ML062780296
| ML062780296 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/19/2006 |
| From: | Hamer M Entergy Corp |
| To: | Johnny Eads NRC/NRR/ADRA/DPR |
| References | |
| %dam200611, 50-271-LR, TAC MC2297 | |
| Download: ML062780296 (36) | |
Text
j5
.Haard -.RE: Items Needed To Fully Respond To AMR/AMP Questions Pagel1 From:
"Hamer, Mike" <mhamer@entergy.com>
To:
"Johnny Eads" <JHE@nrc.gov>, "Faison, Charlene D" <CFaison@entergy.com>, "Lach, David J" <DLach@entergy.com>, "YOUNG, GARRY G" <GYOUNG4@entergy.com>, "Devincentis, Jim"
<jdevinc@entergy.com>, "Hoffman, John" <jhoffml @entergy.com>, <Mmetell@ entergy.com>
Date:
6/19/2006 5:36:51 PM
Subject:
RE: Items Needed To Fully Respond To AMR/AMP Questions
- Johnny, Attached is an updated LR Commitment List (6/19), and a list of the LRA Amendments both in draft form. Please confirm receipt via e-mail reply.
Original Message -----
From: Johnny Eads [1]
Sent: Thursday, June 15, 2006 1:45 PM To: Faison, Charlene D; Lach, David J; YOUNG, GARRY G; Devincentis, Jim; Hoffman, John; Hamer, Mike; Mmetell@entergy.com Cc: Jonathan Rowley; Jacob Zimmerman; Kenneth Chang ; Michael Morgan
Subject:
Fwd: Items Needed To Fully Respond To AMR/AMP Questions A number of VY responses to NRC audit questions refer to "commitments",
"LRA amendments", and "One-Time Inspection (OTI) Items". In order to appropriately address and disposition each of the question responses, the NRC audit team is requesting the following from the applicant:
- 1) The current listing of commitment items
- 2) The current listing of "LRA amendment" items
- 3) The current listing of OTI items Please provide the requested lists by first thing Monday morning, June 19th.
CC:
"Jonathan Rowley" <JGR@nrc.gov>, "Jacob Zimmerman" <JIZ@nrc.gov>, "Kenneth Chang "<KXC2@nrc.gov>, "Michael Morgan" <MJM2@nrc.gov>
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RE: Items Needed To Fully Respond To AMR/AMP Questions 6/19/2006 5:35:29 PM "Hamer, Mike" <mhamer@entergy.com>
mhamer@entergy.com Recipients nrc.gov OWGWPO02.HQGWDO01 JHE (Johnny Eads) nrc.gov TWGWPO03.HQGWDO01 JGR CC (Jonathan Rowley) nrc.gov TWGWPO04.HQGWDO01 JIZ CC (Jacob Zimmerman) nrc.gov OWGWPO03.HQGWDO01 KXC2 CC (Kenneth Chang) nrc.gov ATLPO.ATLDO MJM2 CC (Michael Morgan) entergy.com Mmetell jhoffml (John Hoffman) jdevinc (Jim Devincentis)
GYOUNG4 (GARRY G YOUNG)
DLach (David J Lach)
CFaison (Charlene D Faison)
Post Office OWGWPO02.HQGWDO01 TWGWPO03.HQGWDO01 TWGWPO04.HQGWDO01 OWGWPOO3.HQGWDO01 ATLPO.ATLDO Route nrc.gov nrc.gov nrc.gov nrc.gov nrc.gov entergy.com
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Page 2 ýI Files Size MESSAGE 1006 VY LR Commitment List 6-19-06.pdf VY LRA Amendment List 6-19-06.pdf Mime.822 1
Date & Time 6/19/2006 5:35:29 PM 919483 3339239 Options Expiration Date:
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APPENDIX A COMMITMENTS FOR LICENSE
-J During the development and review of the Vermont Yankee Nuclear Power Station provide aging management programs to manage the effects of aging on structures ar following table lists these license renewal commitments, along with the implementa ITEM COMMITMENT IMPLI 1
Guidance for performing examinations of buried piping will be enhanced to specify that coating degradation and corrosion are attributes to be evaluated.
