ML20149G257
| ML20149G257 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/14/1997 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20149G227 | List: |
| References | |
| PROC-970714, NUDOCS 9707230082 | |
| Download: ML20149G257 (119) | |
Text
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C) #5 lievitork Power
& Authority Jf1MES A. FITZPATRICK NUCLEAR POWER PLANT I.NSERVICE INSPECTION PROGRAM RELIEF REQUESTS for the 7
I 2nd TEN-YEAR INTERVAL CLOSEOUT T
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NEW YORK POWER AUTHORITY O- James A. FitzPatrick Nuclear Power Plant Docht No. 50-333 9707230002 970715 PDR ADOCK 05000333 G PDR
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SUMMARY
LISTING . . . . . . . . . . . . . . . . . . . . . . ..... ..'.'.... ...:.........3-ENCLOSURE
SUMMARY
. . . . . . . . . . .. . . . . . . . . . ... . . . ........ 4 l
INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .... ....... ......... 5 I
I CLAS S 1 COMPONENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ......... 6 Code Category B-A: Pressure Retaining Welds in Reactor Vessel . . . . . . . . . . 7 i l Item No. Bl.21 Circumferential . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 {
Item No. Bl.22 RPV Bottom Head Meridional Welds . . . . . . . . . . 10 Code Category B-D: l Full Penetration Welds of Nozzles in Vessels-Inspection ....... ....... .... . . ...... 13 ;
Item No. B3.90 ' Nozzle -to-Vessel Welds . . .. . ...... . . 13 i ' Code Category B-F: Pressure Retaining Dissimilar Metal Welds . . . . . . . . . 17 i L Item No: B5.130 Piping Nominal Pipe Size 2 4"(Dissimilar Metal ;
l Butt Welds) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17
- Code Category B-G-1: Pressure Retaining Bolting. Greater than 2 in.
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'( p) - . In Diameter . . . . . . . . . .. ... ......... ...... 21 Item No. B6.40 ' RPV Threads in Flange . . . . . . . . . . . . . . . . . . . . . . . 21 1 Item No: B6.190 Flange Surface, when connection disassembled .. . . . . 24 l SECTION S . . . . . . . . . . . ... . ...... .. ... . .. . ... .. 27 Code Category B-H: Integral Attachments for Vessels ... ........... 28 Item No. B8.10 RPV Integral Welded Attachments . ............28 Code Category B-J: I; essure Retaining Welds in Piping . . . . . . . . . . 31 L { Item No. B9.10 Nominal Pipe Size 2 4 in.
{It em No. B9.11 Circumferential Welds . . . . . . . .............. 31
{ Item No. B9.30 Branch Pipe Connection Welds
( { Item No. B9.31 Nominal Pipe Size 2 4" . . . .... ............... 35 L
- Code Category B-K-1: Integral Attachments for Piping, Pumps, and Valves . . 38 Item No. B10.10 Piping Integrady Welded Attachments . . . . . . . . . .. 38 Code Category B-L-2: Pump Casings . ... ..... ... ... ..... 43 Item No. B12.20 Internal Surfaces . . . . ... .... .......43 l, Code Category B-M-2: Valve Bodies > d" Nominal Pipe Size . . . . .. ...... 46 Item No. B12.50 Internal Surfaces ....... ... ........... .. 46 Code Category B-O: . Pressure Retaining Welds in Control Rod Housings . . . 49
!- Item No. B14.10: Welds in CRD Housing . . . . . . . . . . . . . . . . . . . . . 49 i
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CLASS 2 COMPONENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 .
- l. Code Category C-A: Pressure Ret:dning Welds in Pressure Vessels . . . . . . 53 '
- Item No. C1.10 Shell Circumferential Weld (RHR Heat Exchanger) . . . 53-l Item No. C1.30 Tubesheet-to-Shell Weld (RHR Heat l . Exchanger) ................................56-
- Code Category C-A
- Pressure Retaining Welds in Pressure Vessels .
- l. (SCRAM TANK) . . . .. . . . . . . . . . . . . . . . . . . . . . . . 59 l
Item No.' Cl.20 Head Welds . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . 5 9
! . Code Category C-B: Pressure Retaining Nozzle Welds in Vessels l (RHR Heat Exchanger) . . . . . . . . . . . . . . . . . . . . . . 62 ,
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Item No. C2.21 Nozzle-to-Shell (or Head) Weld . . . . . . . , . . . . . . . . . 62 1
L Code Category C-C: Integral Attachments for Vessels, Pip'ing, i l .
Pumps, and Valves . . . . . .. . . . . .. ..............65 .
L Item No. C3.10 Pressure Vessels (Integrally Welded Attachments) . . .- 65 ;
Item No. C3.20 Piping (Integrally Welded Attachments) . . . . . . . . . . . . 68 i Code Category C-F/CG: Pressure Retaining Welds in Piping, Pumps, and . 1 Valves in Sy>icins Whien C;rculate Reactor i Coolant . . . . . . . . . . .........................71 I l { Item No. C2.1 Piping (Circumferential Butt Welds) p { Item No. C2.3 . Piping (Branch Pipe-to-Pipe Weld Joints) . . . . . . . . . . . 71 AJ Item No. C2.1 Piping (Circumferential Butt Welds) . . . . . . . . . . . . . . . 71 l Code Category C-G: Pressure Retaining Welds in Piping, Pumps and Valves in Systems Which Circulate Other Than ,
Reactor Coolant .... ..... .... ........ .... 74- !
Item No. C2.3 Branch Pipe-to-Pipe Weld Joints 74 l
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- { Code Category C-H: All Pressure Retaining Components . . . . . . . . . . .. . . 7 7
{ Code Category D-A/ D-B
{ / D-C: Pressure Retaining Boundary . . . . . . . . . . . . . . . . . 77 i Item No(s): All_............................ . . . . . . 77 ASME Section XI IWE/IWL Containment Repair & Replacement Rule . . 78 l
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INTERVAL. DOC July 14,1997 Pagu of 80 I.
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SUMMARY
LISTING
.V Introduction Class 1 Components l
l- .1 Code Category B-A Pressure Retaining Welds in Reactor Vessel 2 Code Category B-D Full Penetration Welds of Nozzles in Vessels-Inspection -
l Program B 3 ~ Code Category B-F Pressure Retaining Dissimilar Metal Welds I 4 Code Category B-G-1 Pressure Retaining Bolting Greater than 2 in. In Diameter i
- 5 This section has been removed.
6 Code Category B-H ' Integral Attachments for Vessels i 7 Code Category B-J Pressure Retaining Welds in Piping l 8 Code Category B-K-1 Integral Attachments for Piping, Pumps, and Valves 9 Code Category B-L-2 Pump Casings 10 Code Category B-M-2 Valve Bodies >3" Nominal Pipe Size 11 Code Category B-O Pressure Retaining Welds in Control Rod Housings
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Class 2 Components '
12 Code Category C-A Pressure Retaining Welds in Pressure Vessels -
13 Code Category C-A Pressure Retaining Welds in Pressure Vessels (SCRAM TANK) 14 Code Category C-B Pressure Retaining Nozzle Welds in Vessels (RHR Heat
- Exchanger) 15 Code Category C-C Integral Attachments for Vessels, Piping, Pumps and Valves 16L Code Category C-F/C-G Pressure Retaining Welds in Piping, Pumps and Valves in Systems Which Circulate Reactor Coolant 17- Code Category C-G - Pressure Retaining Welds in Piping, Pumps and Valves in l Systems Which Circulate Other Than Reactor Coolant 18 } Code Category C-H All Pressure Retaining Components l 1 Code Category D-A/
l D-B/D-C Pressure Retaining Boundary 19 ' ASME Section XI IWE/IWL Containment Repair & Replacement Rule l
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ENCLOSURE
SUMMARY
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ENCLOSURE 1 5 Pages ..
ENCLOSURE 1A BLANK ENCLOSURE 2 1Page ENCLOSURE 3 7 Pages ENCLOSURE 4 BLANK ENCLOSURE 4A BLANK ENCLOSURE 5 THIS SECTION HAS BEEN REMOVED.
ENCLOSURE 6 5 Pages ENCLOSURE 7 1Page ENCLOSURE 7A 1Page ENCLOSURE 8 1 Page ENCLOSURE 8A BLANK ENCLOSURE 9 BLANK ENCLOSURE 10 BLANK ENCLOSURE 11 3 Pages ENCLOSURE 12 2 Pages ENCLOSURE 12A 1 Page ENCLOSURE 13 1Page ENCLOSURE 14 1 Page ENCLOSURE 15 1Page ENCLOSURE ISA 5 Pages ENCLOSURE 16 1Page ENCLOSURE 17 1 Page O
INTERVAL. DOC July 14,1997 Page4 of 80
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2 INTRODUCTION These ReliefRequests are being submitted as part of the close-out for the 2nd Ten-Year Interval whici. was performed in accordance with the ASME Section XI Code Edition 1980 up to and including Winter Addenda 1981. The requests for relief enclosed are' submitted pursuant to 10 CFR 50.55a (a)(3)(i),10 CFR 50.55a (a)(3)(ii),10 CFR 50.55a (g)(5)(iii) and/or in accordance with an approved ReliefRequest as stipulated in a Safety-Evaluation (SE) by the Office of Nuclear Reactor Regulation. The requests, along with their specific regulatory basis, are described in detail along with supporting technical discussion, documentation and referenced SE. Included in the Tables and Enclosures are welds examined during the 2nd Ten-Year Interval (7/85 - 9/97) whose inspectiom have mal met the code required coverage as defined in Code Case N-460, Alternative Examination Coverage for Class I and Class 2 Welds, along with sketches and/or drawings that depict the limiting condition. Also included are relief requests for pressure testing which are submitted for pressure tests that were not performed during the 2nd period of the 2nd Ten-Year Interval. There are two requests for relief for (1) ASME Code Category B-K-1, Attachment Welds, Item No. B10.10 and (2) ASME Code Category B-G-1, RPV Flange Ligaments, Item No. B6.40, that do not meet Program B,3rd period requirements and a resubmittal for relief which supersedes the initial request from the containment inspection rule ASME Section XI,1992 Edition and Addenda, Subsection IWE/IWL, Repair / Replacement activities.
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ENVAL. DOC July 14,1997 Page 6 of 80
l wj Code Category B-A: Pressure Retninine W Me in Remeter Veneet
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Item No. Bl.20 RPV Bottom Head Welds j Item No. Bl.21- Circumferential Item No. Bl.22 Meridional 1
Item No. Bl.21 Circumferential
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1 L Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full - !
