L-90-156, Forwards Relief Request 6/7 a from Code Requiring Volumetric & Visual Exam of Reactor Coolant Pump Casing Welds & Interior Surfaces.Approval Requested by 900915 to Facilitate Upcoming Outages Beginning Nov & Dec 1990
| ML17348A267 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/30/1990 |
| From: | Harris K FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-90-156, NUDOCS 9006060118 | |
| Download: ML17348A267 (17) | |
Text
ACCELERATED DI<
UTION DEMONSTR TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9006060118 DOC.DATE: 90/05/30 NOTARIZED:
NO DOCKET g
FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION HARRXS.K.N.
Florida Power
& Light Co.
RECXP.NAME RECIPIENT AFFXLIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Relief Request 6/7 A from code required volumetric
& visual exam of RCP casing welds
& interior surfaces.
DISTRIBUTXON CODE:
A047D COPIES RECEIVED:LTR ENCL X SIZE:
i
/
NOTES:
RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G XNTERNAL: AEOD/DSP/TPAB NRR/DET/EMEB 9H OC LF EG 01 EXTERNAL: EG&G BROWN,B LPDR NSIC COPIES LTTR ENCL 1
0 1
1 1
1 1
1 1
0 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS2 RES/DSXR/EIB EG&G RANSOME, C NRC PDR COPIES LTTR ENCL 5
5 1
1 1
1 1
0 1
1 1
1 1
1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 20 ENCL 17
~
~
pp P.O. Box14000, Juno Beach, FL 33408-0420 NAY 3O jggp L-90-156 10 CFR 50.55a(g)(5)(iii)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Request for Relief Inservice Ins ection Pro ram Pursuant to 10 CFR 50.55a(g)(5)(iii), Florida Power 6 Light Company has determined that conformance with certain code requirements is impractical for Turkey Point Units 3 and 4.
Requests for relief from the code required volumetric and visual examination of reactor coolant pump casing welds and interior surfaces (Attachment 1 and 2),
and the basis for such relief, are attached.
Your approval is requested by September 15, 1990 so that we may plan for the upcoming outages, beginning November 1990 for Unit 4 and December, 1990 for Unit 3.
If you should have any questions, please contact us.
Very truly yours, K. N.
Vice Harris resident Turkey Point Plant Nuclear KNH/TCG/gp Attachments cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9006060ii8 900530 I
PDR AGOCK 05000250 9
PDC an FPI. GrouP comPany
t:B't U i Yl'l"i r
~
ATTACHMENT. 1 TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A A.
COMPONENT IDENTIFICATION:
- CLASS 1
- REACTOR COOLANT PUMPS 3P200A LOOP A PUMP 3P200B LOOP B PUMP 3P200C LOOP C
PUMP B.
EXAMINATIONREQUIREMENTS:
EXAM CATEGORY ITEM NO.
B-L-1 B-L-2 C.
FUNCTION:
B12.10 - VOLUMETRIC EXAMINATION, to include 100% of the pressure retaining welds on one pump in each group of pumps performing similar functions in the system.
B12.20 VISUAL EXAMINATIONof the internal pressure boundary surfaces on one pump in each group of pumps performing similar functions in the system.
Turkey Point Plant Unit No.
3 has three (3) reactor coolant pumps.
These pumps function during normal reactor operation to provide forced recirculation through the core.
D RELIEF REQUESTED:
Relief is requested from the Code volumetric and visual examinations of the Reactor Coolant Pump Casing welds and interior surfaces during the inspection interval.
E.
BASIS FOR RELIEF:
Volumetric examination is not feasible due to the coarse grain structure inherent in thick stainless steel castings, that precludes the use of conventional 'ultrasonic examination techniques.
The pump casing is fabricated from cast. stainless steel (ASTM A381, Grade CF8M) material.
Configuration of the pump design requires~disassembly of the pump (including internal parts) to perform radiographic examination.
TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Visual examination is not practical since it requires total disassembly of,the pump.
Radiographic examination is not possible without the complete disassembly of the pump (see Figure 1).
To perform this examination, large expenditures of man-hours and manrem are required with essentially no compensating increase in plant safety.
Based on actual data compiled from the radiographic examination of the Turkey Point Unit No.'
Reactor Coolant Pump casing welds and the visual examination of the internal boundary surface of one pump, in excess of 5900 man-hours and 46 man-rem exposure was expended in the disassembly, examinations and reassembly of the pump.
There is a very low probability, based upon industry experi-ence, to disassemble pump(s) solely for maintenance'purposes.
There is no requirement by the pump manufacturer (Westing-house) to disassemble the pump(s) as part of normal mainte-nance or inspection.
Accordingly, Florida Power Light Company's procedures do not require disassembly of the pump(s) for maintenance or inspection purposes.
There are no reported failures within the pump casings with these model pump(s).
Adequate safety margins are inherent in the basic pump de-sign.
The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime.
The Reactor Coolant Pump casing
- material, cast stainless steel (ASTM A351-CF8m), is widely used in the Nuclear Industry and has performed extremely well.
Satisfactory inspection results achieved in February 1982 coupled with the same inspections conducted by other utility company's and employing the same manufacturing model
- pumps, provides additional assurance as to the pumps'asing integ-rity.'lorida Power
& Light Company through the Westinghouse Owners'roup has submitted to the ASME Code, Code case N-481, Titled "Alternate Examination Requirements for Cast Austenitic Pump Casings"
~ This Code case was approved on March 5, 1990.
TUEL"Y POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST I
RELIEF REQUEST NO. 6/7 A CONTINUED F.
ALTERNATIVE EXAMINATIONS:
Perform a VT-2 visual examination of. the exterior of all pumps during the Hydrostatic pressure tests required by Table IWB-2500-1, Category B-P.
,Perform a VT-1 visual examination of the external surfaces of the weld of one pump casing.
Perform a VT-3 visual examination of the internal surfaces whenever a pump is disassembled for maintenance.
The alternate examination and tests provide assurance of an acceptable level of quality and safety.
G.
IMPLEMENTATION SCHEDULE:
At or near the end of the Inspection Interval Inspection Interval 22 February 1984 to 21 February 1994 Inspection Period 22 February 1991 to 21 February 1994 H.
ATTACHMENTS TO RELIEF REQUEST NO. -6/7 A Fig-. No.
1 Reactor Coolant Pump detail 003-V13A Reactor Coolant Pump drawing 003-V20 Reactor Coolant Pump Interior and weld identification
& location The need for this exemption was recognized by FP&L during the First Inspection Interval.
FP&L submitted and received NRC approval for this request for relief.
FP&L resubmitted this request for relief at the beginning of our Second Inspection Interval and received partial approv-al as denoted below.
SUBMITTED-APPROVED DENIED:
AMENDED:
23 February 1984 (under Request 6/7 TAC NOS.:
49936 Category B-L-2 only Category B-L-1 Amendment 6/7A supplements Request for Relief No. 6/7 originally submitted in 1984.
RE-SUBMITTED'EASON FOR AMENDMENT: Relief from the ASME Code requirements is still required for this interval.
TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A
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NIWS NSI FIGURE NO.
1 REACTOR COOLANT PUMP DETAIL 4
RCP-(i)-24 RCP-(i)-23 RCP-(R)-22 ~
RCP-(i)-21~
RCP-(i)-20 ~
RCP-(R)-19 ~
RCP-(i)-1 RCP-(i)-2 t
R~ (.).
