ML20236U699
| ML20236U699 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/24/1998 |
| From: | Hammer M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9807300383 | |
| Download: ML20236U699 (22) | |
Text
J Northern States Power Company l
Monticello Nuclear Generating Plant
{
2807 West County Road 75 Monticello. MN 55362 l
July 24,1998 10 CFR Part 50 Section 50.55a US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License Nc. DPR-22 Request for Relief for the 3rd 10-Year Interval inservice Inspection Program On March 13,1997 we submitted for review our latest revisicn (No. 2) of our third 10-year Inservice Inspection Examination Plan for Monticello. The purpose of this letter is to request review and approval of ISI Relief Request No.10 to the third 10-year plan.
This relief request is submitted in accordance with a coinmitment made in Monticello LER 97-004 dated March 24,1997 titled " Failure to Submit Relief Requests for Limited in-service inspection Examinations." Relief Request No.10 addressesSection XI inservice inspections of limited examination coverage. Regulatory Guide 1.147 endorses American Society of Mechanical Engineers (ASME) Code Case N-460 which allows greater than 90% coverage of Class 1 anf12 welds to be considered " essentially 100% coverage." Monticello has a number of welds and components that cannot be 100% inspected, primarily due to original design and/or construction obstructions or configuration interferences, for which Regulatory Guide 1.147 is being invoked.
I This letter contains no new Nuclear Regulatory Commission commitments.
)
Please cor' tact Sam Shirey, Sr. Licensing Engineer, at (612) 295-1449 if you require further information.
i i (4f' l
jy Michael F. Hammer l
Plant Manager l
Monticello Nuclear Generating Plant c:
Regional Administrate -lli, NRC NRR Project Manager, NRC Sr. Resident inspector, NRC State of Minnesota Attn: Kris Sanda J Silberg i
Attachment:
ISI Relief Request No.10 9807300383 980724 PDR ADOCK 05000263 G
PDR u_-_-_-------------.-
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN l
ISI Relief Request No.10 l
Limited Examination SYSTEM: Various Class: 1 and 2 Category: Va-ious Item: Various Impractical Examination Requirements:
ASME Section XI (1986 no addenda) Code requires examination of essentially 100% of weld length for in-service inspection (ISI) of components per Table IWB-2500-1, and IWC-2500-1. Reg. Guide 1.147 endorses Code Case N-460, " Alternative Examination Coverage for Class 1 and Class 2 Welds." This code case allows greater than 90%
coverage of a weld to meet the " essentially 100%" requirement.
This relief request is submitted in accordance with a commitment (M97024A) made in NSP Letter to NRC dated: March 24,1997. Titled: LER 97-004 " Failure to Submit
(
Relief Requests for Limited in-service Inspections Examinations".
This facility was designed and constructed with limited accessibility. Due to component configurations and/or physical barriers and interference, essentially 100% inspection coverage is not achievable on some IS! components items examined for the Third Ten I
Year Interval.
Basis for Relief:
The following 10 CFR 50.55a paragraphs apply to the in-service inspection of components in accordance with the ASME Section XI code:
50.55a(g)(1): !'or a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1,1971, components (including supports) must meet the requirements of paragraphs (g) (4) and (5) of this section to the extent practical.
50.55a(g)(4): Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code.. to the extent practical within the limitations of design, geometry and materials of construction of the components.
50.55a(g)(5)(iv): Where an examination requirement by the code or addenda is determined to be l
impractical by the licensee and is not included in the revised in-service inspection program as permitted by paragraph (g)(4) of this section, the basis for this determination must be demonstrated to tne satisfaction of the Commission..
I Page 1 of 21 l
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NORTHERN "ATES POWER INSERVICE INSPECTION MONTICEl. s -
10 INTERVAL.
EXAMINATION PLAN j
l Monticello was designed and constructed prior to development of ASME XI, therefore, plant and component design and layout for inspection coverage required by ASME Section XI Code in many cases, is not sufficient to permit satisfying the current code requirements. Inspection limitations are primarily due to obstructions and configuration interference.
Summary of the limited examinations are described below and also included in Table 1
]
attached.
Part A: Category B-D, " Full Penetration Welds of Nozzles in Vessels" Reactor Vessel Nozzle N-2G NV: Coverage for nozzle / vessel weld is 51%.
Inspection limited due to nozzle configuration. (See Figure 1).
