ML20212P057
| ML20212P057 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/27/1986 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20212P060 | List: |
| References | |
| JPN-86-39, NUDOCS 8609020160 | |
| Download: ML20212P057 (39) | |
Text
_
I 123 hn Street I
Wh.te Plains, th Wrk 10001 914 681.6240 i
- > NewYorkPower 0""XT:s.nt 4# Authority
~~ c-t-August 27, 1986 JPN-86-39 Director of Nuclear Reactor Regulation U.S.
Nuclear Rugulatory Commission Washington, DC 20555 Attention:
Mr. Daniel R. Muller, Director BWR Project Directorate No. 2 Division of BWR Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Inservice Inspection Program for Welds and Supports 2nd 10 vr Interval
References:
1.
NYPA letter, J.
C.
Brons to D.
B. Vassalla, dated September 30, 1985 (JPN-85-18), transmitted ISI Program for Welde and Supports.
2.
NRC letter, H.
I.
Abelson to J.
C.
Brons, dated July 11, 1986, requested additional information.
Dear Mr. Muller:
The Power Authority transmitted the Inservice Inspection program for the FitzPatrick plant in Reference 1.
In Roference 2, the NRC requested additional information.
This letter responds to that request.
The item numbers in Attachment 1 to this letter correspond to the item numbers in Referenc'e 2. through 4 provide information requested in Reference 2.
E609020160 860827 PDR ADOCK 05000333 G
PDR fjf sk$#
v ko47 s
1
'll
o Should you or your staff have any questions regarding our-response, please contact Mr. J. A. Gray, Jr. of my staff.
Very truly yours.
W f
n C.
Brons
/innior Vice President duclear Generation Enclosure cc:
Office of the Resident Inspector U.
S.
Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Boyd Brown EG&G, Idaho Idaho Lake Facility 2151 North Blvd.
POB 1625 Idaho Falls, Idaho 83415 l
,----y-,
--.-p.
+.
ATTACHMENT I TO JPN-86-39 INSERVICE INSPECTION PFCGRAM FOR WELDS AND SUPPORTS RESPONSE TO REQUEST [dR ADDITIONAL INFORMATION NEW YORK POWER AUTHORITY JAMES A.
FII'ZPATRICK NUCLEAR POWER PLANT DOCKEf NO. 50-333 D P R-- 5 9
f Response to Request for Additional Information - Second Interval Inservice Inspection (ISI) Program A. to this letter is a set of color-coded inservice diagrams which define the ASME Class 1, Class 2, and Class 3 b6undaries for those systems listed in Appendix B of-the FitzPatrick Second Ten-Year Interval ISI Program Plan.
This set of diagrams was previously submitted with our original ISI Program.
This attachment is being sent directly to your l
consultant at your request.
B.
The welds in the Scram Discharge Volume piping have been included in the ISI program in accordance with the re qui reme nt s of ASME Code Section XI and the recommendations of NUREG-0803.
The drawings were not prepared in time for the last submittal, 4
but are included as Attachment 3.
C. to this letter is a summary of relief requests.
i k
1 t
J 4
l I
w 3-wr-r v - --
s-m,,,,
-,,,m-mm,,-y*r
-c,.mog-m y,,w,
-e.v.
m-w--..:
--->.-%.,,.-w, rem, pgg y-~
,.m
,,.+r--
93,.-
ATIACHMEN1 11 TO JPN-86-39 INSERVICE INSPECTION PROGRA_M FOR WELDS AND SUPPORTS INSERVICE DIAGRAMS NEW YORK POWER AU Tt10RI TY JAMES A.
FITZP AT RICK NUCLE AR POWER PLANT DOCKET NO. 50-333 DPR-59
ATTACHBIENT III TO JPN-86-39 INSERVICE INSPECTION PROGRAff FOR WELD 3 AND SUPPORTS SCRAff DISCHARGE VOLUtfE PIPING r
I Y-NEW YORK POWER AUTil0RITY JA!!ES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59
6 l
Item B:
'Ihe Scram Disch'trge Volume (SDV) System has been included in the ISI program plan. h recently issued scram tank and piping drawings are attached for reference. h drawings are the following:
DG NO.
DESCRIPTION 850358EM003 ISI Scram Tank Weld Identification 850358 m004 CRD piping-West Side (A) 8503582005 CRD piping-East Side (B)
O h wld numbers and cou=:srycialing inspection information will be entered into the ISI amuriter datahaaa prior to the next refueling outage. This is the first refueling outage in the.2nd-10 year interval.
s
=
q%
rg
~---m y
+ - -. -
w
--.g.c y-e-%-----,my c.
