ML19331B645
| ML19331B645 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/14/1980 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML19331B642 | List: |
| References | |
| NUDOCS 8008120536 | |
| Download: ML19331B645 (17) | |
Text
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4 ATTACHMENT "B" 1
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8008120 SSG
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i (c)
Corrective Action:
Valve malfunctions disclosed by any Class C test shall be corrected and reported in the subsequent Class A test report.
Leaks which exceed the acceptance criteria of (b) shall be repaired and retested until the criteria are met.
Repairs of lesser leaks are optional.
(d)
Test Frequency: At least two Class C tests at approximately equally spaced intervals shall be performed during the interval between any scheduled Class A test.
5.2.1.4 Permissible Periods for Testing:
The performance of Class A tests shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition under administrative control and safety procedures.
5.2.1.5 Report of Test Results:
Class A tests shall be the subject of a summary technical report, which includes a schematic arrangement of the leakage measurement system, the instrumentation employed, the test procedure, test results in graphical form, and the analysis and interpre-tation of results.
Summaries of Class B and C tests performed during the interval preceding the scheduled Class A test are to be included in the same report.
5.2.2 The reactor building isolation system will be tested for proper operation prior to every cold startup, but this test will, not be required more often than at 30-day intervals.
5.2.3 The exterior surfaces of the LACBWR ventilation stack and the smoke stack of the conventional steam power generating station, Genoa 3, adjacent to the LACBWR plant shall be inspected for structural integrity at an interval no longer than 5 years following the initial construction inspection, and at subsequent intervals not longer than 5 years apart.
5.2.4 The reactor vessel shall be hydrostatically tested at 1400 psig after any of its gasketed joints have been opened and resealed.
All hydrostatic tests shall be performed with the vessel at a temperature no lt ver than that specified in Sec. 4.2.2.4 5.2.5 The forced circulation system controls and automatically-operated valves shall be tested for proper operation annually.
5.2.6 The shutdown condenser system control valves shall be tested at least quarterly to demonstrate their operability.
The integrated system shall be tested for proper operation annually.
In addition, the condenser tube bundle shall be pressurized to greater than 1250 psig and tested for leakage annually.
9 5.2.7 The high-pressure core spray system controls and remotely-operated valves shall be tested during cold shutdowns, but not more often than every 3 months, to demonstrate their operability.
The integrated system shall be tested for proper operation annually.
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5.2.8 The Alternate Core Spray System controls and remotely-operated valves shall be tested during cold shutdowns, but not more often than every 3 months, to demonstrate their operability.
The integrated system shall be tested for proper operation annually, with the supply line to the reactor vessel isolated and the coolant flow directed through the system and back to the river.
In addition, an annual test shall be performed to demonstrate that the check valves in the system are not stuck in a closed position.
I 5.2.9 The boron-injection system controls and the remotely-operated l
valves shall be tested for proper operation during cold shutdowns, but not more often than every 3 months.
ORext number is 5.2.121 j
5.2.12 Each control rod scram time shall be measured prior to cold start-ups and the total scram time shall be demonstrated to be within the limit specified in Sec. 4.2.5.1.
These scram time tests will not be required more often that at 30-day intervals, but at least semi-annually, unless the reactor vessel head has been removed or unless maintenance work has been performed on the control rod drives.
5.2.13 Each control rod drive nachanism shall be exercised by moving each partially or fully withdrawn control rod at least one-half inch in any one direction:
a.
At least once per 7 days during the ini ial 31 days of Cycle 5 operation, and b.
At least once per 31 days thereafter.
5.2.14 Proper operation of both control solenoids for each of the hydraulic scram valves will be determined annually by visual observation g
of solenoid arm position following control rod scram.
5.2.15 Instrumentation shall be checked, tested and calibrated as indi-cated in the following chart.
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--~_
INSERVICE IMSPECTION PROGRAM - LACBWR CLASS I COMPONENTS ITEM EXAMINATION EXTENT AND FREQUENCY NUMBER CATEGORY COMPONENTS AND PARTS TO BE EXAMINED METHOD OF EXAMINATION NOTES / REMARKS REACTOR VESSEL AND CLOSURE HEAD - (Cont'd)
U 1.
