ML20236T845
| ML20236T845 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/24/1998 |
| From: | Wirtz C CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20236T831 | List: |
| References | |
| PROC-980624, NUDOCS 9807290076 | |
| Download: ML20236T845 (65) | |
Text
. _ _ - _ _ _ _. - _.
The Cleveland Electric Illuminating Company
,i Ferry Nuclear Power Plant Document Transmittal
' Manual: Inservice Examination Program (ISEP)
ISEP Vol. 1-Control Number 4' 7'4 '
. Revision-Temporary I
Number Change No.
Insert Remove
' 3-3
'Pages (1,11) (vii, viii)
Pages (1, li) (vii, viii)
(1-1,1-2) (1-21 thru l-24 )
(1-1,1-2) (1-21 thru 1-24 )
.j 1-70g thru 1-70j (1-71,1-72) 1-70g thru 1-70j (1-71,1-72)
(1-123,1-124) (1-129,1-130)
(1-123,1-124) (1-129,1-130)
(1-135,1-136) (1-185,1-186)
(1-135,1-136) (1-185,1-186)
(1-269,1-270) (1-339 thru (1-269,1-270) (1-339 thru 342) (1-347,1-348)- (1-363, 342) (1-347,1-348) (1-363, 364) (1-369 thru l-376) 364) (1-369 thru l-376) j (1-381 thru l-388)
(1-381 thru 1-388)
(1-393,1-394) 1-407 thru (1-393,1-394) 1-407 thru 1-407j, 1-408 1-407j, 1-408 Please sign-below acknowledging receipt and inclusion into the appropriate volume.
Signature Date Title
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.If you'no 1onger desire-to maintain a controlled copy of this. document, please discard your-copy of ISEP Vol. 1 & Vol. 2 and sign below.
Signature Date i.
ll-Title Return to:
Perry Nuclear Power Plant Attn: Records Coordinator, A210 P. O. Box 97 Perry, Ohio 44081 I
1 9807290076 990715 i
PDR -ADOCK 05000440
-G PDR
{
1 i
ISEP - Vol. 1 I
Paga: 1 Rev.: 3 The Cleveland Electric Illuminating Company PERRY OPERATIONS MANUAL PNPP Inservice Examination Program
?
d%
No.
TITLE:
INSERVICE EXAMINATION PROGRAM l
REVISION:
3 EFFECTIVE DATE:
7-18-95
,O V
PREPARED:
Charles Wirtz 4-5-95
/
Date j
l 1
EFFECTIVE PIC's PIC Type of Effective No.
Change Date 1
Intent 1-24-97 2
Intent 9-8-97 3
Intent g,
,q g 4
4 i
J
e ISEP - Vol. 1 Page:
ii Inservice Examination Program ISEP
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, 'I
~ ~ ~
Table of Contents N $Nj%
Title Page i
- v1 C" n
1.0 INTRODUCTION
1-1 1-1 1.1 Purpose 1-1 1.2 Scope 1-1 1.3 Compliance 1-3 1.4 Glossary 1.5 System Classifications 1-6 1.6 Examination Methods 1-7 1.7 Instructions and Procedures 1-9 l
1.8 Personnel Qualifications 1-9 1.9 Evaluation Criteria (Characterization Process and Disposition) 1-9 1-12 1.10 Repair Cycle 1-12 1.11 Replacement Cycle 1.12 Scheduling Criteria 1-13 1.13 Reporting (ISI Summary Reports and Relief Requests) 1-15 2.0 IWB (CLASS 1) EXAMINATIONS 1-16 1-16
'2.1 Exemptions f
2.2 Examination Selection Process 1-17 2.3 Additional Examinations 1-23 2.4 Successive Examinations 1-23 2.5 Relief Requests 1-23 2.6 Inservice Examination Table 1-71 3.0 IWC (CLASS 2) EXAMINATIONS 1-143 1-143 3.1 Exemptions 3.2 Examination Selection Process 1-144 3.3 Additional Examinations 1-148 3.4 Successive Examinations 1-148 3.5 Relief Requests 1-148 3.6 Inservice Examination Table 1-171 4.0 IND (CLASS 3) EnuTuamTous 1-218 1-218 4.1 Exemptions 4.2 Examination Selection Process' 1-218 4.3 Additional Examinations 1-220 4.4 Successive Examinations 1-220 1-220 4.5 Relief Requests 1-229 4.6 Inservice Examination Table e
0 z
- e
- 4..
n Tl ?
'ISEP - Vol. 1
~
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Pegn: vii-Rev.: 3 Change History (Cont.)'
,, j a l.f ' '
'PIC'Numberi
.1
]
i g
Summary "of ' Change " (Cont. ) :
l
- 12. Add notes. to Sections 2.6 and' 3.6 that clarify that the' Magnetic Particle L
and, Liquid Penetrant examination methods are interchangeablefor carbon
' steal welds."
'132 nschedule changes made for convenience ? (e.g., Substituting a'n. accessible I'
' weld that'was'not scheduled ~forone that was scheduled, but found'to have.
an? interference).
14 ! Made; numerous editorial-changes to correct typos or for clarification.
n 1,
PIC Number:
2 Affected Pages':
1,?vi,-vil, 1-128,~1-254, 1-327,
.1-332,11-332a,-1-333,114 36, 1-336b, 3
' 1-348 Summary'of Change:
L1.-
. Change recirculation' pump sha't exams;to reflect shaft' replacement in RF04' f
N..
(Pages11-333 and 1-348).
li.> { Editorial corr'ctions to items'shown as scheduled'for Period-3 but'should e
n have indicated not'.scheduledf(NS) (Pages.1-128, 1-254, and 1-327).
'"3..
incorporate CEI Commitment B01134L(Pages.1-332a and 1-336b).
-4 r. Cor, rect discrepancy. between ISEP. and USAR for jet pump hold down beam
~
l examination schedulingLthat was identified by PIF. 97-0789.
i[
'S
Change'CoreI hroud H-3, H-4,-H-6A, and H-7 exams to notischeduled (NS)
S as they_ are being: deferred to RF07, which will-be in the second ten. year interval.' -
r-
- PIC ' Number: J 3 LAffected Pages:
1, vii, viii,'l-2, 1-21,'l-23, 1-70g, 1-70h, 1-701, 1-70j,~1-70k, 1-701, 1-70m,-1-70n, 1-72,.1-123,:1-124, 1-130,.1-135,.1-185,:1-269sm1-339,-
1-341i 1-342, 1-348i 1-363, 1-370, 1-372, 1-373, 1-376,?1-381,-1-382,-
[
1-384, 1-385,=1-387,.1-393, 1-407a, 1-407b, 1-407c, 1-407d,,1-407e, 1-407f, 1-407g, 1-407h, 1-4071, 1-407j (Summary of Chance:
.1.
Add refeconoe to code cases N-498-1,.N-522, N-524, and N-544.
2.
Revision of Table 2.2.6-1 that reflects re-categorization of valve I
1G33-r101?as a. group IX. valve and changes it to not scheduled (NS) under y
' Category B-M-1.
f 3.
" Incorporate,- by reference and exhibition, new relief requests IR-030, I
J IR-031, PT-004, ' PT-005, PT-006 and PT-007.
.l t
l4;- Change all the. Examination Item Bl.11' (i.e., RPV+ shell circumferential welds):to'not scheduled (NS) in accordance with approved relief request
'IR-030.
1
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- - _ - _ _ _ - - _ = _ _ _
i ISEP - Vol. 1 Peg 3: viii Rev.:
3 Change History (Cont.)
PIC Number:
3 Summary of Chance (Cont.):
5.
Revise to reflect changes in scheduling made for dose concerns and/or access restrictions encountered in RFO6.
1E12-0131 was substituted for 1E12-0130 and 1E32-0202 was substituted for 1E32-0242.
6.
Revised to reflect snubber modificat'.ons (i.e., replacements with another type) that were made in accordance riith DCPs 96-5052, 96-5053, 96-5054, 96-5055, 96-5057 and 96-5058, FCRs 24093 through 24097, and PIF 97-1338.
.7.
Add a note for the examina, tion of IB13-SHSB (i.e., the Shroud Head Stud Bo'.s) that reflects no examination in RF06 as the bolts were replaced in accordance with DCP 91-35 and no longer require augmented examination.
8.
Change the augmented examination requirement for IB13-AE-SUR from MT and period 3 to UT and period 1 as the UT performed in period 1 fulfilled the augmented requirements.
b.
Revise the description for the first digit of the snubber categorization codes to reflect all the types of snubbers, currently installed in the plant.
O G
9 4
0
l INSERVICE EXAMINATION PROGRAM O
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1.0 INTRODUCTION
I
~ 1.1 PurDose This program provides methods of verification of the structural integrity p
of. components subject to the examination requirements delineated in the ASME Boiler and Pressure Vessel Code,Section XI,' Rules for Inservice
~ Inspection.
1.2 Scope-W e Inservice Examination Program (ISEP) delineates the components subject to non-destructive and visual examination during the first inspection interval at the Perry P.lant, Unit 1.
Components requiring examination are vessels, pumps, valves, piping systems and their supports. Of the i;
components requiring exams, certain parts such as welds, bolting, core support structures, and interior surfaces may also' require examination.
This program is subject to change. Changes will be affected via request for relief from examination or miscellaneous document revisions which may I
be submitted during the inspection interval.
The program will be updated every 10 years or when necessey to reflect optional OWNER upgrades or r:gulatory commitments.
.D
% e Inservice Testing Program and the associated testing req 6irements for pumps, valves, and snubber functional tests are delineated in site administrative procedures and are not referenced within this document.
1.3 Compliance h e date for issuance of the low power operating license for PNPP Unit 1 was March 18, 1986. He facility operating license number is NPF-45.
h is license restricted the plant to power levels not to exceed.5 percent full power or 178 megawatts. thermal. As of November 13, 1986, the NRC issued a full power operating license for Unit 1.
The facility's. full
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power' license number is NPF-58 with an expiration date'of March 18, 2026.
In accordance with 10CFR50.55a(g)(4)(i), the inservice examination of l
1-components subject to examination during the initial inspection interval shall comply with the' requirements of the code referenced in 10CFR50.55a(b) on the date 12 months prior to the date of issuance of the opacating license. he ee6econood code associatedirith this1 stipulation
' is the 1980 edition of the ASME Boiler and Pressure Vessel Code, section XI.
Effective on October 28,'.1985, the NRC amended the Code reference by updating to the 1983 edition of ASME B&PV Section XI including addenda through the Summer 1983. Adoption of this amendment permits the use of improved methods for inservice inspection and has been elected as the basis for the Inservice Examination Program Plan for Unit 1.
- l 1-1 Rev. 3
_._._._________2__
The ISIP complies with the requirements of Section XI of the ASME.B6PV Code, 1983 Edition including Addenda through the Summer 1983, hereina'fter l
referred to asSection XI.
I 1
Modifications to section XI requirements include, but are not limited to the following:
l a.
Code Case N-235, " Ultrasonic Calibration Checks per Section V,Section XI, Division 1."
b.
Code Case N-356, " Certification Period for Level III NDE Personnel,Section XI, Division 1, 2 and 3."
j c.
Code Case N-408-2, " Alternative Rules for Examination of Class 2 Piping,Section XI, Division 1."
d.
Code Case N-fl6-1, " Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2 and 3,Section XI, Division 1."
e.
Code Case N-429-1, " Alternative Rules for Ultrasonic Instrument-Calibration,Section XI, Division 1."
f.
Code Case N-435-1, " Alternative Requirements for Vessels with Wall Thickness 2 in. or less,Section XI, Division 1."
Code Case N-448, " Qualification of VT-2 and VT-3 Visual Examinat' ion g.
Personnel,Section XI, Division 1."
h.
Code Case N-457, " Qualification Specimen Notch Location for Ultrasonic Examination of Bolts and Studs,Section XI, Division 1."
i.
Code Case N-460, " Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1."
j.
Code Case N-461, " Alternative Rules for Piping Calibration Block Thickness,Section XI, Division 1."
k.
Code Case N-491, " Alternative Rules for Examinations of Class 1, 2, 3 and MC Component Supports of Light Water Cooled Power Plants,Section XI, Division 1."
1.
Code Case N-498-1, " Alternative Rules for 10-Year Hp'rostatic Pressure Testing for Class 1, 2 and 3 Systems,Section XI, Division 1."
m.
Code Care N-522, " Pressure Testing of Containment Penetration Piping,Section XI, Division 1."
n.
Code Case N-524, " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping,Section XI, Division 1."
o.
Code Case N-546, " Alternative Requirements for Qualification of VT-2 Examination Personnel,Section XI, Division 1."
p.
Applicable NUREG's and Regulatory Guides as addressed in Sectron 1.8 of the USAR and including NUREG-0313, NUREG-0619 and Reg.
Guide 1.150.
q.
Requests for Relief from T.xamination r, ranted by the V3NRC.
r.
Augmented Examinations due to site commitments.
The commencement of the initiel inspection interval for Unit 1 coincided with the date of en*Aercial operation. Perry Unit 1 was declared as being in commercial operation at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on November 18, 1987.
At the completion of'the initial in3pection interval (120 months following start of commercial operation) the Inservice Examination Program will be updated to the subsequent edition and addenda of the Code as adopted by the regulatory authority.
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2.3. Additional Examinations which reveals L
Examinations performed during an inspection (outage)
. indications exceeding acceptance standards will be extended to include
-, additional c'omponents within the same examination category, approximately equal to the number of components examined initially during the inspection period l-Additional examinations which reveal a defect require the' performance of-thel remaining interval scheduled examinations for similar components within the examination category. Additional criteria include:
1..
'Where examinations were limited to one. loop or branch run of a similar configuration the additional examinations shall be extended I
to the second loop or branch run and approximately equal to the
- number of components initially examined.
2.
If the additional examinations of the second loop or branch run reveals a defect the remaining number of loops or branch runs, performing a similar-function, shall also be examined.
i 2.4 Successive Examinations Successive' examinations are performed on components reported as having flaws'or relevant conditions and are evaluated as acceptable for continued i
service. These examinations will be scheduled per Section XI as follows:
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k-Components having flaw indications evaluated as acceptable for continued s
. service, will be scheduled for re-examination during the next three' I
inspection periods.