-eme.c-----y
.m,yw--
v.---
-e c
OVERSIZE l DOCUMENT PAGE PULLED l SEE APERTURE CARDS l
NUMBER OF PAGES:
ACCESSION NUMBER (5):
l
%o9090/co s
/&fn I(o ~7 APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TfDC FTS 492 =8989
_ _ _ m _. _,__ _ _. __.. _._ _ _ _ _ __
P ATlACHMENI IV TO JPN-86-39 INSERVICE INSPECTION PROGRAM FOR WELDS AND SUPPOR3 RELIEF REQUESTS NEW YORK POWER AUTHOR 1TY JAMES A.
FIT ZPAT RICK NUCLEAR POWER PLANT DOCKEf NO. 50-333 DPR-59
4 E
l JAMES A. FITZPATPICK 4
NUCLEAR POWER FIANT Prim RByutsp IDR WEIDS AND SUPIORTS SECOND DTIERVAL July 28, 1986 Prepared by:
h-A Date: [/[
R. Penny N.1 clear Operatio and Maintenan Engineer 8 [f/
Reviewed by:
A Date:
D. Sancic Senior Nuclear Operations and Maintenance Engineer Authorized
/
/
bm//
Ms//g(
for Issue:
Date:
fbougherty Di
, Nuclear Operation 3 and Maintenance
._ J
L 4
Requests for Relief Relief Regaest Identifier Belief Recuest R1 As allowed by 10CER50.55a(b) (2) (iv); Pressure-retaining welds in ASIE Code Class 2 piping (applies to Tables IWC-2520 or INC-2320-1, Category C-F).
(A) Aw1.vytlate Cbde Class 2 pipe welds in RHR systems, ECC systems, and CHR systems shall be examined. 'Ihe extent of examination for these systems shall be determined by the requirements of paragraph IWC-1220, Table INC-2520 Category C-F and C-G, and paragraph IWC-2411 in the 1974 Edition and Addenda through the Summer 1975 Addenda of Section XI of the ASME code.
Relief is requested fr m the requirements of Table IWC 2500-1, Examination Category C-F, Note (1) of Section 1
XI, the 1980 Edition through Winter 1981 Addenda, i
R2 As allowed by 10CFR50.55a(b) (2) (ii), the extent of the examination of Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB 2500 and IWB-2500-1 and Category B-J) will be determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B-J of Section XI of the ASME Code in the 1974 Edition and addenda through the Sunner 1975 Addenda.
Relief is requested fr a the requirements of Table IWB 2500-1, Category 1h7, Note (1) of Section XI, the 1980 Edition through Winter 1981 Addenda.
R3 As allowed by 10CFR50.55a(b) (2) (iv) (B), the extent of examination for Code Class 2 pipe welds (Non ECCS) will be determined by the requis.= cuius of paragraph IHC-1220, Table IWC-2520 Category C-F and C-G and pai. w @ IWC-2411 in the 1974 Edition and Addenda through the summer 1975 Addenda of Section XI of the ASME Code. Relief is regaested frun the _Wts of Table IWC 2500-1, Examination Category C-F Note (1) of Section XI, the 1980 Edition through Winter 1981 Addenda.
l i
l page 1 4
R4 Relief is requested from cmponent welds whose location is within a containment penetration. 'Ihis relief request applies to Category B-J and Category C-F welds located in containtrent penetrations. 'Ihe containment penetrations are detailed on the ISI drawings. The welds will be visually examined (VI-2) during hy& wtetic testing once every 10 years. h plant drawing (W-O1L) is shwn in Enclosure #1 for reference. As shwn on the reference drawing the clearance does not all w accessibility to the weld for a volumetric examination. 'Ihe following are the welds within containment penetrations:
CLASS 1 CLASS 2 20-10-128B 6-12-911B 4-10-183B 24-10-139B 3-13-1040C 24-10-152B 10-14-491C 10-14-512C 10-23-670B 24-29-573B 24-29-542B 24-29-673B 24-29-606B 18-34-391A 18-34-425C R5 Relief is requested fr m the requirements of Table IWB 2500-1 Examination Category B-G-2, Category B-M-1, and Category B-M-2.