2 Fifteen (15) percent of the top guide locations will be inspecteA using enhanced visual inspection technique, EVT-1, within first 18 years of the period of extended operation, wit ast one third of the inspections to be completed within t 6
years and at least two-thirds within the first 12 y the period of extended operation. Locations select examination will be areas that ded the fluence threshold.,
3 The Diesel Fuel Monito gram wI ced t M
ensure ultrasonic thic easurement o oil sto tank bottom surfac e performed every 1 s during tank cleaning an ction.
Ltion, Ent?.rgy made commitments to" extended period of operation. The we of the commitment.
Related LRA Section NoJ Comments
.1. 1/Audit Items 5
& 130 1.1.7/Audit Item 1 nitm r
rch 21, 2012 B.1.9 4
The Diesel Fuel Program will be en d to March 21, 2012 B.1.9 specify UT measure the fuel oil storag bottom surface will have aceep erion ý- 60%.*t.
5 The Fatique Monitoring Pr ill be n toeither March 21, 2012 B.1.11 require periodic update of cun
~ f**
sage factors (CUFs), or to require update of number of accumulated cycles approaches the er assumed in the design calculation.
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ITEM COMMITMENT IMPLEMENTATION SCHEDULE SOURCE Related LRA Section NoJ Comments 6
A computerized monitoring program (e.g., FatiguePro) will be March used to directly determine cumulative fatigue usage factors (CUFs) for locations of interest.
7 The allowable number of effective transients will be established MarcIe for monitored transients. This will allow quantitative projection of future margin.
4
.9B.1.11 L.
9
.. 11 B.l.12.1/Audit Items 35, 151, 152
& 153 8
Procedures will be enhanced to specify that fire damper frames in fire barriers shall be inspected for corrosion. Acceptance criteria will be enhanced tod verify no significant corrosion.
March 21,20 9
Procedures will be enhanced to state that the diesel engine sub.
systems (including the fuel supply line) shall be observed whit the pump is running. Acceitance criteria will be enhanced to verify that the diesel engine did not exhibit signs of de atil while it was running; such as fuel oil, lube oil, cool exhaust gas leakage.
I B.I.12.1/Audit Items 33, 150 &
155 p.
10 The Fire Water System Program will be enhan that a sample of sprinkler heads wi inspected guidance of NFPA 25 (2002 5.3.1.
25 also contains guidanice every years after initial field testing.
- ify
~1-t arse after enter gthe eriod of extended operation B.1.12.2
-- i a-lq'*........
. i 7 The Fire Water Sys gram will beenh specify'Y that wall thickne uations of fire protectio g will be performed on sys onents using non-in techniques (e.g., vol testing) to identify nce of loss of material due to corro ese inspecti0 be performed before the end rrent ope term and at intervals thereafter during th of d operation.
Results of the initial evaluations to determine the appropriate inspection interval to e ging effects are identified prior to loss of intended fu tion.
March 21, 2012 I
IB. 1.12.2/Audit Items 37 & 41 I
I I
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ITEM I COMMITMENT IMPLEMENTATION SOURCE SCHEDULE&
Related LRA Section NoJ Comments 12 Implement the Heat Exchanger Monitoring Program as March described in LRA Section B. 1.14.A 13 Implement the Non-EQ Inaccessible Medium-Voltage Cable Marc%
Program as described in LRA Section B.1.17.
14 Implement the Non-EQ Instrumentation Circuits Test Review March 2 Program as described in LRA Section B.1.18.
4 4
B. 1.14 L
m
.1.17 0.18 15 Implement the Non-EQ Insulated Cables and Connections Program as described in LRA Section B.1.19.
March 21,,
B.1.19 m
4 16 Implement the One-Time Inspection Program as described in LRA Section B.1.21.
B.1.21
- 17.
Enhance the Periodic Surveillance and Preventive Maintenan(
Program as necessary to assure that the effects of aging will b managed as described in LRA Section B. 1.22.
