6
MOCK-UPS WERE ROLLED FOR PERSONNEL TRAINING AND ADDITIONAL EQUIPMENT QUALIFICATION.
QUALIFICATION TESTS AFTER ROLLING INCLUDED:
2.
T ST HEATED AT RATE OF 50 F/HR TO 550 F.
SOAKED FOR 1
HOUR AND COOLED AT RATE OF 50 F/HR.
3, F
NA A
T ST 1875 ps1G.
0.
D N
0 A' 0
S 0.065 TO 0.075 INCH DIAMETRAL EXPANSION WAS MEASURED (0 TO 5.0X WALL THINNING).
RESULTED IN INSIGNI-FICANT BORE DIAMETER INCREASE (0.001" ON RADIUS).
ll/18/85
Leak Test Connection Rolled Area
- 5. 250 Type A Mock-Up 4
3/8%
Rolled Area Type B
Mock-Up MOCK-UPS
PURPOSE TO DETERNINE THE CONTACT PRESSURE BETWEEN THE CRD HOUS I NG AND REACTOR VESSEL DURI NG VARIOUS OPERATING CONDITIONS FOLLOWING ROLLING OF THE HOUSING A CRD HOUSING AND VESSEL MODEL MAS DEVELOPED USING ELASTIC-PLASTIC MATERIAL*PROPERTIES, FOLLOWI NG A S I NULATED ROLLING PROCESS ON THE NODEL, A REPEATING SERIES OF THERNAL CYCLES MERE APPLIED.
EACH CYCLE CONSISTED OF:
l.
ISOTHERNAL HEAT UP FROM 70 F
TO 550 F
TO CONSIDER PLANT HEAT UP AND NORNAL OPERATION 2.
RESET SCRAN TRANSIENT, HOUSING AT 070~F, VESSEL AT 550~F
(
T = 80 F)"
1 3,
ISOTHERNAL COOL DOWN TO 75 F
TO CONSIDER PLANT COLD SHUTDOWN CONTACT PRESSURE BETWEEN THE HOUSING AND VESSEL MAS RECORDED.
CONTACT PRESSURE VARIED OVER THE TRANSIENT FROM APPROXINTE 3000 TO 7000 ps'.
NOTE, THIS THERNL CONDITION IS EQUIVALENT TO NORNAL OPERATION WITH COOLING FLOW TO CRD iit>8/85
e S
S 0
CONDITION CONTACT PRESSURE (psI)
BEST ESTIMATE (2)
MINIMUM (3)
COLD SHUTDOWN AFTER INITIAL ROLL STEADY STATE OPERATION AT. 550~F WITH COOLING FLOW WITHOUT COOLING FLOW RESET SCRAM TRANS IENT/
NORMAL COOLING FLOW COOL SHUTDOWN AFTER INITIAL HEATUP AND COOLDOWN 6,500 4,200 7,400 4,200 4,600 5,200 3,000 6,400 3,000 3,200 NOTES 1.
CYCLIC ANALYSIS AFTER 12 SIMULATED LOAD STEPS SHOWS NO RATCHETING.
2.
BEST ESTIMATE BASED ON TYPICAL MATERIAL PROPERTIES.
3
~
MINIMUM BASED ON MINIMUM MATERIAL PROPERTIES.
11/18/85
P TS 0
PENETRAT ON LEA S GARIGLIANO IN 1966 ONE OUTER INCORE PENETRATION STUB TUBE LEAKED HOUSING WAS ROLLED; NO FURTHER LEAKS OYSTER CREEK IN 1970 ONE OUTER INCORE PENETRATION lEAKED THROUGH THE WELD ATTACHING THE INCORE HOUSING TO THE VESSEL BOTTOM HEAD HOUSING WAS ROLLED; NO FURTHER LEAKS
A S
RD STUB TUBE/HOUS N
EA S
A BIG ROCK IN APRIL 1979 A
STA P
ONE OF THE OUTS I DE CRD STUB TUBES OUT OF 32 LEAKED ROLL REPAIRED STUB TUBE IN 1979.
