PY-CEI-NRR-0919, Forwards Relief Request Re Inservice Insp Program,Per NRC .Fee Paid

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Forwards Relief Request Re Inservice Insp Program,Per NRC .Fee Paid
ML20195H192
Person / Time
Site: Perry 
Issue date: 11/18/1988
From: Kaplan A
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
PY-CEI-NRR-0919, PY-CEI-NRR-919, NUDOCS 8811300255
Download: ML20195H192 (48)
v • d • e


Text

.

4 THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY PO DOX 97 e PERAY, OHIO 44081 m

TELEPHONE (216) 259 3737 a A D DR E SS.10 CENTER ROAD Serving The Best Location in the Nation PEPAY NUCLEAR POWER PLANT Al Kaplan M PRI $OENT November 18, 1988 man ym,,

PY-CEI/NRR-0919 L U.S. Nuclear Regulatory Commission Document Control Desk Washingten, D.C.

20555 Perry Nuclear Powcr Plant Docket No. 50-440 Inservice Inspection Relief Requests Centlement v bruary 9, 1988, the NRC staff noted that relief requests for By letter date-e the Perry Int ice Inspection (ISI) Program would have to be submitted, based on guidelines provided in Appendix A to that letter. The subject relief requests are attached; inspection schedules remain as defined in Sections 12 ead 13 of the 10 year Inservice Inspection Program Plan for Perry Nuclear Power Plant, Unit 1, as submitted to the NRC by letter PY-CEI/NRR-0614L on March 31, 1987 (ISI Plan).

Pursuant to 10 CFR 170.12, we have included a fee payment of $150.00.

If you have further questions, please feel free to call.

Very truly yours,

}l- ],$

w U

AL Al Kaplan Vice President Nuclear Croup AK/sc Enclosure cci T. Colburn K. Connaughton j

USNRC Region III

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0S11300255 38111s

{DR ADOCK 0500044o PDC

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Perry Nuclear Power Plant Unit 1 i

RELIRF REQUEST GIR-001 i

i I. Identification of Components j

System Reactor Pressure Vessel, Class I a

A.

Category: B-A, Pressure Retaining Velds

[

t Component Descriptions (See attached table for component d

l identification numbers).

l l

1.

Shell velds (Item No. Bl.11, B1.12) 2.

Head helds (Item No. B1.21. Bl.22)

I 3.

Head to flange (Item No. Bl.40) i l

B.

Category: B-D, Full Penetration Velds of Nozzles in Vessels 1

6 Component Descriptions (See attached table for component

(

identification numbers)

}

i 1.

Nozzle to shell velds (Item No. B3.90)

I j

2.

Nozzle inside radius section (Item No. B3.100)

(

l C.

Categoty: B-F, Pressure Retaining Dissimilar hetal Velds i

i l

j Component Descriptions (See attached table for component

[

1 identification numbers) i j

1.

Nozzle to safe end velds (Item No. B5.10)

II. ASME B&PV Section XI Requirements i

i ASME Code requires 100% volumetric examination of velds and required volume.

III. Relief Requested i

i i

Relief requested from 100% volumetric examination (See attached table for i

percent completion of each specific component) at the first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

p IV. Basis for Relief

[

t l

The structural integrity of the reactor pressure vessel velds was 1

demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections.

All velds vere examined in i

i accordance with the appropriate Code requirements, veld techniques and velders were qualified in accordance with Code requirements, and I

I 4

o 1

4 I

Perry Nuclear Power Plant Unit 1 l

Relief Request 91R-001 i

materials were purchased and traced in accordance with the appropriate l

Code and NRC requirements and guidelines. The Perry Unit I reactor vessel had no reportable indications from preservice inspection results.

l The pressure boundary passed the required hydrostatic testi following i

startup testing the plant has operated between 60% and 70% capacity

[

l factor for a total of about 250 equivalent full power days between i

November 1987 and November 1988, without detectable pressure boundary l

leakage.

1 Complete examinations meeting the requirements of the ASME Codo Section XI will continue to be performed on velds of similar configurations utilizing similar veld techiques, procedures and materials. The inspected velds are subjec.t to the same operating and 6

l' environmental conditions as the partially examined or unexamined velds.

I It is, therefore, reasonable to apply the results from examined velds to the partially examined velds in the attached table.

[

l In addition, catastrophic reactor vessel failure is precluded by avoiding 8

nil ductile temperatures at significant stress levels according to the 4

design, surveillance and operating provisions described in the Perry USAR Sections 5.3.1 and 5.3.2 and the Technical Specifications 3/4.4.6.

l t

In summary, because of initial vessel condition free of reportable

[

indications, successful code hydrotest and operating experience without leakage indications, the capability to examine most vessel velds on a t

continuing basis, the capability to detect pressure boundary leakage, and a

protections against brittle reactor vessel failure, it is concluded that there is no significant impact on the overall level of plant quality and l

l safety.

See the attached table for specific causes of NDE limitation for each component.

)

V. Alternate Examination i

i t

i None f

I i

1 1

i I

l 1

l l

.i

+

PERRY NUCLEAR POUER PLANT UNIT 1 PACE 1 0F 9 RELIEF REQUEST NO. IR-001 SYSTEM: Reactor Pressure Vessel PERCENTAGE CODE COMPLETE ITEM NO.

VELD I.D.

DESCRIPTION CATEGORY

_L BASIS FOR PILIEF*

Bl.11 1-B13-AA Lover head to shell #1 BA 50 50 Examination performed from shell side cire. veld only due to support skirt and base ring obstructica on lover head.

Bl.12 1-B13-BA Shell ti long. seam BA 70 78 Obstructions presented by N1 and at 17' N2 recirculation nozzles.

B1.12 1-B13-BB Shell #1 long. seam BA 74 76 Obstructions presented by at 137' N2 recirculation nozzles.

81.12 1-B13-BC Shell #1 long. seam BA 75 75 Obstructions presented by at 257' N2 recirculation nozzles.

Bl.11 1-B13-AB Shell 31 to shell #2 BA 85 99 Obstructions presented by N1 and cire. veld N2 recirculation nozzles.

Bl.12 1-B13-BE Shell #2 fong. seam BA 92 90 Obstructions presented by at 160' N12 instrumentation nozzle.

Bl.11 1-B13-AC Shell #2 to shell #3 BA 91 100 Obstructions presented by the four cire. veld N12 instrumentation nozzles on

)

shell #2.

l Bl.12 1-B13-BG Shell 33 long. seam BA 70 75 Obstructions presented by N4 feedvater i

at 79*

and N6 RHR/LPCI nozzles.

Bl.12 1-B13-BJ Shell #3 long. seam BA 69 68 Obstructions presented by at 199*

N13 instrumentation and N4 feedvater nozzles.

Bl.12 1-B13-BK Shell 83 long. seam BA 88 100 Perpendicular examination obstructed by at 319' N4 feedvater nozzle. Complete parallel scan performed.

l JL Perpendicular scan

//

Parallel scan Refer to drawings ISI-B13-001, 002, and 005 through 009.

~.

~.-

o PERRY NUCLEAR POBER PLANT UNIT 1 PAGE 2 0F 9 RELIEF REQUEST NO. IR-OOl SYSTEM: Reactor Pressure Vessel PERCE!EACE CODE COMPLETE ITDI NO.

    • ELD I.D.

DESCRIPTION CATEGORY

_L

//

BASIS FOR RELIEF B1.11 1-B13-AD Shell 33 to shell 84 BA 99 97 Parallel scan could not be performed cire. veld for approximately 30" along taper between shell #3 and shell 34.

Bl.12 1-B13-BN Shell 34 long. seam BA 64 69 Obstruction presented by N3 main steam at 48' nozzle and mechanical limits of scanner.