Flaw indications which remain essentially unchanged for three successive inspection periods will revert to the original schedule of successive inspections.
2.5" Relief Requests When compliance to Code examination requirements is not achievable, relief
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- from examinations is requested.- Inservice Relief Requests (IR) which have been filed with the NRC for components subject to the examination requirements'of ASME Section XI, Article IWB are:
IR No.
IR-001 R-1 IR-016 - (Deleted)
IR-002 R-0 IR-017 - (Deleted)
IR-003 R-0 IR-018 R-1 IR-004 R-1 IR-024 R-0 IR-005 R-1 IR-025 R-0 IR-006 R-0 IR-028 R-0 l
-IR-007 R-0 IR-029 R-0 IR-008 R-0 IR-030 R-0 l
(
IR-009 R-0 IR-031 R-0 C-3 1-23 Rev. 3 L
____.-.___.____.______-._-_.-..__--__u_
Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #IR-001, Rev. 1 I.
Identification of Components System:
Reactor Pressure Vessel, Class I A.
Category: B-A, Pressure Retaining Welds Component
Description:
(See attached table for component identification' numbers) 1.
Head welds (Item No. Bl.21, Bl.22) 2.
Head to flange (Item No. Bl.40)
B.
Category: B-D, Full Penetration Welds of Nozzles in Vessels Component
Description:
(See attached table for component identification numbers) 1.
Nozzle to shell welds (Item No'. B3.90) 2.
Nozzle inside radius section (Item No. B3.100)
C.
Category: B-F, Pressure Retaining Dissimilar Metal Welds Component
Description:
(See attached table for component identification numbers) 1.
Nozzle to safe end welds (Item No. B5.10)
II. ASME B&PV Section XI Requirements ASME Code requires 100% volumetric examination of welds and required volume.
III. Relief Requested Relief requested from 100% volumetric examination (See attached table for percent completion of each specific component) at the first and subsequent e==4mtions as licheduled in Section 2.5 W the ISEP.
l IV. Basis for Relief h e structural integrity of the reactor pressure vessel welds 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. 'All welds were examined in 9
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l-24 Rev. 3
I
,, Sheet. 1 of 6 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. IR-030 I.
Identification of Components-Class 1, Category B-A, Item No. Bl.11 reactor pressure vessel pressure retaining circumferential shell welds as identified in the following table:
Lower Head to Number 1 uk 1813,AB Number 1 Shell Ring to Number 2 Shell Ring Circumferential Seam 1B13-AC Number 2 Shell Ring to humber 3 Shell Ring Circumferential Seam 1B13-AD Number 3 Shell Ring to Nember 4 Shell Ring Circumferential Seam Note:
This represents all of PN?P's'Bl.11 welds.
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II. -ASME' Boiler & Pressure vessel Code Section XI and
.10CFR50. 55a (a) (6) (ii) (A) (2) Requirements
-In accordance with Table'IWB-2500-1 of both the 1983 Edition through Summer 1983 Addenda of Section XI (PNPP's current' inservice inspection Os Code of record) and the 1989 Edition of Section XI (as specified in 10CFR50.55a (g) (6) (ii) (A) (2), all reacter pressure vessel pressure retaining circumferential shell welds axe to be volumetrically examined, for essentially 100% of'the weld length, by the end of the first Inspection Interval. The last refueling outage for PNPP's first Inspection Interval is RFO6, scheduled to start on September 12, 1997.
III. Relief Requested-
' Pursuant t010CFR50.55a(s) (3) (i), and consistent with the information contained in Information Notice 97-63, " Status of NRC Staff's Review of
~
BWRVIP-05," relief is requested from performing volumetric examination of r
the reactor pressure vessel pressure retaining circumferential shell welds
_by the end of the_first Inspection Interval. Alternatively, the examinations will be performed, following two additional operating cycles, in RF08.
IV.-
Basis for Relief
^
The basis for this.requ'est for inspection relief is documented in the report "BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BNRVIP-05)," that was transmitted to the NRC in September 1995. The BWRVIP-05 report provides the technical basis for eliminating inspection of Boiling Water Reactor (BWR) RPV circumferent'ial shell welds.- The BWRVIP-05' report concludes that the probability of failure of the BWR RPV circumferential shell welds is O-orders of magnitude lower than that of the axial shell welds. The NRC staff has conducted an independent risk-informed assessment of the analysis contained in'BNRVIP-05. This assessment also concluded that the C-3 1-70g Rev. 3 l
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RELIEF BEQUEST No IR-030 I
probability of failure of the BWR RPV circumferential welds is orders of magnitude lower than that of the axial'shell welds. Additionally, the NRC assessment demonstrated that inspection,of BWR RPV circumferential welds does not measurably affect the probability of failure. Therefore, the NRC evaluation' appears to support the conclusions of BWRVIP-05.
'This' independent NRC assessment used the EAVOR code to perform a g
'probabilistic fracture mechanics (PFM) analysis to estimate RPV failure probabilities.. Three key assumptions in the PFM analysis are: the neutron fluence was that estimated to be end-of-license mean fluence, the chemistry values are mean values based on vessel types, and the potential for beyond design basis events is considered.
- Although BWRVIP-05 provides the technical basis supporting the relief request, the following information is provided to show the c'onservatisms of the NRC analysis for PNPP. In the case of PNPP, there are no circumferential welds within the beltline region. As such, the limiting circumferential welds would be 1B13-AB, which is 6" below the bottom of active fuel, and IB13-AC,-which is 16" above the top of active fuel. Of O-these, it has been determined that 1B13-AB would be the 1Laiting circumferential weld within the vessel (i.e., relative to RTag).
For
' plants.with RPVs fabricated by Chicago Bridge & Iron (CB&I), _ as is. PNPP's, the mean end-of-license neutron. fluence.used in the NRC PFH analysis was 0.19E+19n/ca'.. However, the highest overall fluence - (i.e., peak fluence
'at the vessel ID surface) anticipated at the end of the requested relief 2
period is only 1.53E+18 n/cm for PNPP. Furthermore, the highest fluence
. anticipated at the end of the requested relief period for circumferential 2
welds'1B13-AB and IB13-AC is only 5.8E+17 n/cm and'9.03E+17 n/cm2 respectively. Thus, the fluence effect on embrittlement is much lower, in fact it is negligible for the'circumferential welds, and the NRC anal'ysis I
described at an August 8, 1997, meeting with the industry is very conservative for PNPP in this regard. Therefore, there is significant conservatism in the already low circumf,erential weld failure probabilities as related to PNPP.
Other PNPP 4tFV shell weld,information that the MRC etaff has requested is included in Table 1 of this relief request. As shown in Table 1, the calculated embrittlement shift in RTag (i.e., ARTan) at the and of the requested relief period for circumferential welds 1813-AB and 1B13-AC is 13 'F'and 21.4 *F respectively. By comparison, us_ing,the mean values for fluence and welql chemistry assumed for CB&I reactor vespels in Table 7-5 of. Enclosure 1 to the NRC independent assessment report, a ARTag of-30.16 *F would be derived. Therefore, the calculated ARTm values for the
~
'PNPP circumferential welds are less than, and thus bounded by, the
. embrittlement shift s'ssumed in the NRC's independent assessment.
Furthermore, it can be seen in Table 1 that the calculated Upper Bound RTag value at the end of the requested relief period for circumferential
^
C-3 1-70h Rev. 3
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I Sheet 3 of 6 q)
Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No, IR-030 welds 1B13-AB and IB13-AC is 6 'T and -17.1 'F respective 3y.
For comparison, the highest Upper Bound RTapr value [i.e., " Inner Surface (RTsar + 20)* F"] shown within Tables 7-6, 7-7, 'and 7-8 of Enclosure 1 to the NRC's independent issessment report of BWRVIP-05, would be the RTun of 145.l* F shown within Table 7* 7 for 'the B&W fabricated BWR vessels.
Again, the calculated Upper' Bound RTm, values for PNPP's circumferential vessel welds are clearly bounded by the limiting RTan from Table 7-7 of the NRC independent assessment report, thus providing additional assurance that the PNPP circumferential vessel welds are also bounded by BWKVIP-05.
At the meeting on August 8, 1997, the NRC staff indicated that the potential for, and consequences of, non-design basis events not addressed in the BWRVIP-05 report should be considered.
In particular, the NRC staff stated that non-design basis cold over-pressure transients should be considered. It is highly unlikely that a BWR would experience a cold over-pressure transient.
In fact, for a BWR to experience such an event would generally require several operator errors. At the meeting of August 8, 1997, the NRC staff described several types of events that could be pr4 cursors to BWR RPV cold over-pressure transients. These were
'(}
identified as precursors because no cold over-pressure event has occurred N_,/
at a U. S. BWR. Also, at the August 8 meeting, the NRC staff identified one. actual cold over-pressure event that occurred during shutdown at a non-U. S. BWR.
Thi's event apparently included several operational errors that resulted in a maximum RPV pressure of 1150 pai with a temperature range of 79' F to 88' F.
t One of the two high pressure make-up systems is the Reactor Core Isolation Cooling (RCIC) system which is steam turbine driven.
During reactor cold shutdown conditions, no steam is available for operation of this system.
Therefore, it is not plausible for this system to contribute to an overpressurization event while the unit is in cold shutdown. The other high pressure make-up system is the High Pressure Core Spray System (HPCS). Since the reactor vessel level instruments used to close
.the HPCS injection valve on reactor vessel high water level are calibrated for hot, pressurized conditions, the instruments normally give a false high level signal during mode 4 operations which would, prevent the I
injection valve from opening on a HPCS initiation. Therefore, the L
possibility tyf 1t EPCS initiatitm tausitig 1rn trverpressuriratityn event while the unit is in cold shutdown is very small.
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Perry Nuclear Power Plant
- Unit l' RELIEF REQUEST No. In-030 One precursor event was' identified for PNPP in Table C-1 of the NRC's Independent Assessment Report for BWRVIP-05. The-event was the inadvertent _ starting of the High Pressure Core Spray System'(HPCS) diesel generstr while ist Nedy t' (Cty2d* ShutdownT dtering insintensnew 'of resetor l;
vessel level instrumentation associated with starting of the HPCS system.*
L The HPCS pump and various' valves had been placed in a secured' status prior l
to the eventi therefore, no actual injection of the high pressure system l-
.was'possible. There were no other events during cold shutdown conditions
. which involved a potential inadvertent initiation of the HPCS system.
This event did'not result,in a violation of the pressure-temperature limits since no actual initiation took place.
I PNPP classifies all RPV hydrostatic' tests as Infrequently Performed Tests i
i or Evolutions (IPTE's). - IPTE's receive special management oversight,to maintain the plant's level of safety within acceptable limits. Therefore,
.a' challenge'to the RPV from a non-design' basis cold over-pressure J
transient is highly unlikely for PNPP during the requested delay'and the probability'of'a cold over-pressure transient is considered to'be less l
than or equal to that used in the NRC analysis. described at the August 8 I
meeting..
L
~
The NRC staff has recently transmitted a Request. for AddiMonal Information-(RAI) regarding the BWRVIP-05 report to the BWR Ves'sel and I
)
that-RAI-in:the near future that will include additional information on the BWRVIP.PIM analysis, comparisons to the NRC staff PFM analysis and additional"information regarding beyond design' basis cold over-pressure I
PNPP will work with the BWRVIP to resolve the longer term issues in this area, but PNPP believes BWRVIP-05 and the NRC analysis provide sufficient basis to support approval of this relief request.
I
-It is noteworthy that preservice examinations of PNPP's RPV shell welds were performed in'accordance with the 1977 Edition, Summer 1978 Addenda of Section XI and NRC Regulatory Guide 1.150.
The exams founit that the RPV shell course plate, material contained mid-plate segregate or short-length 1.
4..
< -,4 4,. un.; that'unre h.au below rar miahh. lave throughout:the vessel.- Coverage for the axial and circumferential shell weld exams averaged greater than BM.. Tor the subject circumferential welds, all but IB13-AA, which was;a one sided exam due to the vessel skirt, were " essentially 1006 examined".
Within'th'se welds, there were 4
o
-only 8 recordable indications and no reportable indications.
i C 1 *10j Rev. 3 l
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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No IR-030 In summary, base'd on the documentation in BWRVIP-05, the risk-l'nformed independent assessment; performed by the NRC staff, and the discussio'n above, a delay of two (2) operating cycles (until the end of the eighth refueling outagwy for completion of inspections of the RP1F circumferential' shell welds is justified.
V.
Alternate Examination None.
'OU.
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' RELIEF REQUEST No. IR-030 i
Table 1"3
- j. -
Perry Unit 1 RPV Circumferential Shell Weld Information I-i Neutron' fluence' at the end of the 5.8 E+17 n/cm '
9.03 E+17 n/cm 8
2 requested relief period'(10 EFPY)'83883 l
Initial (unirradiated) reference
-20F.
-60 *F i
temperature j
1 Weld. chemistry fhetor (CF) 41.0
'54.0 Weld copper conte'nt' 0.03 %
0.04 %
Weld nickel conte,nt 0.81 4 0.97 %
i Increase in reference temperature due l
l l'
to irradiation (A RTapr)
E *I l
l 21.4 'F
!~
Margin term p *F 21.4 'F Mean adjusted reference temperature
-7 *F
-38. 6 *F (Mean ART)
~
' Upper bound adjusted reference 6 'F
-17.1 'F temperature (ART)
~
'(1).
Table-information was supplied by GE Nuclear Energy via GE letter LJT-9716, dated August 27, 1997'and assigned Technical Assignment File Number 81658.-
(2). Values in this table were calculated for 10 Effective Full Power Years of operation which is approximately where PNPP will be at the end of the requested relief period (i.e., RFOS).
-(3)
Fluence values were determined using equation 4-2 of report GG-ND 415011795-01, "therry Unit 14LPV Surveillance Materials Testing and Analysis", which was submitted to the NRC in accordance with 10 CFR 50 Appendix H vin' letter PY-CEI/NRR-2129L, dated February 18, 1997.
O
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Perry Nuclear Power Plant Unit 1 t.