It has been and continues to be the Power Authority's policy to examine the pressure retaining bolting, and interior surfaces of pumps and valves whenever the components are made accessible due to routine maintenance. In-place visual examination of bolting does not reveal the areas most susceptible to failure and mi%ent degradation of pressure retaining integrity. In-place inspection results in un e vry radiation exposure and expense.
h Authority does not intend to disassemble components solely for the purpose of inspection. 'Ihis could cause unmMry wear and the possibility, however slight, of damage to the bolting or the interior surfaces,of pumps and valves. 'Ihe Authority will updatAt the valve maintenance procedures to include a VI-1 examination when cmponents are riivsaambled for maintenance. 'Ihis will be accmplished prior to the next refueling outage.
Bolting, valves and pumps not inspected during the 10 year period because the cmponent was not disassembled will be inspected during the hydrostatic examination for leakage in accordance with IWA-5000 and IWB-5000 and the requirements of Category B-P of the 1980 Edition, through the Winter 1981 Addenda of Section XI.
Relief fr m examination of specific c ur nents will be requested at the end of the interval.
Cartponents in category B-G-1 and B-G-2 are listed in the ISI p%me certputer printout (Appendix B).
page 2
-y
R6 Belief is requested frcan Table IWB-2500-1, Examination Category B-0, frcan the examination method required; volumetric or surface. The CRD housing peripheral welds,and the stub tube to flange welds (pg. A-1-10, Note 8) are inarmaaible due to structural interferences and cannot be surface or voltmetrically examined. As an alternative, the Authority will examine 100% of the welds in the CRD housings during the hydrostatic examination at the end of the inspection interval in accordance with INA-5000 and IWB-5000 and the requirements of category B-P of the 1980 Edition, through the Winter 1981 Addenda of Section XI.
Drawings shcWing the armaaibility problems for these inspections are shown in Enclosure #2.
i R7 Relief is requested frcan Table IWB-2500-1, Examination Category B-G-1 for the reactor recirculation punp casing bolting. The bolting will be volumetrically examined in armdance with code requitou==ds. It is requested that relief be granted for the requirements of a VF-1 examination while the bolting is in place under tension. The reasoning is as stated in relief request RS.
If the punp is diaaaaambled for routine mai.h within the inspection interval, the bolting, nuts, bushings and washers will be visually I
examined. If the punp is not diaamaambled, a visual examination (VI-2) will be performed during the hydrostatic examination at the end of the inspection interval in accordance with INA-5000 and IWB-5000 and i
the requirements of category B-P of the 1980 Edition, thrcugh the Winter 1981 Addenda of Section XI.
The ocuponents are listed in the ocmputer printout j
(Appendix B).
R8 Reference ISI pawimu plan, Section 1.3.5.2 pg.5.
The intspections required by Table INC-2500-1, Examination Category FC (Snubbers Only) and IWF-5000, Inservice Testing for Snubbers will be done in accordance with the Technical Specifications. The Technical Specifications, Amendment No. 92 to Facility Operating License No. IRP-59 for the James A.
FitzPatrick Nuclear Power Plant has been approved by the Nuclear Regulatory Commission in a letter dated May 29, 1985. The Technical Specifications regarding srnhhar testing and the Safety Evaluation by the Office of Nuclear Reactor Regulation are attached for reference in Appendix D of the ISI prwima plan. The anubbers are listed in the ocmputer prirfd of Appendix B of the ISI program plan. Snubbers are listed under HS (hydraulic snubbers) and MS (mechanical snubbers).
page 3
R9 As outlined by the ASME Section XI Committee in Code Cases N-322 and N-334, for the integrally forged attachment of Figure 1(c) of the respective Code Cases, exa.nination is not required provided no welds are located within the boundary of Examination Category B-K-1 or Examination Category C-C.
h design of containment penetrations are similar to figure 1(c) of Code Cases N-322 and N-334. h penetrations are shown on the JAF ISI isometrics. A VI-l examination will be performed because of the importance of the integrity of the primary containment boundary. h detail drawing (W-OlL) is shown in Enciosure #1 for reference.
h following welds will be visually examined (VI-1) during the 10 year inspection interval:
Class 1 Class 2 3-03-963P 25-23-671A 10-10-183A 20-10-128A 37-29-573C 37-10-152A 37-29-542C 6-12-911C 37-29-637C 14-13-1040 37-29-606C 20-14-491B 28-34-391A 20-14-512B 28-34-435B Note: h above welds are classified under Subsection IWE, Requirements for Class MC cmponents, Table IWE 2500-1, Examination Category E-B of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 edition through Winter 1981 Addenda.
