ML20087L535
| ML20087L535 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1984 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20087L529 | List: |
| References | |
| PROC-840319, NUDOCS 8403270253 | |
| Download: ML20087L535 (6) | |
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INTRODUCTION-This report defines the' Inservice Inspection (ISI) Program for Class-1, Class 2,
-and; Class 3 pressure retaining components for. the 10-year period starting Septem-a bar 26, 1983,Jto September 26.-1993, and Class 1, Class 2. and Class 3 pump and
- valve testing for the 10-year period from September 26, 1983, to September 26, 1993.
This program has.been developed as required by.Sec. 50.55(a) of 10 CFR Part 50 following the guidance of the ASME. Boiler Pressure Vessel Code Section' XI, " Rules
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' for: Inservice Inspection of Nuclear Power Plant Components".
The ISI Program
- will be controlled by the Fort Calhoun Station Unit 1 Technical Specifications.
This'. program is in compliance, where possible, with the ' applicable requirements of Section XI, of the ASME Boiler and Pressure Vessel Code, 1980 Edition through Winter of 1980 Addenda..
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'This program incorporates the results of previous inservice and preservice
. inspections.. It is the intent of the Licensee to continue to review and apply, as appropriate, changes in the code which would improve the total ISI Program, l pursuant to 10 CFR.50.55(a).
.PART 1:-
Class 1 - Class 2, and Class 3 Pressure Retaining Components
-1.1 Scope ~and Responsibility:
11.1.1
'The Piping and Instrumentation. Drawings (P&lDs) in Appendix 1A identify the class boundaries. These-t fare.always under review and are subject to change.
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1.1.2; Class 1 and Class 2 components and the methods of examina-tion for each component are listed in Tables 1.1 and 1.2, respectively. Class 3 components are those found on the
'P&lDs in Appendix 1A. The specific components to be examined for each class shall be identified ~1n the Fort Calhoun Station Unit 1 Inservice Examination Plan by 1
' title and/or number. Class 3 components will be examined to the extent required by IWD-2500.-
Class 3 portions of the Waste Disposal System have been optionally classified g
as Class 3 in accordance with Subarticle IWA-1300, Para-graph (g.) of the Section XI Code. Examination in accord-ance with the rules of Article-IWD will not be performed.
E' on the-Class 3 portion of the Waste Disposal-System.-
Exceptions to compliance with Tables IWB-2500 and IWC-2500 of Section XI are. listed in Appendix 1B and Appendix 1C, t
respectively..
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Inspection Intervals
.1.2.1J ;The inspection'. intervals for Class 1, Class 2, and Class 3
-components will be 10-year intervals of service commencing on September 26, 1973. As indicated previously, this 1
program plan' covers the second 10-year interval, i.e.,
t September 26, 1983, to September 26, 1993.
f1SI PP Rev. 3.
Feb. 24,1984 -
840327025d840319
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PDR ADOCK 05000285 G
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APPENDIX 18 Exceptions to Compliance with Table IWB-2500-1 (Class 1 Components) in ASME Boiler and Pressure Vessel Code, SectionXI,1980(WinterAddenda)
Item No.
Exception B 1.40 The closure head-to-flange weld has physical obstructions which limit the extent of the ultrasonic and surface exam.
Specifically, there are twelve seismic skirt mounting lugs, each six inches wide, located 37 inches apart, evenly spaced around the exam area. Thus 72 inches of the head-to-flange weld cannot be examined due to this physical obstruction.
Also, due to interference from the seismic skirt and the head flange, the UT scanning is limited to 4 inches either side of the head-to-flange weld. This restricts the volume of-the weld examination, and, depending upon the angle of the transducers used, may result in less than the code-required weld volume to be examined. Radiation levels of 7-8 R/Hr.
area and 10 R/Hr. surface have prohibited access to perform the UT from the inside surface of the head. Therefore, a volumetric and surface exam will be done only on the acces-sible portions of the closure head-to-flange weld.
.B 3.10:
The nozzle-to-vessel welds cannot be 100% volumetrically examined since the nozzle supports present an interference to currently available equipment. The nozzle-to-vessel welds will be examined during the reactor vessel examina-tion. This examination will be from the inside.
B _3.30' The pressurizer surge line nozzle-to-shell weld cannot be 100% volumetrically examined due to interference from heater penetrations. The weld will be volumetrically examined to the extent.possible. The weld area will be visually examined for leakage near the end of the inspec-tion interval in accordance with IWB-5221 and IWB-5222.
B 3.40
_ The pressurizer surge line inside radius section _cannot 1
be 100% volumetrically examined due to interference from heater penetrations. The area will be volumetrically examined to the extent possible. The area will be visu-ally examined for leakage near the end of the inspection interval in accordance with IWB-5221 and IWB-5222.
B_6.20 & B-6.30
. Closure head studs will be ultrasonically examined from the center drilled hole in accordance with ASME Code Case N-307 as referenced in Regulatory Guide 1.147, Inspection l
Code Case. Acceptability.
l B 9.10 - 9.40 The primary piping is fabricated using centrifuga11y cast stainless steel pipe and cast stainless steel elbows.
I ISI PP Rev. 1, Feb. 23, 1984 7
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Experience has shown that these materials and welds are not always amenable to ultrasonic examination.
Radio-graphic techniques have been developed to substantially overcome this problem. Volumetric examination will be performed to the extent practical and according to the schedule designated in the Examination Plan. Should other specialized ultrasonic examination techniques become practical which are more effective, they will be incorporated into the Examination Plan.