Steam Nozzle N at 14
- j. Steam Nozzle S at 194' k.
Emergency Cooling Nozzle in Upper Shell at 315 1.
Emergency Cooling Nozzle in Upper Head Access Nozzle Flange m.
Upper Head Access Nozzle n.
Blow-Down Nozzle in Lower Head Bl.5 B-E (1)
Vessel penetrations, including control Visual 25t/10 Yrs, rod drive and instrumentation penetrations a.
Control Rod Drive Penetrations b.
Experimental Access Penetration 45 c.
Experimental Access Penetration at 165 d.
Experimental Access Penetration at 285 e.
Upper Liquid Level Penetration f.
Intermediate Liquid Level Penetration g.
Lower Liquid Level Penetration 4/1/80
INSERVICE ANSPECTION PROGRAM - LACBWR CLASS I COMPONENTS ITEM EXAMINATION EXTElfr AND FREQUENCY NUMBER CATEGORY COMPONENTS AND PARTS 'IO BE EXAMINED MET 1tOD OF EXAMINATION NOTES / REMARKS h.
Primary Purification Penetration in Lower lie 4d Dl.6 B-F Nozzle-to-safe end welds Volumetric 100%/10 Yrs.
& Surface a.
Emergency Cooling Nozzle in Upper Shell-to-Safe End b.
Blow-Down Nozzle in Lower llead-to-Safe End Bl.7 B-G-1 Nits Surface or 100%/10 Yrs.
Volumetric
& Visual Bl.9 B-G-1 Studs Volumetric 100%/10 Yrs.
& Surface Bl.9 B-G-1 Ligaments between threaded stud holes Volumetric 100%/10 Yrs.
Bl.10 B-G-1 Closure washers, bushings Visual 100%/10 Yrs.
None Exist Bl.11 B-G-2 Pressure-retaining bolting Visual 100%/10 Yrs, a.
Upper IIcad Access Nozzle Flange Studs b.
Upper IIcad Access Nozzle Flange Nuts Bl.12 B-II (1)
Integrally welded vessel supports Volumetric 100%/10 Yrs.
Bl.13 B-1-1 Closure head cladding Visual &
6 Patches /10 Yrs.
Surface Bl.14 B-1-1 (1)
Vessel Cladding
' Visual Each Refueling Bl.15 B-N-1 Vessel interior Visual Each Refueling 4/1/00
INSERVICE IMSPECTION PROGRAM - LACBWR CLASS I COMPONENTS ITEM EXAMINATION EXTENT AND FREQUENCY NUMBER CATEGORY COfiPONENTS AND PARTS TO BE EXAMINED METIIOD OF EXAMINATION NOTES / REMARKS Bl.16 B-N-2 Interior attachments and core support Visual 100%/10 Yrs.
l structures Bl.17 B-N-3 Core-support structures Visual NA PWR's Only l
Bl.18 B-O Control rod drive housings Volumetric 100%/10 Yrs.
None Exist l
Bl.19 B-P Exempted components Visual 100%/10 Yrs.
(IWA-5000)
IIEAT EXCIIANGERS B3.1 B-B Longitudinal and circumferential welds, Volumetric 5%/10 Yrs.
'l-including tube sheet-to-head or shell welds on the primary side, a.
Decay IIcat Channel Head-to-Tube Sheet Weld B3.2 B-D Nozzle-to-head welds and nozzle inside Volumetric 100%/10 Yrs.
radiused sect.lon on the primary side a.
Inlet Decay !! cat Nozzle-to-Channel llead b.
Outlet Decay lieat Nozzle-to-Channel liead B3.3 B-F Nozzle-to-safe end welds Volumetric 100%/10 Yrs.
& Surface B3.5 B-G-1 Pressure-retaining bolts and studs Volumetric 1F20 Yrs.
None Exist
& Surface B3.6 B-G-1 Pressure-retaining bolting Visual 100%/10 Yrs.
None Exist 4/1/80 s
INSERVICE INSPECTION PROGRAM - LACBWR CLASS I COMPONENTS ITEM EXAMINATION EXTENT (REQUENCY NUMBER CATEGORY COMPONENTS AND PARTS TO BE EXAMINED METIIOD OF Ekid41 NATION NOTES / REMARKS B3.7 B-l!