R10 Since the 1980 edition through Winter 1981 Addenda of Section XI does not address exemptions for Class III piping, the criteria of IWC-1220(d) of the 1974 edition through Summer 1975 Addenda of Section XI will be used. Specifically, component connections, piping, and asociated valves and vessels (and their supports) that are 4 in. nominal pipe size and smaller are exempt frm exaimination. Items exempt i
fr m examination will be examined during the additional inservice test, as specified in Section l.3.6 of the ISI program plan for cooling water systems and during the hydrostatic test for the Reactor Core Isolation Cooling (RCIC).
Note: Reference R1 and R3.
page 4 l
l i
R11 Reference Section 1.3.5.1, page 5 of the ISI program plan.
NRC-Required IGSCC Examinations in Stainless Steel Piping Systems The Power Authority, in accordance with the requirements of NUREG 0313 Rev.1, Inspection and Enforcement Bulletin (IEB) 83-02 and' Generic Istter 84-11, as well as any later developed requirements (NOREG 0313 Rev. 2, upon issue), will continue to perforn ultrasonic examination on stainless sted piping welds for the detection of Intergranular Stress Corrosion Cracking (IGSCC). S e systems that will receive these examinations include the Reactor Recirculation System (#02), Cbre Spray (#14), Reactor Water Cleanup (#12) and portions of the RHR System
(#10). h e Authority considers that because of the more stringent requirements for personnel qualifications.4 W by IEB 83-02 and the NRC/BWROG/ Electric Power Research Institute detection and siring training courses (as upgraded in September, 1985), the quality of inspection has been enhanced for these stainless steel welds.
'Ihe recently issued, for comment, draft report of NUREG 0313 Rev.2, elim' Eses the IGSOC inspection issue in Section 5.0, pg. 5.1 of the draft report.
Additionally, many categories of welds are inspected higher frequency than the ASME code requirements (Reference Table 2, pg. 5.7 Of the draft NUREG).
'Iberefore, the Power Authority, in accordance with Section 11&-2240 of the 1980 Edition, Winter 1981 Addenda, requests that the ult W.c examinations performed on these welds to detect IGSOC be used in lieu of the standard code volumetric examination to meet the ASME code examination requirements. 'Ihis avoids duplication of examinations and decreases overall radiation exposure to inspection personnel.
The welds to be inspected by the above examination method are shown in the computer printout in Enclosure #3.
page 5
R12 Reference Section 1.3.6 of the ISI program plan.
Class 3 Systans and Cwwits j
Class 3 systems at the James A. FitzPatrick Plant fall into two categories: (1) the Reactor Core Isolation
. Cooling (RCIC) system, and (2) cooling water systems.
h RCIC system was designed to be pressure tested an:1, I
therefore, will be tested in full accordance with the Code requitau=>w.
^
h cooling water systems were designed and c.urm^uccted prior to the issuance of the first Code Edition that addramaari Class 3 systems and u.mpsits (the 1974 Edition). Since the systems were designed and u.n= uucted without the current inspection requirements
^
in mind,-isolation valves that would permit hydrostatic testirg to current requirements were not installed.
An alternative inspection prwsma detailed below will therefore be implemented to insure the integrity of the pressure boundary of these cooling water systems. 'Ihis pawsma in.utperates features of the 1980 Edition of the Code through the Winter 1981 Addenda for visual inspection of piping systems. To provide additiaral assurance of integrity, these inspections will be oceducted during system inservice tests four times per interval, which ext,aaria the Code requirau=is (once per period, three times per interval), h additional inservice test is in lieu of the hydrostatic test required by IWD-5000. 'Ihis inspection pr@imu was originally approved during the first interval. h inspection yrwicun for Class 3 cooliry water systems is as follows:
Cooling Water System Cwwis Sub'iect to Examination Method Refer M Piping and Cwhis(Not Buried)
VI-2 INA-2212 Piping and Cwhis (Buried)
Flow Verification INA-5244 All references are fran the 1980 Edition of ASME Section XI through the Winter 1981 Addenda.
Piping support inspections required by Category D-A, D-B, D-C will be performed in accordance with Code requirements, as summarized in Appendix A-3 of the ISI program.
page 6 4
n.,
R14 Refere:re pg. A-1-10, Note 1.
i As shown in Enclosure #4, removable insulation panels do not allow the code requita-d. of 100% of the weld length of one beltline region weld for item no. Bl.11 and Bl.12.
'Ihis is due to the sacrificial shield wall and the permanent insulation system. 'Ihe Authority proposes to inspect the weld lengths that are amaaaible. 'Ihe ocuposite inspected weld length for longitudinal welds (Bl.12) will equal one beltline region weld. 'Ihe Authority will use category B-A of the 1974 Edition of ASME Section XI, through the Sumer 4
1975 Addenda for guidance. Permanent structures as diamaaad above will not allow the circumferential weld (Bl.11) to be inspected in accordance with code requirements. 'Ibe Authority ptupcases to inspect the circumferential weld in the beltline region (Weld #
VC-3-4) to the maximum extent allowed (weld length of 180" or 25%)
R15 Reference pg. A-1-10, Note 1.