4 B.1.22 18 Enhance the Reactor Vessel Surveillance Program t proceduralize the data analysis, acceptance criterit corrective actions described in the program des Section B. 1.24.
r L LRA B.1.24 19 Implement the Selective Le descri March 21, 2012 B.1.25 LRA Section B. 1. 19.*
1-20 Enhance the Structure toring Progr ify that March 21, 2012
- B.1.27.2 process facility ce n
idr odn z_-a (CST) enclosure an'nls
,N anke re and restraining wall, trench, diesel generat ble trench, fuel oil pump house,'.
vtlater pipe trench,I ay seals and gaskets, and hatch sgaskets are i d in the 21 Guidance for performing stru ns of wood to March 21, 2012 B. 1.27.2 identify loss of material, crdckid grin material properties will be added to *,the S tr Monitoring Program.
ITEM COMMITMENT IMPLEMENTATIONI SCHEDULE & I SOURCE m
Related LRA Section No!
Comments 27 For each location that'may exceed a CUF of 1.0 when considering environmental effects, VYNPS will implement one or more of the following:
(1) further refinement of the fatigue analyses to lower the predicted CUFs to less thaii 1.0; (2) management of fatigue at the affected locations by an inspection program that has been reviewed and approved by the NRC (e.g., periodic non-destructive examination of the affected locations at inspection intervals to be determined by a method acceptable to the NRC);
(3) repair or replacement of the affected locations.
g 4.3.3/ Audit Items
ý9, 107 & 318 Should VYNPS select the option to manage environme I-assisted fatigue during the period of extended operat tail of the aging management program such as scope,
- cation, method, and frequency will be provided to the or to the period of extended operation.
28 Revise program procedures t e Ins March 21, 2012
.1.16/Audit Item Program will maintain ins*
cord 47 ISA S7.3 29 VYNPS will either i ore plate wedges lete a March 21, 2012 B.1.7/ Audit Item 9 plant-specific an*
determine acceptance
[a for continued inspec ore plate hold down bo in accordance with B
- 5.
- 30.
Revise System Walkdo am to specify ystem March 21, 2012.
.1.28/ Audit Items inspections every 6 mont, 141, 146 & 298 31 Revise Fire Water System P o sp nual fire March 21, 2012 B.1.12.2/ Audit hydrant gasket inspections and Items 39 & 40 32 Implement the Metal Enclosed Bu am in accordance with March 21, 2012 Audit Item 97 a license renewal applicati~
n amend a
nt.
ft
'V
Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
DescriDtion / To ic Submittal Date Commitment (Yes / No' NRC Accession No.
NRC Accession No.
(Yes / No) 001 N/A N/A EPU Power Change 03/15/06 NO 002 N/A N/A Drywell Shell Information 4
4 003 11 B.1.7 Accessible regions of the core shroud welds H1,H2 aare UT examined lAW BWRVIP-76. Portions of the total accessible regions of H1,H2 & H3 are characterized a reliant analysis performed by the shroud repair design determined the minimum design reliant weld lengths.
- 1. The exception to the BWR vessel internals program relate to the core shroud (page B-27) will be deletec l *f, 161380079 05/15/06 NO NO
- 2. Exception Note #1 on page B-29 will 4
+
4 003 26 B.1.10 LRA Appendix B.1.10 will be revised VYNPS may perform re-analysis of a order to extend the qualification,eI under 10 CFR 50.49 on a rou3/4 EQ program. Important attn for aging evaluation include al m And reduction methods, g a, criteria, ae actio e]
detaila NO 003 48 B.1.17 L
-I.
1-revIs lude the following:
i ccumul in manholes is re. An engineering evaluation ocument and determine the lered in manhole inspection NO fr"
Vermont Yankee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA No.
Item No.
Section No.
Descrintion I ToDic
Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit Related LRA Submittal Commitment Date (Yes / No)
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Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit Related LRA Submittal Commitment Date fv-iY / Nn)
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Vermont Yankee License Renewal Application Amendment List LRA Amend.
Mn_
LR Audit It~mrn N.
Related LRA An~tinn Nn.
Submittal Commitment Date lVAn I Nn' fle~rintInn I Tnnir~
NRC A~~sion No.
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203 3.1.1-19 All piping and fittings less than 4" NPS, except for the head NO seal leak detection line, are covered by NUREG-1801 ite IV.C1o-1, which identifies ISI, water chemistry for BWR__
one-time inspection (OTI) for small bore piping as th d
applicable aging management programs for crackine VYNPS ISI program includes piping and fittings lessl NPS. The LRA will be clarified to indicate that ISI in ao to water chemistry control - BWR and OTI applies to components.