RELIEF REQUEST No. IR-031
' Code Case N-524 i
I.
Identification of Components Ch 1.,
'%tT y B-4 and Clace $, Categorizer C-P-1 and C-P-9, longitudinal piping welds (examination items B9.12, B9.22, C5.12, C5.22 and C5.42)
II.
ASME Boiler & Pressure Vessel Code Section XI Requirements In accordance with Table INB-2500-1, Category B-J, the extent of examination for longitudinal welds is to include at least a pipe-diameter length but not more than 12 inches of each longitudinal weld intersecting -
the circumferential welds required to be examined. Similarly, in accordance with Table IWC-2500-1, Categories C-F-1 and C-F-2, the extent.
of examination for longitudinal welds is to include a length of 2.5 times the nominal thickness at the intersecting circumferential weld.
III. Relief Requested Pursuant to 10 CFR 50.55a (a)(3) (ii), relief is requested fran performing
( ')
the full extent of examination on longitudinal welds as required by
~
Table IWB-2500-1, Category B-J and Table IWC-2500-l', Categories C-F-1 and C-F-2.
Alternative requirements for the extent of examination are proposed in Section V below.
IV.
Basis for Relief The structural integrity of the longitudinal welds 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 exams.
Furthermore, through Perry's fifth refueling outage, all inservice examinations of longitudinal welds were performed to the full extent required.. There were no reportable indications during the-preservice or inservice examinations.
~
h try
='==-4=a'= h a=*far=ina 4 a==ewie= mue=in=' inna of Jafety class i
piping has demonstrated that in-service flaws,are not being found in longitudinal welds. This prompted 25ME 15 subcommittee TI to write Code Ca.e N-524.
The conclusion of ASME Subcommittee XI was that examination of longseams beyond their intersection with a circumferential weld provides little or no benefit and, therefore, the extent of examination could be 1Laited to the intersecting portion of the longseam without
{
compromising the level of qualtty and safety.
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Perry Nuclear Power Plant Unit l'
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RELIEF REQUEST No. IR-031 Code Case N-524 Examination of longitudinal welds beyond their intersection with the circumferential weld involves the removal of additional insulation and, in l
some cases, the removal of hanger clamps or other appurtenances.
It is estimated that these activities are cause for at least 2 REM of exposure to workers each refueling. outage. Thus, compliance with the specific requirements results in hardships without a compensating increase in the level of quality and safety.
Although Code Case N-524 is not included in Revision 11 of Regulatory Guide.l.147, " Inservice Inspection Code Case Acceptability - ASME Section XI Division 1,"
it is listed as an accepted Code' Case in DG-1050 (Revision 12 to Regulatory Guide 1.147), which is out for public comment.
V.
Alternate Examination Perry proposes to perform inservice examination of longitudinal welds utilizing the alternative requirements delineated in Code Case N-524.
In accordance with Code Case N-524, the following shal3 apply:
[^}
(a) When only a surface examination is required, examination of
- (_,e longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of the intersecting circumferential welds.
l (b) When both surface'and volumetric examinations are required, examination of, longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of the intersecting circumferential welds provided the following requirements are met.
l (1) Where longitudinal welds are specified and locations are known (as is the case within Perry's current inservice examination boundary), examination requirements shall be met for both transverse and parallel flaws at the intersection of the weldt and for that length of longitudinal weld within the ciredaferential weld volume; Q) Ehara 1 ^=i + ndi aN maids m ee-i ei M M 1 ^>=* 4 ^a-m unknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
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I I
2.6 Inservice Examination Table O
.. h is section contains the listing of all Class 1 components subject to the examination requirements of ASME Section XI, Article IWB. The actual components scheduled for examinations are presented to manegement for
. approval 60 days prior to corunencing a scheduled refueling cutage.
- The information presented in the tables is defined below:
EXAMINATION CATEGORY - S e basis for organizing. components subject to examination.
ITEN NO. - A division within an examination category which separates the specific examination requirements.
O MARK NO. - A unique identification number assigned to each weld or component.
O COMPONENT DESCRIPTION - A brief description used to identify the weld or component.
'O EXAM METHOD - h is abbreviation identifies the unique non-destructive examination method (s) required for the weld or component examination. Se abbreviations used in this listing are as follows:
Magnetic Particle Testing (see Note)
MT Dye Penetrant Testing (see Note)
'O.
Radiography Testing-RT Visual Examination for Surface Conditions VT-1 Visual Examination for Leakage VT-2 Visual, Examination for General Conditions VT-3 Note: For carbon steel welds,.MT & PT are interchangeable.
l 0
, PERIOD SCHED. - W is column identifies the inspection period in which the weld or component is scheduled to be examined. Se period scheduled can be either 1, 2, 3, or any combination of these numbers. Normally there will be 2 refueling outages within each period. Scheduled examinations can be completed in either of the refueling outages as appropriate to facilitate other outage activities,.but must be completed by the end of the f
period. For those welds or components not scheduled for examination, the letters 'NS' will be inserted in place of an inspection period. For those components only examined when a Mt:nist 1rii. o.L 1 nquirement is imet (ex. when removed or L
~
when access is provided to normally inaccessible item by a maintenance repair, or replacement activity), the letters 'SR' will be inserted in place of an inspection period...An asterisk (s) in the schedule column denotes a scheduling i;
peculiarity which will be explained at the end of the applicable category. Welds which have been examined, but due to program changes (e.g., Revision of-the B-J Selection Basis) are not to be credited toward ASME XI completion percentages, will have parenthetical around the period scheduled.
I C-1 Page 17 of 96 1-71 Rev. 3 i
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}7.E'SnubberCategorization.
-Every snubber is given a' unique category classification.- The categoriza-tion is to allow for failure analysis and'to ensure'the random sampling g
1 application covers all types of snubbers. LThe categorization la as
]
follows:
First Digit:
Type - H) E-Systems Hydraulic,.L) Lisega-Hydraulic, M) PSA Mechanical,, P) Phoenix Hydraulic Second. Digit:
ALARA -.1) Accessible or 2) Inaccessible Third Digit::
Size-for PSA Mechanical / Phoenix Hydraulic
- Third Digit: - Size'for E-Systems Hydraulic Snubbers ~ 1) 20 KIP,'2) 30 KIP, 3) 50 KIP, 4) 70 KIP, 5)-100 KIP Third Digit:
Size forJLisega H,ydraulic Snubbers - 1) N/A,'
- 2) 3018,.3) 3038, 4) 3042, 5) 3052, 6) 3062 s 3072, 7) 3082 & 3092 Fourth' Digit System Characteristic.- 1) Inservice or
- 2) Functional' Fifth Digit:
i
.Operat ng Temperature - 1).<200*F.or 2) 2200*F Sixth Digits
. Vibration - 1) <20 mils or'2) 220 mils
'i..
'7.91 Relief Requests
<;\\msI
'When compliance to examination requirements are'not achievable, relief from examinations are requested. The table listed below identifies those Inservice ~ Relief Requests (IR) which have been filed with the NRC for snubbers.-
IR-023 R-0 Note: IR-023 was submitted and approved by NRR with reference to the Technical Specifications. With the incorporation of Improved' Technical Specifications, the'snubberfrequirements were transfered into the Operational Requirements Manual..The requirements themselves were unchanged.' Thus, IR-023, which is: exhibited herein, Estands-as it was originally submitted.
! v..
4 O
C-3
=1-363 Rev. 3 I'
q
l l
Sheet 1 cf 3 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST FIR-023 j
I.
Identification of Components All safety-related hydraulic and mechanical snubbers.
II. ASME B&PV Section XI Requirements 1
IWF-5400(b)
A representative sample
- of 10% of the total number of nonexempt (IWF-1230) snubbers whose load rating is less than 50 kips shall be tested with each inspection period.
Each representative sample shall consist of previously untested snubbers. After all nonexempt snubbers in the plant have been tested, the tests shall be repeated taking the same snubber (or their replacement) in the same sequence as in the original tests. These tests shall verify:
(1) during low velocity displacements, the specified maximum drag or free movement force will' initiate motion of the snubber rod in both tension and compression; (2) activation (restraining action) is achieved within the specified ' range of velocity or acceleration in both tension and compression; (3). snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For units specifically required not to displace under continuous load, the ability of the snubber to' withstand load without displacement shall be demonsta ted.
IWF-5400(c)
Snubbers that fail the inservice tests of (b) above shall be repaired in accordance'with IWF-4000 and retested. An additional sample of 10% of the total number of snubbers shall also be tested at that time. Additional sample testing shall be continued until all units within the sample have met the requirements of (b) above.
- A representative sample shall include snubbers from uarious locations, taking into 1:ensitteration service ana environment.
III. Relief Request Relief is requested from the required method of sampling in IWF-5400(b) and (c).
I I
(
l-364 Rev. 3
MPL NO.
HANGER - MARK NO.
G RY O
F1.3SN 1821H0059 1B21-H0059 M25221 F1.3SN 1B21H0060 IB21-H0060 M24221 F1.3SN 1B21H0063 IB21-H0063 (TANDEM)
M25221 F1.3SN 1321H0064 1B21-H0064 M26221 F1.3SN 1P31H0065 1B21-H0065 (TANDEN)
M26221 F1.3SN 1B21H0066 1B21-H0066 M26221 F1.3SN
.1B21H0068 IB21-H0068 M26221 F1.3SN 1B21H0069 1B21-H0069 (TANDEN)
M24221 F1.3SN 1B21H0071 1B21-H0071 M25221 F1.3SN 1B21H0073' 1B21-H0073 M26221 F1.3SN 1B21H0074 1B21-H0074 (TANDEN)-
M26221 F1.3SN 1B21H0075 1B21-H0075 M26221 F1.3SN 1B21H00'76 1B21-H0076 M25221 F1.3SN 1B21H0077 1B21-H0077 M26221'
- F1.3SN 1B21H0078 1B21-H0078 M25221 F1.3SN 1B21H0079 1B21-H0079 M26221 F1.3SN 1B21H0082 1B21-H0082 M25221 F1.3SN 1B21H0084 1B21-H0084 M26221 F1.3SN 1B21H0085 1B21-H0085 M26221 F1.3SN 1B21H0086 1B21-H0086 (TANDEN)
M26221 F1.3SN 1B21H0087 1B21-H0087 (TANDEN)
M26221 F1.3SN 1B21H0089 1B21-H0089 M25221 F1.3SN 1B21H0091 1B21-H0091 M25221 F1.3SN 1B21H0092 IB21-H0092 (TANDEM)
M25221 F1.3SN 1B21H0094
-1B21-H0094 M25221 F1.3SN 1B21H0095~
1821-H0095 (TANDEN)
M26221 s
F1.3SN 1B21H0096 1B21-H0096 M26221 F1.3SN 1B21H0098 1B21-H0098 (TANDEN)
M26221 F1.3SN 1B21H0100 1B21-H0100 M25221 F1.3SN 1B21H0101 1B21-H0101 M26221 F1.3SN 1B21H0102 1B21-H0102 M25221 2
F1.3SN 1B21H0103 1B21-H0103 M25221 F1.3SN 1B21H0106 1B21-H0106 (TANDEN)
M26221 F1.3SN 1B21H0107 1B21-H0107 (TANDEN)
M26221 F1.3SN 1B21H0108 1B21-H0108 M25221 F1.3SN 1B21H0112-1B21-H0112 M26221 F1.3SN IB21H0113
.1B21-H0113 M24221 F1.3SN 1B21H0114 1B21-H0114 M26221 F1.3SN 1B21H0115 IB21-H0115 M26221 F1.3SN 1821H0117 IB21-H0117 (TANDEN)
M26221 F1.3SN 1B21H0118 1B21-H0118 (TANDEN)
M24221 F1.3SN 1B21H0119 1821-H0119 (TANDEN)
M26221 F1.3SN 1B21H0122 1B21-H0122 v2&221,
F1.3SN' 1B21H0124 1B21-H0124 M26221 F1.3SN IB21H0125 1B21-H0125 M26221 l
F1.3SN 1B21H0126 1B21,H0126 M26221 F1.3SN
.1B21H0127 1B21-H0127 (TANDEN)
M26221 F1.3SN 1B21H0129 1B21-H0129 M26221 F1.3SN 1B21H0130 IB21-H0130
~
M26221 F1.3SN 1321H0133 1B21-H0133 M25221 j
O 1-369 Rev. 3 L
- =
CATEGORY ITEM MPL NO.
HANGER - MARK NO.
NO.
NO.
F1.3SN 1821H0135 1B21-H0135 (TANDEM)
M25221 F1.3SN IB21H0138 1B21-H0138 M25221 F1.3SN 1821H0139 1B21-H0139 H25221 F1.3SN 1821H0140 IB21-H0140 (TANDEM)
M26221 F1.3SN 1B21H0141 1E21-H0141 (TANDEM)
M26221 F1.3SN 1B21H0143 1B21-H0143 M26221 F1.3SN 1B21H0145 1B21-H0145 M25221 F1.3SN 1B21H0146 IB21-H0146 M24221 F1.3SN 1821H0147 1B21-H0147 M26221 F1.3SN 1B21H0148 1B21-H0148 M24221 F1.3SN 1B21H0150 1B21-H0150 (TANDEM)
M26221 F1.3SN 1B21H0151 1B21-H0151 (TANDEM)
M26221 F1.3SN 1B21H0152 IB21-H0152 H24221 F1.3SN 1B21H0153 IB21-H0153 (TANDEM)
M26221 F1.3SN 1B21H0154 1B21-H0154 (TANDEM)
M26221 F1.3SN 1821H0162 IB21-H0162 (TANDEM)
M25221 F1.3SN 1B21H0165 IB21-H0165 M25221 F1.3SN 1B21H0166 IB21-H0166 M26221 F1. 3SN.