! Code-required extent of volumetric examination for the following circumferential welds in the !
L Reactor Vessel Bottom Head listed in Table 1. This reliefis also submitted in accordance_with the ;
>NRC's review of 2nd Ten-Year Inservice Inspection Program and Requests for Relief, Dated October 27,1987, Docket No. 50-333, Relief Request (R14).
!~
Examination Requirements j ASME Section XI,1980 Edition through Winter 1981 Addenda, requires 100% volumetric
! examination of the weld plus %t of the adjacent base metal on each side of the weld crown.
L Basis for Relief Inspections of the Code-required accessible length of one weld was conducted on the RPV l
Bottom Head Circumferential Welds with limitations based on restricted access. Access to the 8
L area is limited to four 18" diameter manways 90 apart in the vessel support skirt. In adddition, I t
y the one hundred and thirty-seven (137) control rod drives and forty-three (43) in-core monitor instrumentation penetrations present extensive interference. The positioning and spacing 'of these components prevent an inspector from physically being able to reach them and allows access to e very limited portion the welds. There is also interference from the vesse.: support skirt which is welded to the bottom head on the lower portion of weld VC-BH-1-2. This combined with the curvature of the bottom head and the Bio-shield wall narrowing in this area precludes access.
Permanent vessel insulation and limited storage space for those insulation panels which require removal is extremely limited because of the small size of the manways.
Pronosed Alternative Fumminations L 1. No additional volumetnc exammations will be performed. The RPV welds have been ;
examined to the maximum extent practical from the outside surface.
- 2. A visual examination (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no evidence of leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integrity.
L RPV Pressure Retaining Welds addressed by this Relief Request are listed in Table 1. Drawings
[i highlighting component design, configuration ofinterferences, and limitations associated with the examinations are included in Enclosure 1.
INTERVAL. DOC July 14,1997 Page7 of so I- . _ _ _ _
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l Table 1 Code Category B-A / I m No.Bl.21 Component ID System Extent Examined Limitation - Remarks
- VC-BH-1-2 RPV Bottom Head i17" Restricted Access VC-BH 2-3 RPV Bottom Head None Inaccessible >
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INTERVAL E July 14,1997 Page 9 of 80
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I l l l lO ENCLOSURE 1 -Page 3 of 5 WELDS VC BH-1-2 & VC-BH-2-3 RPV Support Skirt Access Manways
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m L 3 I d) h ENCLOSURE 1 -Page 4 of 5
, ; , , , ; , , , , , WELDS VC-DH-12 & VC-BH-2-3 CRD Penetratiori .ayout
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Item No. Bl.22 RPV Bottom Head Meridional Welds C'
Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of volumetric examination for the following RPV Bottom Head Meridional 4
Welds listed in Table I A. This reliefis also submi:ted in accordance with the NRC's Safety Evaluation (SE) of the 2nd Ten-Year Inservice Inspection Program,' Dated October 27,1987, Docket No. 50-333 ReliefRequest (R14). In accordance with ReliefRequest (R14) of the 2nd Ten-Year Interval, the Authority is outlining the extent of examinations conducted on RPV 4
Pc:tni Head Meridional Welds. The extent of examination as required by the referencing code
- secien has been met in its entirety. Table 1 A details the extent of examinations conducted.
Pronosed Alternative Examinations
- 1. None
! 2. Inspection of the Code-required accessible length of one weld (Note 1) has been achieved 2
and fully satisfies the extent ofexamination in accordance with ASME Section XI,1980 Edition up to and including Winter Addenda 1981. Components addressed by this Relief
{ Request are in compliance with Relief Request (Rl4) and listed in Table I A.
t- ,
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lE Table 1A
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Code Catenory B-A / Item No. Bl.22 - Meridional Welds ConspensetID System Extent Total Ilmitation -
Reasarks .
Examined length VV-BH 1 A RPVBottom Head 36" (8) 69" Restricted Access Ref Dwg. 5.01-82D VV-BH 1B RPV Bottom Head - 34" (3) 69" Restricted Access Ref Dwg. 5.01-82D l VV-BH 1C RPV Bottom Head None 69" Restricted Access . Ref. Dwg. 5.01-82D VV BH-ID RPV Bottom Head None 69" Restricted Access Ref Dwg.5.01-82D q VV BH-lE RPV Bottom Head None 69" Restricted Access Ref Dwg. 5.01-82D VV BH lF . RPV Bottom Head None 69" Restricted Access Ref Dwg.5.01-82D VV-BH 1G RPV Bottom Head None 69" Restricted Access Ref Dwg. 5.01-82D VV BH lH RPV Bottom Head None 69" Restricted Access Ref. Dwg. 5.01-82D
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Code Category B-A / Item No. Bl.22 - Meridional Welds p~ Consponent ID Systems Estent. Total Limitation Remsarks l Examined length VV-BH-2A RPV Bottom Head None 54" Inaccessible Ref Dwg. 5.0182D VV BH-2B RPV Bottom Head None 54" Inaccessible Ref. Dwg. 5.01-82D VV-BH 2C RPV Bottom Head None 54" Inaccessible Ret Dwg. 5.0182D t
VV-BH-2D RPV Bottom Head None 54" Inaccessible Ref Dwg.5.0182D t
VV-BH-2E RPV Bottom Head None 54" Inaccessible Ref. Dwg. 5.01-82D VV-BH-2F - RPV Bottom Head None 54" Inaccessible Ret Dwg. 5.01-82D l
NOTE:
(1) Cumulative total for the extent of examination performed during the 2nd Ten-Year Interval on RPV Bottom Head Mendional Welds is 70" which exceeds the total length (69") of one Meridional weld.
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CodeCateeorv B-D: Full Penetration Welds of Nozzles in Vessels-Insnection l n Item No. B3.90 Nozzle -to-Vessel Welds
(]
Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of volumetric examination for the following Full Penetration RPV Nozzle
~~
Welds listed in Table 2.
l
! Funmination Reauirements l ASME Section XI,1980 Edition through Winter 1981 Addenda, requires 100% volumetric l
examination of the weld plus % the wall thickness of adjacent base metal on each side of the weld. l Basis for Relief Complete inspection of the Code-required volume is not possible based on restricted access l caused by interference from permanent structures such as non-removable vessel insulation, instrumentation lines / penetrations and other nozzles. Detailed measurements of these interferences were taken for the nozzles, which is typical for a given configuration (i.e.: N1(s), N2 (s), N4 (s), and N5(s)). The examination data detailing restricted access associated with the N-9 nozzle does not have the necessary detail to calculate the exact coverage achieved. In this case an l
estimate of examination coverage is used, based on the examination data sketch generated during i the inspection.
Pyoposed Alternative Examinations
- 1. No additional volumetric examinations will be performed. The RPV nozzle welds have been examined to the maximum extent practical from the outside surface.
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integrity.
RPV Nozzle Welds addressed by this Relief Request are listed in Table 2. Drawings, sketches and the calculated volume of coverage in Enclosure 2 illustrate the restricted conditions encountered that limit examination coverage.
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Table 2 Code Category B-D / Item No. B3.90 Cesaponest Systeam Extent Umitation --
Remarkr ID Examined N1A RPV Recire. Noz. 35 50% Configuration / Typical Configuration for N-1(s)
Insulation N 1B RPV Recire. Noz. 35 - 50 % Configuration / "
Insulation N-2A RPV Recire. Noz. 50 - 65 % Configuration / Typical Configuration for N-2(s)
Insulation N-2B RPV Recirc. Noz. 50 -65 % Configuration / "
Insulation N 2C RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N-2D RPV Recire. Noz. 50 - 65 % Configui.;t:on/ "
Insulation N-2E RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation b
'd N 2F RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N-2G RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N 2H RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N 2J RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N-2K RPV Recire. Noz. 50 - 65 % Configuration / "
Insulation N-3A MS Noz. 50 - 60 % Configuration Typical Configuration for N 3(s)
N 3B MS Noz. 50 -60 % Configuration -
N 3C MS Noz. 50 - 60 % Configuration "
N-3D MS Noz. 50 - 60 % Configuration "
N-4A RPV FW Noz. 60 -70 % Configuration / Typical Configuration for N-4(s)
Insulation i
N-4B RPV FW Noz. 60 - 70 % Configuration / "
/'% Insulation INTERVAL. DOC July 14.1997 Page 14 of' 80
_ - .. . .. _~..- -. . - .- - ~-. ....~. . -. _.-.. . - . . . - . - . . - . _ . ~ . - . . _ _ .
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! Code Category B-D / Item No. B3.90 l
~
N-4C RPV FW Naz. 60 70% Configuration / "
Insulation '
a i N 4D . RPV FW Noz. 60 - 70 % Configuration / "
Insulation N-5A . RPV CS Noz. 70 % Configuration / "
Insulation i
3 N-8A JPI Noz. 60 -70% Configuration / Typical Configuration for N8(s)~ ,
Insulation N-8B ~ JPI Noz. 60470% Configuration /
Insulation N-SB RPV CS Noz. 70 % Configuration / "
insulation i
VN TH-A RPV Head Noz. 60 70% Configuration
- VN-TH-B RPVHead Noz 60 -70 % Configuration
l' insulation NOTE:
- [ (1) Examination data lacks sumcient surface measures to further qualify the volume examined.
i O i INTERVAL. DOC July 14,1997 Page 15 of 80 l
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Nozzle in Shell or Head Code Category B-D l Code Required Coversee .. .
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A-B-C-D-E-F-G-H-l Coverage Achieved for a Specific Weld or Component is Designated in Table 2 - Extent Examined l
i FIGURE 1 i
ENCLOSURE 2 -Page 1 of1 W - -,
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l Code Cateeorv B-F: Pressure Retalning Dissimilar Metal-Welds - -
i Item No. B5.130 Piping Nominal Pipe Size 2 4"(Dissimilar Metal Butt Welds)
Item No: B5.130 Piping Nominal Pipe Size 2 4"(Dissimilar Metal Butt Welds)
Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of volumetric examination for the following Pressure Retaining Dissimilar Metal Welds listed in Table 3.
Eummination Requirements ASME Section XI,1980 Edition through Winter 1981 Addenda, requires the lower %t of the weld be examined volumetrically up to and including adjacent base metal %" from the weld toe on either side of the weld.