L 003 224 3.3.1 The One-Time Inspection program will be revis clude NO activities to confirm the effectiveness of the tri Diesel Fuel Monitoring programs. a 003 122 3.3.1 The One-Time Inspection program will NO activities to confirm the effectivenessograms.
Diesel Fuel Monitoring programs
":e 003 226 3.3.1 The One-Time Inspection pr ill be Ire to Incl NO activities to confirm the tenss of the Diesel Fuel Monitoring rm.
003 227 3.3.1 To prov!
arificatl
.fectiveness of the Water NO
- Che, Maryi*
BWR, and Closed Ce pr rrrnfir *the One-Time tion program.
quiesa me t the rise renewal applic*
change Appendix A, SAR upplement descriptions 1e Water Chemistry Control -
- xiliary Systerns, BWR *Dlosed Cooling Water programs lictlystae*
On-spection. Program activities will l
the effectives
=ese programs.
003 229 3.3.1 T~htii~ *)e
- Insp, rogram will be revised to include iNO acivt
.pi ffectiveness of the Oil Analysis and Diesel NF
.3programs.
S.*
Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit No.
Item No.
Related LRA Section No.
3.3.1 Submittal Commitment Description I Topic N
To provide further clarification, the effectiveness of the Water Chemistry Control - Auxiliary Systems, BWR, and Close Cooling Water programs is confirmed by the One-Tim Inspection program. This requires an amendment to license renewal application to change the Appendix AR 4upplement descriptions for the Water Chemistry Co Auxiliary Systems, BWR and Closed Cooling Water progr to explicitly state One-Time Inspection Program activitie confirm the effectiveness of these programs.
To provide further clarification, the effectivenes,,
-t Water lýhemistry Control - Auxiliary Systems, BW.I d
=
Cooling Water programs is confirmed by ý a-*T.
Inspection program. This requires
'an at t!
men t t license renewal application to chang t*
ppend ' rS~f supplement descriptions for the W~aciter* *mist*
trol--
Auxiliary Systems, BWR and(
l!
C* *g
- r "rogr to, explicitly state One-Time Ir
- n Pro'r
,iie.
confirm the effectiveness
!Atl*e programs.*
RC The NUREG-1801 Vol.
VIII.Fl-8
ýines t
i Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Submittal Commitment
Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Submittal Commitment Description / Topic Accession 003 242 3.5.1 Table 3.5.2-1 on Page 3.5-50 of the LRA, for component Bellows (reactor vessel and drywell) is not consistent wit referenced NUREG-1801 Vol. 2 item. The Table 3.5.
item "Bellows (reactor vessel and drywell)" and the corresponding line item in Table 2.4-1 should be del rpactor vessel and drywell bellows perform no licens intended function. These components are not safety-i -
and are not required to demonstrate compliance with regulations identified in 10 CFR 54.4(a)(3). Failure of bellows will not prevent satisfactory accomplishment of a safety function. Leakage, if any, through the directed to a drain system that prevents th contacting the outer surface of the dryw 1.
°
Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Submittal Commitment Date (Yes / No)
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Vermont Yankee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA Submittal Date Commitment
Vermont Yankee License Renewal Application Amendment'List I
LRA LR Amend. Audit Related LRA Submittal Commitment
)f
Vermont Yankee License Renewal Application Amendment List escription I Topic
- able 3.5.2-6, Page 3.5-72 of the LRA, for component ilectrical and instrument panels and enclosures, material lalvanized steel in an exposed to weather environme iging effect is none. Reference question A-W-13 a ami tow this component is protected from constant wetti dd frying conditions.
Is identified in the response to question A-W-1 3, loss naterial is the aging effect requiring management an Structures Monitoring Program is the aging managemn t irogram. This is consistent NUREG-1801 Vol. 2 m !11.B4-7, rummarized in Table gItem 3.5.1d-50, and N s.