Amaanibility cf the botta head welds (Category B-A, Item No. Bl.21 and Bl.22) was not considered in the plant design. 'Ihe botte head welds cannot be examined to the extent required in the ASME code because of limited access, through the vammal skirt, and also because of tha numerous interferences fran the control rod drive and instrument permi.tutions. A nr= m ite weld length of circumferential and meridonal welds will be inspected where amaan allows to meet ocde requita - tuis. 'Ihe Authority will use category B-B of i
the 1974 Edition of ASME Section XI, through the Sumer 1975 Addenda for guidance. Interference drawings are show in Enclosure #5.
i R16 Reference pg. A-2-4, Note 2 of the ISI pr%tmu plan.
I
'Ihe Authority requests relief fran the volumetric examination of the tuhaaheet-to-shell weld of the heat exchanger (RHR). Volumetric examination will be made if the heat exchanger is dinamaambled for maintenance.
R17 Reference pg. A-3-2, Note 1 of the ISI pr@tmu plan.
'Ihe Authority requests relief from IWA-2214 (a) and (b) of the ASME code. A VI'-4 examination on hwe.nt supports will only be performed when the c.www.nt is diaaaaambled for maintenance. Snubbers will be functionally tested in accordance with Section 1.3.5.2 of the ISI program plan. Reference relief request R8.
During the inspection of c.wwe.nt supports (i.e.
spring Inadad and constant weight hangers) the inspectors shall verifiy the load settings and inspect for fraad m of motion.
[
4 page 7
w i
Enclosure #1 1
J 9
f s
,m.
m-----
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS 1
NUMBER OF PAGES:
ACCESSION NUMBER (5):
?l08902Ol{n) f l
APERTURE CARD / NARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-3959
i 4
l t
Enclosure #2 I
I e
,y
,y.-,-
e T
?-M~-
T'
'^
OVERSIZE DOCUMENT PAGE PULLED i
SEE APERTURE CARDS NUMBER OF PAGES:
I ACCESSION NUMBER (5):
WfoO90GlO/46-Q/
Ris o 4 0 a 0 /70 ~
Hs 6 -o %
17L I'7 6
/76 l
GPERTURE. CARD /MARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492 = 3939
Enclos' Ire #3 f
3 9
{
i
e page 1
LOC SYSDEC COMPID CODEC ITEMNO SIZE THICK 1
Reactor Recirculation N-2A-SE B-F B5.10 12
.547 Reactor Recirculation N-2B-SE B-F B5.10 12 e
.547 2
3 Reactor Recirculation N-2C-SE B-F B5.10 12 *
.547 4
Reactor Recirculation N-2D-SE B-F B5.10 12
.547 5
Reactor Recirculation N-2E-SE B-F B5.10 12
.547 6
Reactor Recirculation N-1B-SE B-F B5.10 28 1.235 7
Reactor Recirculation N-2F-SE B-F B5.10 12
.547 8
Reactor Recirculation N-OG-SE B-F B5.10 12
.547 9
Reacter Recirculation N-2J-SE B-F B5.10 12
.547 10 Reactor Recirculation N-2K-SE B-F B5.10 12
.547 s
11 Reactor Recirculation N-2H-SE B-F B5.10 12
.547 12 Reactor Recirculation N-1A-SE B-F B5.10 28 1.235 13 Reactor Recirculation 12-02-2-1 B-J B9.11 12
.547 14 Reactor Recirculation 12-02-2-2 B-J B9.11 12
.547 15 Reactor Recirculation 12-02-2-3 B-J B9.11 12
.547 16 Reactor Recirculation 12-02-2-4 B-J B9.31 12
.547 17 Reactor Recirculation 22-02-2-6 B-J B9.11 22