Basis for Relief Complete inspection of the Code-required volume is not possible based cn restricted access due to the component's design. These welds represent the tie in of the RHR system to the Recirculation System on Loops A and B. The configuration of these welds are Valve-to-Valve, and Valve-to-Tee. The configuration of Welds 24-10-143,24-10-142,24-10-131, and 24-10-130 are not conducive to conventional ultrasonic examination techniques. This is attributed to I dramatic thickness transitions on the outside and inside surfaces. On-going modifications to equipment and ultrasonic techniques currently being used are improving the testing parameters i
presently utilized to examine these components. Inspections of these components are based on calibration mock-up blocks of the same configuration and materials as the welds. These l calibration mock-up blocks are designed with side drilled (SDH), end drilled (EDH) calibration holes along with numerous ID notches located within the heat effective zones, base material, buttered material and the weld. Supplemental liquid penetrant examinations were performed on these components which exceeds those required by Code Category B-F, Table 2500-1. An L evaluation of testing results utilizing current ultrasonic technology has deemed these exams as L best effort. The inspections conducted on Welds ::4-10-132,24-10-144 both (Elbow-to-Valve) l and 10-14-481 are considered limited examinations employing industry acceptable inspection techniques. Weld 24-10-144 does not have a Umited exam notation included on the inspection data but is clearly a one-sided exam and therefore is being submitted for relief.
l INTERVAL. DOC July 14.1997 Page 17 or 80 l
h-Pronosed Ahernative Fumminations
' l. No additional volumetric examinations will be performed on these welds. The components listed in this relief request have been examined to the maximum extent practical.
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of i component integrity.
l Drawings and sketches that illustrate the restricted conditions encountered which limit examination coverage are included in Enclosure 3.
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Table 3 I Code Category B-F / Item No.B5.130
-., l Camponent System " Estent Umitation Remarks ID Examined .
24 10-142(3) RIR Best Effort OD Surface Contour Tee-to-Valve G)
Est. 25 - 35%
24-10-143(3) RHR Best Efrort OD Surface Contour Valve-to-Valve C)
Est, 25 - 35% ;
24 10-144 (3) RHR 70 - 80 % OD Surface Contour Valve-to-Elbow O' 24-10-130(') RHR Best Effort OD Surface Contour Tec-to-Valve G)
Est. 25 - 35% :
24 10-131(') RHR Best Effort OD Surface Contour Valve-to-Valve G)
Est. 25 - 35% l 1
24-10-132(3) RHR 70 80% OD Surface Contour Valve-to-Elbow ")
l 10 14-481(') Core Spray 65-75% OD Surface Contour Pipe-to-Valve Pup Piece Extension NOTES:
(1) All welds identified by this note are within the IGSCC Inspection Progrsm (2) Sketches depicting OD profiles for welds 24 10-130,24-10-131 and 24 10-132 are typical for 24-10-142,24 10-143 and 24-10 144.
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Calibration Block Drawing for 4-
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o --[ WN ENCLOSURE 3 - Page 7 of 7 jy Weld # 1014-481 Coverage Calc. & Profile
s Cada Catcge B-G-It Pressure Retninine Boltine. Greater than 2 in. In Diameter Item No. B630 Threads in Flange a Item No. B6.190 Flange Surface, when connection disassembled Itua No. B6.40 RPV Threads in Flange
; Examination Requirements i
The Code requirement for examination of RPV Threads in Flange is 100% volumetric inspection each Interval when the connections are disassembled. - ReliefRequest The Authority is requesting relief from the twenty-two (22) RPV Threads in Flange examinations i not examined during the 2nd Ten-Year Interval accordance with the provisions of 10 CFR 50.55a j (a)(3)(ii), 1 Basis for Relief I During the closcout review of JAF's 2nd Ten-Year Inservice Inspection Interval for Code
' Category B-G-1, Item No. B6.40, RPV Threads in Flange, a total of thirty (30) examinations were performed out of a total population of fifty-two (52). The inspection requirement to examine
- 100% of the RPV Threads in Flange was not met in its entirety due to an administrative oversight l '
and a Code interpretational discrepancy. 1 {~ ' Industry experience has not identified a degradation mechanism or failure associated with the RPV Threads in Flange, The Authority does not consider taking the unit offline and removing the RPV Head for the sole purpose of examining the twenty-two (22) RPV Threads in Flange as . providing an :ncrease in the level of quality and safety already achieved by the examinations performed. l Pronosed Alternative Eummination
-1. The Authority is requesting relief from the twenty-two (22) RPV Threads in Flange examinations for the 2nd Ten-Year Interval and is committing to examine these during the j- 3rd Interval,1st period, first refuel outage (ROl3). The twenty-two RPV Threads in Flange examinations committed to based on this relief will be performed in addition to the
= 3rd Ten-Year ISI Inspections requirements.
- 2. . A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of
, component integrity. NIERVALDOC July 14,1997 Page 21 or 80 =
d I i Table 4 l
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Code Category B-G-1/ Item No B6.40 Cosmponent Systems Description Examined Limitation Relief Requested ; ID
- 1. thru - 15 RPV Threadsin Flange Yes None No 16 - thru- 37 RPV Threadsin Flange No None Yes 38.thru 52 RPV Threads in Flange Yes None No i
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I i a i I l l l INTERVALDOC July 14,1997 Page 22 of 80
i O F ENCLOSURE 4 lO THIS SECTION IS INTENTIONALLY LEFT BLANK i I 1-1 1 i i i i O J 4 i INTERVAL. DOC July 14,1997 Page 23 of 80 b
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i 4 Item No: B6.190 Flange Surface, when connection disassembled Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(ii) from the full Code-required extent of examination for the Flange Surface of components listed in Table 4A. Fummination Reauirements
~
This request for reliefis being submitted in accordance with the NRC's Safety Evaluation (SE) of the 2nd Ten-Year Inservice Inspection Program, Dated October 27,1987, Docket No. 50-333 Relief Request (R5B). Relief Request 5 (R5B) requires inspection of these components when disassembled for maintenance and stipulates relief from examination of specific components not
- disassembled will be requested at the end of the interval.
I Basis for Relief Examination Components addressed by this Relief Request are listed in Table 4A. The recirculation pump flange surfaces are only accessible when the pumps are disassembled. These pumps were not disassembled during the 2nd Ten-Year Interval. A visual inspection (VT-2), pressure test is ! conducted on these components every refuel outage in accordance with IWA-5000 and IWB-t 5000. l l Proposed Alternative
- 1. None l 2. The requirements for examination on these components met the approved Relief Request (R5B) for the 2nd Ten -Year ISI Inspection Interval in its entirety. Components addressed in this request for relief are listed in Table 4 A.
l l l l l O . U l NTERVAL. DOC July 14,1997 Page 24 of 80
I o; C1 l V Table 4A i i l _ ,,, m. _fode, Category B-G-1/ Item No B6.190 ) Component System Pump Disassembled Examined Limitatioa Relier : ID Type ' Request 02-2P-1 A Recire. Centrifugal No No Not RSB : Accessible ; 02 2P-1B Recire. Centrifugal No No Not RSB Accessible i O l I i I l i a 4 4 i l t i INTERVALDOC July 14,1997 Page25 of 80 4 8
n O l i 1 ' i i l ! l ENCLOSURE 4A lO 1 4 ! THIS SECTION IS INTENTIONALLY LEFT BLANK l l O INTERVAL. DOC July 14,1997 Page 26 of 80
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l INTERVAL. DOC < July 14, i997 Page 27 of 80
. _ _ _ . ~ _ . . _ . _ _ _ , . - - . _ . . . . . _ .. _ i.~. - - _ _ _ . - .
m Code Oweoorv B-H: Integral Attachments for Vessels i i (mv) Item No.'B8.10 RPV Integral Welded Attachments Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of examination for RPV Integral Welded Attachments listed in Table 6. ; l Examination Reouisments I All RPV Integral Welded Attachments require a 100% volumetric or surface examination once per interval. 1 Basis for Relief I Complete inspection of the Code-required volume is not possiMe based on restricted access caused by design. Examination coverage of VC-SKC (vessel skirt weld) includes 100% of the OD surface being examined using the MT method and a supplemental examination using remote visual equipment (VT-1) was performed on 100% of the inside surface. Access to the inside surface of I weld VC SKC is restricted due to the component's design. Drawings of vessel skirt weld VC-
. SKC are in Enclosure 6 which highlight the inspection surfaces and restricted access caused by design. Examinatbn coverage of Stabilizer-1,2,3, and 4 included 35% of these welds being inspected by MT and the remaining 65% being inspected by VT-1. Components addressed by this Relief Request are listed in Table 6. Drawings and sketches that illustrate the restricted conditions encountered that limit access to th Vessel krt Weld and Stabilizer Brackets are included in (O ,/ Endosr te 6.
Pronosed Alternative
- 1. No additional volumetric and/or surface examinations will be performed on these welds. I 3
^
The components listed in this relief request have been examined to the maximum extent I practical. l
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integrity.
I I I
%/
f INTERVAL. DOC Juh 14,1997 Page 28 of 80
M Table 6 O- Code CatepogB-H / Item No.B8.10 - Cesaposent System Estent IJmitatign Remarks , ID Examined '
~~
VC SKC RPV 50 % Configuration (0 ' Stabilizer 1 RPV 34 % Configuration Ref. Encksure 6 Stabilizer-2 EPV 34 % . Configuration Ref. Enclosure 6 Stabilizer 3 RPV 34 % Configuration Ref. Enclosure 6 . Stabilizer-4 RPV 34 % Configuration Ref. Enclosure 6 NOTE: (1) - 100% of outside surface examined using MT only and 100% ofinside surface examined using VT only. Reference drewings in Enclosure 6 detailing examination coverage. { s 1 l e 4 i INTERVAL. DOC July 14,1997 Page 29 of g0
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l l Rcythosn Engineers & Constructors 1 ov oarE 'I ddE- Y[- OYh SHEET k OF l fr CHKO.eY OATE OF$NO. /OO N ,_2 'Ib k, CLIENT PROJECT . FiTIP4Wic.K sueJECT 3 A81LI2Bf 3RACVMf Atta4ttLY _ 1 l 1e [EACTog VGSSEL. WiitL l g 10* 5 W37ABEU2Kt StActinl'-To. Vassal WsLo 2 . , m m il J . (; - r .: - ama,- < :
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(2) AGeattsdATY: McA 12 Accedttista PMoM Ma74L 24M MDPsK M7sp Af'/36?A3) /0 P*7* OP .TJ24M7)M/ hitaDr 7b fg QtMgeno f%g .TJfg17$V o Q OF 80& Coo}h WOBB . (8) Tsmeawe Dww : "IlVM-d'ol-23 D (MM*/M-oaA"o*AW-o3)
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I Code Cateenry B-J: Pressure Retaining Welds in Pining l i O,. Item No. B9.10 Nominal Pipe Size 2 4 in. V Item No. B9.11 Circumferential Welds l Item No. B9.30 Branch Pipe Connection Welds l~ Item No. B9.31 Nominal Pipe Size 2 4" I Item No. B9.10 Nominal Pipe Size 2 4 in. Item No. B9.11 Circumferential Welds
- Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full l Code-required extent of surface and/or volumetric examination for Circumferential Welds listed in Table 7.
