ML20066C007

Tabs 36 & 42 to Revision 1 to Inservice Insp Program

ML20066C007
Person / Time
Site:	LaSalle
Issue date:	06/30/1982
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20066C005	List: ML20066C003 ML20066C007 ML20066C010
References
PROC-820603-01, NUDOCS 8211090305
Download: ML20066C007 (8)

Text

..

+ J, n b

"', 2 ^

Page 1 of 6 Commonwealth Edison r~N U

@ LaSalle County Nuclear Stauon Unit I AUGHENTED INSERVICE INSPECTIONS 7',,

' o Augmented Inservice Inspections (AISI) are not ASME Section XI Code requirements but are 1) additional examination area requirements, or 2) increased inspection frequency requirements or combinations of both which are requested by the Nuclear Regulatory Commission. When components fall into the scheduled testing of both ISI and AISI, credit for both requirements is taken (no double testing).

There are presently 4 types of Augmented Inservice Inspections required at LaSalle County Nuclear Stations:

Type Description 1A The ASME Category B-F and B-J welds of the high energy line break exclusion regions as identified in the FSAR and requested by the NRC.

See response to FSAR Q111.72.

O IB Examinations of the Feedwater Nozzle Inner Radli, Nozzles Bores, O Nozzle Safe Ends, and Spargers, as requested by the NRC in NUREG-0619.

1C Examinations of the High and Low Pressure Core Spray Spargers and the associated piping inside the RPV each refueling outage, as requested by the NRC in IE Bulletin No. 80-13, 2A Examinations of the Reactor Core Isol.ation Coolant lines that are exempted by ASME Section XI, IWC-1220(b), but are examined due to the NRC requesting this system be treated as an essential system.

l l

i

(

1 Ov 1 ~ " ~

l '~ 8211090305 '821103 '

PDR ADOCK 05000373 l l

O PDR

CommonwealthEdison Page 2 of 6 LaSalle County Nuclear Station Unit 1 k) Augmented Inservice Inspection Type 1A The following ASME Category B-F and B-J welds receive 100% volumetric examination each inspection interval, except as noted. Those welds marked by asterisk (s) receive alternate examinations as follows:

• See RI-05 for alternate examination.

• • See RI-11 for alternate examination.

For further information on a component, such as configuration, material, cal.

std., etc., see Tab 11 "ASME Category B-F", or Tab 15 "ASME Category B-J".

Feedwater Low Pressure Core Spray Main Steam IFW-1001-10 ILP-1001-2 IMS-1054-18 IFW-1001-10LD ILP-1001-2A IMS-1054-18LD IFW-1001-13 ILP-1001-8 IMS-1054-19*

IFW-1001-13LD ILP-1001-9 IMS-1054-19LU*

IFW-1001-13LU ILP-1001-12 IMS-1054-21 IFW-1001-16 ILP-1001-14 IMS-1054-21LD IFW-1001-16LU ILP-1001-15 IMS-1054-26 IFW-1001-18* ILP-1001-16 IMS-1054-25LU IFW-1001-18LD* ILP-1001-17 IFW-1001-20 ILP-1001-18 IMS-0014A-13 IFW-1001-20LU ILP-1001-19 IMS-0014A-14 ILP-1001-21

(])

IFW-1002-10 Main Steam Residual Heat Removal IFW-1002-10LD IFW-1002-12 IMS-1051-15 IRH-1001-2 IFW-1002-12LD IMS-1051-15LD IRH-1001-7 IFW-1002-12LU IMS-1051-16* IRH-1001-10 IFW-1002-15 IMS-1051-16Ll? IRH-1001-12 IFW-1002-15LU IMS-1051-18 IRH-1001-13 IFW-1002-17* IMS-1051-18LD IRH-1001-14 IFW-1002-17LD* IMS-1051-26 IRH-1001-17 IFW-1002-20 IMS-1051-26LU IRH-1001-18 IFW-1002-20LU IRH-1001-19 IMS-1052-17 IRH-1001-20 High Pressure Core Spray IMS-1052-17LD IRH-1001-21 IMS-1052-18* IRH-1001-24 IHf-1001-2 IMS-1052-18LU*

IHP-1001-8 IMS-1052-20 IRH-1002-2 IHP-1001-10 IMS-1052-22LD IRH-1002-5 IHP-1001-13 IMS-1052-28 IRH-1002-6 IHP-1001-15 IMS-1052-26LU IRH-1002-12 IHP-1001-16 IRH-1002-14 IHP-1001-17 IMS-1053-15 IRH-1002-15 IHP-1001-19 IMS-1053-15LD IRH-1002-19 IHP-1001-20 IMS-1053-16* IRH-1002-20 IHP-1001-21 IMS-1053-16LU* IRH-1002-22

(~/)

N_ rHP-1001-22 IMS-1053-18 IRH-1002-23 IHP-1001-28 IMS-1053-19LO IMS-1053-26 IMS-1053-26LU

Commonwealth Edison Page 3 of 6

(~')