.993 18 Reactor Recirculation 12-02-2-7 B-J B9.11 12
.547 19 Reactor Recirculation 12-02-2-8 B-J B9.11 12
.547 20 Reactor Recirculation 12-02-2-9 B-J B9.11 12
.547 I
21 Reactor Recirculation 12-02-2-10 B-J B9.31 12
.547 22 Reactor Recirculation 12-02-2-12 B-J B9.11 12
.547 23 Reactor Recirculation 12-02-2-13 B-J B9.11 12
.547 24 Reactor Recirculation 12-02-2-14 B-J B9.11 12
.547 25 Reactor Recirculat' ion 12-02-2-15 B-J B9.31 12
.547 26 Reactor Recirculation 12-02-2-17 B-J B9.11 12
.547 27 Reactor Recirculation 12-02-2-18 B-J B9.11 12
.547 28 Reactor Recirculation 12-02-2-19 B-J B9.11 12
.547 9
W W
my
Page' 2
LOC SYSDEC COMPID CODEC ITEMNO SIZE THICK 29 Reactor Recirculation 12-02-2-20 B-J B9.31 12
.547 30 Reactor Recirculation 22-02-2-22 B-J B9.11 22 e
.993 31 Reactor Recirculation 12-02-2-23 B-J B9.11 12
.547
. 32 Reactor Recirculation 12-02-2-24 B-J B9.11 12
.547 33 Reactor Recirculation 12-02-2-25 B-J B9.11 12
.547 34 Reactor' Recirculation 12-02-2-26 B-J B9.11 12
.547 35 Reactor Recirculation 28-02-2-27 B-J B9.11 28 1.235 36 Reactor Recirculation 22-02-2-28 B-J 89.11 22
.993 37 Reactor Recirculation 22-02-2-29 B-J B9.11 22
.933 38 Reactor Recirculation 28-02-2-30 B-J B9.11 28 1.235 39 Ruactor Recirculation 28-02-2-31 B-J B9.11 28 1.235 40 Reactor Recirculation 28-02-2-32 B-J B9.31 4
41 Reactor Recirculation 28-02-2-33 B-J B9.11 28 1.235 42 Reactor Recirculation 26-02-2-34 B-J B9.11 28 1.235 43 Reactor Recirculation 28-02-2-35 B-J B9.11 28 1.235 44 Reactor Recirculation 28-02-2-36 B-J
~
B9.31 4
j 45 Reactor Recirculation 28-02-2-37 B-J B9.11 28 1.235 46 Reactor Recirculation 28-02-2-48 B-J B9.11 28 1.235 47 Reactor Recirculation 28-02-2-49 B-J B9.11 28 1.235 1
48 Reactor Recirculation 28-02-2-50 B-J B9.11 28 1.235 49 Reactor Recirculation 28-02-2-50A B-J B9.11 28 1.235 50 Reactor Recirculation 28-02-2-51 B-J B9.11 28 1.235 51 Reactor Recirculation 28-02-2-52 B-J B9.11 28 1.235 52 Reactor Recirculation 28 *2-2-53 B-J B9.11 28 1.235 53 Reactor Recirculatio'n 28 2-2-54 B-J B9.11 28 1.235 54 Reactor Recirculation 28-02-2-55 B-J B9.31 4
SS Reactor Rectreulation 28-03-2-56 B-J B9.11 28 1.235 56 Reactor Recirculation 28-02-2-57 B-J B9.11 28 1.235 W
iw W
. mer
~
O page 3
LOC SYSDEC COMPID CODEC ITEMNO SIZE THICK 57 Reactor Recirculation 22-02-2-5 B-J B9.31 12 58 l Reactor Recirculation 22-02-2-11 B-J B9.31 18 59 Reactor Recirculation 22-02-2-16 B-J B9.31 12' 60 Reactor Recirculation 22-02-2-21 B-J B9.31 12 4
61 Peseter nceirculetion 4-02-0-30 B-J B9.31 4
.337 62 Reactor Recirculation 4-02-2-39 B-J B9.11 4
.337 63 Reactor Recirculation 4-02-2-40 B-J B9.11 4
.337 64 Reactor Recirculation 4-02-2-41 B-J B9.11 4
.337 65 Reactor Recirculation 4-02-d-42 6-J B9.11 4
.337 66 Reactsr Hecirculat ion 4-02-2-43 B-J B9.11 4
.337 s,
67 Reactor Recirculation 4-02-2-44 B-J B9.11 4
.337 68 Reactor Recirculation 4-02-2-45 B-J B9.11 4
.337 69 Reactor Recirculation 4-02-2-46 B-J B9.11 4
.337 70 Reactor Recirculation 4-02-2-47 B-J B9.31 4