Examination Reauirement ASME Section XI,1980 Edition through Winter 1981 Addenda, requires the lower %t of the weld examined volumetrically up to and including adjacent base metal %" from the weld toe on either side of the weld. Surface examinations requires the weld inspection and includes %" on either side of the weld toe. Basis for Relief A C Complete inspection of the Code-required volume for components listed in Table 7 is not possible based on the restricted access caused by component design, support structures, and/or other interferences. Examinations performed on the majority of these components have detailed measurements oflimitations, restrictions and interferences, along with the estimated computed volume ofinspection coverage. Some examinations performed during the beginning of the inspection interval do not have the detailed measurements necessary to estimate the percentage of exam coverage. Most of the cases in which this occurs, the examiner notes a one-sided exam was performed and others state limited exam. When a one-sided exam is recorded or a limited exam is confirmed as a one-side exam (no other restrictions) through drawing verification, a 50% exam coverage credit is taken. If a limited or restricted exam is noted but not enough information exists to derive a percentage of coverage, it will be so noted. Proposed Alternative
- 1. No additional volumetric and/or surface examinations will be performed on these welds.
The components listed in this relief request have been examined to the maximum extent practical.
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing j conducted on these components every refuel outage (with no leakage detected) in lf%J )
l accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integnty. INTERVALDOC July 14.1997 Page 31 of 80
l 3 l A typical configuration drawing wl. ch illustrates restricted is in Enclosure. Table 7 O) ( - Code Category B-J / Item No. B9.11 Component System Extent IJmitation Remarks' ID Exambed 12-02 2 26
- Recire. 50% m OD Surface Contour Pipe-to-Reducer 22-02-2 28
- Recire. 50% m OD Surface Contour Cross-to-Header (2) 22-02-2-29 Recire. 50% ") OD Surface Contour Cross-to-Header 28-02 2-31
- Recire. 50% ") OD Surface Contour Pipe-to-Tee 28-02 2 34
- Recire. 50% ") OD Surface Contour Elbow-to-Valve 28-02 2-35 'N Recire. 50% m OD Surface Contour Pipe-to-Valve (2) 28-02-2-37 Recire. 50% m OD Surface Contour Pump-to-Pipe 28-02-2-50
- Recirc. 60-70% Whip Restraint Elbow-to-Pipe 28-02-2-54
- Recire. 50% ") OD Surface Contour Valve-to-Pipe 28-02 2 57
- Recire. 50% m OD Surface Contour Elbow-to-Pump 12-02 2-84
- Recire. 50% m OD Surface Contour Pipe-to-Reducer l 22-02-2-86 m Recire. 63 % OD Surface Contour Header-to-Cross 22-02-2-87 m Recire. 63 % OD Surface Contour Header-to-Cross 28-02-2 89
- Recire. 50% m OD Surface Contour Pipe-to-Tee 28-02-2-104 m Recire. 50% m OD Surface Contour Pipe-to-Valve 28-02 2-105
- Recire. 50% m OD Surface Contour Pump-to-Pipe 28-02-2-109
- Recire. 50% m OD Surface Contour Pipe-to-Tee 28-02 2 110
- Recire. 50% m OD Surface Contour Tee-to-Pipe 28-02 2-112
- Recire. 8% OD Surface Contour Valve-to-Pipe N-8A-SE-1
- JPI 50% m OD Surface Contour Reducer to-Reducer l JPl 62 % OD Surface Contour Reducer to-Reducer g-8B-SE-1 g-8A-SE-3 JPI 68% Code Plate Pipe-to-Cap l N-8B-SE-3
- JPI 68% Code Plate Pipe-to-Cap 4-02-2-117
- JPI 63 % OD Surface Contour SE-to-Reducer
,, 6-12-901 1 RWCU m 70% m OD Surface Contour Pipe Valve INTERVAL. DOC July 14.1997 Page 32 of 80 l
l
w Table 7
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[d 6-12-141B 1 RWCU 0) s Code Category B-J / Itern No, B9.11 50% ") v-OD Surface C6ntour Vaive-to-Pipe 20-10-120 1 RIIR U) 50 % U) OD Surface Contour Pipe-to-Tec aC 24-10-149 R11R 0) Est. 80% Welded Support Pipe-to-Pipe Component System Extent Limitation Remarks ID Examined 10-14-471 CS M) Est. 75% OD Surface Contour Pipe-to-SE 10-14-492 G) CS 6) Est. 80% OD Surface Contour Pipe-to-SE "I 10-14-493 CS M) Est. 80% U) Drain Line Elbow-to-Elbow 10-23-677 HPCI
- Est. 70-80% Socket Weld Conn Elbow-to-Pipe 24-29-543A MS
- 70 - 80 % Instr. line/ OD Elbow-to-Pipe Surface Contour 24-29-557 MS 0) Est. 65 - 75% Saddle Weld Pipe-to-Pipe Obstmetion 24 29 572 MS ") 75% Welded Support Limitation applies to Surf.
and Vol. Exams
,m
(') 24-29-605 MS ") 75% Welded Support Limitation applies to Surf. and Vol. Exams t 12-34-402 m FW ") 50 % 0) Air Duct Obstruction Pipe-to-Pipe _ NOTES: (1) When a one-sided exam is recorded or a limited exam is confirmed as a one-sided exam,(no other restrictions), through drawing verification a 50% exam coverage credit is taken. (2) All welds identified by this note are within the IGSCO Inspection Program (3) The limited examination coverage of this weld only applies to the surface inspection full examination coverage was achieved by the volumetric method. ' (4) The total weld population for the Feedwater System under this item number is 76 welds. The total number requiring volumetric and surface examinations is 25% - 19 welds. The total number of volumetric and surface examinations performed on welds within this item number for the 2nd Ten-Year Interval is 34 - 45%. (5) The total weld population for the Main Steam System under this item number is 109 welds. The total number requiring volumetric and surface examinations is 25% - 28 welds. The total number of volumetric examinations performed on welds within this item t. umber for the 2nd Ten-Year Interval is 32 - 29%. (6) The total weld population for the Core Spray System under this item number is $1 welds. The total number requiring volumetQ and surface examinations is 25% - 13 welds. The total number of volumetric and surface examinations performed on welds within this item number for the 2nd Ten-Year Interval is 17 - 33%. (7) Total weld population for the RHR System under this item number is 47 welds. The total number requiring volumetric and surface examinations is 25% - 12 wet 's. The total number of solumetric and surface examinations performed on welds within this item number for the 2nd Ten-Year Interval is 12 - 25%. l (8) Total weld population for the IIPCI System under this item number is 26 welds. The total number requiring volumetric and surface examinations is 25% - 7 welds. The total number of volumetric and surface examinations performed on welds within this item number for the 2nd Ten-Year Interval is I i - 42%. (9) Total weld population for the RWCU System under this item number is 32 welds. The total number requiring volumetric and surface examinations is 25% - 8 welds. The total number of volumetric and surface examinations performed on welds O within this item number is 12 - 37%. (/ INTERVAL. DOC July 14,1997 Page 33 of 80 f
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4 i l ENCLOSURE 7 O . I i i O INTERVAL. DOC July 14,1997 Page 34 of 80
e Similar and Dissimilar Metal Welds in Components and Piping Code Category B-F & B-J 4 NPS Greater Than 4 in. .. , Code Regired Volume (CR97 4 cwn saa m' , dofle - of /%. b.Fo ttaa1
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Item No. B9.30 Branch Pipe Connection Welds Item No. B9.31 Nominal Pipe Size > 4" Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of volumetric examination for Branch Pipe Connection Welds (Nominal Pipe Size > 4"). .- Framination Reauirements ASME Section XI,1980 Edition through Winter 1981 Addenda, requires the lower %t of the ! weld examined volumetrically up to and including adja::ent base metal %" from the weld toe on either side of the weld. Basis for Relier ; l Complete inspection of the Code-required volume for components listed in Table 7A is not possible based on restricted access caused by their design. All components in this request for 1 relief are within the IGSCC Inspection Program and have been inspected in accordance with i Generic Letter 88-01 by EPRI qualified examiners. Inspection techniques that are qualified ! through EPRI or PDI for the detection ofIGSCC is limited to same side examinations. l Techniques have not been developed that can qualify IGSCC detection from the far side of the , weld. Components with one-sided access, whether due to configuration and/or OD surface contour, fall into this category. Some examinations performed on these components occurred []s during the beginning of the inspection interval and do nat have the detailed measurements necessary to accurately calculate the percentage of exam coverage. When a one-sided exam is l recorded or a limited exam is confirmed as a one-sided exam (no other restrictions) through examination data and drawing verification, a 50% exam coverage credit will be taken. If a limited or restricted exam is noted but not enough information exists to derive a percentage of coverage, it will be so noted. ! Proposed Alternative l
- 1. No additional volumetric and/or surface examinations will be performed on these welds.
l The components listed in this reliefrequest have been examined to the maximum extent ' practical.