1B21H0170 IB21-H0170 (TANDEM)
M25221 F1.3SN 1B21H0174 IB21-H0174 (TANDEM)
H25221 F1.3SN 1B21H0178 1B21-H0178 (TANDEM)
M25221 F1.3SN 2B21H0181 1B21-H0181 (TANDEM)
M26221 F1.3SN 1B21H0183 IB21-H0183 M25221 F1.3SN 1B21H0184 1821-H0184 M26221 F1.3SN 1B21H0185 IB21-H0185 M25221 F1.3SN 1B21H0187 1B21-H0187 (TANDEM)
M25221 F1.3SN 1B21H0191 IB21-H0191 M26221 F1.3SN 1B21H0222 1B21-H0222 H26221 F1.3SN 1B21H0408 1B21-H0408 M25221 F1.3SN 1B21H0410 1B21-H0410 M26221 F1.3SN 1B21H0412 IB21-H0412 H26221 F1.~3N 1B21H0421 1B21-H0421 M25221 F1.3SN 1B21H0423 1B21-H0423 M25221 F1.3SN 1B21H0427 1B21-H0427 M25221 F1.1SN 1B21H0445 IB21-H0445 L24221 l
F1.1SN 1B21H0446 1B21-H0446 (TANDEM)
P24221 F1.1SN 1B21H0447 1B21-H0447 P24221 F1.1SN 1B21H0449 1B21-H0449 L24221 E1.1SN JR23H0450 IB21.HD450
. 199991 F1.1SN 1B21H0452 1B21-H0452 P23221 T1.1SN ' '1323 0453
~12'21-10453 T24221 1B21H0456 1B21-H0456 M23211 1B21H0457 1821-H0457 M24211 F1.1SN 1B21H0458 1B21-H0458 H24221 F1.1SN 1B21H0459 1B21-H0459 M24221
'F1.1SN 1E21H0462 1B21-H0462 P24221 1B21H0465 1B21-H0465 M23211 F1.1SN 1B21H0471 IB21-H0471 P23221 F1.1SN 1B21H0472 1B21-H0472 P25221 F1.1SN 1B21H0474 1B21-H0474 M24221_
C-3 1-370 Rev. 3
___e__-_ _ _ _ _ _ _ _ _ _
MPL'NO.
HANGER - MARK HO.
CA RY 1B21H0476 IB21-H0476 M21211 I
F1.1SN 1B21H0490 1B21-H0490 P24221 F1.1SN 1B21H0491 1B21-H0491 P24221
.L 1B21H7153 IB21-F0228-H3003 M23221 I
1B21H7503 IB21-F041G-H3005 M22221
'1B21H7548.
1B21-F0478-H3008 M21221 1B21H7637 1B21-F047G-H3002 M22221 IB21H7782 1B21-F051G-H3006 M22221 F1.1SN 1B33G7064A 1B33-G006-S369A H25121 F1.1SN 1B33G70648 1B33-G006-S369B' H25121 F1.1SN 1B33G7065A.
1B33-G006-S370A H25121 F1.1SN 1B33G7065B 1833-G006-S370B-H25121 F1.1SN 1B33G7066A
-IB33-G006-S371A.
.H25121 F1.1SN 1B33G7066B 1B33-G006-S371B H25121 F1.1SN 1B33G7067A 1B33-G006-S372A H25121 F1.1SN 1B33G7067B IB33-G006-S372B H25121 F1.1SN 1B33G7068A IB33-G006-S373A' H25121 F1.1SN 1B33G7068B 1B33-G006-S373B H25121' F1.1SN 1B33G7069A 1B33-G006-S374A.
H25121 F1.1SN '1B33G7069B 1B33-G006-S374B H25121 F1.1SN 1B33G7070A IB33-G006-S375A H25121 F1.1SN 1B33G7070B 1B33-G006-S375B H25121 1B33H0007 1B33-H0007 M23221 F1.2SN 1C11H0659 1C11-H0659 M14121 1
F1.2SN 1C11H0661 1C11-H0661 M14121 O
F1.2SN ~IC11H0662 1011-H0662 M14122 F1.2SN
-1C11H0663 1C11-H0663 M14121 IC11H0664 1011-H0664 M15121 F1.2SN IC11H0666 1C11-H0666 M14121-IC11H0671 1C11-H0671 M15121 F1.2SN 1C11H0673-IC11-H0673 M14121 F1.2SN IC11H0675 1C11-H0675 M14121 4
1C11H0693 1C11-H0693 M11111 1C11H0694 1C11-H0694 M11111-IC11H3081 1C11-H3081 M13121 1C11H3085
, IC11-H3085 M13121
^
F1.2SN IC11H5013
' IC11-H5013 M14121 1
F1.2SN IC11H5014.
!1C11-H5014 M14121 l
F1.1SN 1C41H0067 1C41-H0067 M21221 F1.1SN 1C41H0109-IC41-H0109 (TANDEN)
M23221 F1.1SN IC41H0110 1C41-H0110 M21221
-IC41H3002 1C41-H3002 M13211 IC41H3035 1C41-H3035 M12211,
i F1.1SN IC41H5000 1C41-H5000 M22221 F1.1SN IC41H5001 1C41-H5001 M22221 i
F1.1SN 1C41H5002 1C41-H5002 H24221 F1.1SN IC41H5003 1C41-H5003 -
M21221 F1.1SN IC41H5005 1C41-H5005-M21221 1C41H5020 1C41-H5020 M11211 F1.1SN 1E12H0004 1E12-H0004 M26221 O
~
1-371 Rev. 3 i
l i
CATEGO W e
ITEM MPL NO.
HANGER - MARK NO.
NO.
NO.
F1.1SN 1E12H0005 1E12-H0005 M26221 F1.1SN 1E12H0006' 1E12-H0000 M26221 l
F1.1SN 1E12H0007 1E12-H0007 M26221 F1.1SN 1E12H0010 1E12-H0010 M26221 F1.1SN 1E12H0011 1E12-H0011 M26221 F1. 2 %
1E12H0012 1E12-H0012 M26221 F1.1SN 1E12H0015 1E12-H0015 M25221 F1.1SN 1E12H0016 1E12-H0016 M26221 F1.1SN 1E12H0017 1E12-H0017 M26221 F1.1SN 1E12H0018 1E12-H0018 M25221 F1.1SN 1E12H0026 1E12-H0026 M25221 F1.1SN 1E12H0030 1E12-H0030 M25221 F1.1SN 1E12H0035 1E12-H0035 M15221 F1~1SN 1E12H0036 1E12-H0036 M15221 F1.2SN 1E12H0039 1E12-H0039 M15211 F1.2SN 1E12H0045 1E12-H0045 (TANDEM)
M14211 F1.1SN 1E12H0046 1E12-H0046 M24221 F1.1SN 1E12H0047 1E12-H0047 M25221 F1.1SN 1E12H0049 1E12-H0049 M25211-F1.1SN 1E12H0051 1E12-H0051 M16211 F1.3SN 1E12H0060 1E12-H0060 (TANDr.M)
M14211 1E12H0068 1E12-H0068 (TANDEM)
M14211 1E12H0073 1E12-H0073 (TANDEM)
M15211 F1.1SN 1E12H0074 1E12-H0074 M26221 F1.2SN 1212H0104 1E12-H0104 M15211 F1.2SN 1E12H0105 1E12-H0105 M15211 F1.2SN 1E12H0106 1E12-H0106 M16211 F1.2SN 1E12H0108 1E12-H0108 M16211 F1.2SN 1E12H0109 1E12-H0109 M14211 l
F1.2SN 1E12H0110 1E12-H0110 M13211 F1.2SN 1E12H0115 1E12-H0115 M16211 F1.2SN 1E12H0116 1E12-H0116 (TANDEM)
M16211 F1.2SN 1E12M0122 1E12-H0122 (TANDEM)
M16211 F1.2SN 1E12H0124 1E12-H0124 M16211 F1.2SN 1E12H0162 1E12-H0162 M12211 F1.2SN 1E12H0164 1E12-H0164 M14211 F1.2SN 1E12H0165 1E12-H0165
' M15211 F1.2SN 1E12H0169 1E12-H0169 (TANDEM)
L15211
.L16211 F1.2SN, 1E12H0170 IE12-H0170 F1.2SN 1E12H0171 1E12-H0171 L16211 F1.2SN. 1E12H0172 1E12-H0172 M15211 F1.2SN 1E12H0180 1E12-H0180 M13211 F1.2SN 1E12H0190 1E12-H0190 M13221 F1.2SN 1E12H0192 1E12-H0192 M14221 F1.2SN 1E12H0195 1E12-H0'195 M14211 1E12H0205 1E12-H0205 M14211 F1.2SN 1E12H0211 1E12-H0211 M15221 F1.2SN 1E12H0213 1E12-H0213 M15221 F1.2SN 1E12H0234 1E12-H0234 M15211 F1.2SN 1E12H0255 1E12-H0255 M15211 C-3 1-372 Rev. 3
___m-___
(?~
.V)
ITEM MPL NO.
HANGER - MARK NO.
CATEGORY NO.
NO.
F1.2SN 1E12H0256-1E12-H0256 M15211 F1.2SN 1E12H0257 1E12-H0257 M15211 F1.2SN 1E12H0263 1E12-H0263 (TANDEM)
M15211 F1.2SN 1E12H0264 1E12-H0264.
M15211 F1.2SN 1E12H0280.
M25221-F1.2SN 1E12H0284 1E12-H0284 M25221-F1.2SN 1E12H0288 1E12-H0288 -
M15211
'F1.2SN 1E12H0289' IE12-H0289 M15211 F1.2SN 1E12H0290.
1E12-H0290 M15211 F1.2SN 1E12H0292 1E12-H0292 M15211.
F1.2SN 1E12H0293 1E12-H0293 (TANDEN)
L14211 s
F1'.2SN 1E12H0295 1E12-H0295-M16211
)
F1.2SN 1E12H0303 1E12-H0303 M14211
'l F1.2SN 1E12H0305 1E12-HQ305 M15211 F1.2SN 1E12H0309 1E12-H0309 M15211 F1.2SN 1E12H0310 1E12-H0310 M15211 F1.2SN 1E12H0313-IE12-H0313 M16211 F1.2SN 1E12H0314 1E12-H0314 M16211 F1.2SN 1E12H0315 1E12-H0315 M11211 F1.2SN-1E12H0316 1E12-H0316.
M11211 F1.2SN 1E12H0317 1E12-H0317; M13211 F1.2SN 1E12H0318 1E12-H0318' M13211 F1.2SN 1E12H0322 1E12-H0322 M15211 O-F1.2SN 1E12H0323 1E12-H0323 (TANDEM)
M15211 F1.2SN 1E12H0324 1E12-H0324 M15211 F1'.2SN 1E12H0325-1E12-H0325 M15211
'F1.2SN 1E12H0333 1E12-H0333 M14211-F1.2SN-1E12H0339 1E12-H0339 M14211' F1.2SN 1E12H0340 1E12-H0340 M13211 3
F1.2SN 1E12H0344 1E12-H0344 M14211' j
F1.2SN 1E12H0345 1E12-H0345 M14211' F1.2SN 1E12H0347' 1E12-H0347 M13211 F1.2SN 1E12H0349 1E12-H0349 M25221 F1.2SN 1E12H0359 IE12-H0359 M16211 F1.2SN 1E12H0360 1E12-H0360.
M16211 F1.2SN 1E12H0361 1E12-H0361 M11211 F1.2SN 1E12H0362 1E12-H0362 M11211 F1.2SN 1E12H0365 1E12-H0365 M15211 F1.2SN 1E12H0367-1ElB-H0367 M12211 F1.2SN 1E1280368 12i2-H0368 L15211 j
F1.2SN 1E12H0370 1E12-H0370 M15211 Q..
.F1.2SN 1E12H0373 1E12-H0373 M16211 F1 2SN 1E12H0374 1E12-H0374 M15211 F1.2SN 1E12H0375 1E12-H0375 M15211 h-F1.2SN In12H0376 1E12-H0376 M16211 L
F1.2SN 1E1280377 1E12-H0377-M15211 T1.2SN 1E12H0378 IE12-H0378 M15211 F1.2SN 1E12H0379 1E12-H0379 M15211 F1.2SN 1E12H0382 1E12-H0382 M13211 F1.2SN 1E12H0383 1E12-H0383 M13211.-
C-3 1-373 Rev. 3 l
G RY i
ITEM MPL NO.
HANGER - MARK NO.
g q
F1.2SN 1E12H0385 1E12-H0385 M15211 F1.2SN 1E12H0386 1E12-H0386 M16211 F1.2SN 1E12H0388 1E12-H0388 M15211 F1.2SN 1E12H0389 1E12-H0389 M25211 F1.2SN 1E12H0391
- 1E12-H0391 M15211 F1.2SN 1E12H0392 1E12-H0392 M15211 F1.2SN 1E12H0393 1E12-H0393 M25211 F1.2SN 1E12H0394 1E12-H03!:1 M25211 F1.2SN 1E12H0407 IE12-H0407 M14211 F1.2SN 1E12H0408 1E12-H0408~
M14211 F1.2SN 1E12H0410 1E12-H0410 M16211 M13211 F1.2SN 1E12H0414 1E12-H0414 F1.1SN 1E12H0416 1E12-H0416 M15221 F1.1SN 1E12H0418 1E12-20418 M15221 F1.1SN 1E12H0419 1E12-H0419 M14221 F1.2SN 1E12H0421 1E12-H0421 M13211 F1.2SN 1E12H0422 1E12-H0422 M14211 F1.2SN 1E12H0423 1E12-H0423 M14211 F1.2SN 1E12H0424 1E12-H0424 M15211 F1.2SN 1E12H0425 1E12-H0425 M15211 F1.2SN 1E12H0427 1E12-H0427 M15211 F1.2SN 1E12H0428 1E12-H0428 M15211 1E12H0429 1E12-H0429 M15211 F1.2SN 1E12H0430 1E12-H0430 M15211 1E12H0431 1E12-H0431 M15211 F1.2SN 1E12H0435 1E12-H0435 M14221 F1.2SN 1E12H0437 1E12-H0437 M14221 F1.2SN 1E12H0439 1E12-H0439 M14221 F1.2SN 1E12H0440 1E12-H0440 M14221 F1.2SN 1E12H0441 1E12-H0441 M14221 F1.2SN 1E12H0447 1E12-H0447 (TANDEM)
M14221 F1.2SN 1E12H0449 1E12-H0449 M15211 F1.2SN 1E12H0455 1E12-H0455 M15221 F1.2SN 1E12H0457 1E12-H0457 M13221 F1.2SN 1E12H0459 1E12-H0459 M14221 F1.2SN 1E12H0460 1E12-H0460 (TANDER)
M14221 F1.2SN 1E12H0462 1E12-H0462 M14221 F1.2SN 1E12H0466 1E12-H0466 (TANDEM)
M14221 F1.2SN 1E12H0467 1E12-H0467 (TANDEM)
M14221 F1.25H IE12H0484 1E12-H0484 M15211 F?. 2SN 1E12H0485 1E12-H0485 M15211 E1.2SN 1E12H0486 1E12-H0486 M15211 E.1.2.SN m M 488 1E12 BD488 M14211 <
F1.2SN 1E12H0490 1E12-H.0490 M11211 F1.2SN 1E12H0491 1E12-H0491
'M11211 F1.2SN 1E12H0492 1E12-H0492 M11211 F1.2SN 1E12H0496 1E12-H0496 M15211 F1.2SN 1E12H0497 1E12-H0497 M15211 F1.2SN 1E12H0498 1E12-H0498 (TANDEM)
M14211 F1.2SN 1E12H0500 1E12-H0500 M16211 0
1-374 Rev. 3
i MPL NO.
