ML20236L523
| ML20236L523 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/16/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20236L525 | List: |
| References | |
| 3722K, NUDOCS 8711100390 | |
| Download: ML20236L523 (11) | |
Text
{{#Wiki_filter:, Comm:nw:elth Edison 2 One First National Plaza, Chicago, Illinois V Address Reply to: Post Office Box 767 Chicago, Illinois 60690 0767 October 16, 1987 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTN: Document Control Desk
Subject:
Braidwood Station Unit 1 Inservice Inspection (ISI) program NRC Docket No. 50-456
Dear Mr. Murley:
This letter provides a description of the Braidwood Unit 1 ISI-Program and presents the differences that exist between the Braidwood Unit 1 ISI program and the Byron Unit 1 ISI program. The Braidwood Unit 1 ISI program consists of a tabular listing of ASME Class 1, 2, and 3 piping components requiring inspection in a manner consistent with the ASME Section XI examination tables. Included in this listing are e series of Notes and Relief Requests. A similar ISI program Plan for component supports and snubbers is also included. The Braidwood Unit 1 inservice inspection requirements are the same as those used for Byron Unit 1. Ten (10) Notes and seventeen (17) Relief Requests are included in the piping components program. Attachment A provides a cross reference list for comparison of the Braidwood Unit-1 and Byron Unit 1 ISI program Notes. Attachment B provides a similar listing for the Relief Requests. (Relief Requests 1NR-1, INR-7, INR-8, INR-13, INR-16, and 1NR-17 are included for Braidwood Unit 1 and are not applicable to Byron Unit 1). Also, one (1) Note and two (2) Relief Requests are included in component support and snubber programs, respectively. Attachments C, D, E and F provide the applicable cross reference lists to Byron Unit 1. Brai4 Wood Unit 1 components exempted from ISI examination per Section "I paragraphs IWB-1220 and IWC-1220, and not subject to examination per Table IWD-2500-1, correspond to the Byron Unit 1 exempted components. There are some differences between units in the components exempted, due to design changes and minor installation differences. Inspectior.5 af the piping components, component supports and snubbers will be performed to the requirements of the ASME, Section XI Code, 1983 Edition with addenda up to and including the Summer,1983 Adder:Ja.. In addition to the code required inspections, augmented inspections h of high energy lines (described in Note 5 of the piping program), reactor k> 8711100390 071016 (}\\ a PDR ADOCK 05000456 / G PDR
1 T.E. Murley Octobsr 16, 1987 I coolant pump flywheels (Note 6 of the piping program), loop 1 steam generator weld #6 and pressurizer weld #8C (Note 7 of the piping program), I l high and low pressure turbine discs and rotors (Note 8 of the piping 'l program) and containment spray lines containing stagnant borated water (Note l l 10 of the piping program). Note 10 states that a sampling of seven and l l one-half percent (7.5%) of Class 2 containment spray (CS) welds in a single train between the CS pump and the first weld beyond the isolation valve inside the containment will be volumetrically examined. This differs from the previous Braidwood Unit 1 commitment in the Braidwood Safety Evaluation ) Report, Supplement 2 dated October, 1986, in which a random sampling of seven and one-half percent (7.5%) of the large bore (greater than 4") piping circumferential welds in the safety injection (SI) chemical and volumetric l valve (CV) and containment spray (CS) systems were to be ultrasonically examined during the first refueling outage for baseline information, and reexamined each ten year interval. These lines were normally exempt from ISI. This adjustment was made so that the Byron and Braidwood commitments are the same. The sample of the Braidwood Unit 1 components and parts of the l pressure retaining boundarieF that will receive ISI examinations is essentially identical those chosen for Byron Unit 1. Differences do exist in the tabular listings due to design changes and renumbering of lines. Also, the additional welds chosen to make up, for example, twenty-five percent (25%) of the total circumferential butt welds in the reactor coolant piping (listed as "h" in the ID SEL column of the component tables), are chosen at the discretion of the Station Technical Staff ISI Group, resulting in an equivalent difference between the two units. Notes 2 and 3 detail the use of ASME Code Cases N-419 and N-426, respectively. Both of these Code Cases were approved for use on July 18, 1985. Neither Code case was utilized at Byron. Note 7 describes the augmented ultrasonic exams of one weld in the Loop 1 steam generator pressurizer due to indications found during the preservice exam of these components. Byron does not have these augmented exams. As stated above, Note 10 has been written to parallel the Byron commitment. Relief Request 9 differs somewhat from Byron's Relief Request 1 because of the method each station's contractor used when remotely examining the reactor vessel. Relief Requests 1, 7, and 16 contain welds that are included in augmented exams, are high stress, and cannot be completely examined to the Code requirements. These welds differ from those listed in i the Byron program. Also Relief Requests 8, 13, and 17 are unique to Braidwood Unit 1. j The component support program is essentially similar to that of Byron. Note 1 to the program parallels Byron Relief Request CR-4. Because it is an explanation of the auxiliary feedwater components it is included as 1 a note. Relief Requests CR-1 and CR-2 parallel Byron's Relief Requests CR-2 { and CR-3 respectively. J l i I
24 - ) T.E. Murley.