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of '
component integrity. Drawings and sketches which illustrate the restricted conditions encountered, (in some cases typical for a given configuration), that limit examination coverage are in Enclosure 7A. l INTERVAL. DOC July 14,1997 Page 35 of 80 i
Table 7A 1 Code Category B-J / Item No. B9.31 _ Component System , Extent Limitation Remarks ID Examined (2) 12-02 2-4 , Recire. 79% U) OD Surface Con ur . dwph-to-Pipe , 22-0225 G) Recire. 50% (') Configuration Saddle Weld 12-02 2 10 G) Recire. 50% (') OD Surface Contour Swptt-to-Pape 22-02 2-11 ") Recire. 50 % 03 Configuration Saddle Weld 22-02-2-16 G) Recire. 50 % "I Configuration Saddle Weld l 12-02-2 20 0) Recire. 50 % U) OD Surface Contour Swpit to Pipe 28-02 2 55 ") Recire. 50% ") One-sided Exam Branch Connection 1 12-02-2-61 U) Recire. 50% U) One-sided Exam Branch Connection 22-02-2-62 U) Recire. 50 % U) Configuration Saddle Weld 0)
]
12-02-2-67 ") Recire. 50% (') OD Surface Contour Swpit-to-Pipe G) 12-02-2 72 Recire. 50% ") OD Surface Contour Swpit-to-Pipe 12-02 2 78 0) Recire. 50 % U) OD Surface Contour - Swpit-to-Pipe 28-02 2-114 0) Recire. 50 % U) One-sided Exam Branch Connection ") NOTES: 4 (1) When a one-sided exam is recorded or a limited exam is confirmed as a one-sided exam, (no other restrictions), through I drawing verification, a 50% exam coverage credit is taken. (2) All welds identified by this note are within the IOSCC Inspection Program (3) Weld 22 02-242 has a saddle weld configuration that is typical of 22 02-2 5. (4) Weld 28 02-2114 has a branch connection configuration that is typical of Weld 28 02-2-55. (5) Swptt - Sweep olet l 1 l l I I I l 4 l INTERVAL. DOC July 14,1997 Page 36 of 80
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l l t 4 4 ENCLOSURE 7A O L a
- O INTERVALDOC July 14,1997 Page 37 of 80
~. yj Pine Branch Connection
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Code Category B-J i i NPS Greater Than 4 in. .. . . ; Code Required Volume (CRV)
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d Code Cateeorv B-K-It Intevral Attachments for Pinine. Pumns. and Valves ; O Item No. B10.10 Piping Integrally Welded Attachments V j Reliefis requested pursuant to the provisions of 10 CFR 50.55a (a)(3)(I), and 10 CFR 50.55a ' (a)(3)(ii) from the ASME Boiler and Pressure Vessel Code surface or volumetric examination requirements ofeight (8) integrally welded attachments listed in Table 8, and incomplete examination of the Code-required surfaces for components listed in Table 8A. Frarninstion Reauirements ASME Code Section XI,1980 Edition through Winter 1981 Addenda requires examinations to . include the welded attachment of piping required to be examined by Examination Category B-J, and includes essentially 100% of the weld length, for those attachments whose base material i design thickness is 5/8 in. and greater. j 1 Basin For Relief Pursuant to 10 CFR 50.55a (a)(3)(I) During the review of the JAF 2nd Ten-Year Inservice examinations for Category B-K-1 interval closcout, eight (8) integrally welded piping attachments were not examined out of a total required i population of fifly-four (54). l Reactor Recirculation System - Seventeen (17) integrally welded attachments were examined, l
- (accepted by examination for continued service), out of a total population of twenty (20), which J provides an overall system percentage completion of 85% for Examination Category B-K-1.
Main Steam System - Twenty-five (25) integrally welded attachments were examined, (accepted l by examination for continued service), out of a total population of forty-two (42), which provides an overall system percentage completion of 60% for Examination Category B-K-1. Overall Status for the Interval - Forty-seven (47) nonexempt integrally welded piping attachments i out of a total nonexempt population of fifly-four (54) Category B-K-1 components in all of the Class 1 Systems were examined during JAF 2nd Inservice Inspection Interval, for a total percentage examined of 87%. All other Class 1 systems meet ASME Section XI 1980 Edition, Winter 81 Addenda criteria for Program B requirements in it's entirety. ) 1 The ASME B&PVC recognized that the extent ofexamination for B-K-1 integrally welded j attachments by earlier code editions was impractical. To address this issue ASME issued Code Case N-509, which is pending approval by USNRC through Reg. Guide 1.147 Rev.12. If Code Case N-509 was applied to the two (2) systems above the percentages examined would far exceeds the 10% examination requirements of the Code Case. The extent of examinations performed, coupled with the system pressure tests, will provide an acceptable level of quality and
- safety.
Proposed Alternative Examinations A None L] I INTERVAL. DOC July 14.1997 Page 38 cf 80
! "' l i Beals for Relief of Partini Ermminations Pursuant to 10 CFR 50.55afal(3)(ii} ! l D l l () Components addressed within this relief are welded attachments that have limitations and j restrictions which impede inspection coverage. Drawings and sketches which illustrate the l restricted conditions encountered that limit examination coverage are in Enclosure 8. Pronused Alternative l
- 1. No additional volumetric and/or surface examinations will be performed on these welds. ,
The components listed in Table 8A of this relief request have been examined to the ! maximum extent practical. l
- 2. A visual inspection (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integrity.
l 0 I l l i l l l l l l l INTERVAL. DOC July 14,1997 Pege 39 of 80
4' Tcble 8 Code Category B-K 1/ Item No. Blo.10 Coasponent ID System Description 24 29 527A 24.0" M S System Integrally Welded Attachment 24 29-539B 24.0" M S System Integrally Welded Attachment l 24 29-572A 24.0" M S System Integrally Welded Attachment i 24 29 585B 24.0" M S System Integrally Welded Attachment 24 29 593A 24.0" M S System Integrally Welded Attachment 28-02 2 51 A 28.0" Reactor Recire. System Integrally Welded Attachment 28-02 2 31A 28.0" Reactor Recire. System Integrally Welded Attachment j 28-02 2-89C 28.0" Reactor Recire. System Integrally Welded Attachment Table 8A
, Code Category B-K-1/ B10.10 Component System Extent L, imitation Remarks !
ID Examined Q V 28-02-2 3iC Recire. 60-70 % Support obstruction See Enclosure 8 28-02-2 110E Recire. 60 -70% Support Obstmetion See Enclosure 8 24 29-605B Main Steam 50-60 % Circ. Weld See Enclosure 8 Interference 24-29-618A Main Steam 50 % Restricted Access See Enclosure 8 l - O) INTERVALDOC July I4.1997 Page 40 of 80
'?
. O 4 t t ENCLOSURE 8-O ) I l l l 1 l l l
)
1 O l 1 INTERVALDOC July 14,1997 page al or go
InteFral Attachment O . Code Category B-K-1 Code Reauired Coverage 4 4 5 i B n v O & , _, s
--^r %. sa. + + hsa. 4--
Sur. nm / Yt. f,. ku A~A_ E C C S"' G^* l . A p ; Asp c-p } Coverage Achieved for a Specific Weld or Component is Designated in Table 8 - Extent Examined FIGURE l' t
'V ENCLOSURE 8-Page 1 of1 i
. . ~ . . _ = . . . . - - . . . . . . . . - . . . . - . - . - - . - - . . . . - . - . . ~ . . - - . . . . - . . - . ~ . . - - - . - . . ~ . . - . ~ . . . . . ~ - . . . ~ . . . . . . . . . . -
l _. l O 1 . l l 1 1 l l-l' l ENCLOSURE 8A O rais sacrion is 1xrsurioxitty tsgr stixx l l O INTERVALDOC July 14,1997 Page 42 of 80
l 1 Code Cateenry B-L-2: Pumn Canines Item No. B12.20 Internal Surfaces .
- :O l Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(ii) from the full i Code-required extent of visual examination for Pump Casing Internals for components listed in f
Table 9. .. .. . l l Examination Requirements
~
This request for reliefis being submitted in accordance with NRC Safety Evaluation'(SE) of the J 2nd Ten-Year Inservice Inspection Program, Dated October 27,~ 1987, Docket No. 50-333 . I
+
approved Relief Request 5 (RSB). Relief Request 5 (R5B) requires visual (VT-3) inspection of ' internal surfaces of pump casings once per interval when these components are disassembled for l maintenance and stipulates that relief from examination of specific components not disassembled l will be submitted at the end of the interval. ' Basis for Relief Examination ! i The recirculation pump internal surfaces are only accessible when the pumps are disassembled. These pumps were not disassembled during the 2nd Ten-Year Interval. A visual inspection (VT-2), pressure test is conducted on these components every refuel outage in accordance with IWA-5000 and IWB-5000. This request for reliefis being submitted in accordance with JAF's 2nd Ten-Year Interval Inservice Inspection Program approved Relief Request 5 (R5B) . Components addressed by this Relief Request are listed in Table 9. Pronosed Alternative
- 1. None
- 2. The requirements for examination on these components met the approved Relief Request (R5B) for the 2nd Ten-Year ISI Inspection Interval in its entirety. Components addressed in this request for relief are listed in Table 9.
l l I l l O INTERVAL. DOC July 14,1997 Page43 of 80
Table 9 Code Category B-L-2 / Item No. B12.20 Component System Pump Function Disassembled Examined Relief ID Type Request 02 2P-1 A Recire. Centrifugal Recirculation No No RSB 02-2P-1B Recire. Centrifugal Recirculation No No RSB l 1 j i l i l l l ~ l l l l l O I INTERVAL. DOC July 14,1997 Page44 of 80 1 l
4
- i. .;
.O! t j * . J . 1 1 l I ENCLOS~URE 9 1
-O ,
THIS SECTION IS INTENTIONALLY LEFT BLANK l I i n O i I N1ERVALDOC July 14,1997 Page 45 of 80 l l I
O Code Cateenry B-M-2: V VmIve Bodies > 4" Nominal Pipe Size Item No. B12.50 Internal Surfaces Reliefis requested in accordance with the provisions of 10 CFR 50.$$a(a)(3)(ii) fr6m the full Code-required extent of visual examination for Valve Body Internals listed in Table 10.
- Fummination Reauirements This request for reliefis being submitted in accordance with NRC Safety Evaluation (SE) of the 2nd Ten-Year Inservice Inspection Program, Dated October 27,1987, Docket No. 50-333 approved ReliefRequest 5 (RSC). ReliefRequest 5 (RSC) requires visual (VT-3) inspection of internal surfaces of valve bodies once per interval when these components are disassembled for maintenance and stipulates that a relief from examination of specific components not disassembled will be submitted at the end of the interval.
Basis for Relief The valve internal surfaces are only accessible when the valves are disassembled. These valves were not disassembled during the 2nd Ten-Year Interval. A visual inspection (VT-2) , pressure test is conducted on these components every refuel outage in accordance with IWA-5000 and 3 IWB-5000. This request for reliefis being submitted in accordance with JAF's 2nd Ten-Year (V Interval, Inservice Inspection Program approved Relief Request 5 (RSC) . The Authority has elected to implement a conservative inspection criteria for valves. This inspection selection criteria is based not only on type of valve and function but also on which system requires a larger population, (i.e.: gates valves), and an increased frequency ofinspection for those valves that are disassembled more than once per interval. This request is being submitted in accordance with the approved NRC Relief Request (RSC) for the 2nd Ten Year Interval. Components addressed by this ReliefRequest are listed in Table 10. Proposed Altern11ir.t None O L.) INTERVAL. DOC July 14,1997 Page 46 of 80
a Table 10 f-] O Code Category B-M-2 / Item No. B12.50 i Consponent Systesa Valve Function Disassembled Examined Relief ID I Type Request j 02MOV-43A Recire. Gate a Isolation
~
No No RSC ) 02MOV 43B Recire. Gate Isolation No No RSC l 02MOV-53A Recire. Gate Isolation No No RSC 02MOV-5?B Recire. Gate Iwlation No No RSC 13MOV 21 RCIC Gate Isolation No No RSC 34FWS-29A FW Gate Isolation No No RSC JWWS-29B FW Gate Isolation No No RSC A N 1 V INTF.RVAL. DOC - July 14,1997 Page 47 of 80
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- 4. .