Reactor Vessel Nozzle N-2H NV: Coverage for nozzle / vessel weld is 47%.
Inspection limited due to two instrumentation attachments at bottom dead center and nozzle configuration. (See Figure 2).
Reactor Vessel Nozzle Inner Radius N-2H-IR: Coverage for the inner radius inspection is limited to 92% due to two instrument attachments at bottom dead center. (See Figure 3).
Reactor Vessel Nozzle N-3C NV: wverage for nozzle / vessel weld is 51%
inspection limited due to nozzle configuration. (See Figure 4).
Reactor Vessel Nozzle N-4B NV: Coverage for nozzle / vessel weld is 51%.
Inspection limited due to nozzle configuration and welded instrument attachments at 16" CW limits all scans. (See Figure 5).
Reactor Vessel Nozzle Inner Radius N-4B-IR " overage for the inner rad!us inspection is limited to 98%, due to instrumentaaon attachments located 6" from bend radius and 24" CW from TDC. (See Figure 6).
Reactor Vessel Nozzle N-7 NV: Coverage for nozzle / vessel weld is 89%
limitation due to nozzle configuration. (See Figure 7).
Part B: Category B-J, " Pressure Retaining Welds in Piping" l
l RHR Return A weld W-10: Volumetric examination limited to 43%. Limitation due to weld orientation and pipe configuration. (See Figure 8).
i Page 2 of 21 hE-- --
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN RHR Return A weld W-11: Volumetric examination limited to 50%. Limitation due to configuration of flange and weldolet. (See Figure 9).
l RHR Return B weld W-6: Volumetric examination limited to 88 %. Limitation due to due to proximity of structural beam.(See Figure 10).
1 Recirc. Manifold B weld W-13 LS U&D: Volumetric examination limited to 50%
of long seam weld. Examination limited to only six inches of downstream long seam weld due to support interference. (See Figure 11).
I Part C: Category B-G-1, " Pressure Retaining Bolting, Greater than 2 in. in Diameter."
Reactor Vessel Closure head nuts: Surface examination limited to 57%.
Limitation is due to threading. (See Figure 12).
Reactor Vessel Ligament Threads in Flange: Volumetric examination limited to 96%. Limitation is due to seal ring groove on reactor fk.1ge. (See Figure 13).
Part D: Category C-C, " Integral Attachments for Vessels, Piping, Pumps, and Valves".
CRD Scram Header B hanger attachment H-7: Surface examination limited to 1
0%. Limitation due to restraint configuration. (See Figure 14).
RHR Discharge B, Double Spring 4 lugs H-9: Surface examination limited to 85%. Limitat;on due to stabilizing lug welded to clamp prohibits examination of
]
one end of weld. (See Figure 15) 1 Part E: Category C-F-2, " Pressure Retaining Welds in Carbon Steel or Low Alloy Steel Piping,"
HPCI Steam Discharge Weld W-29: Volumetric and Surface examination limited to 80% and 58%. Limitations due to restraint with fillet weld on weld crown and downstream area of weld.(See Figure 16).
Additional Means of Establishing Integrity:
In addition, hydrostatic tests are performed during regu',arinspection intervals to ensure the piping system is capable of maintaining pressure integrity. System integrity is l
l i
Page 3 of 21
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I NORTHERN GTATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN monitored continuously during normal operation by routine operator rounds during shift and remote monitoring methods, e.g., containment radiation monitoring, containment air monitoring, containment leakage detection and monitoring, containment temperature monitoring, etc.
Alternate Examination:
l The nature of the limitations have been noted on the ISI examination reports and are included in the ISI Outage Summary Report. NSP will cor "nue to document the
}
limitations.
l l
All in-service inspection at Monticello has been done to the greatest extent practical.
I When limitations to required inspections are encountered Materials &Special Process
)
procedure ISI-LTS-1 is applied, which requires alternative examination techniques to be considered, or applied to gain the maximum obta:nable inspection coverage practical.
In all of the above items identified this procedure was used and the maximum inspection coverage was achieved.
The Reactor Vessel head nuts (Part C: Category B-G-1 " Pressure Retaining Bolting, Greater than 2 "in Diameter") require surface examination under 1986 ASME Code Sec. XI, Table IWB-2500-1, item B.6.10. Because of the limitation of examination methodology on the threaded region of the nuts, future examination on this item will be performed according to the requirements of 1992 ASME Code Sec. XI, Table IWB 3
2500-1, item B 6.10, which requires a visual, VT-1 inspection of the surface area of the l
nuts.