ROLLfD JOINT STILL fFFECTIVE AS OF DECEMBER 1983, SANTA MARIA DE GARONIA (NUCLENOR)
IN 1981 ONE STUB TUBE I,N THE SECOND ROM WAS FOUND LEAKING AS A RESULT OF A STUB TUBE CRACK 1/0 INCH BELOM THE ROOT OF THE STUB TUBE-TO-HOUSING MELD A SECOND STUB TUBE HAS FOUND TO BE LfAKING IN SEPTEMBER 1983 DURING A HYDROTEST TO DATE 55 STUB TUBES OUT OF 97 HAVE BEEN EXAMINED AND 02 CONTAIN DEFECTS.
ONLY THE TWO LEAKERS HAVE BEEN REPAIRED TO MINIMIZE LEAKAGE REPAIR WAS COMPLETED INITIALLYUSING ROLL RfPAIR.
LEAKAGE WAS OBSERVED FROM ROLLED PENETRATION AND A MECHANICAL SEAL WAS INSTALLED.
(MECHANICAL SEAL DISCUSSED LATER IN MEETING) ll/18/85
S STA E
LABORATORY TESTS HAVE SHOWN THAT EXCESSIVE AMOUNTS OF COLD WORK CAN INCREASE THE POTENTIAL OF IGSCC IN 300 STAINLESS STEELS.
USING TEST DATA, GE ESTABLISHED A CORRELATION BETWEEN EXPECTED IGSCC RESISTANCE OF COLD WORKED MATERIAL WITH SURFACE HARDNESS.
SURFACE HARDNESS NOT EXCEEDING ROCKWELL B 95 IS NOT EXPECTED TO SIGNIFICANTLY LOWER RESISTANCE OF HOUSING MATERIAL TO IGSCC.
HARDNESS IN ROLLED REGION IS NOT A CONCERN.
(PLACED IN NET COMPRESSION BY ROLLING.)
o TRANSITION REGIONS AT END OF ROLLS ARE AREAS OF CONCERN FOR IGSCC TENSILE STRESS STATE.
HARDNESS TESTS OF MOCK-UPS INDICATE TRANSITION'EGION TO BE IN RANGE OF 87 TO 93 ROCKWELL B.
o ABSENCE OF ANY IGSCC ATTACK IN SIMILAR ROLL JOINTS AT OTHER BWRs CONFIRMS HARDNESS RESULTS:
10 YEARS SATISFACTORY EXPERIENCE AT OYSTER CREEK 5
YEARS SATISFACTORY EXPERIENCE AT BIG ROCK POI NT ll/18/85
STUB TUBE RA S
PREVIOUS SAFETY ASSESSMENTS OF CRD STUB TUBE CRACKS ARE APPLICABLE TO NMP-1 AND REMAIN VALID LEAKAGE L I MITED CRD HOUS I NG EJECT I ON NOT P OSS IBLE STRUCTURAL INTEGRITY OF RCS BOUNDARY NOT AFFECTED NO EFFECT ON CRD OPERATION/SCRAM TUBE ROLLING OPERATION FURTHER MINIMIZES ANY LEAKAGE AND PROVIDES ADDITIONAL HOUSING SUPPORT; DOES NOT CHANGE SAFETY ASSESSMENT EXISTING DRYWELL LEAKAGE MONITORING CAPABILITY IS EXCELLENT AND ADEQUATE TO MONITOR PENETRATION LEAKAGE IN SERVICE LEVEL RATE-OF-RISE IN DRYWELL FLOOR DRAIN TANK (CR ALARM AND RECORDER, 1/4 GPM SENSITIVITY)
PUMP-OUT TIMER (CR,ALARM AND RATE, SENSITIVITY 5
GPM IN 18 MIN., 0.5 GPM IN 180 MIN., ETC.)
INTEGRATED FLOW TO WASTE DISPOSAL IS MONITORED 11/18/85
0 TA E A.
HYDROTEST S.
VISUAL EXAVS C
ULTRASONIC EXAMS 11/18/85
0 E
A.