4 ' a 2 1 I j i, 1 1 1 4 1 1 o 5 1. 1 j INTERVAL. DOC July 14,1997 Page48 of 80 i .. . _. . . . . _ . . . .~ _ - - . . - ...- - _-., . ,. .-. - .--_ _- _ .. . _ . . , _ - -
i 1 I l . i e , 1 i I
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. Code Cateenev B-O; Pressure Retairdng Welds in Control Rod Housings
\
l 4 l Item No. B14.10: Welds in CRD Housing Examination Reauirements ASME Section XI requires that 10% of the pressure retaining welds in peripheral CRD Housings are inspected once every interval. 1 1 . Basis for Relief l Access is limited to four 18" diarneter manways 90" apart in the vessel suppon skirt. In addition, the one-hundred and thirty-seven (137) control rod drives and forty-three (43)in-core monitor instrumentation penetrations present extensive interference. The positioning and spacing of these components prevent an inspector from physically being able to reach teyond the manway openings. Based on design, there are 28 peripheral CRD housings and (12) twelve = 42%, have been inspected. CRD Housing Welds inspected during the 2nd Ten-Year Interval are listed in Table 11 and are illustrated in the drawings of Enclosure 11. f Pronosed Alternative None l I o \ U INTERVALDOC July 14,1997 Page 49 of 80
.. . _ . . . -- _- ..-___. -- . _ . - = - ..
Table 11 Code Category B-O / Item No. B14.10 RPV Bottaan CRD No. RPV & Penetration CRD Coordinates - Head Reference Drawings Reference Drawing
- Penetrations j V8 22 51 MSK-3036 & 5.0182D 5.01 '3."D
] V1 30-51 MSK-3036 & 5.01-82D 5.01-135D U4 02-27 MSK-3036 & 5.01-82D 5.01-135D V2 50-31 MSK-3036 & 5.01-82D 5.01 135D V3 50-23 MSK-3036 & 5.01-82D 5.01-135D , U3 26-03 MSK-3036 & 5.01-82D 5.01-135D Ul 26-51 MSK-3036 & 5.0182D 5.01 135D i V7 02 31 MSK-3036 & 5.01-82D 5.01 135D V6 02-23 MSK-3036 & 5.01-82D 5.01-135D 1 U2 50-27 MSK-3036 & 5.0182D 5.01-135D V4 30-03 MSK 3036 & 5.01-82D 5.01-135D V5 22-03 MSK-3036 & 5.01-82D 5.01 135D j i 4 i L l d INTERVAL. DOC July 14.1997 Page 50 of 80
- O i
~ I l 3 1 1 i s l 1 ENCLOSURE 11 i i i i s I 9 e EMEM July 14,1997 Page 51 of 80
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-- " ' ' * " " " l ENCLOSURE 11 - Page 3 of 3 .
ds . . . ,..,. @ ,.. ~- l i CRD Penetration Detail _
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_g ! Drawing 11825-5.01-135D l I sists- s.oi-nso l ' ! I i
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i { O CLASS 2 COMPONENTS O ME July 14,1997 Page $2 of 80 3
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l
- Code Cateenry C-A
- Pressure Retninine Welds in Pressure Vessels !
l Item No. C1.10 Shell Circumferential Wchl (RHR Heat Exchanger) l Item No. C1.30 Tubesheet-to-Shell Weld (RHR hem Exchanger)' I Item No. C1.10 Shell Circumferential Weld (RHR Heat Exchanger) l Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(ii) from the full l
- Code-required extent of volumetric examination for RHR Heat Exchanger Pressure Vessel Circumferential Weld # C3-B listed in Table 12.
Ermmination Reauirements ] ASME Section XI requires 100% volumetric examination of this weld once per interval. l Basis For Relief l Complete inspection of the Code-required volume is not possible based on restricted access l caused by interference due to the close proximity of the vessel flange bolting and the N4B nozzle. Drawings and sketches which illustrate the restricted conditions encountered that limit examination coverage are included in Enclosure 12. Examination Alternative j 1. No additional volumetric examinations will be performed on these welds. The component i l listed in this relief request has been examined to the maximum extent practical. l l
- 2. A visual inspection (VT-2) was performed during the pressure testing which is conducted on this component every refuel outage (no leakage detected) in accordance with IWA-l 5000 and IWC-5000, which provides reasonable assurance of component integrity.
l I i l i l l l l
- O L
l INTERVAL. DOC July 14.1997 Page 53 of 80
( Table 12 Code Catgery C-A / Item No. C1.10 (RHR Heat Exchanger) l CossponentID System Extent Examined 1Amitation - Remarks - C3 B RHRlh. Est. 70 - 80%
- Flange Bolting & See Enclosure 12 Exch. "B" Nozzle i
O NJ l l O NME July 14,1997 Page 54 of 80
a 4 i i E !O ENCLOSURE 12 1 N I j l i 4 4 d O
, INTERVALDOC July 14,1997 Page 55 of 80
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y l l l !O Item No. C1.30 Tubesheet-to-Shell Weld (RHR Heat Exchanger) i' Reliefis requested in accordance with the provisions of 10 CFR 50.5$a (a)(3)(ii) fr'om the Code ~ required extent of volumetric examination for Pressure Retaining Welds in Pressure Vessels for the RHR Heat Exchanger Tubesheet-to-Shell Welds # C2-A & C2-B. Fummination Reauirements ASME Section XI requires 100% volumetric examination of this weld once per interval. Basis for Relief Relief from the Code-required volume was requested in the initial 2nd Ten-Year Inservice Inspection Program submittal (Reference NRC Safety Evaluation, dated October 27,1987, Relief l Request (R15). The NRC denied this application for relief based on the possibility of disassembly I and inspection during the Interval. The RHR Heat Exchangers have not been disassembled during the 2nd Ten-Year Interval and, therefore, the Authority is re-submitting this request for relief from the Code-required extent of examination for the Tubesheet-to-Shell Welds which was a part of the original Inservice Inspection Program's 2nd Ten-Year submittal. Fummination Alternative
- 1. No additional volumetric examinations will be performed on these welds. The components listed in this relief request have been examined to the maximum extant practical.
- 2. A visual inspection (VT-2) was performed during the pressure test which is conducted on i this component every refuel outage (no leakage detected) in accordance with IWA-5000 and IWC-5000.
i LO i INTERVALDOC July 14,1997 Page 56 of 80
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l 4 Code Catenerv C-A: fressure Retnining Welds in Pressure Vessels (SCRAM TANK)
.l 1 Item No. C1.20 Head Welds 4
Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full I Code-required extent of volumetric examination for Pressure Retaining Welds in Pressure Vessels 4 for Scram Tank Head Welds listed in Table 13. I Examinatios. Requirements F ( ASME Section XI requires 100% volumetric examination of this weld once per interval. I 1 Basis for Relief l Complete inspection of the Code-required volume is not possible based on welded appurtenances ! on the vessel which restrict accessibility. Drawings and sketches which illustrate the restricted ] conditions encountered that limit examination coverage are included in Enclosure 13. I Fummination Alternative i O 1. . No additional volumetric examinations will be performed on these welds. The components listed in this relief request have been examined to the maximum extent practical. l- 2. A visual inspection (VT-2) was performed during the pressure test which is conducted on
- j. this component every refuel outage (no leakage detected) in accordance with IWA-5000
! and IWC-5000. l l + i O INTERVAL. DOC July I4,1997 Page 59 of 80
Table 13 O Code Category C-A / C1.20 (Scram T,ank) , , Component ID System Extent Examined Limitation - Remarks - THI-B Scram Est. 80 - 85% (4) Socket Weld Noz(s) See Enclosure 13 Tank BH1-B Scram Est. 60 -75% (4) Support Legs See Enclosure 13 Tank O l l. i i i O INTERVAL. DOC July 14.1997 Page 60 of 80
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I Code Cateenry C-B: Pressure Retnining Nozzle Welds in Vessels (RHR Heat Exchanger) i \ Item No. C2.21 Nozzle-to-Shell (or Head) Weld .. l Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of volumetric examination for the RHR Heat Exchanger Nozzle-to-Shell (or Head) Welds listed in Table 14. Framination Reautrements l ASME Section XI requires 100% volumetric and surface examination of this weld once per interval. Basis for Relief Complete volumetric inspection of the Code-required volume is not possible based on nozzle design and the proximity of the vessel flange and associated bolting. Inspection data performed on l these components include sketches which illustrate the restricted conditions encountered that limit the, examination coverage. Full examination coverage for the required surface examination was achieved Drawings and sketches which illustrate the restricted conditions encountered that limit l v(] examination average are included in Enclosure 14. Eremination Alternative l l 1. No additional volumetric or surface examinations will be performed on these welds. The components listed in this relief request have been examined to the maximum extent practical. l l 2. A visual inspection (VT-2) was performed during the pressure test which is conducted on this component every refuel outage (no leakage detected) in accordance with IWA-5000 and IWC-5000. l l l INTERVAL. DOC July 14,1997 Page 62 of 80 l l
_( Table 14 Code Category C-B / Item No. C2.21 (RHR Ht. Exch.) Consponent ID System Extent Examined Limitation - Remarks l 1 N3A RHR Ht. Est.10% One-sided Configuration See Enclosure 14 Exch N4A RHR Ht. 40-50% One-sided Configuration See Enclosure 14 Exch j 1 N4B RHR Ht. 40-50% One-sided Configuration See Enclosure 14 Exch , l O O INTERVAL. DOC July 14.1997 Page 63 of 80
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l ( Code Cateenry C-C: htgral Attachments for Vessels. Piping. Pumns. and Valves Item No. C3.10 Pressure Vessels (Integrally Welded Attacaments) Item No. C3.20 Piping (Integrally Welded Attachments) , Item No. C3.10 Pressure Vessels (Integrally Welded Attachments) Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(ii) from the full' Code-required extent of surface examination for the RHR Heat Exchanger Pressure Vessels (Integrally Welded Attachments) listed in Table 15 , j h=i== tion Reauiremegt i ASME Section XI requires 100% surface examination of this weld once per interval. Basisfor. Relief Complete inspection of the Code-required surface area utilizing a surface inspection method was not possible based on restricted accessibility due to the interferences of design. These welds are support lugs which are part of the rigid support structure that stabilizes the upper portion of the RHR Heat Exchanger. The lower portion of these lugs are restricted by an attached structural O angle member frame which extends beyond the bottom edge of the lugs limiting access to these areas. This limiting condition restricts the access necessary to perform a magnetic particle inspection and the ability to use surface preparation equipment needed to prepare for liquid penetrant testing. In order to obtain full Code examination coverage on these components, it would require removal of the structural angle members and increase radiological exposure which would constitute a hardship and unusual difficulty for the sole purpose of providing access to obtain additional examination coverage. Partial code required coverage was obtained examining components SUP-1 A, SUP-2A, SUP-3 A, and SUP-4A using magnetic particle, liquid penetrant surface inspection methods and visual examination (VT-1). A visual inspection (VT-2) was performed during the pressure test (no_ leakage detected) which is conducted on these components eveny refuel outage in accordance with IWA-5000 and IWC-5000. Drawings and sketches which illustrate the restricted conditions encountered that limit examination coverage are included in Enclosure 15. Proposed Alternative Nmination
- 1. A supplemental visual inspection (VT-1) was performed on the inaccessible areas (lower portion) of these welds with no adverse or reportable conditions observed.