I
~ RCP-(R)-4 RCP-(i)-5 RCP-SPA-L2 RCP-SPA-L3 RCP-(P)-18~
RCP-(i)-17~
RCP-(R)-16~
RCP-( )-1S ~
RCP-( )-14 +g RCP-(i)-13 RCP-(P)-6
~ RCP-( )-7 RCP-(R)-8 I/ i )(
~RCP-( )-9 l ~ RCP-(i)-10 RCP-( ~)-11 RCP-(R)-12 REACTOR COOLANT PUMP LOOP A"
RCP-SPA-L1 ~
MAIN COOLANT PUMP LOOP A
SUPPORT LOCATIONS HOKE THE IDENTIFICATION OF APPLICABLE STUDS. NUTS, AND LIGAMENTS SHALL BE MADE BY INSERTING THE FOLLONNG DESINATIONS IN PLACE OF THE ( )
MAIN COOLANT PUMP LOOP "A" STUDS (FSA)
MAIN COOLANT PUMP LOOP A
NUTS - (FNA)
MAIN COOLANT PUMP LOOP, A" UGAMENTS - (FLA)
SUPPORT DETAIL FROM ABOVE REFERENCE, DRAWINGS PRESSURE I)c TEMPERATURE STATS MATERIAL SPECS SIZE SCH TYPE PP) ~e CODES k PROGRAMS GROUP TURKEY POINT UNIT 3 DESIGN PSIG:
OPERATING PSIG:
HYDROSTATIC PSIG:
TEMP(F):
TEMP(F):
TEMP(F):
UT CALIBRATION BLOCK: UT-18. UT-19 TITLE:
REACTOR COOLANT PUMP 3PZOOA DATE: 10-12-89 REVISION APPROVED BY:
3,.
I. I. ANf)FRRÃitl ZONE: 056 DRAI))ING NUMBER:
003-VI3A
44.0 WELD "A 0"
44.5 1 8.69 0"
74.0 T'.50 I
i 67.81 WELD "8 1
. 7 65 /
////
28.0 PREPRATION FOR EXAMINATION
- 1. REMOVE INSULATION
- 2. CLEAN 0.0. SURFACE
- 3. REMOVE INTERNALS
- 4. OECON OUTSIDE FLANGE
- 5. CLEAN ID SURFACE
- 7. SCAFFOLD WHEN REQUIRED NOTES:
MANUFACTURER WESTINGHOUSE CODE CASE N-481 "ALTERNAllVEEXAMINATION REQUIREMENTS FOR CAST AUSTENITIC PUMP CASINGS WELD C"
REFERENCE DRAWINGS DESIGN PSIG:
OPERATING PSIG:
HYDROSTATIC PSIG:
TEMP(F):
TEMP(F):
TEMP(F):
PRESSURE Ec TEMPERATURE STATS SIZE MATERIAL SPECS SCH TYPE UT CALIBRATION BLOCK: N/A CASTING SA-351, GR. CFBM DATE: 16 APRIL 1990 REVISION APPROVED BY:
n r
I Arrnlrr~nrr ZONE: 56.57.58 DRAWING NUMBER:
nn3 v7n RELIEF REQUEST 6/7
~~
alkyd CODES k PROGRAMS GROUP TURKEY POINT PLANT UNIT 3 TITLE: REACTOR COOLAN'T PUMP (TYPICAL ALL 3 )
ATTACHMENT 2 TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A A.
COMPONENT IDENTIFICATION:
- CLASS 1
- REACTOR COOLANT PUMPS 4P200A LOOP A PUMP 4P200B LOOP B PUMP 4P200C LOOP C PUMP B.
EXAMINATIONREQUIREMENTS:
EXAM CATEGORY B-L-1 B-L-2 C.
FUNCTION:
ITEM NO.
B12.10 VOLUMETRIC EXAMINATION, to include 1004 of the pressure retaining welds on one pump in each group of pumps performing similar.
functions in the system.
B12.20 VISUAL EXAMINATION of the internal pressure boundary surfaces on one pump in each group of pumps performing similar functions in the system.
Turkey Point Plant Unit No.