\/

@ LaSalle County Nuclear Station Unit 1 Augmented Inservice Inspection Type 1A (Cont'd)

Residual Heat Residual Heat Reactor Core Removal (Cont'd) Removal (Cont'd) Isolation Coolant IRH-1003-2 IRH-1031-20ALD IRI-1002-1 IRH-1003-9 IRH-1031-20BLD IRI-1002-3 IRH-1003-10 IRH-1031-25 IRI-1002-4 IRH-1003-12 IRH-1031-25ALU IRI-1002-5 IRH-1003-13 IRH-1031-25BLU IRI-1002-6 IRH-1003-15 IRH-1031-27 IRI-1002-8 IRH-1003-16 IRH-1031-29 IRI-1002-9 IRH-1003-19 IRH-1031-31 IRH-1003-20 IRH-1031-31ALD IRI-1003-9 IRH-1003-21 IRH-1031-31BLD IRI-1003-10 IRH-1003-22 IRH-1031-32 IRI-1003-11 IRH-1003-24' IRH-1031-32ALU IRI-1003-13C IRH-1003-26 IRH-1031-32BLU IRI-1003-14 IRH-1031-40 IRI-1003-15 IRH-1004-2 IRH-1031-43 IRI-1003-17 IRH-1004-3 IRI-1003-18 IRH-1004-9 Reactor Core IRI-1003-19 IRH-1004-11 Isolation Coolant IRI-1003-20 IRH-1004-12 IRI-1003-22 fs IRH-1004-16 IRI-1001-1 IRI-1003-23

!s ,) IRH-1004-17 IRI-1001-2 IRI-1003-24 IRH-1004-19 IRI-1001-3 IRI-1003-25 IRH-1004-20 IRI-1001-4 IRI-1003-27 IRI-1001-5 IRI-1003-28 IRH-1005-2 IRI-1001-6 IRI-1003-29 IRH-1005-8 IRI-1001-7 IRI-1003-30 IRH-1005-10 IRI-1001-7A IRI-1003-31 IRH-1005-13 IRI-1001-8 IRI-1003-32 IRH-1005-15 IRI-1001-9 IRH-1005-16 IRI-1001-9A** Reactor Water Clean-Up IRH-1005-17 IRI-1001-15 IRH-1005-18 IRI-1001-16 IRT-1001-24 IRH-1005-20 IRI-1001-16A IRT-1001-25 IRI-1001-18 IRT-1001-26 IRH-1031-9 IRI-1001-19 IRT-1001-27 IRH-1031-12 IRI-1001-20 IRT-1001-28 IRH-1031-12ALD IRI-1001-21 IRT-1001-29 IRH-1031-12BLO IRI-1001-24 IRT-1001-30 IRH-1031-17 IRI-1001-25 IRT-1001-31 IRH-1031-17ALU IRI-1001-26 IRT-1001-32 IRH-1031-178LU IRI-1001-27 IRT-1001-33 IRH-1031-20 IRI-1001-28 IRT-1001-37 IRT-1001-38 v

l l

CommonwealthEdison Page 4 of 6 I

@ LaSaHe County Nuclear Station Unit 1 Augmented Inservice Inspection Type 18 The feedwater components listed in Table 1 receive examination per Section 4.3.2.3 of NUREG-0619 and Table 2. As required by Section 4.4.3.1 of NUREG-0619, within 6 months of completing an outage at which an inspection was performed in accordance with Table 2, the licensee must submit a detailed report discussing the inspection (s) performed. Information required includes:

(a) Number of startup/ shutdown cycles since the previous inspection, and the total number of cycles. This will include cycles accumulated during the initial startup and testing of the plant.

(b) Summary of methods used and results of previous inspections, including maximum crack depth and number of cracks found in previous PT-and-grind operations, and number of startup/ shutdown cylces between such inspections.

(c) Description of any additional system changes or changes in operating procedures that will affect feedwater flow or temperature and that should be considered in predicting future cracking tendencies based on past history.

(d) A detailed discussion of the inspection results, including a complete description of cracking location, dimensions, and profile, if cracking

(]. was found. Drawings and photographs, if available, are requested.

(e) Information regarding the results of leakage monitoring. However, the staff must be informed imediately if on-line leakage monitoring during operation discloses any leakage on welded spargers or leakage on the order of 0.3 gpm through single-sleeve / single-piston-ring spargers or triple-sleeve spargers.

(f) Information regarding all UT crack-like indications and any subsequent PT indications. Information regarding UT techniques should be as precise and as extensive as possible in order that it may be of benefit in future inspections.

(g) The above information is to be submitted to the Regional Director, IE, with copies to Director, IE, and Director, NRR.