INSERVICE INSPECTION PLAN SUBMITTED TO NRC SEPTEMBER 1980 B.
THE FOLLOWING INSPECTIONS ARE PLANNED:
1.
HYDROTEST INSPECT FOR EVIDENCE OF LEAKAGE SUCH AS MATER DROPS AT CRD HOUSING FLANGE B ~
IF LEAKAGE IS
- OBSERVED, CONFIRM THE SOURCE OF LEAKAGE BY EXAMINING VICINITY OF LOWER VESSEL HEAD, I.E.,
WATER STREAKS, DISCOLORATION OR CORROSION PRODUCTS c.
PERFORM INSPECTION DURING EACH SYSTEM lEAKAGE OR SYSTEM HYDROSTATIC TEST D.
EVALUATE ANY OBSERVED LEAKAGE ON CASE BAS IS (GUI DEL INES FOR REPAIR HAVE BEEN DEVELOPED) 11/18/85
2.
VISUAL EXAMINATION FROM INSIDE THE REACTOR VESSEL INSPECT FOR CRACKING WHICH COULD RESULT IN FUTURE LEAKAGE B
UTILIZE CLOSED CIRCUIT TV c.
EXAMINE THE FOLLOWING:
(1)
WELD AND HEAT AFFECTED ZONES (HAZ)
OF STUB TUBE-TO-VESSEL WELD AND ADJACENT AREAS (2)
WELD AND HAZ OF STUB: TUBE-TO-CRD HOUSING J-WELD AND ADJACENT AREAS; (3)
ALL ACCESSIBLE SURFACES OF STUB TUBES D.
EXAMINE WHENEVER ACCESSIBLE DURING EACH 10 YEAR INSPECTION INTERVAL (ASME SECTION XI, TABLE IWB-2500-1)
E.
EVALUATE CRACKS ON A CASE BASIS.
11/18/85
3.
ULTRASONIC EXAMINATION A ~
INSPECT FOR CRACKS OR DEFECTS IN CRD HOUSING AND FUSION ZONE OF THE CRD HOUSING TO STUB TUBE MELD.
B EXAMINE THE FOLLOMING:
(1)
ENTIRE INTERIOR SURFACE OF CRD HOUSING FROM OUTSIDE EDGE OF VESSEL BOTTOM HEAD THROUGH AND INCLUDING ROLLED AREA TO APPROXIMATELY 2 INCHES ABOVE THE J-MELD (2)
ROLLED AREA INSPECTION TO INCLUDE TRANSITION FROM ROLLED TO UNROLLED AREAS FOR EVIDENCE OF DEFECTS c.
EXAMINE AT LEAST ONE PREVIOUSLY ROLLED HOUSING EACH REFUEL OUTAGE.
EXAMINE DIFFERENT HOUSINGS EACH OUTAGE AS PRACTICAL D
IF NO DEFECTS ARE FOUND DURING THE FIRST THREE REFUEL
- OUTAGES, REDUCE FREQUENCY OF INSPECTION TO ONE PENETRATION EVERY THIRD REFUEL OUTAGE E
EVALUATE RESULTS ON A CASE BASIS 11/18/85
A.
VERIFICATION OF ACCEPTABILITY OF ROLLING PROCESS - EPRI METALLURGICAL/MGCL2TESTS B.
DEVELOP MENT OF ROLL REPAIR IMPROVEMENTS 1.
PROCUREMENT OF IMPROVED ROLLING EQUIPMENT, MOCKUPS 2.
MOCK-UP TESTS OF METHODS FOR RE-ROLLING PREVIOUSLY ROLLED HOUSINGS 3.