)
i I
1 l
Page 4 of 21 l
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NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN Table 1: Summary of Limited Examinations "dbbEUakkb!nnI $I iN5IMSiSTE$1N
- INdfS NiiEMS I 'M5iHUD 'dUNveShd Ti$lt$tibsY B-D B 3.90 REACTOR VESSEL FIG S N-2G NV Volumetric 51 Figure 1 B-D B 3.90 REACTOR VESSEL FIG 5 N-2H NV Volumetric 47 Figure 2 B-D B 3.100 REACTOR VESSEL FIG 5 N-2H-IR Volumetric 92 Figure 3 B-D B 3.90 REACTOR VESSEL FIG S N-3C NV Volumetric 51 Figure 4 B-D B 3.90 REACTOR VESSEL FIG 5 N-4B NV
. Volumetric 51 Figure 5 B-D B 3.100 REACTOR VESSEL FIG 5 N-4 B-IR Volumetric 98 Figure 6 B-D B 3.90 REACTOR VESSEL FIG 1 N-7 NV Volumetric 89 Figure 7 B-J B 9.31 RHR RETURN A 97003-A W-10 Volumetric, 43 Figure 8 B-J B 9.11 RHR RETURN A 97003-A W 11 Volumetric 50 Figure 9 B-J B 9.11 RHR RETURN B 97004-A W-6 Surface 88 Figure 10 B-J B 9.11 RECIRC MANIFOLD B 97006-B W-13 LS-U&D Volumetric 50 Figure 11 B-G-1 B 6.10 REACTOR VESSEL FIG 6 NUTS Surface 57 Figure 12 B-G-1 B 6.40 REACTOR VESSEL FIG 6 LIGAMENTS Volumetric 96 Figure 13 C-C C 3.20 CRD SCRAM HDR B 93268-3A H-7 Surface 0
Figure 14 C-C C 3.20 RHR DISCHARGE B 13142-18a H-9 Surface 87 Figure 15 C-F-2 C 5.51 HPCI STEAM DISCH 13142-19A W-29 Volumetric 80 Figure 16 C-F-2 C 5.51 HPCI STEAM DISCH 13142-19A W-29 Surface 58 Figure 10 Page 5 of 21 i
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4 NORTHERN STATES POWER INSERVICE INSPECTION l
MONTICELLO,3RD INTERVAL EXAMINATION PLAN 1
)
FIGURE 1 Reactor Vessel Nozzle to Vessel N-2G NV Limitatioi; Data Sheet i
Initial Exam Report No: 98-0089 Procedure No. ISI-UT-3A (Rev.7) j ISO No. ISI-FIG S lte m N N 2G NV Description of Limitathn:
All scans limited $.e to nozzle configuration. Exam areas shown below.
l Sketch of Limitation:
l' 0,
aw us cua Ma l
a u sou n a a.r-L se O
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to.m w 1 e q 7
limitation removal requirements:
I None.
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I Page 6 of 21
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NORTHERN STATES POWER INSERVICE INSPECTION l
MONTICELLO,3RD INTERVAL EXAMINATION PLAN t
l FIGURE 2 Reactor Vessel Nozzle to Vessel N-2H NV i
Limitation Data Sheet
}
1 Initial Exam Report No; 98-0087 Procedure No. ISI-UT-3A (Rev. 7)
ISO No. ISI-FIG 5 ftem No. N 2H NV Description of Limitation:
All scans limited due to nozzle configuration. Exam areas shown below. All scans also limited due to I,nstrument attachment at BDC.
I Sketch of Limitation:
"O' sama.es ccad Min M al $ CA Al Ad /E+
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Limitation removal requirements:
)
None.
I Page 7 of 21 E-_--------____--_-
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tJORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN l
Figure 3 l
Reactor Vessel N-2H Inner Fudus l
Limitation Data Sheet initial Exam Report No: 98-0106 Procedure No. ISI-UT-5 (Rev. 5)
ISO No. ISI-FIG S Item No. N-2H inner Radius Description of Umitation:
Twoinstrumentation attachments at SDC.