4 has three (3) reactor coolant pumps.
These pumps function during normal reactor operation to provide forced recirculation through the core.
D. RELIEF REQUESTED:
Relief is requested from the Code volumetric and visual examinations of the Reactor Coolant Pump Casing welds and interior surfaces during the inspection interval.
E.
BASIS FOR RELIEF:
Volumetric examination is not feasible due to the coarse grain structure inherent in thick stainless steel
- castings, that precludes the use of conventional ultrasonic examination techniques.
The pump casing is fabricated from cast stainless steel (ASTM A351, Grade CF8M) material.
Configuration of the pump design requires disassembly of the pump (including internal parts) to, perform radiographic examination.
Visual examination is not practical since it requires total disassembly of the pump.
TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Radiographic examination is not possible without the complete disassembly of the pump (see Figure 1).
To perform this examination, large expenditures of man-hours and manrem are required with essentially no compensating increase in plant safety.
Based on actual data compiled from the radiographic examination of the Turkey Point Unit No.
3 Reactor Coolant Pump casing welds and the visual examination'f the internal boundary surface of one pump, in excess of 5900 man-hours and 46 man-rem exposure was expended in the disassembly, examination, and reassembly of the pump.
There is a
very low probability, based upon industry experience, to disassemble pump(s) solely for maintenance purposes.
There is no requirement by the pump manufacturer (Westinghouse) to disassemble the pump(s) as part of normal maintenance or inspection.
Accordingly, Florida Power
& Light Company's procedures do not require disassembly of the pump(s) for maintenance or inspection purposes.. There are no reported failures within the pump casings with these model pump(s).
Adequate safety margins are inherent in the basic pump design.
The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime.
The Reactor Coolant Pump casing material, cast stainless steel (ASTM A351-CF8m), is widely used in the Nuclear Industry and has performed extremely well.
Satisfactory inspection results achieved in February 1982 coupled with the same inspections conducted by other utilities and employing the same manufacturing model
- pumps, provides additional assurance as to the pumps'asing integrity.
Florida Power
& Light Company through the Westinghouse Owners'roup has submitted to the ASME Code, Code case N-481, Titled "Alternate Examination Requirements for Cast Austenitic Pump Casings".
This Code case was approved on March 5, 1990.
F.
ALTERNATIVE EXAMINATIONS:
Perform a VT-2 visual examination of the exterior of all pumps during the Hydrostatic pressure tests required by Table IWB-2500-1, Category B-P.
Perform a VT-1 visual examination of the external surfaces of the welds of one pump casing.
Perform a VT-3 visual examination of the. internal surfaces whenever a pump is disassembled for maintenance.
TURKEY POINT UNXT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Perform a
VT-3 visual examination of the" internal surfaces whenever a pump is disassembled for maintenance.
The alternate examination and tests provide assurance of an acceptable level of quality and safety.
G.
IMPLEMENTATION SCHEDULE:
At or near the end of the Inspection Interval Inspection Interval 15 April 1984 to 14 April 1994 Inspection Period 15 April 1991 to 14 April 1994 H.
ATTACHMENTS TO RELIEF REQUEST NO. 6/7 A Fig. No.
1 Reactor Coolant Pump detail 4-V13A 004-V20 Reactor Coolant Pump drawing Reactor Coolant Pump Xnterior and weld identification
& location The need for this exemption was recognized by FP&L during the First Inspection Interval.
FP&L submitted and received NRC approval for this request for relief.
FP&L resubmitted this request for relief at the beginning of our Second Inspection Interval and received partial approval as denoted below.
SUBMITTED:
APPROVED:
DENXED:
AMENDED 23 February 1984 (under Request 6/7)
TAC NOS.:
49936 Category B-L-2 only Category B-L-1 Amendment -6/7A supplements Request for Relief No. 6/7 originally submitted in 1984.