.337 71 Reactor Recirculatior 12-02-2-58 B-J B9.11' 12
.547 72 Reactor Recirculation 12-02-2-59 B-J B9.11 12
.547 73 Reactor Recirculation 12-02-2-60 B-J B9.11 12
.547 74 Reactor Recirculation 12-02-2-61 B-J B9.31 12
.547 75 Reactor Recirculation 22-02-2-63 B-J B9.11 22
.933 76 Reactor Recirculation 12-02-2-64 B-J B9.11 22
.547 77 Reactor Recirculation 12-02-2-65 B-J B9.11 22
.547 78 Reactor Recirculation-12-02-2-66 B-J B9.11 22
.547 79 Reactor Recirculation 12-02-2-67 B-J B9.31 12
.547 80 Reactor Recirculation 12-02-2-69 B-J B9.11 '
12
.547 81 Reactor Recircula' tion 12-02-2-70 B-J B9.11 12
.547 82 Reactor Recirculation 12-02-2-71 B-J B9.11 12
.547 i
83 Reactor Recirculation 12-02-2-72 B-J B9.31 12
.547 84 Reactor Recirculation 12-02-2-75 B-J B9.11 12
.547 M9
9 page 4
LOC SYSDEC COMPID CODEC ITEMNO SIZE THICK 85 Reactor Recirculation 12-02-2-76 B-J B9.11 12
.547 86 '
Rea: tor Recirculation 12-02-2-77 B-J B9.11 12e
.547 87 Reactor Recirculation 12-02-2-78 B-J B9.31 12'
.547 88 Reactor Recirculation 22-02-2-80 B-J B9.11 22'
.933 89 Reactor Recirculation 12-02-2-81 B-J B9.11 12
.547 90 Reactor Recirculation 12-02-2-82 B-J B9.11 12
.547 91 Reactor Recirculation 12-02-2-83 B-J B9.11 12
.547 92 Reactor Recirculation 12-02-2-84 B-J B9.11 12
.5*7 93 Reactor Recirculation 28-02-2-85 B-J B9.11 28 1.235 94 Reactor Recirculation 22-02-2-86 B-J B9.11 22
.993 s s 95 Reactor Recirculation 22-02-2-87 B-J B9.11 22
.993 96 Reactor Recirculation 28-02-2-88 D-J B9.11 28 1.235 97 Reactor Recirculation 28-02-2-89 D-J B9.11 28 1.235 98 Reactor Recirculation 28-02-2-90 B-J B9.31 4
99 Reactor Recirculation 28-02-2-91 B-J B9.11 28 1.235 100 Reactor Recirculation 28-02-2-92 B-J B9.11 28 1.235 101 Reactor Recirculation 28-02-2-103 B-J B9.31 4
102 Reactor Recirculation 28-02-2-104 B-J B9.11 28 1.235 103 Reactor Recirculation 28-02-2-105 B-J B9.11 28 1.235 104 Reactor Recirculation 28-02-2-106 B-J B9.11 28 1.235 105 Reactor Recirculation 28-02-2-107 B-J B9.11 28 1.235 106 Reactor Recirculation 28-02-2-108 B-J B9.11 28 1.235 107 Reactor Recirculation 28-02-2-109 B-J B9.11 28 1.235 108 Reactor Recirculation 28-02-2-110A B-J B9.11 28 1.235 109 Reactor Recirculation 28-02-2-110 B-J 89.11 28 1.235 110 Reactor Recirculation 28-02-2-111 B-J B9.11 28 1.235 111 Reactor Recirculation 28-02-2-112 B-J B9.11 28 1.235 112 Reactor Recirculation 28-02-2-113 B-J B9.11 28 1.235 L
N wW 9
9
page 5
LDC SYSDEC COMPID CODEO ITEMNO SIZE THICK 113 Reactor Recirculation 28-02-2-114 B-J B9.31 4
114 l Reactor Recirculation 28-02-2-115 B-J E9.11 28 1.235 115 Reactor Recirculation 28-02-2-116 B-J B9.11 28
- 1.235 116 Reactor Recirculation 22-02-2-62 B-J B9.21 12 117 Reactor Recirculation 22-02-2-68 B-J B9.31 12 118 Reactor Recirculation 22-02-2-73 B-J B9.31 12 119 Reactor Recirculation 22-02-2-79 B-J B9.31 12 120 Reactor Recirculation 4-02-2-93 B-J B9.31 4
.337 121 Reacton Recirculation 4-02-2-94 B-J B9.11 4
.337 122 Reactor Rectrculation 4-02-2-95 B-J B9.11 4