Table 3.5.2-6 on Page 3.5-78 of the I'RA*
o IL Structural bolting, material galvanized st fn an e) y/eather environment; the aging effect j ne. R nc*
question A-W-1 3 and explain how h~is
, t~oen*
prote(*
from constant wetting and dryit *ndi t s.,
As identified in the response estion A-loss material is the aging effe ring manage
'tructures Monitoring Pr the aging m t
hrogram i nsisten oi-1801 Vol. 2 Item 114-7, summ
,,4 00 Itmnd Note C applies.
F T able,*
.5.1.5, cussion column
- d read, "Th del shell'! *e moisture barrier iere the drywell shell I es embe* *ed in the drywell
-oncrete floor are inspec* accordance with the
- tainment Inservice In tion (IWE) Program. To be
- tent, LRA Section *.2.1.4, should indicate that the o1 floor molstur ter will be inspected under the CO nt Inservi*
ection (IWE) Program. The inlspe iart
- ontainment Inservice Inspection (JWE) P'*1*
- I be retained as part of that program through thq
- f extended operation.
D* *.
I Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
I Description / Topic NRC Accession No.
Submittal Date Commitment (Yes / No) 003 267 3.5.2
- 1) The LRA will be amended to reflect the following changes.
NO The following line for the torus penetrations will be addedc Table 3.5.2-1:
AW Torus mechanical penetrations PB, SSR Carbon steel Protected.from weather Cracking.n 1
(fatigue) TLAA-metal fatigue II.B4-4 (C-13) 3.5.1 9A
- 2) Since fatigue for the vent system is event driven an is n an age related effect, the following line will be de d from Table 3.5.2-1:
Drywell to torus vent system PB, SSR Carbon steel Protected from weather C ng (fatigue) TLAA-metal fatigue I1.B13.
(C-21) 3.5.1 8 A
- 3) The discussion column e able 3.
em 3.5.
Will be changed to state:
Fatigue analysis is a T e torus shell.
torus to d ent syste nt driven and analysis is riot a Ion 3.5
- 4) cuss entrn-e 3.5.1 item 3.5.1-9 the torui*enetrations. See hanged to read as follows:
Iance with 10 CFR 54.21 (c) as tigue TLAAs for the torus and evaluated and documented in a
I
Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Description / Topic NRC Accession No.
Submittal Commitment Date (Yes / No) r V
t Cont.
Cont.
i Cont.
- 6) Section 3.5.2.3, Time-Limited Aging Analyses, will be changed to state:
TLAA identified for structural components and comm include fatigue analyses for the torus and torus pene*
These topics are discussed in Section 4.6.
I.
NO 003 268 3.5.2
- 1) A link from items 3.5.1-12 and 3.5.1-13 will be adi section 3.5.2.2.1.8.
- 2) Section 3.5.2.2.1.8 should state:.
NO Cyclic loading can lead to cracking of steel and ess steel penetration bellows, and dissimilar metal we 1
containments and BWR suppression pool downcomers.
003 269 3.5.2 See Item 268 Response NO 003 270 3.5.1 For clarity, drywell floor liner s ill b an dryw NO shell to floor seal (moisture b
. (Also se it ques
- 76 and 243 which addrei ges to the L t.
r 003 278 3.5.2 The aging management suits for galN FI&
eel NO mponechn oor air f
d dicate loss of material as an a ng effe ctures t*yig as the aging m
eMnt pa i
ge foel
'scussion applies to 11c*ussion colu ~l for ite 50.
- Item 278 in D-Bas' lditional ' *ails.
""I 003 279 3.5.1 RATable 3.5.1, Item 3.*
will be revised to read as NO I
- mechanical funj due to the-listed mechanisms is n*
n'g effect. S +* Ilues typically result from i~a Ilsi n
aing events rather than from the effects s due to cyclic thermal loads are rare for struct s due to their relatively low temperature____
Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit No.
Item No.
Related LRA Submittal Commitment Date (Yes / No)
Vermont Yankee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA
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vermont YanKee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA Submittal Commitment No.
Item No.
Section No.
Description / Topic NRC Accession No.