Bl.12 1-B13-BP Shell 84 long. seam BA 85 88 Perpendicular examination obstructed by at 168*

N16 vibration instrumentation nozzle, N14 instrumentation nozzle and mechanical limits of scanner. Parallel examination obstructed by N14 and mechanical limits of scanner.

Bl.12 1-D13-BR Shell #4 long. seam BA 89 86 Obstructions presented by N3 nain steam at 2R8' nozzle and mechanical limits of scanner.

B3.90 1-B13-NIA-KA N1 nozzle to shell BD 89 46

  • Scan path obstructed by nozzle geometry veld and mechanical limits of scanner.

B3.100 1-B13-NIA-IR N1 nozzle inner BD 92 N/A Shell side examination limited by taper radius area between shell 31 and shell t2.

B3.90 1-B13-NIB-KA N1 nozzle to shell BD 83 10

  • Scan path obstructed by nozzle geometry veld and mechanical limits of scanner.

B3.100 1-B13-N18-IR N1 nozzle inner BD 92 N/A Shell side examination limited by taper radius area between shell #1 and shell #2.

B3.90 1-B13-N2A-KA N2 nozzle to shell BD 65 36

  • Scan path obstructed by nozzle geometry veld biovall doors and mechanical limits of scanner.

Perpendicular scan

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline,

a 0

PERRY NUCLEAR POSER PLANT UNIT 1 PAGE 3 0F 9 RELIEF REQUEST NO. IR-001 SYSTEM: Reactor Pressure Vessel j

PERCENTAGE CODE COMPLETE l

ITEM NO.

VELD I.D.

DESCRIPTION CATEGORY

.t

//

BASIS FOR RELIEF B3.100 1-B13-N2A-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper radiu area between shell #1 and shell #2.

B5.10 1-B13-N2A-F.B N2 nozzle to BF 55 75 Scan path obstructed by nozzle geometry safe end veld and permanent vessel track at 20' Az.

B3.90 1-B13-N2B-FJs N2 nczzle to shell BD 86 49

  • Scan path obstructed b-nozzle geometry veld and mechanical limits of scanner.

B3.100 1-B13-N2B-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper radies area between shell il and shell #2.

B5.10 1-B13-N2B-KB N2 nozzle to EF 74 87 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

B3.90 1-B13-N2C-KA N2 nozzle to shell BD 86 74

  • Scan path obstructed by nozzle veld geometry, N9 jet pump instrumentation nozzle and mechanical limits of scanner.

B3.100 1-B13-N2C-IR N2 nozzle inner BD 86 N/A Shell side examination limited by taper radius area between shell il and shell #2 and N9 jet pump instrumentation nozz?e.

1 B5.10 1-B13-N2C-KB N2 nozzle to BF 22 75 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

B3.90 1-B13-N2D-KA N2 nozzle to shell BD 74 46

  • Scan path obstructed by nozzle veld geometry, N9 jet pump instrumentation nozzle, permanent vessel tracks at 110' and 135' Az., and mechanical limits of ses.uner.

1-Perpendicular scan el Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline.

O PERRY NUCLEAR POBER PLANT UNIT 1 PAGE 4 0F 9 c

RELIEF REQUEST NO. IR-001 SYSTEM: Reactor Pressure Vessel PERCENTAGE CODE COMPLETE ITEM NO.

VELD I.D.

DESCRIPTION CATEGORY

//

BASIS FOR RF'lc.t' B3.100 1-B13-N2D-IR N2 nozzle inner BD 86 N/A Shell side examination limited by taper rai:us area between shell #1 and shell #2 and N9 jet pump instrumentation nozzle.

B5.10 1-B13-N2D-KB N2 nozzle to BF 47 100 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

B3.90 1-B13-N2E-KA N2 nozzle to shell BD 73 67

  • Scan path obstructed by nozzle veld geometry, permanent vessel track at 135' Az., and mechanical limits of scanner.

B3.100 1-B13-N2E-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper j

radius area between shell #1 and shell 32.

1 B5.10 1-B13-N2E-KB N2 nozzle to BF 15 88 Scan path obstructed by nozzle safe end veld geometry.

B3.90 1-B13-N2F-KA N2 nozzle to shell BD 87 37

  • Scan path obstructed by nozzle l

veld geometry, permanent vessel track at 200* Az., and mechanical limits of scanner.

B3.100 1-B13-N2F-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper

]

radius area between shell il and shell 12.

i l

35.10 1-B13-N2F-KB N2 nozzle to BF 12 85 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

B3.90 1-B13-N2C-KA N2 nozzle to shell BD 83 37

  • Scan path obstructed by nozzle geometry i

veld and mechanical limits of scanner.

j B3.100 1-B13-N2G-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper l

radius area between shell #1 and shell #2.

i

-L Perpendicular scan

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline.

4

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PERRY NUCLEAR POL'ER PLANT UNIT 1 PAGE 5 0F 9 RELIEF REQUEST NO. IR-001 SYSTEM: React.or Pressure Vessel PERCENTAGE i

CODE COMPLETE ITEM NO.

L' ELD I.D.

DESCRIPTION CATEGORT 1

BASIS FOR RELIEF B5.10 1-B13-N2C-KB N2 nozzle to BF 24 97 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

a D3.90 1-B13-N2H-KA N2 nozzle to shell ED 89 37

  • Scan path obstructed by nozzle veld geometry, N9 jet pump instrumentation nozzle and mechanical limits of scanner.

B3.100 1-B13-N2H-IR N2 nozzle inner BD 86 N/A Shell side examination limited by taper radius area between shell il and shell #2 and jet pump instrumentation nozzle.

B5.10 1-B13-N2H-KB N2 nozzle to BF 57 97 Scan path obstructed by nozzle geometry safe end veld and OD veld contour.

B3.90 1-B13-N2J-KA N2 nozzle to shell BD 88 53

  • Scan path obstructed by nozzle veld geometry, N9 je* pump instrumentation nozzle and mechanical limits of scanner.

83.100 1-B13-N2J-IR N2 nozzle inner BD 86 N/A Shell side examination limited by taper radius area between shell #1 and shell #2 and jet pump instrumentation nozzle.

l 35.10 1-B13-N2J-KB N2 nozzle to BF 83 88 Scan path obstructed by nozzle safe end veld geometry.

B3.90 1-B13-N2K-KA N2 nozzle to shell BD 86 46

  • Scan path obstructed by nozzle veld geometry, permanent vessel track at 340* Az., and mechanical limits of scanner.

B3.100 1-B13-N2T-IR N2 nozzle inner BD 88 N/A Shell side examination limited by taper radius area between shell il and shell #2.

1 Perpendicular scan

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline.

s o

PERRY NUCLEAR POUER PLANI UNIT 1 PAGE 6 0F 9 J

RELIEF REQUEST NO. YR-001 SYSTEM: Reactor Pressure Vessel 1

I, i

PERCENTAGE CODE COMPLETE ITEM NO.

VELD I.D.

DESCRIPTION CATEGORY

_1_

//

BASIS FOR RELIEF l

)

85.10 1-B13-N2K-KB N2 nozzle to BF 74 88 Scan path obstructed by nozzle j

safe end veld geometry.

B3.90 1-B13-N4A-KA N4 nozzle to shell BD 97 32

  • Scan path obstructed by nozzle veld geometry.

B3.100 1-B13-N4A-IR N4 nozzle inner BD 96 N/A Shell side examination limited by radius area N13. instrumentation nozzle at 15' Az.

5 B5.10 1-B13-N4A-KB N4 nozzle to BF 87 100 Scan path obstructed by nozzle safe end veld geometry.

i B3.90 1-B13-N4B-KA N4 nozzle to shell BD 99 59

  • Scan path obstructed by nozzle j

veld geometry.

l B5.10 1-B13-N4B-KB N4 nozzle to BF 77 98 Scan path obstructed by nozzle safe end veld geometry.

83.90 1-B13-N4C-KA N4 nozzle to shell BD 93 32

  • Scan path obstructed by nozzle veld geometry.