Sketch of Limitation:
N~ 2 H e
.3~
.Te.sy /
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l Limitation removal requirements:
None.
l Page 8 of 21 t-
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN 4
~ FIGURE 4
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Reactor Vcssel Nozzle to Vessel N-3C NV Limitation Data Sheet initial Exam Report No: 98-0085 Procedure No. ISI-UT-3A (Rev. 7)
ISO No. ISI-FIG S Item No. N 3C No-a:-to-Vessel Weld Description of Limitation:
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All scans limited due to nozzle configuration Exam.'.reas shown below.
Sketch of Limitation:
17 c '
i acea,ats cend M N Acrt:s L $ LA 4 AKA U* W ~
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7 umitation removai requirements:
- None, Page 9 of 21
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 5 Reactor Vessel Nozzle to Vessel N-4B NV Limitation Data Sheet initial Exam Report No: 98-0063 Procedure No, ISI-UT-3A (Rev.7)
ISO No. ISI-FIG S ltem No. N-4B NV Description of Limitation:
Nozzle configuration limits all scans, also welded instrument attachments 2" from l
weld toe 16" CW limits all scans.
Sketch of Limitation:
haan seu Ma al'
,z y
kroat sw wa 9 oc" (W
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Limitation removal requirements:
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Removal is not possible.
Page 10 of 21 E---________.________.
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN
)
Figure 6 Reactor Vessel N-4B Inner Radius Limitation Data Sheet Initial Exam Report No: 984058 Procedure No. ISI-UT 5 (Rev. 5)
ISO No. ISI lG 5 Item No. N-4B Description of Limitation:
Instrumentation attachments located 6" from blend radius and 24" CW from TDC.
Sketch of Limitation:
Toe
%h.
O
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f Limitation removal requirements:
'None.
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l Page 11 of 21
NORTHERN STATES POWER INSERVICE INSPECTION
' MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 7 Reactor Vessel Nozzle to Vessel N-7 NV Limitation Data Sheet initial Exam Report No: 98-0234(0*)
Procedure No. ISI-UT-3A (Rev. 7) 98-0241(45'); 98-0242(60*)
ISO No. ISI-FIG 1 Item No. N-7 NOZZLE / HEAD VENT Description of Limitatiert Scan 2 area limited to 1.5" from centerline on nozzle side due to nozzle configuration. Scan 1 ccan area limited to 6.65" for 45' and 9.5" for 60* due to nozzle configuration. 88.9% code coverage achieved.
Sketch of Limitation:
M-7 NV i
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I Limitation removal requirements:
None.
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Page 12 of 21
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NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN FIGURE 8 RHR Return A W-10 Limitation Data Sheet i
Initial Exam Report No: 98-0141 Procedure No. ISI-UT-1 (Rev.12)
ISO No. ISI 97003-A Item No. W-10
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l Description of Limitation:
No scan on 16" pipe due to weld orientation. No circ scans on weld and 16" pipe i
due to configuration.1.25" average scan area on weldotet side. 43.4% code
)
coveraga achieved.
Sketch of Limitation:
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Limitation removal requirements:
None.
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Page 13 of 21 l
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 9 RHR Return A W-11 Limitation Data Sheet 99-oWJ Initial Exam Report No: ".," ^;,1 e* Procedure No. ISl-UT-1 (Rev.12)
ISO No. ISI 97003 A Item No. W-11 Description of Limitation:
No scans 1 & 2 due to configuration of flange and weldolet. 50.0% code coverage achieved.
Sketch of Limitation:
)
i WhDodf i
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Limitation removal requirements:
None.
+
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Page 14 of 21 l
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NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 10 RHR Return B W-6 Limitation Data Sheet
.I initial Exam Report No: 98-0160 Procedure No. ISI-MT-1 (Rev. 9) '
ISO No. ISI 97004-A Item No. W 6
)
l Description of Limitation:
Limitation due to structural beam at 3" CW and 3" CCW from 0*.
Sketch of Limitation:
6'
-A.
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I Limitation removal requirements:
None. Permanent building structure.
I l
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i Page 15 of 21 L
J
NORTHERN STATES POWER INSERVICE INSPECTION j
MONTICELLO,3RD INTERVAL EXAMINAT;3N PLAN 1
FIGURE 11 Recirc. Manifold B W-13 LS-U&D Lirnitation Data Sheet Iritial exam report #
9al c o 4 M Procedure # 151 07-/s I, 7
ISO #
is t-9 7oa G -8 Item #
U - 13 Ls D Description of Limitation n~a 6, " e r n..mxerw n m t wesmm f]r4m MGo n.s f D
n* PA:rV
>M nce rrtentes.
roe ?.
es s wet-on.