Date (Yes / No) 003 295 3.3.2 LRA Table 3.3.2-11 includes stainless steel post-accident NO sampling system (PASS) sample line tubing and valves t t'
are exposed to treated water or steam from the reacto coolant system on internal surfaces. The componen less than 4" NPS and are outside the Class I reacto ant system (ROS) pressure boundary. They are, theref outside the scope of the BWR SCC program. Aging o PASS sample line tubing and valves is managed by t Chemistry Control - BWR Program, which is verified e
One-Time Inspection Program. To provide further clarification, the effectiveness of the Water Chemistry Con iary Systems, BWR, and Closed Cooling Wate confirmed by the One-Time Inspection p Thi s
an amendment to the license renewal ation t the Appendix A, SAR supplement des ons to Chemistry Control -Auxiliary Sys
- nms, a
sed Cooling Water programs to e st On e
Inspection Program activities onfirm th ctiven f
these programs. Howev ections pero small-bore piping activi pplies to co the Class-ressure
, will also provi e data usefu con hese downstream
- co
.1 Vermont Yankee License Renewal Application
.Amendment List LRA LR Amend. Audit Related LRA Submittal Commitment Date (Yes I No)
Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit Related LRA Section No.
Submittal Commitment Date (Yes / No) i
Vermont Yankee License Renewal Application Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Description I Topic Submittal Commitment Date (Yes / No)
NRC Accession No.
003 319 4.3.1.1 the last paragraph of Section 4.3.1.1 will be clarified as NO follows.
The VYNPS Fatigue Monitoring Program will assure t; dllowed number of transient cycles is not exceeded.l*
.program requires corrective action if transient cycle Iiare approached. Consequently, the TLAA (fatigue analy]
l based on those transients will remain valid for the peri extended operation In accordance with 10 CFR 54.21*
H~owever, when the effects of reactor coolant environm Jnt oi !
fWigue are added to the existing fatigue analyses,,,veral locations have a projected cumulative usage cess of 1.0. See section 4.3.3 for further discu ts of reactor water environment on fatigue.A*
003 320 Ref. 4.3-1 The correct reference is letter BVY96-ot 96-he NO originator, addressee, title and da* w~or lm h letter number was Wrong. Th
- i n*tth
" et citaJ for Reference 4.3-.1.
tll' S4.3-1 Sojka, R. E. (VYN SNRC DoctJ Desk, "Response to Req Additional Inf Regardin *tYanke hroud Modification," BVY 003 321 4.3.1.2 T
.1.2-1,3 81% I 3.1.2-revised to eliminate NO I
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Vermont Yankee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA Submittal Commitment No.
Item No.
Section No.
Description / Topic NRC Accession No.
Date (Yes / No) 003 322 4.3.1.3 Section 4.3.1.3 should read as follows.
NO "VYNPS replaced reactor recirculation (RR) system pipi i
1986. Also replaced were connecting portions of the r I
heat removal (RHR) system piping. The new piping designed and analyzed to ANSI B31.1 but was insp an tested to ASME Section III requirements. Stress ana the reactor recirculation system were performed to B3 requirements. These analyses were not based on an) limited assufnptions and as such are not TLAA.
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Vermont Yankee License Renewal Application
.Amendment List LRA Amend.
No.
LR Audit Item No.
Related LRA Section No.
Submittal Date Commitment
Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit Related LRA Submittal Date Commitment
Vermont Yankee License Renewal Application Amendment List LRA Amend.
NO.
LR Audit Item No.
Related LRA Section No.
Submittal Commitment Date (Yes / No)
DescriDtion / Tonic NRC Accession No.
No.
Ite No Seto No 003 345 3.3.2-13 LRA line item error. Stainless steel that is exposed to outdoor air and wet/dry cycling is subject to loss of material. This4 correction requires an amendment to the LRA to ident s
of material as an aging effect which is managed by t tem walkdown program.
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Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit Related LRA
)escription I Topic i) LRPD-02 Section 4.21.3.B. "Program Description" will be revised to read; Submittal Commitment Date (Yes / No)
Vermont Yankee License Renewal Application Amendment List LRA LR Related Amend. Audit LRA I
11
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Vermont Yankee License Renewal Application Amendment List LRA LR Amend. Audit No.
Item No.
Related LRA Section No.
Description I Topic NRC Accession No.
Submittal Commitment Date (Yes / No)
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