B3.100 1-B13-N4C-IR N4 nozzle inner BD 96 N/A Shell side examination limited by radius area N13 instrumentation nozzle at 165' Az.

B5.10 1-B13-N4C-KB N4 nozzle to BF 83 98 Scan path obstructed by nozzle safe end veld geometry.

i B3.90 1-B13-N4D-KA N4 nozzle to shell BD 83 32

  • Scan path obstructed by nozzle geometry veld and permanent vessel track at 200* Az.

B3.100 1-B13-N4D-IR N4 nozzle inner BD 96 N/A Shell side examination limited by radius area N13 instrumentation nozzle at 195* Az.

4 B5.10 1-B13-N4D-KB N4 nozzle to DF 83 93 Scan path obstructed by nozzle i

safe end veld geometry.

j

.l.

Perped culaz scan 1

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline.

1

_ _ =--

. _ = _ _

l PEERT NUCLEAR P00ER PLANT UNIT 1 PAGE 7 OF 9 RELIEF PEQUEST NO. IR-001 l

STA"TEM: Reactor Pressure Vessel PERCENTAGE CODE C0hrLETE ITEM NO.

VELD I.D.

DESCRIPTION CATEGORY L

//

EASIS FOR RELIEF B3.90 1-B13-N4E-KA N4 nozzle to shell BD 98 59

  • Scan path obstructed by nozzle veld geometry.

I B5.10 1-B13-N4E-KB A4 nozzle to BF 80 98 Sean path obstructed by nozzle i

safe end veld geometry.

i B3.90 1-B13-N4F-KA N4 nozzle to shell BD 97

$9

  • Scan pcth obstructed by nozzle i

veld geometry.

B3.100 1-B13-N4F-IR N4 nozzle inner BD 96 N/A Shell side examination limited by radius area N13 instrumentation razzle st 345' Az.

1 B5.10 1-B13-N4F-KB N4 nozzle to BF 79 73 Scan path obstructed by nozzle safe end veld geometry and OD veld contour.

B3.90 1-B13-NSA-KA N5 nozzle to shell BD 98 61

  • Scan path obstructed by nozzle veld geometry.

B5.10 1-B13-NSA-KB N5 nozzle to BF 86 100 Scan path obstructed by safe end safe end veld transition taper.

B3.90 1-B13-NSB-KA N5 nozzle to shell BD 98 29

  • Scan path obstructed by nozzle veld geometry.

h5.10 1-B13-N58-KB N5 nozzle to BF 86 100 Scan path obstructed by safe end safe end veld transition taper.

83.90 1-B13-N6A-KA W6 nozzle to shell BD 95 56

  • Scan path obstructed by nozzle veld geometry.

35.10 1-B13-N6A-KB N6 nozzle to BF 91 100 Scan path obstructed by nazzle safe end veld geometry and safe end transition taper.

B2.90 1-B13-N6B-KA N6 no:zle to shell BD 93 70

  • Scan path obstructed by nozzle veld geometry.

i Perpenoicular scan

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centarline.

PZitR7 NLCLEAR P07ER PfANT UNIT 1 PAGE 8 0F 9 RELIEF REQUEST NO. IR-001 S1 STEM: Reactor Pressure Vessel PERCENTAGE CODE COMPLETE

    • ELD I.D.

DFSCRIPTION CATEGORT

_L

//

BASIS FOR RELIEF ITEM NO.

B5.10 1-B13-N6B-KB N6 nozzle to BF 93 74 Scan path obstructed by nozzle safe end veld geometry, safe end transition taper and OD veld contour.

B3.90 1-B13-N6C-KA N6 nozzle to shell BD 95 56

  • Scan path obstructed by nozzle j

veld geometry.

r B5.10 1-B13-N6C-KB N6 nozzle to BF 95 82 Scan path obstructed by nozzle safe end veld geometry, safe end transition and OD veld contour.

B1.40 1-B13-AG Top head to top BA 50 50 Scan path restricted on top head side head flange veld only (Drawing ISI-B13-23).

Bl.21 1-B13-AH Top head dollar plate BA 96 100 Scan path obstructed by four lifting to side plate vel,8 lugs at 0*, 90', 180', and 270' Az.

B3.90 1-B13-N7-KA N7 head spare nozzle BD 89 100

  • Scan path obstructed by N8 head spray to top head veld nozzle.

B3.100 1-B13-N7-IR N7 head spare nor::le BD 94 N/A Shell side examination limited by inner radius area N8 head spray nozzle.

B3.90 1-B13-N8-KA N8 head spray nozzle BD 89 100

  • Scan path obstructed by N7 head spare to shell veld nozzle.

B3.10C 1-B13-N8-IR N8 head spray nozzle BD 94 N/A Shell side examination limited by Inner radius area N7 head spare nonle.

B3.90 1-B13-N9A-KA N9 nozzle to shell BD 81 100

  • Scan path obstreseted by i

veld N2 recirculatian inlet nozzles at 90' and 120* Az.

i 2.

Perpendicular scan

//

Parallel scan Perpendicular veld examination lialted to one di.-ection toward nozzle centerline.

PERRY NUCLEAR POVER PLA;rr UNIT 1 PAGE 9 0F 9 RELIEF REQUEsi' 130. IR-001 SYSTEM: Reactor Pressure Vessel PERCENTAGE C00E COMPLETE ITEM NO.

VELD I.D.

DESCRIPTION CATECORT

.1.

//

BASIS FOR RELIEF B3.100 1-B13-N9A-IR N9 nozzle inner BD 96 N/A Shell side examination limited by radius area N2 recirculation inlet nozzles at 90*

and 120* Az.

i B3.90 1-B13-N9B-KA N9 nozzle to shell BD 81 100

  • Scan path obstructed by veld N2 recirculation inlet nozzles at 270*

and 300* Az.

B3.100 1-B13-N9B-IR N9 nozzle inner BD 96 N/A Shell side examination limited by radits area N2 recirculation inlet nozzles at 270*

and 300* Az.

B4.11 1-B13-N15-KA NIS nozzle to Botton BD 0

0 Obstruction presented by CRD tube Head bundle (Draving ISI-B13-004).

Bl.22 1-B13-DG Bottom Head Center BA 29 29 Obstruction presented by CRD tube Plate to Side Plates, bundle and skirt knuckle.

270* Side Bl.22 1-B13-DH Botton Head Center BA 29 29 Obstruction presented by CRD tube l

Plate to Side Plates, bundle and skirt knuckle.

90* Side

.L Perpendicular scan

//

Parallel scan Perpendicular veld examination limited to one direction toward nozzle centerline.

O Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IIR-002 3

)

I. Identification of Components Class 1, Category B-G-1. Item No. B6.180, reactor recirculation pump bolts and studs, in place (See attached table for ID numbers).

II. ASME B&PV Section XI Requirements Table IVB-2500-1 requires a 100% volumetric examination.

III. Relief Requested Relief from the required 100% volumetric examination of the reactor recirculation pump studs (attached table) is requested at the first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

IV. Basis for Relief (Refer to draving ISI-B33-034, Section 14 of ISI Plan)

Volumetric examination of the reactor recirculation pump studs was limited by the elongation measurement hole. This hole (approximately 0.5 in. dia.) extends through 80% of bolt length and interferes with UT examination of the bolt volume in the proximity of the hole. The volume affected is approximately 22% of the total required volume.

The structural integrity of the recirculation pump bolting vas demonstrated during construction by meeting the requirements of the ASHE Code Section III, and additionally by oneting the requirements of ASME Section XI during preservice inspectio'is.

Materials vere purchased and i

traced in accordance vith the sppropriate Code and NRC requirements and

{

guidelines. There vere no (

ka observed from preservice inspection.