Integrally welded vessel supports Volumetric 100%/10 Yrs.
None Exist B3.8 B-1-2 Vessel Cladding Visual 1 Patch /10 Yrs.
a.
Decay Heat Cooler B3.9 B-P Exempted components visual 100%/10 Yrs.
B3.10 B-G-2 Pressure-retaining bolting Visual 100%/10 Yrs.
a.
Decay IIcat Cooler llead Studs, 56-03-001 b.
Decay lleat Cooler Head duts, 56-03-001 c.
Primary Purification Regnerative Cooler IIcad Studs d.
Primary Purification Regenerative Cooler Head Bolts B3.ll B-Q Steam generator tubing Volumetric 3%/10 Yrs.
None Exist PIPING PRESSURE BOUNDARY B4.1 B-F
'l)
Safe-end to piping welds and safe-end Volumetric 100%/10 Yrs.
in branch piping welds
& Surface a.
2-Inch Purification Branch b.
2-Inch Boss on Loop Isolation Valves c.
8-Inch Decay Heat Suction 4/1/80
m INSERVICE INSPECTION PROGRAM - LACBWR CLASS I COMPONENTS ITEM EXAMINATION EXTENT AND FREQUENCY NUMBER CATEGORY COMPONENTS AND PARTS TO BE EXAMINED METI!OD OF EXAMINATION NOTES / REMARKS d.
6-Inch Decay lleat Discharge e.
Decay IIeat Cooler Inlet and Outlet f.
8-Inch Steam Lines g.
10-Inch Steam Lines h.
6-Inch Alternate Core Spray Line
- i. 4-Inch Alternate Core Spray Linc
- j. 2\\-Inch Boron Inject Line B4.2 B-G-1 Pressure-retaining bolts and studs in place Volumetric None Exist l I
B4.3 B-G-1 Pressure-retaining bolts and studs Volumetric None Exist l when removed
& Surface B4.4 B-G-1 Pressure-retaining bolting Visual None Exist l
B4.5 B-J (1)
Circumferential and longitudinal pipe welds Volumetric 25%/10 Years I
i B4.6 B-J Branch pipe connection welds exceeding Volumetric 25%/10 Years l
l 6 inches in diameter B4.7 B-J Branch pipe connection welds 6 inches Surface 25%/10 Years l
in diameter and smaller B4.8 B-J Socket welds Surface 25%/10 Years i
B4.9 B-K-1 (1)
Integrally welded supports Surface 25%/10 Years 4/1/80
+-
~-
INSERVICE INSPECTION PROGRAM - LACDWR CIASS I COMPONENTS ITEM EXAMINATION EXTENT A!!D FREQUENCY NI?MI5ER CATECORY COMPONENTS AND PARTS TO DE EXAMINED METilOD OF EXAMINATION NOTES / REMARKS B 4.' 10 D-K-2 Support components Visual 100%/10 Yrs.
D4.11 D-P Exempted componento Visual 100%/10 Yrs.
li4.12 B-G-2 Pressure-retaining bolting Visual 100%/10 Yrs.
A.
Purification filter cover Pi?MP PPESStlPE BOUNDARY 155.2 B-C-1 Pressure-retaining bolta and studa Volumetric 1004/10 Yrs, when removed
& Surface A.
Forced Circulation Pumps Casing H5.3 H-G-?
Pressure-retaining bolting Visual 100%/10 Yrs.
145.4 D A-1 Integrally welded supportn Volumetric 25%/10 Yrn.
Nono Exist 115.5 Il-r-2 Support componenta Visual 100%/10 Yrs.
I$ 5. 6 li-L- 1 Pump casing welds Volumetric 100%/10 Yrs.
None Exist l 115.7 15-L- 2 Pump canings Vinual 100%/10 Yrn.
l h5.R D-P Exempted components Visual 100%/10 Yrn.
li5.9 D-C-2 Prennure-rotaining bolting Visual 100%/10 Yrs.
A.