- 2. No additional examinations will be performed on these welds. The components listed in this relief request have been examined to the maximum extent practical.
O INTERVALDOC July 14,1997 Page 6s or 80 t
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Table 15 3 i i-Code Category C-C / Item No. C3{(Integrally Welded Attachments) { Consponeet ID System Extent Examined Limitations Remarks ) SUP 1 A RHR Heat Est. 70% Whip Restraint See Enclosure 15 E-'=.- Attached to Lug l SUP-2A RHR Heat Est. 83% Whip Restraint See Enclosure 15 j 9"h"?" Attached to Lug } SUP-3A RHR Heat Est. 81% Whip Restraint See Enclosure 15 Exchanger Attached to Lug j SUP-4A RHR Heat Est. 80% Whip Restraint See Enclosure 15 i Exchanger Attached to Lug i } l i. i 4 a f, $ (i i b I
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INTERVAL. DOC July 14,1997 Pagc 66 of 80
l l I O ENCLOSURE 15 1 l l l O INTERVAL. DOC July 14.1997 Page 67 of 80
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f~~h v Item No. C3.20 Piping (Integrally Welded Attachments) Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of surface examination for Piping (Integrally Welded Attachinents) listed in ~ Table 15A. Emmabation Reauirements ASME Section XI requires 100% of required areas of each welded attachment. Basis for Relief Complete inspection of the Code-required surface volume for components listed in Table 15A is not possible based on restricted accessibility caused by interferences due to design limitations ; and/or support stmetures encountered when employing the surface inspection methods. Drawings ; and sketches which illustrate the restricted conditions encountered that limit examination coverage are included in Enclosure 15A. j Proposed Alternative Ernminations [] w/
- 1. No additional surface examinations will be performed. These welds have been examined to the maximum extent practical.
- 2. A visual inspection (VT-2) was performed during the pressure test (no leakage detected) I which is conducted on these components every refuel outage in accordance with IWA-5000 and IWC-5000.
O O INTERVAL DOC July 14.1997 Page 68 of 80
Table 15A
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Code Category C-C / Item Ng3.20 (Piping: Integrally Welded Attachments) l Component ID System , Extent Examined IJmitation Remarks - 12 t.0-697A RHR Approx. 50% m Design See Enclosure ISA n-10-862B RHR 80-90 % Pipe Support see Enclosure 1SA 20-10 889 RHR Esst. 75% Pipe Support See Enclosure ISA 12-14 750A Core Spray 86,% Concrete Wall See Enclosure ISA NOTE: i (1) An approximate percentage of 50% for Code required coverage of Weld 12 10-697A is being used based on the outside surface being accessible for examination b v I 1 f3 l U i INTERVALDOC July 14,1997 Page 69 of 80
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EBASCO SERVICES INCORPOFIATED jab' Y sy l)M oars / /9 '/2 swesT 2.- o, .2 cwxo.sv CL oars) 'TO OFS NO l N usur AlYAA
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3 Code rateenry C-F/CG: Pressure Retninine Welds in Pipir .e. Pumps. and Valves q in Systems Which Circulate Reactor Coolant Item No. C2.1 Piping (Circumferential Butt Welds) Item No. C2.3 Piping -(Branch Pipe-to-Pipe Weld Joints) Item No. C2.1 Piping (Circumferential Butt Welds) Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full Code-required extent of surface and/or volumetric examination for Circumferential Butt Welds listed in Table 16. Examination Reauirem,gggg ASME Section XI,1980 Edition through Winter 1981 Addenda, requires the lower %t of the weld examined volumetrically up to and including adjacent base metal %" from the weld toe on either side of the weld. Surface examinations requires the weld inspection and includes %" on either side of the weld toe. Basis for Relief O V Complete inspection of the Code-required volume for components listed in Table 16 is not possible based on restricted access caused by permanent interference such as saddle welds, and integrally welded supports. Proposed Alternative Eummination
- 1. No additional volumetric examinations will be performed. These welds have been examined to the maximum extent practical.
- 2. A visual inspection (VT-2)_was performed during the pressure test (no leakage detected) which is conducted on these components every refuel outage in accordance with IWA-5000 and IWC-5000.
O INTERVAL. DOC July 14,1997 Page 71 of 80 ___m____---
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- Table 16 i
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,, Code Category C-F/ Item No. C2.1 Cesaposeet ID Systems Estent Examined Limitation Remarks 20 10-227 RilR 50-60 % Saddle Weld Limitation applies to i
Interference Sur & Vol. Exams 16-10-565 RHR 70-80 % Integrally Welded Limitation applies to Attachment Sur. Exam Only 16-10-643 RHR Est. 70-80% Integrally Welded Limitation applies to Attachment Sur. Exams Only 16-10-644 RHR Est. 70-80% Integrally Welded Limitation applies to Attachment Sur. Exams Only O 1 O INTERVAL. DOC July 14.1997 Page 72 of 80
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+ Vw. +- -+' yz . . <-- j A. /.,8 ., o :: . :: 1 / v , x k fy gg, W 04< +---- > G M m vet, c-o.e-r Coverage Achieved for a Specific Weld or Component is Designated in ; Table 16 - Extent Examined ' l FIGURE 1 l l i l ENCLOSURE 16 - Page.1 of 1 l i Code Cateenry C-C: ~~ Pressure Retninine Welds in Pinine. Pumns and Valves in Systems Which Circulate Other Than Reactor Coolant Item No. C2.3 Branch Pipe-to-Pipe Weld Joints Reliefis requested in accordance with the provisions of 10 CFR 50.55a (a)(3)(iii) from the full l Code-required extent of surface and/or volumetric examination for Branch Pipe-to-Pipe Weld l Joints listed in Table 17. Fummination Renuirements o I l: ASME Section XI,1980 Edition through Winter 1981 Addenda, requires the lower %t of the ' weld examined volumetrically up to and including adjacent base metal %" from the weld toe on either side of the weld. Surface examinations requires the weld inspection and includes %" on either side of the weld toe. Basis for Relief j Complete inspection of the Code-required volume for components listed in Table 17 is not i possible based on restricted accecsibility caused by interference from a socket weld drain line connection and an adjacent suppo t structure. Pronosed Alternative Examination
- 1. No additional volumetric examinations will be performed. These welds have been examined to the maximum extent practical.
l
- 2. A visual inspection (VT-2) was performed during the pressure test (no leakage detected) s which is conducted on these components every refuel outage in accordance with IWA-l 5000 and IWC-5000.
i. I l I i INTERVAL. DOC July 14,1997 Page 74 of 80 . . . . - . . - - - . - . . . - . . . . . . . . . _ . - ~ - - . . (- ( Table 17 Code Category C-G / Item No. C2.3 < Conspement ID System Extent Examined Limitation Remarks 16-14-709 Core Spray 50% (8) Adjacent Suppo t Limitation applies to Structure Surf. Exam Only 14-23-46i HPCI Est. 80-90% 4" Socket Weld Limitation applie.* to Surf. And Vol. l Exams j NOTE: (1) Credited exanunation volume of 50% for Weld 16-14 709 is based on a one-sided access inspection. No credit is taken for partial exanunation coverage on the support structure side of the weld. 1 O l t l l I l < O V ' INTERVAL. DOC July 14,1997 Page 75 of 80 . - . . . . - - . . . . - . . . . . . . ~ - . ~ . . . . - . . . . - - . . . ~ . . . - A l l l l l l e, l l 1 l l l I l l l l l l l 1 l 1 l 1 1 I i l l lO ENCLOSURE 17 l' l I l 1 l 4 l l INTERVALM July 14,1997 Page 76 of 80 l l l n n Branch Connection Welds V Code Category C-F & C-G ' ~ Code Required Coversee _, k.*,' \s = 8 A , l1 - ~ - ,5 i / T --+ +-inin. [ _ 3 Branch connection O 1 h. 1 11 - gi _ \ T 8 i < ^\ f* v Er- l <a ' s, i S - _.-.. ~ . ~ _ i Coverage Achieved for a Specific Weld or Component is Designated in , Table 17 - Extent Examined ! FIGURE 1 I
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sW l , Code Category C-H: All Pressure Retnining Comnonents / Code Categm yR ,A/ D-B/ D-C: Pressure Retnining Boundary Item No(s): All Reliefis requested from the ASME Section XI Code requirements for Code Category C-H and D - A, D-B and D-C for pressure test surveillances that were not completed during the second period of the 2nd ISI Interval. The NRC was previously notified of this discrepancy via Licensee Event Report 92-022. Pressure testing of the Standby Liquid Control (ISI Class 2), Emergency Service Water (ISI Class 3) and Fuel Pool Cooling (ISI Class 3) systems was not performed during the first inspection period in accordance with the ASME Code edition applicable to the FitzPatrick plant at ' that time. The pressure tests used 10-minute hold times, recognized by later editions of the Code, instead of the required four-hour hold time. These tests were completed in the 2nd and 3rd periods of the 2nd Interval as required by Code. Root causes were completed and documented in the 1992 time frame and all pressure tests except those noted above were completed. An assessment was also completed by an outside consultant in late 1995 to ensure all tests scheduled for the remainder of the interval were completed or being tracked to completion. All required tests for Code Categories B-P, C-H and D-A, D-B and D-C have been completed except those noted above. '( In addition, the following programmatic improvements were initiated to ensure that no tests would be missed in the future:
- 1. A procedure was developed, Plant Standing Order 31B, which defined responsibilities for the ISI Pressure Test Program. This also included improvements in the Post-Work Test Program, currently AP-19,02.