The pressure boundazy passed the required hydrostatic test, and has 1

operated for a total of about 250 equivalent full power days between November 1987 and November 1988 without leak indication attributable to 3

the subject components.

i The major area of interest, the thread root area, received 100%

volumetric examination. Material in the examined volume is identical to the non-examined portion of the studs.

Since the construction, operating conditions and environmental conditions of the non-examined portions are identical to the examined volume, it is reasonable to apply satisfactory j

results obtained from the inservice inspections to the non-examined volume.

i Design, procurement, and operational provisions against nil ductile f ailure of the subject components remains as described in the Ferry USAR Section 5.2.3.3.

Perry Nuclear Pover Plant Unit 1 Relief Request IIR-002 In summary, because of acceptable initial bolt condition, successful code hydrotest and operating experience without related leakage indications, the capability to examine about 78% oi bolt volume on a continuing basis, and protection against brittle failure, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None 1

i 4

I E

a

PERRY NUCLEAR POVER PIMP UNIT 1 RELIEP REQUEST IIR-002 COMPONENT I.D.

DESCRIPTION 1-B33-C0018-1B REACTOR RECIRC. PUMP B STUD 1 1-B33-C001B-2B REACTOR RECIRC. PUMP B STUD 2 1-B33-C001B-3B REACTOR RECIRC. PUMP B STUD 3 1-B33-COU18-4B REACTOR RECIRC. PUMP B STUD 4 1-B33-C001B-5B REACTOR RECIRC. PUMP B STUD 5 1-B33-C001B-6B REACTOR RECIRC. PUMP B STUD 6 1-B33-C001B-7B REACTOR RECIRC. PUMP B STUD 7 1-B33-C001B-8B REACTOR RECIRC. PUMP B STUD 8 1-B33-C001B-9B REACTOR RECIRC. PUMP B STUD 9 l

1-B33-COO 1B-10B REACTOR RECIRC. PUMP B STUD 10 l

1-B33-C001B-11B REACTOR RECIRC. PUMP B STUD 11 1-B33-C0018-12B REACTOR RECIRC. PUMP B STUD 12 1-833-C001B-13B REACTOR RECIRC. PUMP B STUD 13 l

1-B33-C0018-14B REACTOR RECIRC. PUMP B STUD 14 1-B33-C001B-15B REACTOR RECIRC. PUMP B STUD 15 1-B33-C001B-16B REACTOP RECIRC. PUMP B STUD 16

_ _ = _

l i

i Ferry Nuclear Power Plant Unit 1 RgLIgP Rg0UgST $1R-003 i

i I. Identification of components Class 1, Category B-G-1, Item No. B6.40, thresca in reactor vessel flange i

(flange ligaments - see attached table and Figure ISI-B13-014 for ID l

numbers).

II. ASME BlPV Section XI Requirements Table IVB-2500-1 requires a 100% volumetric examination of the stud hole ligament area.

III. Relief Requested j

Relief from the required 100% volumetric examination is requested at the i

first and subsequent examinations as scheduled in Section 13 of the j

ISI Plan.

Because of interference with the lip of the flange seal

]

surface, examination is limited to 93% of required volume.

I j

IV. Basis for Relief l

The structural integrity of the reactor vessel flange was demonstrated during construction by meeting the requirements of the ASME Code i

Section III, and additionally by meeting the requirementu of ASME l

Section XI during preservice inspections. The Perry Unit I reactor j

vessel had no reportable indications from preservice inspection results.

i i

The pressure boundary passed the required hydrostatic tests following l

startup testing the plant has operated between 60% and 70% capacity l

factor for a total of about 250 equivalent full power days between i

November 1987 and November 1988, without detectable pressure boundary leakage.

Examinations meeting the requirements of the ASME Code Section XI will continu to be performed on 93% of the subject volume, which is subject to the same nperating and environmental conditions as the unexamined volume.

It to, therefore, reasonable to apply the results from examined volume to the non-examined volume.

I j

In addition, catastrophic reactor vessel failure is precluded by avoiding j

nil ductile temperatures at significant stress levels according to the design, surveillance and operating provisions described in the Perry USAR Sections 5.3.1 and 5.3.2 and the Technical Specifications 3/4.4.6.

I l,

Perry Nuclear Power Plant Unit 1 Relief Request IIP.-OO3 In summary, because of initial vessel condition free of reportable indications, successful code hydrotest and operating experience without leakage indications, the capability to examine most of the subject volume on a continuing basis, the capability to detect pressure boundary liakage, and protections against brittle reactor vessel failure, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examinatfor, None i

l r

.I i

f i

i

Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IIR-004 I. Identification of Components Class 1, Category B-J (Item numbers in attached table), piping velds 4 inches NPS and greater.

II. ASHE B&PV Section XI Requirements Table IVB-2500-1 requires 100% surface and volumetric examination.

III. Relief Requested Relief is requested from the required volumetric examination because of partial inaccessibility of the veld and required volume, at the first and subsequent examinations as scheduled Section 13 of the ISI Plan.

IV. Basit for Relief The structural integrity of the piping pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section III, and tdditionally by meeting the requirements of ASME Section XI during preservice inspections. The subject velds vere examined in accordance with the appropriate Code requirements, veld techniques and velders were qualified in accordance with Code requirements, and materials were purchased and traced in accordance with the appropriate Code ard NRC requirements and guidelines. There vere no reportable indications during preservice inspection.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power days between November 1987 and November 1988 vithout leakage indication attributable to the subject velds.

In addition to partial inspection of the subject velds, complete examinations meeting the requirements of the ASHE Code Section XI are performed on velds of similar configurations which utilize the same veld techniques, procedures and materials. The examined velds are subject to the same operating and environmental conditions as the partially examined velds, t

since the construction, operating conditions and environmental conditions of the non-examined portion of the velds are identical to the examined l

portions, it is reasonable to apply satisfactory results from examined to the non-examined portions.

Design, procurement and operational provisions against nil ductile l

f ailure of the subject velds remain as described in the Perry USAR.

l l

Perry Nuclear Power Plant Unit 1 Relief Request IIR-004 In summary, because of acceptable initial condition, successful code hydrotest and operating experience without related leakage indications, the capability to examine most of the subject veld volumes on a continuing basis, the capability to detect pressure boundary leakage, and protection against brittle failure, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None l

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l PERRY NUCLEAR POVER PLANT UNIT 1 PAGE 1 0F 1 RELIEF REQUEST NO. IR-004 ITEM NO.

VELD I.D.

SYSTEM */D"G. NO.

DESCRIPTION NATURE OF OBSTRUCTION EST. % COMPLETE l

B9.11 1-B21-0025 MS/ISI-B21-001 Contour Nozzle to Geometry Perpendicular 50%

Flange 89.12 1-B21-01.~ 2'J MS/ISI-B21-001 26" Elbow Seas, Branch Connection Perpendicular &

Upstream Parallel 95%

B9.11 1-B21-0133 MS/ISI-B21-001 Contour Nozzle to Geometry Perpendicular 50%

Flange B9.11 1-E12-0406 RHR/ISI-E12-007 12" Pipe to 7alve Structural Perpendicular 50%,

Interference Parallel 75%

B9.11 1-E12-0880 RHR/ISI-E12-018 12" Process Pipe Containment Penatration Perpendf.cular 80%

to Elbov

& Weld Geonctry B9.11 1-E22-0012 HPCS/ISI-E22-002 12" Elbov to Joint Geometry Perpendicular 95%

Penetration B9.12 1-B33-0027U1 RR/ISI-B33-001 16" Pipe Seam Lug Perpendicular &

Parallel 92%

B9.11 1-B33-0062

't/ISI-B33-002 22" Nozzle to Pipe Geometry Parallel 75%

  • MS

- Main Steam RER = Residual Feat Removal HPCS - High Pressure Core Spray RR - Reactor Recirculation

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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST SIR-005 I. Identification of Components l

Class 1, Category B-J, Item B9.ll, piping velds 4 inches NPS and greater (see attached table for I.D. numbers).