Forced Circulation Pump Seal Cover 4/1/80
R O
p? SERVICE INSPECTION PROGRAM - LACBWR CLASS I _T)MPONENTS ITEM EXAMINATION EXTENT AND FREQUENCY MUMBER CATEGORY COMPONENTS AND PARTS M BE EXAMINED METHOD OF EXAMINATION NOTES / REMARKS VALVE PRESSURE BOUNDARY 86.2 B-G-1 Pressure-retraining bolts and studs Volumetric 100%/10 Yrs.
when removed
& Surface a.
Forced Circulation Rotoport Upper Head B6.3 B-G-1 Pressure-retaining bolting Visual 103%/10 Yrs.
None Exist B6.4 B-K-1 Integrally welded supports Volumetric 25%/10 Yrs.
None Exist B6.5 B-K-2 Support components Visual 100%/10 Yrs.
None Exist B5.6 B-M-1 Valve-body welds Volumetric 100%/10 Yrs.
None Exist B6.7 B-M-2 Valve Bodies Visual As Applicable (2 )
(1 of a type)
B6.8 B-P Exempted components Visual 100%/10 Yrs.
B6.9 B-G-2 Pressure-retaining bolting Visual 100%/10 Yrs.
c.
Forced Circulation Rotoport Lower Head b.
Main Steam Relief valves in Mounting Flange c.
Decay Heat Pump Check Valve d.
Main Steam Rotoport Valve - Head e.
Feedwater Check Valve NOTES:
(2)
See Letter, Madgett to Keppler, LAC-2786, dated October 8, 1974.
4/1/80
2 RELIEF FOR CLASS I C06'9NENTS Page 1
~
REQUIRING'ISI TO ASME XI EXAMINATION CATEGORY INSPECTION ITEM TABLE REQUIRED N0.
IWB-2500 IDENTIFICATION OF WELD OR COMPONENT BY IWB-2600 BASIS FOR REQUESTING RELIEF REACTOR VESSEL LONGITUDINAL WELDS AND CIRCUMFERENTIAL WELDS IN CORE REGION Bl.1 B-A LONGITUDINAL JOINT #12 VOLUMETRIC A CONCRETE SHIELD WALL AR0UND THE VESSEL IN THIS AREA PREVENTS ACCESS TO THE WELDS, CIRCUMFERENTIAL JOINT #13 LONGITUDINAL JOINT #14 CIRCUMFERENTIAL JOINT #15 LONGITUDINAL JOINT #16 CIRCUMFEPENTIAL JOINT #17 LONGITUDINAL JOINT #18 v
REACTOR VESSEL LONGITUDINAL AND CIRCUMFERENTIAL WELDS NOT IN THE CORE REGION Bl.2 B-B LONGITUDINAL JOINT #6 VOLUMETRIC A CONCRETE BLOCK SHIELD WALL AROUND THE VESSEL IN THIS AREA PREVENTS ACCESS TO THE WELDS.
CIRCUMFERENTIAL JOINT #7 LONGITUDINAL JOINT #8 CIRCUMFERENTIAL JOINT #9 LONGITUDINAL JOINT #10 CIRCUMFERENTIAL JOINT #11 CIRCUMFERENTIAL JOINT #19 LONGITUDINAL JOINT #20 CIRCUMFERENTIAL JOINT #21 4/1/80
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TT RELIEF FOR CLASS I COMPONENTS Paga 3 REQUIRING ISI TO ASME XI EXAMINATION CATEGORY INSPECTION ITEM TABLE REQUIRED NO.
IWB-2500 IDENTIFICATION OF WELD OR COMPONENT BY IWB-2600 BASIS FOR REQUESTING RELIEF B4.5 B-E PRIMARY PURIFICATION PENETRATION IN VOLUMETRIC N0 ACCESS DUE TO REACTOR VESSEL LOWER HEAD TI. EXTENSION PIPE SUPPORT RING.
Bl.12 B-H INTEGRALLY WELDED REACTOR VESSEL VOLUMETRIC RELIEF REQUESTED TO USE ALTERNATE SUPPORTS INSPECTION METHOD UTILIZING SURFACE NDE.