EVALUATION OF CRD THERMAL SLEEVE EFFECTIVENESS JUSTIFICATION FOR SECURING COOLING C,
GUIDELINES FOR REPAIR OF LEAKING CRD PENETRATIONS 11/18/85
0 SS AS DISCUSSED, EVALUATIONS WERE COMPLETED TO DETERNINE.COLD WORK EFFECTS ON IGSCC RESISTANCE PRIOR TO ROLL REPAIR IN 1980 OUTAGE IGSCC RESISTANCE WAS FOUND TO BE UNAFFECTED BASED ON SERVICE EXPERIENCE AND CORRELATIONS USING HARDNESS LEVELS FURTHER INVESTIGATIONS UNDERWAY AT EPRI-CHARLOTTE:
EVAlUATION OF STRAIN-INDUCED NRTENS ITE STUDY OF RESIDUAL STRESSES P REL I NI NARY RESULTS NRTENSITE IS
- PRESENT, BUT ONLY IN ROLLED REGIONS OF HOUSING I.D.
NET STRESSES IN ROLLED REGION ARE COMPRESSIVE AND MILL ARREST ANY CRACKING ROLLING DOES NOT AFFECT IGSCC RESISTANCE OF ROLLED HOUSING 11/18/85
A D T ONAL O
STS PURPOSE TO EVALUATE AND BETTER UNDERSTAND THE EFFECTIVENESS OF ROLL REPAIR APPROACHES.
THREE ADDITIONAL TESTS N
EST CONSISTS OF ROLLING TWO ADDITIONAL EXPANSION ROLLS ON A PREVIOUSLY ROLLED HOUSING.
THIS TEST MILL PROVIDE:
ROLLING PROCEDURES FOR REPAIR OF PREVIOUSLY ROLLED HOUSINGS FOUND TO BE LEAKING DATA ON EFFECT OF RE-ROLLING ST CONSISTS OF PULLING A HOUS I NG OUT OF ITS ROLLED JOI NT.
TH IS TEST MILL DETERMINE THE EFFECTIVENESS OF THE ROLLED JOINT IN RETAINING THE CRD HOUSING AGAINST STEADY-STATE AND TRANSIENT LOADS.
11/18/85
T A
A CONSISTS OF ROLLING A HOUSING FABRICATED FRON NUCLEAR GRADE NTERIAL.
THIS TEST DETERNINES THE EFFECTIVENESS OF THE ROLLED SEAL AND ADEQUACY OF EXISTING TOOLS AND PROCEDURES WHEN USING A NUCLEAR GRADE NTERIAL.
(FOR EYALUA-TION OF POSSIBLE LONG-TERN REPAIR APPROACH DISCUSSED LATER.)
TEST PLANNED, AT SITE IN DECEtSER 1985 JANUARY 1986 11/18/85
EVA AT 0 0
E VE CONCERN IS EXCESS COOL I NG WATER BYPASSING THE THERNAL SLEEVE, THEREBY DECREASING THE EFFECTIVENESS OF THE ROLLED JOINT?
A FRACTION OF THE NORlQL COOLING MATER FLOW CAN PASS THROUGH THE GAP BETWEEN THE CRD HOUSING AND THE THERNL SLEEVE THIS FLOM IS LINITED BY CLOSE FIT CLEARANCES BETWEEN THE LOWER PORTION OF THE THERMAL SLEEVE AND THE HOUSING EVALUATIONS SHOW THAT THE THERNL SLEEVE BYPASS FLOW IS ACCEPTABLY LOM.
11./1 8/85
0 EXPERIENCE AND ANALYSIS INDICATE COOLING WATER FLOW REDUCES ROLLED JOINT EFFECTIVENESS.
AT LEAST ONE BWR HAS OPERATED WITHOUT COOLING WATER TO SELECTED DRIVES WITH NO SIGNIFICANT EFFECT ON DRIVE OPERATION OR LIFETIME.
SECURING COOLING FLOW WAS EFFECTIVE IN REDUCING LEAKAGE.
NMPC IS EVALUATING ACCEPTABILITY OF SECURING COOL I NG TO SELECTED DR IVES WH I CH LEAK I N SERV I CE.
AREAS BEING EVALUATED:
CRD OPERATION LIFETIME OF NON-METALLI CS TECH SPEC LIMITS 11/18/85
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IV.