II. ASME B&PV Section XI %equirements j

Table IVB-2500-1 requires 100% surface and volumetric examination.

l i

i III. Relief Requested i

i Relief is requested from the required volumetric examination, at the i

first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

[

IV. Basis for Relief l

q Ultrasonic examinations conducted on velds in the recirculation loops which vere inlaid and overlaid with corrosion resistant cladding required

[

specialized techniques.

Typical techniques identified in Appendix III of Section XI proved to be ineffective.

1 To overcome the metallurgical properties impeding conventional shear vave ultrasonic transmission, refracted longitudinal wave examinations were employed. The acoustic properties of refracted longitudinal wave propagation limit the technique to 1/2 vee path. The Code required j

volume necessitates a full vee path through the veld and required volume.

I Therefore, when access to a butt veld was limited to one side only due to 1

t component geometry (e.g. pipe to valve) the perpendicular examination is considered to be only 50% complete.

During construction, the subject velds vere examined in accordance with the appropriate Code requirements, veld techniques and velders were qualified in accordance vith Code requirements, and materials were purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines.

In addition, there vere no reportable indications during preservice inspections.

The pressure boundary passed the required hydrostatic test, and has operated for a total or about 250 equivalent full power days between November 1987 and November 1988 vithout leakage indication attributable to the subject velds.

Since the construction, operating conditions and endronmental conditions of the non-examined portion of the velds are identical to the examined portions, it is reasonable to apply satisfactory results from examined to the non-examined portions.

I Perry Nuclear Power Plant Unit 1 Relief Request IIR-005 In summary, because of acceptable initial condition, successful code hydrotest and operating experience without related leakage indications, and the capability to examine half of the subject veld volume on a continuing basis, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None

i PERRY NUCLEAR POWER FLANT UNIT 1 PAGE 1 0F 2 RELIEF REQUEST NO. IR-005 REACTOR RECIRC.

VELD I.D.

DRAVING NUMBER DESCRIPTION NATURE OF OBSTRUCTION EST. % COMPLETE 1-B33-0027 ISI-B33-001 16" Cap to Pipe Geometry Perpendicular 95%

1-B33-0038 ISI-B33-001 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0043 ISI-B33-001 12" Pipe to Nozzle Geonetry Perpendicular 50%

1-B33-0049 ISI-B33-001 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0054 151-B33- 001 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0056 ISI-B33-001 16" x 12" Sweepelst Geonetry Perpendicular 50%

to 12" Pipe 1-B33-0059 ISI-B33-001 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0074 ISI-B33-002 22" Elbow to Pump Geonetry Perpendicular 50%

C001B 1-B33-0076 ISI-833-002 24" Pipe to Pump Geometry verpendicular 50%

C001B 1-B33-0081 ISI-B33-002 24" Valve F060B Geometry Perpendicular 50%

to Pipe 1-B33-0088 ISI-B33-002 24" Pipe to Geometry Perpendicular 50%

24 x 16" Cross 1-B33-0097 ISI-833-002 16" x 12" Sweepolet Geonetry Perpendicular 50%

to 12" Pipe 1-B33-0100 ISI-B33-002 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0105 ISI-B33-002 12" Pipe to Nozzle Geometry Perpendicular 50%

1-B33-0111 ISI-B33-002 12" Pipe to Nozzle Geometry Perpendicular 50%

l PERRY NUCLEAR POVER PLANT UNIT 1 PAGE 2 0F 2 RELIEP REQUEST NO. IR-005 REACTOR RECIRC.

VELD I.D.

DRAVING NUMBER DESCF70N NATURE OF OBSTRUCTION EST. % COMPLETE 1-B33-0116 ISI-B33-002 12" Pipe to Nozzle C(onetry Perpendicular 50%

1-B33-0118 ISI-833-002 16* x 12" Sweepolet Geometry Perpendicular 50%

to 12" Pipe 1-B33-0121 ISI-B33-002 12" Pipe to Nozzle Geometry Perpendicular 50%

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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST GIR-006 l

l 3

I. Identification of Components 2

L 4

Class 1. Category B-J, Item B9.12 (piping velds 4 inches NPS and j

greater), Veld 1-B33-0027U1 in reactor recirculation system (drawing ISI-B33-001).

II. ASME B&PV Section XI Requirements l

Table IVB-2500-1 requires 100% surface and volumetric examination.

1 i

III. Relief Requested Relief is tea m ted from the required surface examinations, at the first 1

and su'squent examinations as scheduled in Section 13 of the ISI Plan, j

to allow examination of only 90% of the required surface due to a pipe lug which prevents contact with 10% of the veld surface.

[

t IV. Basis for Relief j

i The ntructural integrity of the piping pressure boundary was demonstrated i

during construction by meeting the requirements of the ASME Code f

i Section III, and additionally by meeting the requirements of ASME j

Section XI during preservice inepections. The subject velds were i

examined in accordance with the appropriate Code requirements, veld l

techniques and velders were qualified in accordance with Code j

l requirements, and materials were purchased and traced la accordance with the appropriate Code and NRC requirements and guidelines. There were no i

reportable indications during preservice inspections.

j The pressure boundary prssed the required hydrostatic test, and has I

.l operated for a total of about 250 equivalent full power days between November 1987 and November 1988, without leakage indication attributable j

to the subject velds.

1 In addition to partial examination of the subject velds, complete l

examinations meeting the requirements of the ASME Code Section XI are performed on velds of similar configurations which utilize the same veld i

techniques, procedures and e terials. The examined velds are subject to I

the same operating and environmental conditions as the partially l

1 examined velds, f

i i

i Since the construction, operating conditions and environmental conditions

[

of the non-examined portion of the velds are identical to the examined portions, it is reasonable to apply satisfactory results from examined to the non-examined portions.

t I

.i Design, procurement and operational provisions against nil ductile

(

failure of the subject velds remain as dascribed in the Perry USAR.

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Perry Nuclear Power Plant Unit 1 Relief Request IIR-006

summary, because of acceptable initial conditions, successful code hydrotast and operating experience without related leakage indications, the capability to examine most of the subject veld surface on a continuing basis, the capability to detect pressure boundary leakage, and protection against brittle failure, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None 6

o Perry Nuclear Pover Plant Unit 1 RELIEF REQUEST IIR-007 I. Identification __of components Class 1, Category B-K-1 Item No. B10.10 integrally velded support attachments for piping (See attached table for ID numbers).

II. ASHE B&PV Section XI Requirements Table IVB-2500-1 requires a 100% surface examination (volumetric is not applicable.)

III. Relief Requested Relief is requested from the required 100% surfsce examination of the penetration to process pipe attachment velds due to inaccessibility of the veld face within the ID of the penetration.

50% of the required surface is accessible and vill be examined at the first and subsequent inspections scheduled in Section 13 of the ISI Plan.

IV. Basit. for Relief The structural integrity of the piping pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section III.

The subjtet velds vere examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and materials vere purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines.

Examinations meeting the requirements of the ASME Code Section XI were performed on the accessible face of the attachment veld with acceptable results during preservice inspection.

Penetration attachment velds within the high energy break exclusion region of piping systems were ultrasonically examined from the OD surface of the penetration.

Although not performed specifically to supplement the limited surface examinations, these examinations do provide additional assurance of structutal integrity.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full pover days between November 1987 and November 1988.

Since the construction, operating conditions and environmental conditions of the non-examined pertion of the velds ara identical to the examined portions, it is reasonable to apply satisfactory results from examined to the non-exaained portions.

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Perry Nuclear Power Plant Unit 1 j

Relief Request SIR-007 1

Design, procurement and operational provisions against nil ductile 4

failure of the subject velds remain as described in the Perry USAR.

7 In summary, because of acceptable initial condition, successful code hydrotest and operating experience, the capability to examine half of the subject veld surface on a c:r.tjuulng basis, and prote tion against brittle failure, it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None.