Inaccessible Piping Welds:
Figure No.*
Line No.
Weld No.
A-22 12 in. - SI-12 16 A-25 12 in. - SI-24 16 A-27 6 in. - SI-14 10 A-27 6 in. - SI-14 11 A-32 3 in. - HPH-22 1
A-32 3 in. - HPH-22 3
A-38 2 in. - HPH-2.12 5
A-42 12 in. - SDC-20 7
The welds listed above are inaccessible for examination because they are located within walls or floors. Areas on either side of the walls or floors containisig these piuping welds will be examined for signs of leakage during the pressure and hydrostatic testing of the piping systems.
B 12.10 The reactor coolant pump casings are made of cast stain-less steel sections which are then welded together. This type of material is not amenable to ultrasonic examination.
Further, radiographic examination of a Byron Jackson pump casing has not yet been demonstrated to be feasible in an operating environment. Acceptable methods of performing a volumetric examination of these welds may be developed before the end of the second 10 year inspection interval.
If such methods are found, they will be considered for use at the Fort Calhoun Station.
If no acceptable volume-tric examination can be performed, a surface exam will be performed on 100% of the casing welds on one pump prior to the end of this 10-year inspection interval.
B 12.20 The District's position is that a visual examination will be performed only if a pump is disassembled for main-tenance permitting such inspection. This is judged to be adequate based upon design, fabrication, and accessi-bility considerations.
- See the 10-Year Inservice Examination Plan, fort Calhoun Station Unit 1 ISI PP Rev. 3, Feb. 24, 1984 8
Operating Modes Subarticle Required for Test Parameter _
Frequency _
Exceptions Testing Inlet Pressure Quarterly IWP-3100 1, 2 or 3 Differential Quarterly IWP-3100 1, 2 or 3 Pressure 1, 2 or 3 Flow Rate Quarterly 1, 2 or 3 Vibration Quarterly Amplitude 1, 2 or 3 7
Yearly Bearing Temperature Exceptions:
IWP-3100 Inlet pressure measurement Basis: System design does not permit direct measurement of inlet pressure.
Inlet pressure to be measured by observing Aux FW tank level or head.
Differential pressure measurement Basis: Because of the inability to measure inlet pressure, direct different-tal pressure measurement is not possible, but it will be calculated by subtracting input from output pressure (in consistent units.)
ISI PP Rev. 2,4.Feb._2, 1984 :?!
211
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.SI-194 These valves function to prevent back-flow through the 195 safety injection pump discharge headers. These valves 197 cannot be stroke-tested during cold shutdowns or quar-198 terly during operation because to do so using the 200 safety injection system would require introducing cold 201 water into the reactor coolant system causing thermal 203 shock and possibly a reactor excursion. To do so 204 using the chemical volume control system would disrupt charging and letdown flow to the reactor coolant system causing chemical and volume control to the system to be dis rupted. Testing shall be performed per Tech.
Spec. 2.1, and Tech. Spec. 3.3(3).
SI-208 These valves function to prevent back-flow from the 212 reactor coolant system through the safety injection 216 system. These valves cannot be tested during cold 220 shutdowns or quarterly during operation because to do so would introduce cold charging water to the reactor coolant system causing thermal shaci. The valves cannot be partial-stroked for the same reasons. Testing shall be performed per Tech. Spec. 2.1, and Tech. Spec.
3.3(3).
HCV-240 Cycling this valve during operation would cause excess pressurizer spray, causing a reactivity excursion.
HCV-249 Cycling this valve during operation would cause excess pressurizer spray, causing a reactivity excursion.
ISI PP Rev. 2, Feb. 2, 1984 29 x
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s CATEGORY B VALVES (Cont'd)
Max. Permissible Exercise Exceptions P&lD Stroke Time Test Nor. Pos.,
(Refer to Valve Number Vahe P&ID.
Location Size Sec.
(Oper.)
Schedule Fallare Mode Appendix 2C)
(System)
Type Nweber 7
HCV-1387B(FW)
Gate GFDR-11405-M-253 C2 2"
51 (AD)
CS -
No, FC.
Ex-4 HCV-1388A(FW)
Gate G2R-11405-M-253 AZ 2"
39 (AD)
Gate GHDR-11405-M-253 A2 2*
39 (AD)
CS N0,FC (x
LCV-218-2(CH)'
Gate CE-E-23866-14 4*
28 (MO)
RO NO Ex 210-120-1 of 2 HCV-238(CH)
Globe CE-E-23866-A7 2"
48 (AD)
Q NO, F0 -
210-120-1 of 2 HCV-239(CH)
Globe CE-E-23866-A7 2"
51 (AD)
Q NO, F0 210-120-1 of 2 HVC-240(CH)
Globe CE-E-23866--
A8 2"
50 (AO)
RO NC, FC Ex l
210-120-1 of 2 HVC-247(CH)
Globe CE-E-23866 87 2"
NA.
(50)
Q NO, F0 210-120-1 of 2 HVC-248(CH)
Globe CE-E-23866 87 2"
NA (50)
Q NO, F0 210-120-1 of 2 HVC-249(CH)
Globe CE-E-23866 A8 2"
NA (50)
RO NC,FC Ex l
210-120-1 of 2 HCV-257(CH)
Globe CE-E-23866-F4 2"
20 (AD)
Q NO, FC 210-121 t'
,ECV-258(CH)
Gate CE-E-23866-E3 3" ~
46 (MO)
RO NC Ex 210-121 S
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