HANGER - MARK NO.
N RY O
- C F1'.2SN 1E12H0501-1E12-H0501 M15211 F1.2SN 1E12H0502 1E12-H0502 M15211 F1.2SN 1E12H0503 1E12-H0503 M15211 F1.2SN 1E12H0506 1E12-H0506 (TANDEN)
M14211 F1.2SN 1E12H0510-1E12-H0510 M13212 F1.2SN 1E12H0511 1E12-H0511 M13212 F1.2SN 1E12H0512 1E12-H0512 M13212.
F1.2SN 1E12H0513 1E12-H0513 M13212 1E12H0518 1E12-H0518 M11221 1E12H0520 1E12-H0520 M12221
-1E12H0521 1E12-H0521 M11221 1E12H0522 1E12-H0522 M13221 1E12H0523 1E12-H0523 M12221 F1.2SN 1E12H0526 1E12-H0526 M15211 F1.2SN 1E12H0528 1E12-H0528~
M16211 F1.2SN 1E12H0533
'1E12-H0533 M15211 F1.2SN 1E12H0535 1E12-H0535 M15211 1E12H0538 1E12-H0538 M13221 1E12H0539 1E12-H0539 M13221 1E12H0542-1E12-H0542 M12221 F1.2SN 1E12H0545 1E12-H0545 M13221 F1.2SN 1E12H0546 1E12-H0546 M13221 F1.2SN 1E12H0551
.1E12-H0551-M15211 F1.2SN 1E12H0554 1E12-H0554 M15211 F1.2SN 1E12H0555-1E12-H0555 M16211 F1.2SN 1E12H0556
'1E12-H0556 (TANDEN)
M15211 F1.2SN 1E12H0557 :
1E12-H0557 M15211 F1.2SN 1E12H0558 1E12-H0558~
'M15211 F1.2SN 1E12H0560 1E12-H0560 (TANDEN)
M15211 F1.2SN 1E12H0561 1E12-H0561 M14211 F1.2SN 1E12H0565' 1E12-H0565 (TANDEN)
M14221 F1.2SN 1E12H0567 1E12-H0567 M15221 1E12H0568 1E12-H0568 M14221 F1.2SN 1E12H0569-1E12-H0569 M16211 F1.2SN 1E12H0570 1E12-H0570 M16211 F1.2SN 1E12H0571-1E12-H0571-M16211
-1E12H0580 1E12-H0580 (TANDEN)
M13221' 1E12H0581 1E12-H0581 M15221 1E12H0582 1E12-H0582 M15221 1E12H0583 1E12-H0583 M14221 1E12H0585 1E12-H0585 M14211 1E12H0586 1E12-H0586 M14211 l
1E12H0587-1E12-H0587 M14211 1E12n 584 1E12-20588 (TANDEN)
M14211 <
1E12H0590 1E12-H0590 M14211
'1E12H0591 1E12-H0591 M14211 1E12H0595 1E12-H0595-M15211 1E12H0597 1E12-Hv597 (TANDEN)
M13211 1E12H0599 1E12-H0599 M14211 1E12H0601 1E12-H0601-M14211
/]
b 1-375 Rev. 3 m
_i_______________
5 'M l.
MPL NO.
HANGER - MARK NO.
CATEGORY NO.
NO.
1E12H0602 1E12-H0602 M14211 1E12H0603 1E12-H0603 M14211 1E12H0604 1E12-H0604 M13211 1E12H0605 1E12-H0605 M15211 1E12H0606 1E12-H0606 M14211 F1.2SN 1E12H0616 1E12-H0616 M15211 F1.2SN 1E12H0617 1E12-H0617 M15211 1E12H0623 1E12-H0623 M15211 F1.1SN 1E12H0652 1E12-H0652 M16211 F1.1SN 1E12H0653 1E12-H0653 M15211 F1.1SN 1E12H0660 1E12-H0660 (TANDEM)
M16211 F1.2SN 1E12H0666 1E12-H0666 M14211 1E12H0668 1E12-H0668 M14211 F1.1SN 1E12H0671 1E12-H0671 (TANDEM)
M26221 F1.2SN 1E12H0679 1E12-H0679 M12211 F1.2SN 1E12H0680 1E12-H0680 M12211 F1.2SN 1E12H0681 IE12-H0681 M14211 F1.2SN 1E12H0682 1E12-H0682 M14211 F1.2SN 1E12H0694 1E12-H0694 M15211 F1.3SN 1E12H0699 IE12-H0699 M16211 F1.2SN 1E12H0710 1E12-H0710 M15211 F1.2SN 1E12H0712 1E12-H0712 M14211 F1.1SN 1E12H0726 1E12-H0726 L26221 l
F1.2SN 1E12H0729 1E12-H0729 M26211 F1.2SN 1E12H0730 1E12-H0730 M16211 F1.2SN 1E12H0731 1E12-H0731 M26211 F1.2SN 1E12H0734 1E12-H0734 M16211 F1.1SN 1E12H0736-1E12-H0736 M16221 F1.2SN 1E12H0737 1E12-H0737 M15211 F1.2SN 1E12H0738 1E12-H0738 M15211 F1.1SN 1E12H0741 1E12-H0741 (TANDEM)
M25221 F1.1SN 1E12H0747 in12-H0747 M14211 F1.1SN 1E12H0749 1E12-H0749 M26221 F1.1SN 1E12H0750 1E12-H0750 M26221 F1.2SN 1E12H0751 1E12-H0751 M15211 F1.2SN 1E12H0752 1E12-H0752 M14211 1E12H0754 1E12-H0754 M12211 1E12H0756 1E12-H0756 M15211 1E12H0758 1E12-H0758 M14211
- 1E12HU759
'1T12-11U759 P11~3211 IE12H0760 1E12-1t0760 Wi"3221 1E12H0761 1E12-H0761 (TANDEM)
M14221 1E12H0762 1E12-H0762 i
M13211 F1.1SN 1E12H0764 1E12-H0764 M26221 F1.1SN 1E12H0765 1E12-H0765 M26221 F1.1SN 1E12H0766 1E12-H0766 (TANDEM)
M26221 F1.2SN 1E12H0769 1E12-H0769 M16211 F1.2SN 1E12H0770 1E12-H0770 M15211 F1.2SN 1E12H0771 1E12-H0771 M16211 F1.2SN 1E12H0772 1E12-H0772 M16211 C-3 1-376 Rev. 3
I ITEM ypt yo,
. HANGER - MARK NO.
CATEGORY NO.
NO.
1E32H0250 1E32-H0250 M21211 i
1E32H0251 1E32-H0251-M21211' l
1E32H0258 1E32-H0258 M22221.
i 1E32H0260 1E32-H0260 M22221 L
1E32H0261 1E32-H0261 M21211 1E32H0262 1E32-H0262, M23221 1
1E32H0268, 1E32-H0268 M12221 1E32H2002 1E32 H2002 M11221 1E32H2006-1E32-H2006-M11221 1E32H5003 1E32-H5003 M13221 1E51H0002 1E51-H0002 M14221 F1.2SN 1E51H0008' 1E51-H0008 M13221 1E51H0036 1E51-H0036 M15221 1E51H0053 1E51-H0053 M13221 F1.2SN 1E51H0056 1E51-H0056 M11221-F1.2SN 1E51H0057-1E51-H0057 M13211 1E51H0062 1E51-H0062 (TANDEM)
M13211 F1.1SN 1E51H0072 1E51-H0072 P24221-F1.1SN 1E51H0073 1E51-H0073 L24221 F1.1SN 1E51H0074 1E51-H0074 L24221 1E51H0105 1E51-H0105 M11221 1E51H0106 1E51-H0106 M12221 F1.1SN 1E51H0110 1E51-H0110 M25221 F1.1SN 1E51H0111 1E51-H0111 H25221
(
j.
1E51H0122 1E51-H0122 M14221 1E51H0132 1E51-H0132 M14221-1E51H0134 1E51-H0134 M11221 1E51H0135 1E51-H0135 M13221 F1.2SN 1E51H0156 1E51-H0156 M13221 1E51H0168 1E51-H0168 (TANDEM)
M13221 1E51H1018 1E51-H1018 M12211 1E51H1020 1E51-H1020 M13211 1E51H1031 1E51-H1031 M12211 1E51H2028 1E51-H2028 M11221 1E51H2069 IE51-H2069 P22221 l
1E51H2074 1E51-H2074 M11221 l
1E51H2076 1E51-H2076 P22221 1E51H2078 1E51-H2078 L22221
]
1E61H0047 1E61-H0047.
M15211 1E61H0058:
1E61-H0058 M13211 1E61H1005 1961-61005 M11211 1E61H1011 1E61+-H1011 M11211 1E61H1015 1E61-H1015.(TANDEN)
M21211 1G33H0001 1G33-H0001 M25121 1G33H0003 1G33-H0003 M23121 1G33H0004 1G33-H0004 M23121 1G33H0032 1G33-H0032 H24121 L
1G33H0037 1G33-H0037 M24121 l
O C-3 1-381 Rev. 3 1
f CATEGORY l
ITEM MPL NO.
HANGER - MARK NO.
NO.
NO.
1G33H0052 1G33-H0052 H24121 1G33H0054 1G33-H0054 M24121 1G33H0056 1G33-H0056 H23121 1G33H0057 1G33-H0057 (TANDEM)
M23121-F1.50 1G33H0142 1G33-H0142 H25121 F1.50 1G33H0144 1G33-H0144 M24121 F1.50 1G33H0146 1G33-H0146 M24121 1G33H0147 1G33-H0147 M24121 1G33H0149 1G33-H0149 M14121 1G33H0158 1G33-H0158 (TANDEM)
M13121 1G33H0160 1G33-H0160 (TANDEM)
M14121 1G33H0163 1G33-H0163 M14121 1G33H0171 1G33-H0171 M13121 1G33H0175 1G33-H0175 M24121 1G33H0176 1G33-H0176 M24121 1G33H0200 1G33-H0200 M24121 F1.2SN 1G33H0215 1G33-H0215 M24121 F1.2SN 1G33H0216 1G33-H0216 M24321 F1.2SN 1G33H0217 1G33-H0217 M25121 F1.2SN 1G33H0218 1G33-H0218
!i25121 F1.2SN 1G33H0219 1G33-H0219 M25121 F1. 2SN.
1G33H0220 1G33-H0220 M25121 F1.2SN 1G33H0221 1G33-H0221 M25121 F1.2SN 1G33H0222 1G33-H0222 M25121 F1.2SN 1G33H0223 1G33-H0223 M25121 F1.2SN 1G33H0224 1G33-H0224 (TANDEM)
M25121 1G33H0228 1G33-H0228 (TANDEM)
M23121 1G33H0234 1G33-H0234 M23121 1G33H0236 1G33-H0236 M14121 1G33H0237 IG33-H0237 M14121 F1.2SN 1G33H0239 1G33-H0239 M24121 F1.2SN 1G33H0240 1G33-H0240 M24121 1G33H0250 1G33-H0250 M24121 1G33H0268 1G33-H0268 (TANDEM)
M24121 F1.2SN 1G33H0269 1G33-H0269 M23121 1G33H0272 1G33-H0272 M13121 F1.1SN 1G33H0276 1G33-H0276 M22123 F1.1SN, 1G33H0277 1G33,-H0277 L22121 j j
F1.1SN 1G33H0279 1G33-H0279 M22122 F1.1SN 1G33H0280 1G33-H0280 L22122 l
F1.3SN 1G41H0012 1G41-H0012 (TANDEM)
M12211 g F1.3SN 1G41H0025 1G41-H0025 M13211 F1.3SN 1G41H0037 1G41-H0037 (TANDEM)
M14211 M16211 F1.3SN 1G41H0048 IG41-H0048 F1.3SN 1G41H0050 1G41-H0050 M14211 O
Rev. 3 C-3 1-382
y o-o l_
MPL NO.
HANGER - MARK H0.
G RY (3
- U F1.3SN 1G41H0051 1G41-H0051 M14211 L
F1.3SN 1G41H0059 1G41-H0059 M14211 F1.3SN.1G41H0068 1G41-H0068 M14211 i
F1.3SN 1G41H0070 1G41-H0070 M13211 F1.3SN
-1G41H0119 1G41-H0119 M14211 L
F1.3SN 1G41H0121-IG41-H0121 M16211 1
1G41H0138 1G41-H0138 M14211
'1G41H0143 1G41-H0143-M14211 1G41H0145 1G41-H0145 M15211 l-1G41H0149' 1G41-H0149 M15211 L
1G41H0151 1G41-H0151 (TANDI!N)
M14211 L
F1.3SN 1G41H0170 1G41-H0170 M15211 F1.3SN -1G41H0171
-1G41-H0171
.M15211 lE F1.3SN 1G41H0179 1G41-H0179 M14211 1G41H0181 1G41-H0181 M15211 L
1G41H0182 1G41-H0182 M15211 1G41H0183 1G41-H0183 M14211 1G41H0185 1G41-H0185 M15211 F1.3SN
-1G41H0191 1G41-H0191 M14211 F1.3SN 1G41H0227 1G41-H0227 M14211 F1.3SN 1G41H0228 1G41-H0228 (TANDEN)
'M14211-F1.3SN 1G41H0230 1G41-H0230 M14211 F1.3SN IG41H0232 1G41-H0232 M14211 F1.3SN 1G41H0233' 1G41-H0233 M14211 4
F1.3SN 1G41H0236 1G41-H0236 (TANDEN)
M14211 J
F1.3SN 1G41H0238 1G41-H0238 M15211 I
F1.3SN 1G41H0241 1G41-H0241
-M14211 L
F1.3SN
.1G41H0242 1G41-H0242 (TANDEN)
M16211-F1.3SN 1G41H0243 1G41-H0243 M14211 L
F1.3SN 1G41H0301 1G41-H0301 M13211 l
1G41H0321 1G41-30321 M16211 1G41H0322.