PERRY NUCLEAR POWER PLANP IMIT 1 RELIEF REQUEST 91R-007 COMPONENT I.D.

SYSTEM */DVG. NO.

1-E12-P411-VA RHR/ISI-E12-017 1-E12-P421-VA RHR/ISI-E12-001 1-E12-PRB2035-VA RHR/ISI-E12-018 1-E12-PRB2036-VA RHR/ISI-E12-013 1-E12-PRB2044-VA RHR/ISI-E12-007 1-E21-P112-VA LPCS/ISI-E21-003 1-E21-PRB3046-VA LPCS/ISI-E21-003 1-E22-P410-VA HPCS/ISI-E22-002 1-E22-PRB3052-VA HPCS/ISI-E22-002 1-E51-P123-VA RCIC/ISI-E51-003

    • 1-E51-P422-VA RCIC/ISI-E51-001
    • 1-N27-P121-VA FV/ISI-N27-001
    • 1-N27-P414-VA FV/ISI-N27-002
    • 1-G33-P131-VA RVCU/ISI-G33-001
    • 1-N22-P423-VA MS/ISI-N22-001
    • 1-821-P122-VA MS/ISI-B21-001
    • 1-521-P124-VA MS/ISI-B21-001
    • 1-B21-P415-VA MS/ISI-821-002
  • RNR

=

LPCS = Low Pressure Core Spray HPCS = High Pressure Core Spray ACIC = Reactor Core Isolation Cooling Feedvater FV a

RVCU = Reactor Vater Cleanup Main Steam MS

    • Received augmented ultrasonic examination as part of high energy break exclusion region.

Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IIR-008 I. Identification of Components Class 1, Category B-H-1, Item number B12.40, valve body velds (see attached table for veld ID numbers).

II. ASME B&PV Section XI Requirements Table IVB-2500-1 requires 1004 volumetric examination.

III. Relief Requested Relief is requested from the required 100% volumetric examinations because part geometry and code plate obstructions limit examination of required volume, at the first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

IV. Ba, sis for Relief The structural integrity of the valve pressure boundary was demonstrated durin7 construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections. The subject velds were exe. mined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and materials vere purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines. There vere no reportable indications during preservice inspections.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power days between November 1987 and November 1988, without leakage indication attributable to the subject velds.

Since the construction, operating conditions and environmental conditions of the non-examined portions of the velds are identical to the examined portions, it is reasonable to apply satisfactory results to the non-examined portions.

Design, procurement and operational provisions against nil ductile f ailure of the subject velds remain as described in the Perry USAR.

In summary, because of acceptable initial condition, successful code hydrotest and operating experience without related leakage indications, the capability to examine about 90% of the veld volume on a continuing basis, the capability to detect pressure boundary leakage (USAR 5.2.5),

and protection against brittle failure, it is concluded that there is no significant impact on tha overall level of plant quality and safety.

Perry Nuclear Power Plant Unit 1 Relief Request IIR-008 V. Alternate Examination None l

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PERRY NUCLEAR POVER PLANT UNIT 1 PAGE 1 0F 1 RELIEF REQUEST NO. IR-008 VELD I.D.

SYSTEM */DVG. NO.

DESCRIPTION NATURE OF OBSTRUCTION EST. % COMPLETE 1-E12-F019 SEAM RHR/13I-E12-028 6" Forged Check Geometry / Code Plate Perpendicular 92%

Vlv. Body Veld 1-E12-F04?A SEAM RHR/ISI-E12-029 12" Forged Gate Geometry / Code Plate Perpendicular 90%

Viv. Body veld 1-E21-F005 SEAM LPCS/ISI-E21-005 12" Fotged Gate Geometry / Code Plate Perpendicular 90%

Viv. Body Veld 1-E22-F036 SEAM HPCS/ISI-E22-006 12" Forged Cate Geometr// Code Plate Perpendicular 90%

l Viv. Body Veld 1-E51-F064 SEAM RCIC/ISI-E31-005 10" Forged Cate Geometry / Code Plate Perpendicular 93%

Viv. Body Veld 1-E51-F013 SEAM RCIC/ISI-E51-006 6" Forged Gate Geometry / Code Plate Perpendicular 94%

viv. Body Veld 1-G33-F004 SEAM RVCU/ISI-G33-007 6" Forged Gate Georaetry/ Code Plate Perpendicular 39%

Viv. Body Veld 1-G33-F100 SEAM RVCU/ISI.G33-005 4" Forged Cate Geometry / Code Plate Perpendiculae 92%

Viv. Body Veld

i Perry Nuclear fover Plant Unit 1 i

j RELIEP REQUEST GIR-009 I

I. Identification of Components Class 1, Category B-0, Item B14.10, flange velds in control rod drive i

housing (See attached table for I.D. numbers and drawing ISI-B13-016).

II. ASME B&PV Section XI Requirements

[

Table IVB-2500-1 requires a 100% surface or volumetric examination.

III. Relief Requested Relief is requested from the required 100% surface examination because of partial inaccessibility of the examination area due to control line interferences, at the first and subsequent examinations as scheduled in i

Section 13 of the ISI Plan. Approximately 85% of subject veld surf ace vill be subjected to a dye penetrant examination.

l IV. Basis for Relief The structural integrity of the subject velds was demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections. The subject velds were examined in accordance with the appropriate Code requirements, veld techniques and velders were qualified in accordance with Code requirements, and materials were purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines. The subject velds had no reportable indications during preservice inspection.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power days between November 1987 and November 1988 without leakage indication attributable to the subject velds.

Portions of velds examined are subject to the same operating and environmental conditions as the unexamined portions. Approximately 85%

of veld surface vill continue to be examined.

It is, therefore, reasonable to apply the results from examined veld portions to the unexamined portions.

In summary, because of acceptabic initial veld condition, successful code hydrotest and operating experience vithout leakage indications, the capability to examine most veld curface on a continuing basis, and the capability to detect pressure boundary leakage, it is concluded that there is no significant impact on the overall level of plant quality and safety.

o Perry Nucicar Power Plant Unit 1 Relief Request IIR-009 V. Alternate Examination None i

PERRY NUCLEAR POVER PIJMr UNIT 1 REl.IEF REQUEST 81R-009 VELD I.D.

VELD I.D.

1-B13-02/23-FV 1-B13-30/59-FV 1-B13-02/27-FV 1-B13-34/03-FV 1-B13-02/31-FV 1-B13-34/59-FV 1-B13-02/35-FU 1-B13-38/03-FV 1-b13-02/39 '/V 1-B13-38/59-TV 1-B13-06/15-TV 1-B13-46/07-FV i-B13-06/47-FV 1-B13-46/55-FV 1-B13-10/11-FV 1-B13-50/11-FV 1-B13-10/51-FV 1-B13-50/51-TV 1-B13-14/07-FV 1-B13-54/15-FV 1-B13-14/55-TV 1-B13-54/47-FV 1-B13-22/03-TV 1-B13-58/23-FV 1-B13-22/59-TV 1-B13-58/27-FV 1-B13-26/03-FV 1-B13-58/31-FV 1-B13-26/59-FV 1-B13-58/35-FV 1-B13-30/03-FV 1-B13-58/39-FV

Perry Nuclear Power Plant Unit 1 RELIEP REQUEST IIR-010 I. Identification of Components Class 2, Category C-A, Item No. C1.20, pressure retaining shall cylinder-to-head veld number 1-E12-B001A-003 in Residual lleat Removal heat exchanger IB001A (Draving ISI-E12-021).

II. ASME B&PV Section XI Requirements Table IVC-2500-1 requires a 100% volumetric examination of the veld.

III. Relief Requested Relief is requested from the required volumetric examinations because of seismic lug interferences only about 43% of veld volume (perpendicular scan) can be examined, at the first and subsequent examinations as scheduled in Section 13 if the ISI Plan.