(vD

e CommonwealthEdison Page 5 of 6 V'

@ LaSalle County Nuclear Station Unit 1 Table 1 Components Receiving Examination

_ Exam./ Component I.D. No. For Further Information See:

1 - NIR - 4A (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4B (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4C (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4D (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4E (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4F (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - Feedwater Spargers Tab 21 "ASME Category B-N-1" IFW-1001-71A Tab 11 "ASME Category B-F" IFW-1001-81A Tab 11 "ASME Category B-F" IFW-1001-89A Tab 11 "ASME Category B-F" IFW-1002-53A Tab 11 "ASME Category B-F" IFW-1002-63A Tab 11 "ASME Category B-F" IFW-1002-72A Tab 11 "ASME Category B-F" 1Further information such as: examination type, material specification, calibration standard, etc.

Table 2 c Routine Inspection Intervals Inspection Interval-Refueling Cycles (or Startup/ shutdown Cycles)

Visual Inspection Configuration UT of Sparger l Routine PT2 ,3 Triple-sleeve spargers 2 4 9 (or 135) with two piston-ring seals, clad removed.

1 Visual inspection of flow holes and welds in sparger arms and sparger tees.

2 To be performed even if the UT and leak test results are satisf actory.

3 The routine PT consists of removal of a sparger from one nozzle followed by flapper wheel grinding of the nozzle and PT examination of both the nozzle and the accessible portions of the other feedwater nozzles.

4The UT examination consists of external UT examination of all feedwater nozzle safe ends, nozzles bores, and nozzle blend radii.

S If UT recordable indications are interpreted to be cracks in any nozzle (s),

{s~} remove the sparger(s) from the nozzle (s), perform PT examination on the nozzle bore and nozzle blend radius, and repair. Also, perform PT examination on the accessible portions of the remaining nozzles.

1 CommonwealthEdison Page 6 of 6 ry b'

@ LaSalle County Nuclear Station Unit 1 Augmented Inservice Inspection Type IC Visual examination of the High and Low Pressure Core Spray Spargers and the associated piping inside the RPV is performed each refueling outage, as requested by the NRC in IE Bulletin No. 80-13. The visual examination is performed using LaSalle County Station Procedure LTS 600-8.

Augmented Inservice Inspection Type 2A The components of the Reactor Core Isolation Coolant piping lines listed in Table 3 are exempt from examination by ASME Section XI, IWC-1220(b). Due to the NRC requesting this system be treated as an essential system, the components are scheduled for examination using ASME Section XI selection criteria. For further information, see Tab 5 " Component and Piping Line Number Table: CPLN". The type and number of components requiring examination are listed in the CPLN.

Table 3 RCIC System AISI Piping Lines 1RIO2A 1RIO2B 1RIO2C

- 1RIl2A L, IRI16A 1RI16B 1RI17A 1RI24A 1RI408 1RI43B O

.. . ]

CommonwealthEdison jE <f ' --

LaSalle County Nuclear Station Unit 1 O @

NDE PROCEDURES The NDE procedures used to perform the Inservice Inspection examinations are listed in Table 1. The NDE procedures are contained in the LaSalle County Station Inservice Inspection Nondestructive Examination Procedures Manual and are available for review at the LaSalle County Station.

O The NDe procedures ere written in eccordence ith the aSxE 80iier end eressure Vessel Cod _e,1980 Edition thru Winter 1980 Addenda. The ISI examinations are performed tising the revision of the NDE procedure in effect at the time of the examination, n

U

}

CommonwealthEdison m

@ LaSailo County Nuclear Stauon Unit 1 TABLE 1 NDE Procedure No. Title APUN-W801 Automated Ultrasonic Testing of Nozzle to Vessel Welds APUV-W801 Automated Ultrasonic Testing of RPV Welds and Base Material MPUB-W801 Ultrasonic Inspection of Pressure Retaining Greater Than Two Inches in Diameter MPUD-W801 Manual UT Examination of Full Penetration Piping Welds (Half-Vee Technique)

MPUL-W801 Manual UT Examination of Flange Ligaments MPUP-W801 Manual UT Examination of Full Penetration Piping Welds MPURHX-W801 Manual Ultrasonic Testing of RHR Heat Exchanger Welds O

k> MPUV-W801 Manual Ultrasonic Testing of RPV Welds NIRRHX-W801 Ultrasonic Examination of RHR Heat Exchanger Nozzle Inner Radius NIRZ1-W801 Procedure for Nozzle Inner Radius Zone 1 Ult.rasonic Examination NIRZ2-W801 Procedure for Nozzle Inner Radius Zone 2 Ultrasonic Examination NIRZ2-N9-W801 Ultrasonic Examination for Nozzle Inner i Radius Zone 2 on LaSalle Unit 1 Jet Pump l Instrumentation Nozzles PP-W801 Liquid Penetrant Examination of Nuclear Power Plant Components PV1-W801 Visual Examination VT-1  !

l PV2-W801 Visual Examination VT-2 j PV3-W801 Visual Examination VT-3 s PV4-W801 Visual Examination VT-4 l

1 l

1

J MS6 War 9xsjxdis f htu Se/if

!$Mef//