.337 123 Reactor Recirculation 4-02-2-96 B-J B9.11 4
.337 124 Reactor Recirculation 4-02-2-97 B-J B9.11 4
.337 125 Reactor Recirculation 4-02-2-98 B-J B9.11 4
.337 126 Reactor Recirculation 4-02-2-99 B-J B9.11 4
.337 127 Reactor Recirculation 4-02-2-100 B-J B9.11 4
.337 128 Reactor Recirculation 4-02-2-101 B-J B9.11 4
.337 129 Reactor Recirculation 4-02-2-102 B-J B9.31 4
.337 130 CRD N-9-C1 B-F B5.20 3
.300 131 RWC 6-12-141A B-J
$9.11 6
.432 132 RWC 6-12-141B B-F B5.130 6
.432 133 Core Spray N-5A-SE B-F B5.10 10
.594 134 Core Spray N-5B-SE B-F B5.10 10
.394 135 Core Spray 10-14-471 B-J B9.11 10
.237 136 Core Spray 10-14-472 B-J B9.11 le
.594 137 Core Spray 10-14-473 B-J B9.11 1A
.594 138 Core Spray 10-14-474 B-J B9.11 10
.594 139 Core Spray 10-14-475 B-J B9.11 10
.594 140 Core Spray 10-14-476-B-J B9.11 10
.594 W
+O Y
page 6
LOC SYSDEC COMPID CODEC ITEMNO SIZE THICK a
141 Core Spray 10-14-477 B-J B9.11 la
.-594 142l Core Spray 10-14-480
,B-J B9.11 10
.594 143 Core Spray 10-14-451 B-F B5.130 10
.594 144 Core Spray 10-14-492 B-J B9.11 10
.594 145 Core Spray 10-14-493 B-J B9.11 10
.594 146 Core Spray 10-14-494 B-J B9.11 10
.594 147 Cors Spray 10-14-495 B-J B9.11 10
.594 148 Core Spray 10-14-436 B-J B9.11 10
.594 149 Core Spray 10-14-497 B-J B9.11 10
.594 150 Core Spray 10-14-498 B-J B9.11 10
.594 s
151 Core Spray 10-14-501 B-J B9.11 10
.594 152 Core Spray 10-14-502 B-F B5.130 10
.594 153 RHR 20-10-143 B-F B5.130 24 1.219 154 RHR 20-10-117 B-J B9.11 20 1.031 155 RHR 20-10-118 B-J B9.11 20 1.031 156 RHR 20-10-119 B-J B9.11 20 1.031 157 RHR 20-10-141 20 158 PHR 20-10-120 B-F B5.130 20 1.031 159 RHR 24-10-130 B-F B5.130 24 1.219 160 RHR 24-10-131 B-F B5.130 24 1.219 161 RHR 24-10-132 B-F B5.130 24 1.219 162 RHR 24-10-142 B-F B5.130 24 1.219 163 RHR 24-10-144 B-F B5.130 24 1.219 164 JET PUMP N8A-SE B-F
.9 165 JET DUMo neb-SE B-F
.9 166 JET PUMP NOZZLE NBA-SE-1 B-J 167 JET PUMP NOZZLE N3A-SE-2 B-J 168 JET PUMP NOZZLE N8A-SE-3 B-J s
k tre M
1 W
e W
e Page 7
)
LDC SYSDEC COMPID CODEC ITEMNO SIZE THICK a
169 JET PUMP NOZZLE N8B-SE-1 B-J 178.'
JET PUMP NOZZLC
.N8B-SE-2 B-J s
171 JET PUMP NOZZLE 4-02-2-117 B-J 1
172 JET PUMP NOZZLE-4-02-2-118 9-J l
, 173 JET POMP NOZZLE N88-SE-3 B-J
==
f' M
1
- t s
l
.i a
J 4
J e
4 e
i i
s 9#
4 W
i j
er 1
i w
m M
~
g h
L s.
Enclosure #4
/
4 9
- "eF-
+ - -, - -,,,,
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF PAGES:
ACCESSION NUMBER (S):
gs/o 29n 5so l
r APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES SRANCH,TIDC FTS 492-3939 m-r e,--m-,-
- ---,,--=
,me
.,..., _,,,.---,.---,-,ww.w..
r--,--_
--.--- - e-,
- - -,. -- -. - - ~
-w
e Enclosure #5 1
l 4
1
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF PAGES:
ACCESSION NUMBER (5):
$(9 09 De52 O]7'7
/6b -o s as2.e b & S(D D R D Q b I~1 D I
r
' 9Lo b ol D Q O I~7 Ol l
I APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVM:ES BRANCH,TIDC FT5 492-B989
r w --+w-ur-%--ww----
- r-e- %.- - -
wwr---w.ra,w
--as,-w.m we w-- em ar-w-
-r--
--e
..