IV. Basis for Relief The structural integrity of the subject pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections.

The veld vas examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and materials were purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines. There vere no reportable indications during preservice inspection.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power daya between November 1987 and November 1988, without leakage indication attributable to the subject veld.

Since the construction, operating conditions and environmental conditions of the non-examined portions of the velds are identical to the examined portions, it is reasonable to apply satisfactory results to the non-examined portions.

In summary, because of acceptaole initial veld condition, successful code hydrotest and operating experience without related leakage indications, the capability to examine about 40% of veld volume on a continuing basis, and the capability to detect pressure boundary leakage, it is concluded that there is no significan'. impact on the overall 4evel of plant quality and safety.

V. Alternate Examination None

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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST GIR-011 I. Identification of Ctmponents Class 2. Category C-B, Item No. C2.21, inlet nozzle veld number 1-E12-B001A-004 ja the residual heat removal heat exchanger shell head (Drawing ISI-E12 021).

II. ASME B&PV Sect'.on XI Requirements Table IVC-2500-1. Item No. C2.20 requires a 100% surface and volumetric examination of the veld.

III. Relief Ret,uested Relief is requested f rom the required 100% volumetric examination of the subject veld, because instrumentation line obstructions limit examiration to 95% of required volume, at the first end subsequent examinations as scheduled in Section 13 of the ISI Plan.

IV. Bar,is for Relief The structural integrity of the subject pressure boundary was j

demonstrated during construction by meeting the requirements of the ASHE

,/ Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections. The veld was examined in

['accordancewiththeappropriateCoderequirements,veldtachniquesand velders were qualified in accordance with Code requirements, and f

/

materials were purchased and traced in accordance with the apptcpriate

/

Code and NRC requirements an/. guidelines.

There vere no reportable

/

indications during preservice inspection.

/

The pressure boundary passed the required hydrostatic test, and has

/

operated for a total of about 250 equivalent full power days between

/

November 1987 and November 1988, without leakage indication attributable to the subject velds.

Since the construction, operating conditions and environmental conditions of the non-examined portion of the veld are identical to the examined portion (95%), it is reasonable to apply the satisfactory results to the non-examined portion.

In summary, because of acceptable initial condition, successful code hydrotest and operating experience without related leakage indications, the capability to examine about 95% of veld volume on a continuing basis, and the capability to detect pressure boundary leakage. it is concluded that there is no significant impact on the overall level of plant quality and safety.

V. Alternate Examination None r

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r Perry Nucl?ar Power plant Unit 1 RELIEF REQUEST lIR-012 I. Identification of Components Class 2 Category C-C (Item and component numbers in attached table),

integrally velded support attachments.

II. ASME B&PV Section XI Requirements Table IVC-2500-1 requires a 100% surface examination.

III. Relief Requested Relief is requested from the required surface examinations because of partial or complete inaccessibility of the examination area, at the first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

IV., Basis for Relief The structural integrity of the piping pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections. The subject velds vere examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and raterials vere purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines. There vere no reportable indirations during preservice inspections.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power days between November 1987 and November 1988, without leakage indication attributable to the subject velds.

Complete examinations meeting the requirements of the ASME Code Section XI will be performed on velds of similar configurations which utilized essentially similar veld techniques, procedures and materials.

The examined velds are subject to the same operating and environmental conditions as the partially examined velds.

1 Since the construction, operating conditions end environmental conditions of the non-examined portion of the velds are identical to the examined portions, it is reasonable to apply satisfactory results from examined to l

the non-examined portions.

(

l In summary, because of acceptable initial veld condition, successful code

)

hydrotest and operating experience without related leakage indications, and the capability to examine most or similar veld surface on a l

continuing basis, it is concluded that there is no significant impact on the overall level of plant quality and safety.

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Perry Nuclear Power Plant Unit 1 Relief Request IIR-012 V. Alternate Examination None i

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PERRY NUCLEAR POVER PLANT UNIT 1 PACE 1 0F 2 RELIET REQUEST NO. IR-012 ITEM NO.

COMPONENT I.D SYSTEM */DVG. NO.

DESCRIPTION NATURE OF OBSTRUCTION E.',T.

% COMPLETE C3.10 1-E12-B001A-SLI RHR/ISI-E12-025 SEISMIC LUG GEOMETRY SURFACE 95%

C3.10 1-E12-B001A-SL2 RHR/ISI-E12-025 SEISMIC LUG CEOMETRT SURFACE 95%

C3.10 1-E12-B001A-SL3 RER/ISI-E12-025 SEISMIC LUG GEOMETRY SUPSACE 95%

C3.10 1-E12-B001A-SL4 RHR/ISI-E12-025 SEISMIC LUG CEOMETRY SURFACE 95%

C3.20 1-E22-8087-VA HPCS/ISI-E22-004 VELDED ATTACHMDir HANGER / CODE BAND AND SURFACE 85%

DRAIN LINE INTER-FERENCES C3.20 1-E12-H173-VA RHR/ISI-E12-001 VELDED ATTACHMEhT HANGER CLAMP INTER-SURFACE 90%

FERENCE C3.20 1-E12-H289 VA RHR/ISI-E12-002 UELDED ATTACHMENT GEOMETRY SURFACE 60%

C3.20 1-E12-H290-VA RHR/ISI-E12-C02 VELDED ATTACHMENT GEOMETRY SURFACE 60%

C3.20 1-E12-H359-VA RHR/ISI-E12-009 VEGED ATTACHMENT GEOMETRT SURFACE 50%

C3.20 1-E12-8360 VA RHR/ISI-E12-009 VEIEED ATTACHMDff GE0 METRY SURFACE 50%

C3.20 1-E12-H368 VA RER/ISI-E12-009 VELDED ATTACHMENT GEOMETRY SURFACE 60%

C3.20 1-E12-H369-VA RHR/ISI-E12-009 VELDED ATTACHMENT GEOMETRT SURFACE 60%

C3.20 1-N11-H221-VA MS/ISI-B21-002 VELDE0 ATT/13fMENT SEISMIC RESTRAINT SURFACE 0%

BLOCKS ACCESS C3.20 1-N11-H222-VA MS/ISI-B21-002 VELDED ATTACHMENT SEISMIC RESTRAINT SURFACE 0%

BLOCKS ACCESS

  • MS

- Main Steam RHR - Residual Heat Removal HPCS - High Pressure Core Spray F"J

- Feedvater

PERRY NUCLEAR POVER PIANT UNIT 1 PACE 2 0F 2 RELIEF REGUEST NO. IR-012 ITEM NO.

COMPOND.T I.D.

SYSTEM */DUC. NO.

DESCRIPTION NATURE OF OBSTRUCTION EST. % COMPLETE C3.20 1-N11-H223 VA MS/ISI-B21-001 VELDED ATTACHMENT SEISMIC RESTRAINT SURFACE 0%

BLOCKS ACCESS t

C3.20 1-N11-H224-VA MS/ISI-521-001 VELDED ATTACHMENT SEISMIC RESTRAINT SURFACE 0%

BLOCKS ACCESS C3.20 1-N27-8031-VA FV/ISI-N27-002 VELDED ATTACHMENT SEISMIC RETIRAINT SURFACE 0%

BLOCKS ACCESS C3.20 1-N27-H032-VA FV/ISI-N27-001 VELDED ATTACHMENT SEISMIC RESTRAINT SURFACE 0%

BLOCKS ACCESS

  • MS

. Main Steam RHR - Residual Heat Removal HPCS High Pressure Core Spray FV

. Feedvater

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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IIR-013 I. Identification of Components Class 1. Category C-G, Item C6.10, pump casing velds (See attached table for ID numbers).

l II. ASME B&PV Section XI Requirements t

Table IVC-2500-1 requires a 100% surface examination.