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'Z% toJrras n$7Ando o4 ths.'syreum toJ4 frpm FOTh>y ~n I
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.Ske:ch of Lirnitation Liniitation removal requirements NewE
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l-Page 16 of 21 l
e NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN I
FIGURE 12 Reactor Vessel Closure Nuts Limitation Data Sheet Innic! Exam Report No; 98-0263 Procedure No. ISI-MT-2 (Rev. 9) i ISO No. ISI FIG 6 Item No. NUTS 4
Description of Limitation:
No exam on inner threads due to configuration.
57.1% coverage obtained.
j Sketch of Lirnitation:
f.r v * '&
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Limitation removal requirements:
l None.
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I Page 17 of 21 lL______________________
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NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN Figure 13 Reactor Vessel Ligaments Limitation Data Sheet initial Exam Report No: 98-0014 Procedure No. ISI-UT-7 (Rev. 5)
ISO No. ISI-FIG 6 Item No. LIGAMENTS Description of Umitatiert
- Seal ring" groove. Ref. drawing NX-8290-63 (Rev A). Examined studs: 3,5,7,8,9, 10,11,12,14,18,17,20,21, 22,44,45,46,53,54,57,60 Sketch of Limitation:
_QEAL RING" GROOVE k
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plan view Limitation removal requirements:
None.
i Page 18 of 21
{
l NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 14 CRD Scram Header B H-7 I
I TITLE: Limitations to NDE.
NUMBER:
Isi-LTS-1 Revision 0 Figure 3 Limitation Data Sheet initial exam report #'
9 7 c?/ 3 7 Procedure # IsT-MT-I R.CV. &
ISO #
-r s r - 9 'r 26 6 A ltem # H -7 Description of Limitation rao A cccs< Tr> / H\\ L o c r, e u ET-w6 LD5.
C X. A A4 )eJATlO P 3 WA<
d O T~
6 C k.F o R. M m B t) e7 fi3 26:STEAsMT~ eu n.) Fin tJf A To O s). s WM.
Sketch of Limitation
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- 2 Limitation removal requirements N,/A a
Page 19 of 21
NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO,3RD INTERVAL EXAMINATION PLAN FIGURE 15.
RHR Discharge B H-9 Limitation Data Sheet initial exam repert# 94 -0220 Precedure # /5/-M T-/
9.7 iso n 15l-13142 -lS ~A nem # H9 Des tipuon of UmitationSTA2il_l2/NG"LliG WFLDED TO CL AMP P90HIGlTS EXAMINATION GF OME END OF WELD. CLAMP PRCHiSITS EXAMINATION QF PEQll! PED t/2 "GF ADJACENT BASE ME TA L.
MCIO47
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J f:-i. c! - f e.. r !< J e c c e s Sketch ci Lirritation L msteion removal ecuiremen s REMO\\ A L OF Cl A MP :.SS EMBL Y REQlllR ED TO ACHIEVE A DDITIONA L COVERAGE.
Page 20 of 21 L_-_-_______________..___._.____
1 i
l NORTHERN STATES POWER INSERVICE INSPECTION MONTICELLO, 3RD INTERVAL EXAMINATION PLAN l
l I
FIGURE 16.
HPCI Steam Discharge W-29 1
TITLE:
Limitations to NDE I
NUMBER:
ISI LTS-1 Revision 0 Figurs 3 l
Limitation Data Sheet 97 o091(m) {#5 9 7 004 5 B L 6#
initial exam report #
97-ooe6 at Oo-Frocedure # t At-ov-i Q av, gg ISO # tsr-ra.m-1 A A Item #
vo - 1 g Description of Umitation 7 c. sy ti. A i u-t-em s r w A t s. s r-vueen l
ou w E.e o
- c. Q_o em Aw0 b o m 4 W tt E A m Aon
!op w a t,n,
Ses 'GL re tow C~ o o_
C o v s 2. A G E, Ptors su wa H C-*
G o*, Aub ~40
- A u6'E.
41ch Sketch of Limitation Nets: Utom kt ntrear 91 cm)
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Unitation removal r quirements Nav isasi M @E1 e
- l*
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Page 21 of 21
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