1G41-H0322 M16211-1G41H0330
'1G41-H0330 M15211 l
1G41H0331 1G41-H0331 M15211
-IG41H0332 1G41-H0332 M16211 1G41H0333 1G41-H0333 M16211' 1G41H0342 1G41-H0342 M15211 1G41H0343 1G41-H0343 M15211 1G41H0344 1G41-H0344 M14211
.1G41H0345 1G41-H0345 M15211 1G41H0346-1G41-110346 M15211 1G41H0352 1G41-H0352 M15211 E1.3SN.
JG422A363 JG41-R0363 M14211' <
F1.3SN 1G41H0368 1G41-H0368 M16211 F1.3SN 1G41H0369 1G41-H0369 M15211 F1.3SN 1G41H0388-1G41-H0388 M15211 F1.3SN 1G41H0389 1G41-H0389 M15211
-1G41H0397 1G41-H0397
.M14211-IG41H0398 1G41-H0398 M14211 F1.3SN 1G41H0450 1G41-H0450 (TANDEM)
M14211 0
1-383 Rev. 3 l
1 J
o 1
CATEGORY' ITEM MPL NO.
HANGER - MARK NO.
NO.
NO.
1G41H0466 1G41-H0466 M13211 F1.3SN 1G41H0472 1G41-H0472 M14211 1G41H0474 1G41-H0474 M14211 1G41H0475 1G41-H0475 M15211 F1.3SN 1G41H0478 IG41-H0478 M14211 1G41H0403 1G41-H0483 M14211 F1.3SN 1G41H0493 1G41-H0493 M14211 F1.3SN 1G41H0494 1G41-H0494 M15211 1G41H1009 1G41-H1009' L22211 l
1G41H1011 1G41-H1011 P21211 1G41H1025 1G41-H1025 L22211 1G41H1026 1G41-H1026 L22211 F1.3SN 1G41H5001 1G41eH5001 (TANDEM)
M14211 F1.3SN 1G42H0004 1G42-H0004 M14211 F1.3SN 1G42H0010 1G42-H0010 M14211 F1.3SN 1G42H0013 1G42-H0013' M14211 F1.3SN 1G42H0048 1G42-H0048 M15211 1G50H0068 1G50-H0068 M22211 1G61H0038 1G61-H0038 M14211 1G61H0045 1G61-H0045 M11211 1H22H0208 1H22-P0004-H1042 M21121 1H22H0209 1H22-P0004-H1043 M21121 1H22H0365 1H22-P0004-H1206 M21121 1H22H0379 1H22-P0004-H1220 M21121 j
1H22H0389 1H22-P0004-H1230 M21121 1H22H0561 1H22-P0005-H1072 M21121 1H22E0564 1H22-P0005-H1075 M21121 1H22H1910 1H22-P0015-H1291 M21121 1H22H1915 1H22-P0015-H1297 M21121 1H22H2495 1H22-P0026-H1086 M21121 1H22H2683 1H22-P0027-H1058 M21121 1H22H2687 1H22-P0027-H1062' M21121 1H22H2706 1H22-P0027-H1083 M21121 1H22H2710 1H22-P0027-H1087 M21121 1H22H2744 1H22-P0027-H1122 P21121 1H22H2761 1H22-P0027-H1140 M21121 1H22H2764 1H22-P0027-H1143 M21121 1H22H4577 1H22-P0021-H0203 M11121 I
1H51H0068 1H51-P1368-H0068 M11111 TH51E0073 1551-7136B-110073 7111111 1H51H0078 1H51-P1368-H0078 M11111 1H51H0083 1H51-P1368-H0083 M11111 1H51H0301 1H51-P1370-H3013 M21111 1M14H0005 1M14-H0005 M15211 l
1M14H0007 1M14-H0007 M15211 IM17H0002 1M17-H0002 M14211 l
1M17H0003 1M17-H0003 M14211 1M17H0005 1M17-H0005 M14211-1H17H0006 1M17-H0006 M14211
)
IM17H0008 IM17-H0008 M14211
]
C-3 1-384 Rev. 3 l
I
n-_-__.
0 p
['
ITEM.
MPL NO.
. HANGER - MARK NO.
CATEGORY-NO.
NO.
b 1M17H0009 1M17-H0009 M14211 1M17H0011 1M17-H0011~
M14211 1M17H0012' 1M17-H0012 M14211 IM51H0054 1M51-H0054-M14211 IM51H0055 1M51-H0055.
M12211 1U51H9068 1M51-H0068 M22211 1M51H0070 1M51-H0070 M14211 l
1M51H0071 1H51-H0071
-M12211 1H51H008F 1M51-H0089 M22211 1M51H102s 1M51-H1024 M21211 o
1M51H1028 1M51-H1028 M12211 1M51H1031 1M51-H1031 M12211 1M51H1076 1M51-H1076 M11211 1N11H0205 '
1N11-H0205 L27121 IN11H0206-IN11-H0206
- L27121 IN11H0207 1N11-H0207-L27121 1N11H0208 1N11-H0208 L27121 IN11H027,8 1N11-H0278 M26121 IN11H0279-IN11-H0279.
H26121 1N11H0280 IN11-H0280 M26121 IN11H02S1' 1N11-H0281
'M26121-IN11H0281 IN11-H0282' M26121-IN11H0283' 1N11-H0283 M26121.
IN11H0284 1N11-H0284-H26121-1N11H0285 1N11-H0285.
M26121-IN11H0286~
IN11-H0286 H25121 IN11H0287 1N11-H0287
.H25121 1N11H0288-1N11-H0288 H25121 IN11H0289-IN11-H0289 H25121 1N11H0290-IN11-H0290 P27121 IN11H0291 1N11-H0291.
_P27121 l
IN11H0292 IN11-H0292 P27121 1N11H0293 1N11-H0293 P27121 1N11H0294 1N11-H0294 P27121-1N11H0295 1N11-H0295 P27121 IN11H0357 1N11-H0357
.P27121 1N11H0358 1N11-H0358
'P27121f 1N11H0468-IN11-H0468-M26121 l
IN11NO469 IN11-HO469 M26121 1N11H0470 IN11-H0470-M26121 1
IN1130471 "1N11-1t0471 N26171-g IN11H0472-IN11-H0472 M26121.
L IN11H0473 1N11-H0473
~ '~
-M26121 1N11H0474 1N11-H0474
- M26121 l'
1N11L 0475 M26121-1N11H0475 H
F1.1SN IN22H0004 1N22-H0004 M23121
-)
F1.1SN IN22H0006 IN22-H0006 M24121 j
F1.1SN IN2280008 IN22-H0008 M23121 F1.1SN IN22H0011 IN22-H0011 M23121 i
F1.1SN IN22H0013 1N22-H0013 M23121 l
h
. C 1-385 Rev. 3
.__--____1______.______-.m--_._____m_-____.__m[___Y__
i i
I G
RY MPL NO.
HANGER - MARK NO.
NO F1.1SN IN22H0015 1N22-H0015 M23121' F1.1SN IN22H0017 IN22-H0017 M23121 1N22H0025 1N22-H0025 M24121 IN22H0029 1N22-H0029 M24121 1N22H0030 IN22-H0030 M24121 1N22H0036 1N22-H0036 M24121 1N22H0038 IN22-H0038 M21121 1N22H0040 IN22-H0040 M21121 1N22H0044 1N22-H0044 M21121 1N22H0046 1N22-H0046
.M21121 IN22H0048 1N22-H0048 M21121 M21121 IN22H0050 IN22-H0050 1N22H0052 IN22-H0052 M21121 1N22H0055 1N22-H0055 M21121 IN22H0056 IN22-H0056 M22121 IN22H0057 IN22-H0057 M21121 1N22H0059 IN22-H0059 (TANDEM)
M21121 IN22H0060 IN22-H0060 M21121 IN22H0062 IN22-H0062 1
M21121 1N22H0064 1N22-H0064 M21121 1N22H0065 1N22-H0065 M21121 IN22H0066 1N22-H0066 M21121 1N22H0068 1N22-H0068 M22121 IN22H0070 1N22-H0070 M21121 IN22H0072 IN22-H0072 M21121
~
IN22H0074 1N22-H0674 M21121 h
1N22H0078 1N22-H0078 M23121 IN22H0079 1N22-H0079 M21121 IN22H0081 IN22-H0081 M21121 IN22H0083
- N22-H0083 (TANDEM)
M21121 1N22H0084 IN22-H0084 (TANDEM)
M21121 IN22H0087 1N22-H0087 M21121-IN22H0089 1N22-H0089 M22121 IN22H0091 1N22-H0091 M21121 1N22H0093 1N22-H0093 M21121 1N22H0095 1N22-H0095 M23121 1N22H0097 1N22-H0097 M21121 IN22H0099 1N22-H0099 H21121 l
1N22H0100 IN22-H0100 M21121 1N22H0101 IN22-H0101 M21121 IN22H0109 1N22-H0109 M23121 1N22H0111 1N22-H0111 M21121 IN22H0113 JN22-H0113 M21121 IN22H0115 1N22-H0115 4t21121 <
IN22H0116 1N22-H0116 M21121 1N2280117 1N22-H0117 (TANDEM)
M21121 IN22H0119 IN22-H0119 (TANDEM)
M21121 1N22H0121 IN22-H0121 (TANDEM)
M21121 IN22H0123 1N22-H0123 (TANDEM)
M21121 F1.1SN IN22H0126 IN22-H0126 '
H22121 l
1-386 Rev. 3
L O
. ITEM-MPL NO.
HANGER - MARK NO.
CATEGORY Q.
NO.
NO.
F1.1SN IN22H0127 IN22-H0127 M23121 F1.1SN.
IN22H0128 1N22-H0128 M22121 F1.1SN 1N22H0129.
1N22-H0129 M23121 F1.1SN IN22H0130 1N22-H0130 M24121 F1.1SN IN22H0131 1N22-H0131 M23121 L
IN22H0146
,1N22-H0146 M22121 1N22H0147 IN22-H0147 M22121 F1.1SN IN22H0148' 1N22-H0148 M23121 l_
IN22H0255 1N22-H0255.
M22121 1N22H0257 1N22-H0257 M22121 1N22H0259.
IN22-H0259 M22121
(:
F1.1SN IN27H0001 IN27-H0001 M23121 L
.F1.1SN IN27H0004 1N27-H0004 M23121 F1.1SN IN27H0005 1N27-H0005 M23121-F1.1SN IN27H0006 1N27-H0006 M24121 F1.1SN IN27H0007 1N27-H0007 M24121 F1.1SN IN27H0013 1N27-H0013 M23121 F1.1SN IN27H0016~
IN27-H0016
'M23121 F1.1SN IN27H0017 1N27-H0017 M23121 l
F1.1SN IN27H0018 1N27-H0018 M24121 F1.1SN IN27H0019
.1N27-H0019 M24121 l
1N27H0220~
IN27-H0220 M26121 IN27H0221 IN27-H0221 M26121 1N27H0222 IN27-H0222 127121 l
>Q 1N27H0223 1N27-H0223 M26121
(,)
IN27H0224 1N27-H0224 M26121-L IN27H0225' 1N27-H0225
'P27121 jl 1N27H0226 1N27-H0226'
-M26121 IN27H0227 1N27-H0227 P27121 1N27H1012-IN27-H1012*
M21121 IN27H1016 IN27-H1016 M21121 IN27H1068 1N27-H1068 M11121 1N27H1086' 1N27-H1086 M22121 1N27H1145 1N27-H1145 P21121 1P11H0063-1P11-H0063 M16211 1P11H0079 IP11-H0079 M15211 1P11H0083 1P11-H0083 M15211 1P11H0085 1P11-H0085 M14211 1P11H5000.
1P11-H5000 M16211 1P41H0115 1P41-H0115 M16111 1P41H0121~
.M14111 178250049 1712-110041
' Tilt 111 1P42H0050.
1P42-H0050 M14111 1P42H0051 1P42-H0051 M14111 IP42H0052.
IP42-H0052' M14111' 1P42H0057 1P42-H0057 '
M14111
~
1P42H0058 1P42-H0058 (TANDEM)I M1411A IP42H0059 1P42-H0059 M14111 4 1P42H0060 1P42-H0060 M13111 1P42H0100 1P42-H0100 M13111 n
(_ /
C-3 1-387 Rev. 3
O RY MPL NO.
HANGER - MARK NO.