III. Relief Requested Relief from the required surface examinations is requested because the pump barrel is belov floor level making the velds inaccessible, at the first and subsequent examinations as scheduled in Section 13 of the ISI Plan.

If any of the subject pumps are disassembled for repair or j

maintenance, with the pump barrel removed, accessible velds vill be inspected at that time.

IV. Basis for Relief The structural integrity of the subject pressure boundaries was demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections.

The subject velds vere i

examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code I

tequirements, and materials were purchased and traced in accordance with j

the appropriate Code and NRC requirements and guidelines.

The subject j

velds had no reportable indications during preservice inspections.

[

The pressure boundary passed the required hydrostatic test, and has i

oper.ted for a total of about 250 equivalent full power days between i

November 1987 and November 1988, without leakage indication attributable I

to the subject velds.

I In summary, because of acceptable initial veld condition, successful code d

hydrotest and operating experience without relateo leakage indication, it is concluded that there is no significant lepact on the overall level t

of plant quality and safety.

l V. Alternate Examination L

4 None I

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o PERRY NUCLEAR POVER PLANT UNIT 1 PACE 1 0F 2 RELIEF REQUEST NO. IR-013 VELD I.D.

STSTEM*/DVG. NO.

DESCRIPTION 1-E22-C001-001 HPCS/ISI-E22-005 Pump Head to Barrel Shell Veld 1-E22-C001-002 HPCS/ISI-E22-005 Pump Shell to Shell Veld 1-E22-C001-003 EPCS/ISI-E22-005 Pump Shell to Shell Veld 1-E22-C001-904 HPCS/ISI-E22-005 Pump Shell to Flange Veld 1-E22-C001-013 HPC5/ISI-E22-005 Pump Barrel tongseam 1-E22-C001-014 BPCS/ISI-E22-005 Pump Barrel Longseam 1-E22-C001-015 HPCS/ISI-E22-005 Pump Barrel Longseam 1-E21-C001-001 LPCS/ISI-E21-004 Pump Head to Barrel Shell Veld 1-E21-C001-002 LPCS/ISI-E21-004 Pump Shell to Shell Veld 1-E21-C001-003 LPCS/ISI-E21-004 Pump Shell to Flange Veld i

1-E21-C001-012 LPCS/ISI-E21-004 Pump Shell to Shell Veld 1-E21-C001-013 LPCS/ISI-E21-004 Pump Barrel Longseam 1-E21-C001-014 LPCS/ISI-E21-004 Pump Barrel Longseam 1-E21-C001-015 LPCS/ISI-E21-004 Pump Barrel longseam 1-E12-C002A-001 RHR/ISI-E12-026 Pump Head to Barrel Shell Veld 1-E12-C002A-002 RHR/ISI-E12-026 Pump Shell to Shell Veld 1-E12-C002A-003 RHR/ISI-E12-026 Pump Shell to Flange Veld

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PERRY NUCLEAR POVER PLANT UNIT 1 PACE 2 OF 2 RELIEF REQUEST NO. IR-013 UELD I.D.

STSTEM*/DVC. NO.

DESCRIPTION 1-E12-C002A-012 RHR/ISI-E12-026 Pump Shell to Shell Veld 1-E12-C002A-013 RHR/ISI-E12-026 Pump Barrel Longseam 1-E12-C002A-014 RHR/ISI-E12-026 Pump Barrel Longseam 1-E12-C002A-015 RHR/ISI-E12-026 Pump Barrel Longseam 1-E12-C002C-001 RHR/ISI-E12-027 Pump Head to Barrel Shell Veld 1-E12-C002C-002 RER/ISI-E12-027 Pump Shell to Shell Veld 1-E12-C002C-003 RHR/ISI-E12-027 Pump Shell to Flange Veld 1-E12-C002C-012 RHR/ISI-E12-027 Pump Shell to Shell Veld 1-E12-C002C-013 RHR/ISI-E12-027 Pump Barrel Longseam 1-E12-C002C-014 RER/ISI-E12-027 Pump Barrel Longseam 1-E12-C002C-015 RER/ISI-E12-027 Pump Barrel longseam

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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST l!R-014 I. Iden*ification of Components Class 2, Category C-G, Item No. C6.20, 6" high pressure core spray check valve, body veld number 1-E22-F003 SEAM (0 raving Isl-E22-007).

II. ASME B&pV Section XI Requirements Table IVC-2500-1 requires a 100% surface examinstion.

III. Relief Requested Relief from the required surface examination is requested because a code plate psrtially obstructs about 5% of the examination area, at the first and subsequent examinations scheduled in Section 13 of the ISI plan.

IV. Basis for Relief l

The structural integrity of the valve pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section III, and additionally by meeting the requirements of ASME Section XI during preservice inspections. The subject veld was examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and materials vere purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines. There vere no reportable indications during preservice inspection.

The pressure boundary passed the required hydrostatic test, and hes operated for a total of about 250 equivalent full power days between November 1987 and November 1988.

Since the construction, operating conditions and environmental conditions of the non-examined portion of the veld are identical to the examined portion, it is reasonable to apply satisfactory results to the non-examined portion.

Design, procurement and operational provisions against nil duettle failure of the subject velds remain as described in the perry USAR.

In summary, because of acceptable initial condition, successful code hydrotest and operating experience, the capability to examine about 95%

of the veld surface on a continuing basis, and protection against brittle failure, it is concluded that there is no significant impact on the i

overall level of plant quality and safety.

{

V. Alternate Examination i

None

o Perry Nuclear Power Plant Unit 1 Relief kequest SIR-015 I. Mentification of Compon g Class 2, Category C-C, Item No. C3.20 integrally velded support l

attachments for piping (See attached table for ID numbers).

j II. ASME B&PV Section XI Requirements Table IVC-2500 1 requires a 100% surface examination.

III. Rellef Requested i

Relief is requested from the required 100% surface examination of the penetration to process pipv attachment velds due to inaccessibility of the veld face within the ID of the penetration.

50% of the required surface is accessible and will be examined at the first and subsequent I

inspections scheduled in Section 13 of the ISI Plan.

IV. Basis for Relief The structural integrity of the piping pressure boundary was demonstrated during construction by meeting the requirements of the ASME Code Section I;I. The subject velds vere examined in accordance with the appropriate Code requirements, veld techniques and velders vere qualified in accordance with Code requirements, and materials vere purchased and traced in accordance with the appropriate Code and NRC requirements and guidelines.

Examinations meeting the requirements of the ASME Code Section XI were performed on the eccessible face of the attachment veld with acceptable results during preservice inspection.

Penetration at achment velds within the high energy break exclusion region of piping systems vere ultrasonteally examined from the OD surface of the penetration.

Although not performed specifically to supplement the limited surface examinations, these examinations do provide additional assurance of structural integrity.

The pressure boundary passed the required hydrostatic test, and has operated for a total of about 250 equivalent full power days between November 1987 and November 1988.

Since the construction, operating conditions and environmental conditions of the non-examined portion of the velds are identical to the examined portions, it is reasonable to apply satisfactory resultr from examined to the non-examined portions.

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Perry Nuclear Pover Plant Unit 1 Relief Request IIR-015 Design, procurement and operational provisions against nil ductile f ailure of the subject velds remain as described in the Perry USAR.

In sur. mary, because of acceptable initial condition, successful code hydrotest and operating experience, the capability to examine half of the subject veld surf ace on a continuing basis, ar.d protection against brittle failure, it is concluded that there is no significant impact on the overall level of plant quality and safety V. Alternate Examination None.

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PP.RRY NUCLEAR POVER Pl. ANT UNIT 1 RELIEP REQUEST IIR-015 COMPONENT I.D.

SYSTEM *

    • 1G33-P132-VA RVCU

'E12-P105-VA RHR 1E12-P407-VA RHP 1E21-P113-VA LPCI 1E21-P412-VA LPCI

    • Received augmented ultrasonic examination as part of high energy break exclusion region.
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