- 2. A basis document was developed for use by Engineering and Operations personnel which clearly defined the system boundaries for each ISI system. The report # JAF-RPT-MISC-00658 has been revised three times to include guidance for personnel and for the inclusion of various NRC approved relief requests and code cases approved for use in NRC Regulatory Guide 1.147.
In summary, three tests were not completed as required by ASME Section XI Code requirements. Subsequent testing was completed in the 2nd and 3rd periods for these tests. Programmatic improvements have been initiated to prevent recurrence of this event. A l l INTERVALDOC July 15,1997 Page 77 of 80 e Code Cateeory C-H: All Pressure Retninine Comnonents ~ Code Categmy D-A/ D-B/ D-C Pressure Retnining Boundary Item No(s): All Reliefis requested from the ASME Section XI Code requirements for Code Category C-H and D - A, D-B and D-C for pressure test surveillances that were not c mpk ed during the second period of the 2nd ISI Interval. The NRC was previously notified of this ( erepancy via Licensee Event Report 92-022. ' Pressure testing of the Standby Liquid Control (ISI Class 2), Emergency Service Water (ISI Class 3) and Fuel Pool Cooling (ISI Class 3) systems was not performed during the first inspection period in accordance with the ASME Code edition applicable to the FitzPatrick plant at that time. The pressure tests used 10-minute hold times, recognized by later editions of the Code, . instead of the required four-hour hold time. These tests were completed in the 2nd and 3rd periods of the 2nd Interval as required by Code. Root causes were completed and documented in the 1992 time frame and all pressure tests except those noted above were completed. An assessment was also completed by an outside consultant l in late 1995 to ensure all tests scheduled for the remainder of the interval were completed or being tracked to completion. All required tests for Code Categories B-P, C-H and D-A, D-B and D-C have been completed except those noted above. In ad.:lition, the following programmatic improvements were initiated to ensure that no tests would be missed in the future:
- 1. A procedure was developed, Plant Standing Order 31B, which defined responsibilities for the ISI Pressure Test Program. This also included improvements in the Post-Work Test Program, currently AP-19.02. ~
- 2. A basis document was developed for use by Engineering and Operations personnel which clearly defmed the system boundaries for each ISI system. The report # JAF-RPT-MISC-00658 has been revised three times to include guidance for persoral and for the inclusion of various NRC approved relief requests and code cases approved for use in NRC Regulatory Guide 1.147. '
' In summary, three tests were not completed as required by ASME Section XI Code requirements. Subsequent testing was completed in the 2nd and 3rd periods for these tests. Programmatic improvements have been initiated to prevent recurrence of this event. l s. LO INIT.RVAL. DOC July 15,1997 Page 77 or 80 l l t , i 1 2 . ASME SECTION XI { Ei,T/flyiContainment Renair & Renlacement Rule The Authority submitte[a request for relief from the primary containment repair and replaceme t provisions in th?.1992 Edition af ASME Section XI, Subsection IWE on November 26,1996 d (Reference 1); The NkC issued Information Notice 97-29 (Reference 2) to provide guidance to ) licensees concerning the content of these relief reguests. Subsequently, the NRC requested i additional information regarding the JAF relief request (Reference 3). The following information ; supplements Reference 1 and provides the information requested by Reference 3. Suppleisnt 12 JAF Relief Request Regarding Implementation [j- Schedule for Coretahment Repair / Replacement Requirements Funlanation of Hardrh:n Impa.ad Bv Final Rule l The Authority initially requested (Reference 1) the implementation of the repair and replacement j provisions of the 1992 Section XI, Subsections IWE and IWL be deferred by one year from September 9,1996 to September 9,1997. A relief from the NRC to defer the implementation of i the Code provisions would allow the Authority sufficient time to provide appropriate resources to
- train necessary personnel and implement a containment repair / replacement program.
1 i The JAF ISI program for Cla'ss 1,2, and 3 components and their supports is based on ASME !p Section XI,1980 Edition with Addenda through Winter 1981, The classification of systems and j their components is based on requirements in 10 CFR 50.55 (a) and Regulatory Guide 1.26. The i 1992 Edition including the Addenda IWE-1220 (d) requires that all piping, pumps, and valves that l are part of the containment system, or which penetrate or are attached to the containment vessel, i be examined in accordance with the rules oflWB or IWC. This would require the portion of i piping systems (up to the first isolation on either side of the containment) that penetrates the
- containment be upgraded to either ISI Class 1 or Class 2 for the purpose of examination for any i repair / replacement activities. Implementation of the rule requires
- identification and re-
+ classification of the applicabb ISI boundaries for engineering, design and planning personnel 1 (drawing development, preparation, and issuance); revision of applicable plant programs and i procedures related to maintenance and modification work packages preparation; and review -and/or revision of all work packages prior to the start of the Fall 1996 refueling outage to
- determine the potential impact of the activity relative to repair and replacement rules implemented j by the Code in Subsections IWE and IWL. Since the rule became effective on September 9,
! 1996, enough time was not available to implement these new provisions prior to the start of the !- Fall 1996 refueling outage. Similarly, the ISI program defines the VT-1 and VT-3 examinations and includes all factors l' necessary to qualify the examiners and assure the examinations are performed to the highest l quality levels (in accordance with the ASME Section XI,1980 Edition up to and including the j 1981 Winter Addenda and 1980 Edition of SNT-TC-1 A). The imposition of 1992 Code i requirements (ANSI /ASNT CP-189,1991 Edition) for containment would necessitate a separate administrative program including procedures, certification tests and record keeping requirements, ] 1 DrrERVAL. DOC July 14,1997 Page 78 of 80 y which would merely parallel the existing prcyam v' tith no benefit to qualityc The existing program is the same as used on the reactor veel r.rrd other Class I components, and continues to prove effective. Implementing and maintainitg trio separate programs for similar inspections is a significant burden at this time to the Autheity,ind would not provide a compensatory increase in the level of quality and safety. The Authority understands that the lack of pr$perly qualified inspectors is an industry-wide situation. Although the qualification of the authorized inspector is the responsibility of the authorized inspection agency, the Authority has encouraged Arkwright (the third party inspection agency for FitzPatrick) to obtain any additional qualification that would be required to implement Subsections IWE and IWL. In the interim, the Authority will continue to address any , containment repair (or restoration) issues in accordance with its corrective action program. Experienced individuals will be utilized to inspect, evaluate, and perform the required . repair / replacement activities. JAF entered a refueling outage at the end of October 1996. The date of the final rule, and implementation date, for the containment repair / replacement provisions was September 9,1996. A revision to the FitzPatrick ASME Section XI Repair / Replacement program prior to the outage to incorporate the provisions of the 1992 ASME Section XI, Subsections IWE and IWL would have had a significant negative impact on the outage schedule. A significant diversion of resources would have been required for: reviewing all outage related modifications and maintenance repair / replacement activities and the thousands of associated outage work package.s p V (many were initiated prior to the issuance of the rule change) for potential impact of the planned activities relative to repair and replacement rules implemented by the Code in Subsections 1 IWE/IWL; training of maintenance, engineering and design personnel; training and qualification ofNDE personnel; review, preparation and incorporation of a repair / replacement program to the 1992 Code requirements; and review and revision ofISI class boundary documents (drawing development, preparation and issuance). These activities would have required significant resources, but would not have resulted in a compensatory increase in the level of quality and safety. The Authority has implemented the following actions toward the development and implementation of a containment repair / replacement program in accordance with the provisions of the 1992 Section XI, Subsections IWE/IWL a responsible individual from the engineering programs group (ISI Containment Coordinator), QA personnel and civil / structural engineers have attended a training class on the subject Code requirements: action items have been generated and assigned to responsible individuals to incorporate the requirements ofIWE/IWL into the JAF ISI program, and to develop a containment repair / replacement program by September 1997 which is contingent on the approval of this Relief Request; and a general walkdown and video taping of the inside exposed surfaces of the containment is planned in preparation for the general visual inspection to be performed prior to September 2001, as required under IWE-1231. Pronosed Alternative Reauirements The containment, including its components, containment penetrations and the associated process lines that pass through these penetrations up to the first isolation, are designed to QA Category I INTERVAL. DOC July 14,1997 Page 79 of 80 wm ^ p.. I and Seismic Class I requirements. A listmg of the applicable codes and:c;* ions for the O Pri- rv ce t i - t >i t a i rs^ sectie- 16.7.3.2.2. iii,eper/agimment (R/R) activities, including those for the containment, are controlled by winas Wn::trative and l implementation procedures. The following are examples of thes:froc-hs: g5 " A) . Modification Control Manual Procedures which control thh uJsis,cring and design processes of plant modifications, such as: - MCM-3A, Modification Package Preparation Review and Approval, a MCM-4, Nuclear Safety and Environmental Impact Screens and Nuclear Safety . Evaluations; MCM-5A, Minor Modification Package Preparation, Review and Approval; and a MCM-14A, Type 1 Change (JAF). B) Station Administrative Procedures (AP) which establish control on the planning, work control, quality assurance, and implementation of work packages associated with the repair / replacement activities, such as: AP-05.14, ASME Section XI Repair / Replacement Program; AP-10.01, Problem Identification and Work Control; ) 1 AP-10.03, Work Package Planning; and AP-18.01, Quality Assurance Program Implementation at JAF. These proce/ 3, together with other lower level implementation procedures, ensure iny containment . A activities meet or exceed the original design criteria. Our QA personnel are also j involved wim. 11 containment related R/R activities. The examination requirements for containment reinted repair / replacement activities in many cases are actually more stringent than are required under the provisions of 1992 IWE (VT-1 or VT-3). Therefore, deferral of the l implementation date for the repair and replacement provisions of the 1992 ASME Code will not compromise the structural integrity of the containment, and is consistent with maintaining the continued health and safety of the public. References
- 1. NYPA letter, W. J. Cahill, Jr. to NRC (JPN-96-050), " Request for Relief From ASME l
" Section XI Code Regarding Implementation Schedule For Containment Repair / Replacement Requirements," dated November 26,1996. 1
- 2. NRC Information Notice 97-29, " Containment Inspection Rule," dated May 30,1997.
l 3. NRC letter, Karen R. Cotton to James Knubel, " Request for Additional Information Regarding Relief Request From Implementation of 10 CFR 50.55a Related to ] Containment Repair / Replacement Requirements - Jr.mes A. FitzPatrick Nuclear Power i Plant (TAC No. M98061), dated June 25,1997. INTERVAL, DOC July 14.1997 Page 80 of 80 I j}}