Bl.14 B-I-l REACTOR VESSEL CLADDING VISUAL NO ACCESS JUSTIFIED DUE TO HIGH RADIATION LEVELS.
20" FORCED CIRCULATION SUCTION LOOP IB B4.1 B-F 22 BC,2" BRANCH CONNECTION VOLUMETRIC CONFIGURATION PRECLUDES VOLUMETRIC 2" FORCED CIRCULATION BYPASS LOAD 1A B4.1 B-F VALVE TO PIPE WELD #91A VOLUMETRIC CONFIGURATION PRECLUDES VOLUMETRIC B4.1 B-F PIPE TO VALVE WELD #90A VOLUMETRIC EXAMINATION. RELIEF REQUESTED TO 00 SURFACE NDE INSPECTION.
2" FORCED CIRCULATION BYPASS LOOP IB B4.1 B-F VALVE TO PIPE WELD #93A VOLUMETRIC CONFIGURATION PRECLUDES VOLUMETRIC B4.1 B-F PIPE TO VALVE WELD #92A VOLUMETRIC EXAMINATION.
RELIEF REQUESTED TO 00 SURFACE NDE INSPECTION.
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RELIEF FOR CLASS I COMPONENTS Page 4 REQUIRING ISI TO ASME XI
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EXAMINATION CATEGORY INSPECTION ITEM TABLE REQUIRED NO.
IWB-2500 IDENTIFICATION OF L' ELD OR COMPONENT BY IWB-2600 BASIS FOR REQUESTING RELIEF 10" MAIN STEAM PIPING B4.5 B-J PIPE TO PIPE, WELD #19 VOLUMETRIC N0 PERSONNEL ACCESS IN THIS AREA DUE TO THE SAMLL INTERIOR OF THE PIPE PIPE TO PIPE, WELD #20 CHASE CAVITY (2' SQUARE).
PIPE TO PIPE, WELD #21 PIPE TO PIPE, WELD #22
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MISCELLANE0US PIPING COMPONENTS:
MAIN STEAM AND SHUTDOWN CONDENSER PIPING SYSTEM HANGERS 84.9 B-K- 1 INTEGRALLY WELDED ATTACHMENT #MS-102 VOLUMETRIC ACCESS RESTRICTIONS DUE TO PIPE CHASE CAVITY AND RADIATION LEVELS OF 1100 TO 1500 MR/HR GENERAL AREA.
B4.9 B-K-1 REMAINING INTEGRALLY WELDED VOLUMETRIC BECAUSE OF WEuD CONFIGURATION, RELIEF ATTACHMENTS IS REQUESTED TO USE ALTERNATE INSPEC-TION METHOD UTILIZING SURFACE NDE.
FEEDWATER AND CONDENSER CONDENSATE PIPING SYSTEM HANGERS B4.9 B V-I INTEGRALLY WELDED ATTACHMENTS VOLUMETRIC ALTERNATE CORE SPRAY PIPING SYSTEM HANGERS B4.9 B-K- 1 INTEGRALLY WELDED ATTACHMENTS VOLUMETRIC V--
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RELIEF FOR CLASS I COMPONENTS Paga 5 REQUIRING ISI TO ASME XI EXAMINATION CATEGORY INSPECTION ITEM TABLE REQUIRED N0.
IWB-2500 IDENTIFICATION OF WELD OR COMPONENT BY IWB-2600 BASIS FOR REQUESTING RELIEF DECAY HEAT SUCTION AND DISCHARGE PIPING SYSTEM PANGERS B4.9 B-K- 1 INTEGRALLY WELDED ATTACHMENTS VOLUMETRIC BECAUSE OF WELD CONFIGURATION, REL~EF 1
IS REQUESTED TO USE ALTERNATE INSPEC-TION METHOD UTILIZING SURFACE NDE.
FORCED CIRCULATION SUCTION AND DISCHARGE HEADER PIPING HANGERS B4.9 B-K- 1 INTEGRALLY WELDED ATTACHMENTS VOLUMETRIC FORCED CIRCULATION SUCTION AND DISCHARGE AND PIPING SYSTEM HANGERS
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B4.9 B-K-1 INTEGRALLY WELDED ATTACHMENT VOLUMETRIC v
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