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~i gl GRAPHOIL SEAL 304 SS CLADDING INCONEL YYELQ:
>IACHIN-D SEALING SURFACE IN VESSEL CL'Dliw:-
- C4 SS CRD HOUSli~lG ALLOY CARBON STEEL VESSEL COM BUST ION ENGI NEER IN 6 BOTTOM HEAD SEAL CONCEPTUAL DESIGN
RETAIN CRD HOUS ING/RENOVE STUB TUBE; USE EXISTING ROLLED JOINT AND NECHANICAL BACKUP SEAL
85 43-55 4/S4/85 EXISTING STUB TUBE KESSEL-BOTTOM HEAD EXISTING ROLL EXISTING CRD HOUSING INSTALL BLIND FLANGE STEP I REMOVE CRD MECHANISM, INSTALL BLIND FLANGE.REMOVE CONTROL ROD 6. GUIDE TUBE
CUTTING TOOL MPR ASSOCtATSS F-65-45 56 0/24/85 MACHINE GROOVE MACHINE OUT EXISTING STUB TUBE
- ALL MACHINING OF INSTALLED CRD HOUSING PERFORMED UNDERNATER BY REMOTE MEANS FROM ABOVE REACTOR VESSEL FLANGE.
STEP 2 MACHINE OUT EXISTING STUB TUBE 8 MACHINE GROOVE AT TOP OF CRD HOUSING
IIPR ASSOCIATES F 85 45 57 4/24!85 LOCKING RINGS SEAL a CRD HOUSING RETAINER ASSEMBLY BELLVILLESPRING GLAND S SEAL ASSEMBLY
(
SEE STEP 3A )
EXISTING CRD HOUSING BLIND FLANGE STEP 3 INSTALL SEAL, GLAND, & LOCKING RINGS
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MPR A880CIAT28 F 85 58 1/21/85, fQ" SLEEVE PORTION OF GLAND INSTALLATION TOOL GLAND WITH GLAllD RINGi AND PACKING SEAL)
ATTACHED EXISTING CRD HOUSING "VESSEL BOTTOH HEAD STEP 3A LOWERING OF GLAND INTO BOTTOM HEAD CAVITY WITH GLAND RING & PACKING.SEAL ATTACHED
A ON REPLACE CRD HOUSING; USE ROLLED JOINT AND NECHANICAL SEAL,FOR SEAL ING'ONCEPTUAL DESIGN AND INSTALLATION PROCEDURE DEYELOPED 11/18/85
1.
DEMONSTRATION OF STUB TUBE AND HOUSING MACHI N I NG PCI EXPLORATORY TESTS COMPLETE FULL SCALE MOCKUP TO BE FABRICATED FULL SCALE MACHINING DEMONSTRATION PLANNED FOR LATE 1985, EARLY 1986-2.
MECHANICAL SEAL ASSEMBLY DESIGN DETAIL DESIGN COMPLETE 3.
INSTALLATION TOOLING CONCEPTUAL DESIGNS COMPLETE STRESS ANALYSIS COMPLETE 11/18/85
NMP-f PROTOTYPE MECHANlCALSEAL ASSEMBLY
SEA ASSE P
OT V
OP T
ST N
PROTOTYPE SEAL FABRICATION OUT FOR BIDS, FABRICATION LATE 1985, EARLY 1986 TEST F I XTURE DES I GN OUT FOR B I DS, FABRICATION LATE 1985, EARLY 1986 TEST PLAN SEAL lEAKAGE TESTS, ANBIENT CONDITIONS NORtQL CONDITIONS DIFFERENT SEAL MATERIALS MITH AND MITHOUT PRELOAD ROUGHENED, RUSTED SEAL SURFACES I I /18/85
NMP-I PROTOTYPE MECHANICAL SEAL-ASSEMBLY TEST FIXTURE
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OF ON -TER REPAIR PROCUREMENT SPEC FOR NG MATERIALS COMPLETE INSTALLATION SPEC PROCUREMENT SPEC FOR PRODUCTION TOOLING PROCUREMENT OF SELECTED LONG LEAD MATERIALS 11/18/85
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