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Octobar 16, -1987:: i i The number of' snubbers listed in the snubber program differs somewhat,from Byron's because of'the snubber reduction program,' Note-1 j . parallels Note 1 of the' Byron program. ~Similarly, Relief: Requests SR-1 and-SR-2 parallel Byron's Relief. Requests SR-1 and SR-2. This is being submitted for NRC. review.. Please' address any . questions concerning this matter to this office. k Very truly'yours, -l ~ L,/c. d e2x S.-C. Hunsader 'I Nuclear Licensing' Administrator- ] 1 cc: S. Sands ~ i. NRC RIII (Letter only) Braidwood Resident Inspector-(Letter only) M. Parker (IDNS) (Letter only) j i-I I 3722K I ) _.--_n
Paga: 1lof 2-ATTACHMhNT'A 1 Braidwood Unit 1/ Byron Unit.1' "ISI Program Plan Piping Components Note Cross' Reference' List-Braidwood Unit'l Byron Unit 10 l Note No. Note Description-Note No. 1 The' main steam nozzle was designed 14-with an interna 1' multiple venturi type: flow restriction and not a revised nozzle as shown in Figures IWC-2500-4(a)' L (b) and'is not subject to inner. radii inspection. 2 ASME Code Case N-419 whichi llows limiting- ~'N/A a the examinations required under subsection IWB, Table IWB-2500-1, Examination Category B-G-1 will be utilized.' 3 ASME Code Case N-426 which allows' limiting 'N/A l the examinations required under Subsection. IWB, Table IWB-2500-1, Examination Category B-G-2 will be utilized. 4 Eddy Current examination of steam . N/A generator U-tubes will be performed'- (The Description of in accordance with Braidwood, Technical Eddy Current Specification 3/4 4.5. [ASME Code-Examination of-Case N-401 which allows the use.of' Steam Generator digitally encoded eddy current data U-TubesJis in will be utilized. Section 2.5'of ByronfUnit'l ISI Program) 5 Supplemented volumetric examinations. 5~ are to be performed'on Class l2 and 3 high energy piping systems-(main steam,. main feedwater) outside.the containment where breaks have not been postulated. l 6 Augmented surface.and volumetric-examinations ,6' l-will be performed on the' reactor coolant-pump flywheels. I L __ _ _ __ _ 1 _ o
't. .PIga 2'of 2 1 . ATTACHMENT A> Braidwood Unit'1/ Byron Unit 1 ~ ISI Program Plan Piping Components ' Note Cross Reference _ List Braidwood Unit 1 Byron Unit-l' Note No. Note Description Note No.' N/A' '7 Augmented volumeric ex'aminations on the.. shell-to-transition core weld (Weld #6) of-the loop' steam' generator and the lower-to-upper intermediateicircumferential shellt weld (weld'#8c)'of the pressurizer will.be: performed per the requirements of NURBG-1002 Supplement No. 1; Section 5.2.4.4. dated September, 1986'(Braidwood SER).. 7 8 Augmented nondestructive testing is to bey performed on the high'and low pressure turbine discs and rotors.' Subsection IWB, Table IWB-2500-1, Examination 1: 9 Category B-A, Stem Bl.21 requires volumetric examination of the accessible portions of the. head circumferential welds in the-reactor vessel. Portions of theLlower disk-to-dutchman weld and the dutchman forging-to-closure head; dome weld are inaccessible. N/A 10 Augmented volumetric examinations of a random sampling of seven and one-half percent (Additional (7.5%) of1 Class 2 containment spray:(CS) welds commitment to be in a single train between the CS' pump and ~ included in the first weld beyond the isolation valve' inside the containment will be performed. . Byron Unit. 1 ISI-Program)~ a ~' 1 ~ d 1 3722K. ',f lh'+ 2 .c q. g(
\\ x paga 1 of 2 ' ATTACHMENT B' l Braidwood Unit 1/ Byron Unit 1 g ISI program plan ] piping Components j gelief Request Cross Reference List i Braidwood Unit 1 Byron Unit 1 Relief Request No. Relief Request Description Relief Request No. INR-1 Class 2 main steam welds are. inaccessible N/A: for surface examinations due to the location of saddle plates over the subject welds.7 l INR-2 Limited volumetric examinations'can NR-6 be performed on class.~1-Cast stainless steel elbow to pump / valve' welds. 1NR-3 A VT-3 examination will be performed on NR-9 one'(1) valve per design group.in each system performing a similar function when disassembly is required for maintenance purposes but not to exceed once per: inspection interval per design group.