~
IP4280154 1P42-H0154 M11111 1P42H0372 1P42-H0372 M13111 1P42H0388 1P42-H0388 M13111 1P42H0401 1P42-H0401 M14111 1P42H0422 1P42-H0422 M14111 1P42H0430 1P42-H0430 M13111 1P43H0047 1P43-H0047 (TANDEM)
M15111 1P43H0052 1P43-H0052 M14111 F1.3SN ~1P45H0097 1P45-H0097 M15111 F1.3SN 1P45H0104 1P45-H0104 (TANDEM)
M14111 F1.3SN 1P45H0126 IP45-H0126 M15111 F1.3SN 1P45H0132 1P45-H0132 (TANDM)
M14111 F1.3SN 1P45H0176 1P45-H0176 (TANDEM)
M14111 F1.3SN 1P45H0177 1P45-H0177 (TANDEM)
M14111 F1.3SN 1P45H0179 IP45-H0179 M15111 F1.3SN 1P45H0183 1P45-dO183 M15111 F1.3SN 1P45H0185 1P45-H0185 (TANDEM)
M14111 F1.3SN 1P45H0186 1P45-H0186 M15111 F1.38N 1P45H0192 1P45-H0192 M14111 F1.3SN 1P45H0212 1P45-H0212 M15111 F1.3SN 1P45H0216 1P45-H0216 M14111 F1.3SN 1P45H0222 1P45-H0222 M15111 F1.3SN IP45H0270 1P45-H0270 H11111 F1.3SN IP45H0292 1P45-H0292 M14111 F1.3SN 1P45H0353 1P45-H0353 (TANDEM)
M14111 F1.3SN 1P45H0422 1P45-H0422 M16111 F1.3SN 1P45H0440 1P45-H0440 M14111 F1.3SN 1P45H0441 1P45-H0441 M14111 F1.3SN 1P45H0444 1P45-H0444 M14111 F1.3SN 1P45H0445 1P45-H0445 M14111 F1.3SN 1P45H0502 1P45-H0502 M15111 F1.3SN 1P45H0509 1P45-H0509 M15111 F1.3SN 1P45H0510 1P45-H0510 M15111 F1.3SN 1P45H0512 1P45-H0512 M16111 F1.3SN 1P45H0516 1P45-H0516 M15111 F1.3SN 1P45H0521 1P45-H0521 M15111 F1.3SN IP45H0525 1P45-H0525 (TANDEM)
M14111 F1.3SN 1P45H0526 1P45-H0526 M15111 F1.2SN 1P45H0610 1P45-H0610 (TANDEM)
M15111 F1.2SN 1P45H0611 1P45-H0611 M16111 F1.3SN 1P45H0617 1P45-H0617 (TANDEM)
M14111 F1.3SN 1P45H0684 1P45-H0684 M14111 1P45H1050 1P45-H1050 M13111 IP4'5HIV5B
' IP E-WIDEB W1~3111 1P45H1233 1P45-H1233 M12111 1P45H1234 1P45-H1234 M12111 1P45H1328 1P45-H1328 M11111 F1.3SN 1P47H0278 IP47-H0278 M15111 F1.3SN 1P47H0279 1P47-H0279 M15111 1P51H0037 1 1P51-H0037 H12111 O
1-388 Rev. 3 I
8:6. Reference Requirements for System Pressure Tests The'following table' identifies paragraphs for compliance to the.ASME Boiler and P,ressure Vessel Code,Section XI, 1983 Edition; through Summer 1983 Addenda with the use of Code Case N-416-1.
^
EXAMINATION CORRECTIVE
^
CATEGORY MEASURES CLASS
' TESTS REPLACEMENT INA-5211(a)
IWA-5000 Table IWA-5250 IWA-5211(d) 1992 Edition IWB-2500-1
.1 Category IWB-5210 B-P IWA-5211(a)
' Table IWA-5250 IWA-5211(d) 1992 Edition IWC-2500-1 2
Category IWB-5210 C-H IWA-5211(a)
IWA-50001 Table IWA-5250 3
IWA-5211(d) 1992 Edition IWB-2500-1 Category IWB-5210 D-A, D-B, D-C 8.7 Relief Requests t
When compliance to code specified testing requirements are not achievable I
? relief must be requested. The following Pressure Test'(PT) Relief I
Requests have been filed with the NRC:
PR NO.
PT-001 R-1 PT-002 R-1 PT-004 R-0 1
PT-005 R-0 PT-006 R-O' i
PT-007 R-0 l
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C-3 1-393 Rev. 3
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Sheet 1 of 2 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IPT-001 l
I.
Identification of Components l
Class 2 systems / components attached to the Reactor Coolant Pressure a
Boundary (Class 1) which are not provided with either pressure or test isolation (i.e., instrumentation, drain, vent, and test piping)..A list of valve numbers identifies the affected components (i.e., valves, piping systems and instruments).
II. ASME B&PV Section XI Requirements IWA-5213(c) Test Condition Holding Time, ' System Inservice Tests - no holding time required, provided the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."
IWC-5210(a)(2) Test, 'A system pressure test conducted during a system inservice test [IWA-5211(c)] for those systems required to operate during normal plant operation."
III. Relief Requesti Relief is requested from using the requirement of - operating the system for four hours before commencing the VT-2 examinations - for class 2 components and instruments non-isolable from the Reactor Coolant Pressure Boundary (Class 1). These components shall be examined (VT-2 Visual Examination) during the Class 1 Reactor Coolant Boundary System Leakage Pressure Test at the frequency intervals specified within Subsection IW.
Thus, this relief request proposes substituting IWA-5213(a) for IWA-5213(c) and IWB-5210(a)(1) for IWC-5210(a)(2).
IV. Basis for Relief Numerous components attached to the reactor coolant pressure boundary are covered by the provisions of 10CFR50.554(c) Reactor Coolant Pressure Boundary. The following excerpt from 10CFR50a(c) is provided:
'(2) Components which are connected to the reactor coolant system and are part of the reactor coolant pressure boundary as defined in Section 50.2 need not meet the requirements of paragraph (c)(1) of this section, Provided:
(i) In the event of postulated failure of the component during normal acadut trperation, the reactor can be shut down an5 coolea Bown in an orderly manner, assuming makeup is provided by the reactor coolant makeup system; or 1-394 Rev. 3
Sheet 7 of 7 Perry Nuclear Power Plant Unit 1 i
RELIEF REQUEST fPT-002 Valve No.
Description
,PJID No.
'1B21-F544 R W Level Instrument Line Vent D-302-606 0-
~1B21-F546 RPV Level Instrument Line Dt,in D-302-606
-1821-FS15 Instrument Isolation valve for LT-N080B, D-302-606 LT-N004,,LT-N017, LT-N027, LT-N0958 IETT-F55T
'RPFEeverIhstrument Line Vent N-707-6W
.1B21-F540-RW Level Instrument Line Drain -
D-302-606 l
-1B21-F545 RPV Level Instrument Line Vent.
D-302-606
.1B21-F509 Instrument Isolation Valve for LT-N073L, D-302-606 LT-N073R, LT-N081D, LT-N402F 1B21-F548 RPV Level Instrument Line Drain
. D-302-606 1B21-F549 RPV Level Instrument Line Vent D-302-606 1B21-F513 Instrument Isolation Valve for LT-N081B, D-302-606 1B21-F583...
LT-N091F, dPI-R009B, LT-N402B, LT-N091B Instrument Isolation Valve for PT-N081, D-302-606, 962 1
dPT-NO32 i
IB21-F582.
Jet' Pump Instrument Line Vent D-302-606
[
1B21-F585 Instrument Isolation Valve For dPT-N011, D-302-606, 872 dPT-N008 1B21-F523 Instrument. Isolation Valve for Flow D-302-606, 604, Instruments P009, dPI-R005, LT-N490, 671
,7' dPT-N032, FT-N037, FT-N032, dPI-R005
!A'.-
1B21-F584 Jet Pump Instrument'Line Vent.
D-302-606 1B21-F553 Instrument Isolation Valve for LT-N095A, D-302-606
~
l PT-N403A, PI-R004A, PT-N403E, PT-N005,.
PT-N068A, PT-N050, PT-N068E, PT-N006, L
PT-N008A, PT-N078A, PT-N062A, LT-N004A, LT-N080A, LT-N010, LT-N091A, LT-N402A, L
. 1B21-F505 Instrument Isolation Valves for LT-N080C, D-302-606 dPI-R009A, LT-N091E, LT-N081A p'
PT-N078C, LT-N004C, LT-N073G, LT-N402E, LT-N073C, LT-N081C, LT-N044C 1B21-F536 RPV Level Instrument Line Drain D-302-606 1B21-F506 Instrument, Isolation Valve for LT-N080C, D-302-606 LT-N004C l1 1B21-F539-RPV Level Instrument Line Vent D-302-606 l
- 1B21-F528 RPV Level Instrument Line Drain' D-302-606 1B21-F552 Instrument Isolation Valve for LT-N080A,-
D-302-606 LT-N004A, LT-N095A 1B21-F533 RPV Level Instrument Line Vent D-302-606
-1B21-F535 RPV Level Instrument Line Drain D-302-606 1821-F504 Instrument Isolation valves for LT-N081C, D-302-606 LT-N073C, LT-N402E, LT-N073G
-1B21-F534 RPV Level Instrument Line Vent.
D-302-606 1B21-F529 RPV Level Instrument LIne Drain D-302-606 1B21-F555-Instrument Isolation Valve for LT-N081A,
'D-302-606 LT-N091E, dPI-R009A, LT-N402A, 7 -d 91A, t
LT-N010-1B21-F531 RPV Level Instrument Line Vent D-302-606 1-407,'
Rev. 3 t
Sheet 1 of'2-Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. PT-004 p
I.
Identification of Components-c1=r 1, 2, e ey t.
.2.,.d e, :.d..c.ue e.ein,..
II.
ASME Boiler & Pressure Vessel Code Section XI' Requirements Hydrostatic pressure tests per the 1983 Edition through Summer 1983
- Addenda of Section XI, Table'INB-2500-1, Table INC-2500-1, and Table IND-2500-1.
III. Relief Requested I-Pursuant to 10 CER 50.55a(a) (3) (ii), relief is requested from performing, the Code-required hydrostatic tests. Alternative examinations are
-proposed.
-IV.
Basis for Relief I'
ASME Section XI requires hydrostatic testing of Class 1,-2, and 3 systems I)O to be performed at the end of each 10-year inservice inspection interval.
The.use of Code Case N-498, " Alternative Rules for 10-Year System Hydrostatic Testing for Class 1 and 2 Systems," was previously approved by the NRC in Regulatory Guide 1.147, Revision 11.
The N-498-1 alternative requirements for Code Class 1 and 2 are unchanged from N-498; Code Case'N-498-1 expands.the' scope of Code Case N-498 to include Class 3 rystems.
1 i
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(i The Cleveland Electric Illuminating. Company (CEI) has determined that l
hydrostatic tests' represent a-hardship with little benefit. Hardships are
('
generally encountered with the performance of hydrostatic testing in L
accordance with the Code. Because hydrostatic test pressure is higher than the nominal operating pressure, hydrostatic presssre testing frequently, requires significant effort to set up and perform. The preparation for the performance cf the 10-year system hydrostatic tests
- E volves mneiderahla time and rad'=+4na dose ui.th 14++1=.or.no ll compensating increase in the level of quality or safety.
The ASME Subcommittee Working Group on Pressure Testing concluded that no additional' benefit is gained by conducting the existing system hydrostatic tests in place of the alternate requirements which require a system leakage test at the nominal operating' pressure. The conclusion of the I.
group was that Section XI hydrostatic testing does not verify structural integrity and could result in extended outages and increased costs.
O C-3 1-407a Rev. 3 l
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Sheet 2 of 2 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. PT-004 Code Case N-498-1 Indu'stry experience has demonstrated that in-service leaks are not discovered as a result of hydrostatic pressures propagating an existing flaw throughvall. The experience. indicates that, in most cases, leaks are be&ng found saben thw system is at normal operating preseure. -
V.
Alternate Exam!, nation CEI proposes to perform the alternative examination delineated in Code Case N-498-1 as en option to performing the Code-required hydrostatic tests. Code Case N-498-1 expands the scope of N-498 to i c'.ude Class 3 system.
For' Class 3 systems, in lieu of the 10-year sysL.m hydrostatic test required by ASME Section XI (Division 1) Table IWD-2500-1, Code Case N-498-1 allows the alternative requirements summarized as fpilows:
1.
A system pressure test shall be conducted $t or near the end of each inspect!.on interval.
4 2.
The test boundary shall extend to all Class 3 components included in
~
th>se portions of systems' required to operate or support the safety function up to and including the firsi; normally closed isolation O
valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
3.
A VT-2 visual examination shall be performed with the system maintained at nominal operating pressure. The system shall be pressurized for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for noninsulated systems, prior to performing the VT-2 visual examination.
4.
The VT-2 visual examination shall include all components within the boundary identified in (2) above.
J 5.
The test instrument requirements of IRA-5260 are not applicable.
l Rev. 3 l
C-3 1-407b 1
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Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. PT-005 Code Case N-522-Identification of Components-Penetration No.
Drawing No.
Associated ISI Pressure Test Instruction P204 D-302-871 ISI-C11-T1201-2 P201 D-806-004 ISI-D17-T1100-2 i
P317 D-806-007 ISI-D17-T1101-2
^
P109 D-302-811 ISI-E61-T1100-2 g
P119 D-302-811 ISI-E61-T1101-2 l
P120 D-302-811-ISI-E61-T1102-2 P317 D-302-811 ISI-E61-T1103-2 P319 D-302-811 ISI-E61-71104-2
{
P424 D-302-672 ISI-G33-T1100-2 P420 D-302-737' ISI-G50-T1100-2 P417 D-302-739 ISI-G61-71100-2 P418 D-302-740 ISI-G61-T1101-2 V313 D-912-604 ISI-M14-T1100-2 V314 D-912-604 ISI-M14-T1101-2 P114 D-912-606 ISI-M17-T1100-2 P208 D-912-606 ISI-M17-T1101-2
~~
~"
' ~ ~ ~ ~ ~
P428 D-912-606 ISI-M17-T1102-2 P436 D-912-606 ISI-M17-T1103-2
~~
P108 D-302-102 ISI-P11-T1100-2 Pill D-302-102 ISI-P11-T1101-2 P309 D-302-713 ISI-P22-71100-2 P310/P311 D-302-613 ISI-P43-T1200-2 P404/P405 D-913-008 ISI-P50-T1200-2 P308-D-302-242 ISI-P51-T1200-2 P305/P306 D-302-244 ISI-PS2-T1200-2 P312 D-302-243 ISI-P52-T1200-2 P406 D-9?s-003 13I-P54-T1100-2 P210 D-914-005 ISI-P54-T1101-2 P117 D-302-950 ISI-P86-T1100-2 P413 D-302-431-ICI-P87-T1100-2
[II. ASME Boiler & Pressure Vessel Code Section XI Requirements i
~
The fonowing requirements of the 1983Tdition through Summer 1983 %ddenda of.Section XI apply:
1.