RE-SUBMITTED REASON FOR AMENDMENT:
Relief from the ASME Code requirements is still required for this interval.
l TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED
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WIII arun FIGURE NO.
1 REACTOR COOLANT PUMP DETAIL
~
4
4-RCP-(e)-24 4-RCP-(o)>>23 4-RCP<<(t)-22 4-RCP-(o)-21 4-RCP-(i)-I 4-RCP-(e)-2 4-RCP-( )-20 4-RCP-(o)-19 4-RCP-(o)-18 4-RCP-(i)-17 4-RCP-(o)-I 8 4-RCP-(o)-IS 000~
0 0
0 0
0 0
0 0
0 ooo 4-RCP-(a)-3 4-RCP-(a)-4 4-RCP-(i)-5 4-RCP-(o)-8 4-RCP-(t)-7 4-RCP-(o)-8
~4-RCP-(i)-9 4-RCP-SPA-L2~
REACTOR COOLANT PUMP LOOP A
~ 4-RCP-SPA-L3 4-RCP-(o)-14 RCP-(o)-13 4-RCP-(o)-IO 4-RCP-(i)-I I 4-RCP-(o)-12 SUPPORT LOCATIONS HAZIER QK IDENTIFICAllON OF STUDS, NUTS, AND FLANGE SURFACE AREAS SHALL BE MADE 8Y NSERTIHG THE FOLQWNG DESGNATIONS 81 PLACE OF THE (i)
MAIN COOLANT PVLIP LOOP A
STUDS FSA MAIN COOLANT PUMP LOOP A
NUTS FHA MAIN COOLANT'VLIP LOOP A
FLANGE RHFACE AA SUPPORT DETAIL FROM ABOVE REFERENCE DRAWINGS DESGH PSG:
OPERAllNG PSG:
HYDROSTATIC PSIG:
TEMP(r):
TEMPS (r):
TEMP(F):
PRESSURE 4 TGAPERATURE STATS MATERIAL SPECS SIZE SCH TYPE UT CKIBRAllON BLOCK: UT-18, UT-19 DATE: 4/28/90 REVISON APPROVED BY:
0 R. L. TURNER ZONE: 055 DRANNG NVLIBER; 4-VljA
~p)Q CODES Jt PROGRAMS GROUP lURKEY POINT UNIT 4 lllLE:
REACTOR COOLANT PULIP LIAIN FLANGE STUDS, NUTS AND PVLIP SUPPORTS (4P200A)
44.0 WELD "A 74 0" 0"
44.5 j'.50" I-I I
i 67 44.5 81 WELD B
l
. 7 65'
///
28.0 PREPRATION FOR EXAMINATION
- 1. REMOVE INSULATlON
- 2. CLEAN O.D. SURFACE
- 3. REMOVE INTERNALS
- 4. OECON OUTSIDE FLANGE
- 5. CLEAN ID SURFACE
- 7. SCAFFOLD WHEN REQUIRED
'OTES:
MANUFACTURER WESTINGHOUSE CODE CASE N-481 "ALTERNATIVE EXAMINATION REQUIREMENTS FOR CAST AUSTENITIC PUMP CASINGS WELD C"
REFERENCE DRAWINGS PRESSURE dr, TEMPERATURE STATS SIZE MATERIAL SPECS SCH TYPE RELIEF REQUEST 6/7
~~
Igloo CODES IL PROGRAMS GROUP TURKEY POINT PLANT UNIT 4 DESIGN PSIG:
OPERATING PSIG:
HYDROSTATIC PSIG:
TEMP(F):
TEMP(F):
TEMP(F):
CASTING SA-351, GR. CFBM UT CALIBRATION BLOCK: N/A DATE: 17 Ma 1990 REVISION APPROVEO BY:
0 F.
I ANDERSON ZONE: 56,57,58 DRAWING NUMBER:
004-V20 TITLE: REACTOR COOLANT PUMP (TYPICAL ALL 3 )
0 0
1