(Class 1 reactor coolant'(RC)' pressurizer, residual heat. removal (RHR), and safety. injection (SI) systems.) INR-4 VT-1 examinations will be performed in lieu 'NR-3 of volumetric examinations for the Class 1 pressurizer and steam generator nozzles because of inherent geometric constraints and clad inner surfaces 1NR-5 Limited volumetric examinations can be' NR-4 performed on Class 1 Case stainless steel elbow-to-steam generator nozzle welds. INR-6 Limited volumetric examinations can be NR-5 performed on Class l' case stainless steel' elbow / pump / valve to pipe welds 1NR-7 Limited volumetric examinations can be' N/A performed on Class 1 reactor: coolant' welds because of interfering conditions-INR-8 Surface examinations will be performed in N/A lieu ~of volumetric examinations on Class.2-1 reactor coolant and chemical and volume l control (CV) thin walled vessel welds '!l f
i i - Pagi 2 of 21 Braidwood Unit 1/ Byron Unit 1 ISI Program _ Plan Piping Components Relief Request Cross Reference List'. Braidwood Unit 1 Byron' Unit 1. Relief Request No. Relief Request Description Relief Request No. INR-9 Limited volumetric examinations will be ' NR-l~ performed on reactor pressure vessel circumferential welds due-to inaccessibility 1NR-10 A surface examination'will'be performed in NR-ll lieu of.a volumetric examination on the: shell circumferential weld of the CV letdown heat exchanger due~to interference of. flange bolting INR-ll A surface examination will be performed in NR-10 lieu of a volumetric examination on the.shell circumferential weld of the CV excess letdown. heat exchanger due to interference of branch connections. 1NR-12 VT-1 examinations will be performed.in' lieu-NR-12 of volumetric examinations on the Class 2 steam generator and RHR heat exchanger nozzles due to inherent geometric constraints. INR-13 A volumetric examination will not be N/AL performed on a Class 1 RC weld'because of the geometrical constraints of the nozzle-reducer 2 INR-14 A VT-3 examination will be performed on: .NR-8 one (1) of the RC pumps when dissassmebly is required for maintenance purposes but, not to exceed one inspection per interval' 1NR-15 A VT-1 examination will be' performed in NR-13 lieu of a surface examination in the centrifugal-charging and RHR pumps due to' the location of. structural supports INR-16 Limited volumetric examinations will be: N/A performed on Class 2 main steam and feedwater welds due to interfering conditions INR-17 Surface examinations.will be performed in" N/A' lieu of volumetric examinations'on RC and CV thin walled vessels f-3722K I ____m. -m._.. m
-pig 3;.1 of l'. .n ATTACHMENT C'
- Braidwood Unit l1/ Byron Unit 1'
.ISI. Program Plan Component Supports Relief Request Cross Reference" List-Braidwood Unit 1 Byron Unit'l. Note No. ' Note
Description:
Note No. 1 - Augaented auxiliary: N/A-Feedwater System-Component -' Suppor t.. Examinations ^) i i 3722K' {' g 'i ._____z_z____1___________li.,_
._ I e P2gsfl: of l = i ATTACHMENT D. Braidwood' Unit 1/ Byron Unit 1 ISI Program Plan. -{ Component Sup;Mrts .S. .) Belief Request Cross Reference List l f .1 J Byron Unitcl Braidwood Unit 1. Relief Request No. Relief Request No. Relief Request Description CR-1 Removal of Insulation for CR Examination of nonintegral and l integral.'etachments' Examination of-' adjacent component t . CR-3 l' CR-2 supports following. corrective. action' -l l t i 1 i 3722K-
.. J o. ?! PIga 1 of 1 -) J ATTACHMENT E' .) 1 i .i l Braidwood Unit:1/ Byron' Unit.1 ISI Program Plan Snubbers-Note Cross Reference List j
- s Braidwood Unit 1 Byron' Unit 1' Note No.
Note Description ' Note No. y 1 optional functional 1. '1 testing methods forl steam'- generator, snubbers. i l .y 4 i W 3722K I-i h .l l .-_2--_-___ I
i ' j l .i Pfg3 1 of;1l f ATTACHMENT F- ' i Braidwood Unit 1/ Byron Unit.1. ISI Program Plan Snubbers Relief Request Cross Reference List ~ d I j i Byron Unit 1 - Braidwood Unit 1 Relief Request No. Relief Request No. Relief Request Description 1 SR-1 Removal of: Insulation for^ SR-l' examination of.nonintegral. attachments SR-2 Examination.of' adjacent SR-2 Components following corrective' action u -l 1 l s i 3722K -1 t.
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