IWA-5211, states "The pressure retaining components within wach system boundary shall be subject to system pressure tests under which g
conditions visual examination VT-2 is performed in ac::ordance with
- IME-5240 to detect leakages."
2.
IWC-5210(a) states, "The pressure retaining components within each
. system boundary shall be subjected to a system pressure test
.O
-conducted during'a system-functional test, system inservice test, or
- a. hydrostatic test, and visually examined by the method specified in
' Table IWC-2500-1, Examination Category C-H."
C-3 1-407c Rev. 3 l
Sh,e't 2'of 3 e
Perry Nuclear Power Plant Unit 1*
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RELIEF REQUEST No. PT-005 I
- 3..
Table INC-2500-1, Examination Category C-H, specifies a VT-2 examination once per inspection period for inservice or functional testing and once per inspection interval for hydrostatic testing.
III. Relief' Requested Code Case N-522 accepts the test requirements of 10 CFR 50, Appendix J as an alternative to the testing requirements of ASME Section XI, Table IwC-2500-1, Category C-H, for pressure testing piping that
.. penetrates a containment resse1~when the piping and isolation valves that
- are part of the containment system are Class 2 but the balance of the piping system is outside the scope of Section XI.
IV.
Batis for Relief Pursuant to-10 CFR 50.55a(a) (3)(i), the proposed alternative provides an.
acceptable level of quality and safety.'
- The proposed alternative reduces the amount of redundant testing' required on the -same' systems' by the imposition of both ASME Section XI and 10 CFR 50, Appendix J.
Currently, imposition of the INC-2500-1 test
-requirements results in additional testing as follows:
'1.
Water systems are flooded and pressurized through the associated penetration test tap and a VT-2 v4sual examination-performed during.
the pressurization period.
2.
Air and gas systems are tested in'an identical manner to the 10 CFR 50, Appendix J method and a VT-2 visual examination is performed during the pressurization period.
9 For the penetrations listed in S6ction I above, 10 CFR 50, Appendix J testing is performed by draining the test volume and pressurizing the test voluce with air tc a pressure of-P.,' where P. is the peak calculated
-containment internal pressure. The rate of makeup flow is determined and compared to acceptance criteria based on allowable containment leak ra'tes.
I Thus, by being.able to taks credit for the ASME Section XI testing by.
using the:10 CFR 50, Appendix J testing,~ elimination-of the redundant testing reduces the number of tests required ou the same system.
t.
Leakage from water systems would be-indicated during,the 30'CFR'50, Appendix J. test more,readily than the INC-2500-1 test due to the lower-density of the air test medium. Based on this fact, use of the Appendix J
. test program for water systems is conservative when compared to the ASME Section XI program.
C-3 1-407d Rev. 3 l
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1h Sh.eet 3 of 3' x_j Perry Nuclear Power Plant ~ Unit 1 RELIEF REQUEST No. PT-005 Code Case N-522 Leakage from'au and other gas systems would be Indicated by 10 CFR 50,
^
Appendix J testing in m'similar manner to an 2WC-2500-1 test. Based *on 3 -
this f'act,.the two programs are e.ssentially equivalent.
- The frequency of testing will be'in accordance with 10 CFR 50, Appendix J.
The 10 CFR 50, Appendix J testing is performed by a staff of Perry employees supplemented by' contract personnel. All personnel involved in
. local' leak rate, testing-(LLRT) at Perry are qualified in accordance with the current' Perry-specific ~LLRT training program..Therefore, Appendix J testing is performed by personnel trained to recognize unacceptable leakage from a pressure boundary.
V.
Alternate Ex'mination a
)
In' lieu of the requirements specified in IWA-5211 and IWC-5210, Perry will I
follow the guidance of Code Case F-522 for pressure testing of safety class 2 containment penetrations associated with non-safety class' systems.
Testing required by 10 CFR 50, Appendix J may be used as an alternative to
~
s the rules in Table IWC-2500-1, Category C-H, for pressure testing piping-that penetrates a containment vessel, when the piping and isolatfon valves that are part of the containment system are Class 2 but the balance of the piping system is outside the scope of Section XI.
~
1 The. testing will be conducted at a pressure of P., where P. is the peak calculated containment internal pressure. Whenever the testing results indicate leakage, the test procedure will provide criteria for identification _of.the source of the leakage, including provisions for detection and location of through-wall leakage in the containment isolation valves and pipe segments'in between.
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l C-3 1-407e.
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. Perry Nuclear' Power Plant Unit l' RELIEF REQUEST No. PT-006
~
Code Case H-546 I.
Identification of Components Class 1, 2, and 3. systems subject to pressure testing.
i II.
ASME Boiler & Pressure Vessel' Code Section XI Requirements Tables IWB-2500-1, IWC-2500-1 and IND-2500-1 of the 1983 Edition through Summer 1983 Addenda of Sect. ton XI require the VT-2 examination method for pressure testing.- INA-2300(c) requires that personnel performing the VT-2 visual' examinations be qualified by the. Owner or-the Owner's. agent in accordance with the comparable levels of competency as defined in
-ANSI N45.2.6-1973.
Perry further utilizes' Code Case N-448, " Qualification
- of'VT-2 and VT-3 Visual Examination Personnel,'Section XI, Division 1,"
which reflects later editions of IWA-2300 that require personnel
' performing visual examination to be qualified and certified to comparable levels of qualification as defined.in f%T-TC-1A and the Employers written
- I practice.
4 III. Relief Requested.
Pursuant to 10 CFR 50.55a(a) (3) (i), relief is requested from requiring that the personnel performing the VT-2 examinations be qualified and certified to' comparable levels of.quM ification as defined in.SNT-TC-1A.
IV.,
Basis for Relief The use of' Code Case N-546 will eliminate the need to treat VT-2 examination personnel as NDE personnel'..The Abstract of SNT-TC-1A states, "This standard applies to personnel whose specific tasks or jobs require Appropriate knowledge of the technical principals underlying "r nondestructive testing. (NDT) methods' for which they have responsibilities a
-within the scope of VT-1 and VT-3. examination" methods." VT-2 requires no special knowledge of technical principals' underlying its performance.
It,
e -
is simply the straight forward examination for leakage. No special skills
..ar +='hai m1 +=iaiac are 'e ri-ad Ja ardar to dasarra uatar Arinaia? Jzca a component or bubbles -forming on a joint wetted with leak detection solution., As such, qualification in accordance with'the provisions of the
~
' Code Case does not.present any reduction in quality or safety.
In. fact,.
l it will.' facilitate the qualification of those personnel most familiar with i
the wa1Adown of plant systems.
l i.
Additionally, there is a-cost' benefit of approximate 1y' $12,000 per t
operating. cycle realized by. eliminating the formal certifi. cation of Perry l
and contracted VT-2 examination, personnel.
i M
I C-3 1-407f Rev. 3 l
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Perry Nuclear Power Plant Unit 1
(
RELIEF REQUEST No. PT-006
- Code Case H-546 l
In summary, approval of this request would be in accordance with l
10 CIlt 50.55a(a) (3) (1), as compliance with Code Case N-546 will provide.an essentially equivalent alternative to the IMA-2300 requirements.
It would also provide relief from the administrative and financial burdens of certificat, ion, which do not' provide any compensating increase in-the level of quality or safety.
V.-
Alternate Examination-
~
CEI proposes to perform VT-2 examinations utilizing personnel qualified in accordance with the provisions of Code Case N-546 in lieu of personnel who -
are qualified and certified to comparable levels of qualification as defined in SNT-TC-1A.' The qualification provisions specified in Code Case N-546 are as follows:
(1). Personnel must have at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of plant walkdown experience, such as that gained by licensed and'nonlicensed operators, 1ccal leak rate personnel, system engineers, and inspection and nondestructive examination personnel.
(2)- Personnel must receive at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of training on Section XI
--requirement 6 and plant. specific procedures for VT-2 examination.
(3)
Personnel must meet 4 vision test requirements of IMA-2321,
^
1995 Edition.
Training and qualification of VT-2 personnel will be documented and the records will be maintained.
Additionally, to provide for consistent, quality VT-2 visual examinations, the examinations.will be performed using standard procedures. An L
independent review and evaluation of the VT-2 visual examination results will be performed and documented'on *he examination records.
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.Sh et 1.of 3 Perry Nuclear. Power Plant Unit 1,
RELIEF REQUEST No. PT-007
-I.
Identification of Components cimas 3 maiety or re&ierf vel w piping which dischargoe interthe-containment pressure suppression pool.
II.
ASME Boiler & Pressure Vessel Code Section XI Requirements Hydrostatic pressure tests per the 1983 Edition through Summer 1983 Addenda of Section XI, section IND-5223(f).
III. Relief Requested Pursuant to 10 CFR 50.55a(a) (3) (ii), relief is requested from performing the Code required hydrostatic tests. An alternative pressure test is proposed.
IV.
Basis for Reilef ASME Code,Section XI, Table IWD-2500-1, requires hydrostatic testing of O)
Class 3 pressure retaining components. For safety or relief valve piping
(
which discharges into the containment pressure suppression pool, section IWD 5223(f) states that a pneumatic test (at a' pressure of 90% of the pipe submergence head of water) that demonstrates leakage integrity shall be performed in lieu of system hydrostatic tests at the end of each
.10-year inservice inspection (ISI) interval.
The reactor coolant system has a total of 19 safety / relief valr4 discharge lines. These lines are used to direct steam from the main steam lines to
' the suppression pool allowing removal of the latent heat through condensing of the steam within'the suppression pool. The valve'disch'arge piping and associated valves (i.e., vacuum breakers) are designated ISI Safety Class 3 from the safety / relief valve discharge ports to the end of the submerged quenchers. Each line's multiple vacuum breakers (i.e.,
simple ~ check valves) eliminate the pressure differential created between the drywell atmosphere and piping following a safety / relief valve actuation. Therefore,,Kdi d...y. piping vrwsure Twtaiming
",vmM.,, is not leaktight.
L The safety / relief valves are routinely (i.e., each refueling outage) used during valve testing and expected to see service during unplanned plant
~ transient conditions (i.e., reactor scrams!. The proper operation of the relief system ensu*es the int.egrity of the piping to perform its design functicn.
IOm C-3 1-407h Rev. 3 l
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Slye'ei 2 of 3, l
Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. PT-007 The Cleveland Electric Illuminating Company (CEI) has determined that performing hydrostatic testing results in a hardship without a compensating _ increase in the level of qpality and safety.
The following hardships would be encountere,d with the performance of hydrostatic testing in accordance with the Code, First, the hydrostatic test pressure conditions are unique to these discharge lines, and therefore, special.
test equipment will need manufacturing (e.g., blank flanges with test ports). Additionally, the VT-2 examinat; n during the pressurization of the pneumatic test pressure boundary would include the application of leak checking solution (i.e., snoop) to over 35 welds and mechanical connections for each of tce 19 discharge lines. To perform the snooping approximately 35 feet of scaffolding would be needed for each of the 19 discharge pipes within the.drywell structure.
Portions of the drywell scaffolding would have to be ecected in high radiation fields. The total effect on radiation exposure cai not be easily estimated due to the massive task being undertaken. Lowever, dose calculations have been estimated as an additional 5.0 manrem, for the staging (i.e., scaffolding)
- work, for the examinations and test equipment, for the performance of the VT-2 exams, and fcr restoration. Therefore, preparation and p,erformance O
of the 10-year system hydrostatic tests at 90% of submergence pressure (i.e., approximately 5.4 psig) involvos considerab1'e time, expense, manpower and radiation dose without a compensating increase in the level of quality or safety.
Since the 1983 Edition, the ASME Subcommittee XI concluded that the requirements of section IWD-5223(f) served no useful purpose and the pressure test has been exempted.Section XI, section IWD-5223(f),
1992 Addenda, states that open ended Class 3 safety or relief valve discharge lines including safety and relief valve piping which discharges into the containment pressure suppression pool, are exempt from hydrostatic test.
Industry experience has demonstrated that inservice leaks are not discovered as a result of hydrostatic pressures propagating an existing flaw through-wall. X1so, since the purpose of these discharge lines is to direct.staam.f. low, Jusd.not provida.a 1 =d* 4 che h=re4 =r: de*= = 4 n i ng.zAs location of flaws would not provide.a compensating increase in the level of quality and safety.
The safety / relief valve discharge lines are basically open ended piping, that function to direct the steam flow to the quencher, and are c.T a leaktight pressure retaining boundary. Therefore, rather than performing the 90% submergence pressare test of Section XI, section IWD-5223(f),
1983 Edition, performing the requirements for open ended portions of discharge lines stated in aection IWD-5223(d) of the sale Code Edition O
would be appropriate.. Section IWD-5223(d) requires confirmation of adequate flow during systen' operation in lieu of performing system hydrostatic testing.
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' <.,Sgget 3 of 3 Perry' Nuclear Power Plant Unit l' RELIEF REQUEST No. PT-007 V.
Alternate Examination' As an alternative to the hydrostatic / pressure test requirement of section.
IWD-5227(17, CErproposes to perform the hydrostatic / pressure' test requirements of section IND-5223(d). Confirmation of adequate flow in accordance with section IWD-5223(d) will satisfy the inspection'
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requirements oft extent of examination (pressure retaining material),
examination method (visual, VT-2), and frequency of examination (each inspection interval).
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'9.0 -CALIBRATION STANDARD DRAWINGS 9.1, Calibration Standards 9,
p; Included in this'section is a listing of NDE calibration standards-required to perform ultrasonic examinations on piping and components subject to the examination requirements of ASME Section XI.
The UT calibration standard design and material selection is in accordance with the requirements.of ASME Section V and XI as applicable. In addition to the required notches, drilled holes have been installed as additional reflectors in accordanca with tha Drovi=4a== oL the.applicabla Pad **-
The actual drawings are not' included in this' document at'this time. They are in process of being fabricated as 'As-Builts' and will be added upon completion.
Table 9-1 is a listing of the calibration standards required in the performance of reactor vessel tacminations.
Table 9-2 is a listing of the' calibration standards required in the performance of examinations on piping and components other than the reactor vessel.
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