ML20054A490
| ML20054A490 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/15/1981 |
| From: | Paillaman R, Sawicky W EBASCO SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20054A474 | List: |
| References | |
| PROC-811015, NUDOCS 8204150495 | |
| Download: ML20054A490 (600) | |
Text
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?ROCR.*JI PLAN PRESERVICE INSPECTION
, BYRON UNIT 1
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8204150495 820407 PDR ADOCK 05000454
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kt:. oc w.. . :... . a - VOLUME 1 SECTION I PROGRAM DESCRIPTION i ,hSECTIONII IDENTIFICATION OF EXAMINATION REQUIREMENTS
. Inspection Plan No. 445TI000001 Rev N/C for Reactor Pressure Vessel
. Diagram of Mainsteam M-1001 Sheet 1&2
. Diagram of Feedwater (Main) Sheet 1
. Diagram of Reactor Coolant Loop 1 M-1013 -
Sheet 1
. Diagram of Reactor Coolant Loop 2 M-1013 Sheet 2
. Diagram of Reactor Coolant Loop 3 M-1013 Sheet 3
. Diagram of Reactor Coolant Loop 4 M-1013 . Sheet 4
. Diagram of Reactor Coolant Pressurizer M-1013 Sheet 5
. Diagram of Saf ety Injection M-1014 Sheet 1
._ Diagram of Safety Injection M-1014 Sheet 2
. Diagram of Safety Injection M-1014 Sheet 3
. Diagram of Safety Injection M-1014 Sheet 4
. Diagram of Safety Injection M-1014 Sheet. 5
. Diagram of Safety Injection M-1014 -
Sheet 6
. Diagram of Residual Heat Re eval M-1015 Sheet 1
. Diagram of Chemical & Volume Control M-1017 Sheet 1
. Diagram of Chemical & Volune Control M-1017 Sheet 2
.Diagra= of Chemical & Volume Control M-1017 Sheet 5 9 .Line List Auxiliary Feedwater 3 Pages
. .Line List Contain=ent Spray , 4 Pa;;es j .Line List Chemical & Volume Control 21 Pages
] q .Line List Main Feedwater 6 Pages
* .Line List Main Steam 5 Pages
), .Line List Reactor Coolant 12 Pages i
.Line List Reactor Heat Removal 4 Pages
.Line List Reactor Coolant-Pressurizer 3 Pages
.Line List Safety Injection 17 Pages
. Component List-Reactor Pressure Vessel 3 Pages
-RPV Closure Heaa 1 Page
-Reactor Coolant Pu=p 1RC 01 PA 2 Pages
-Reactor Coolant Pump 1RC 01 PB 2 Pages
, -Reactor Coolant Pump 1RC 01 FC 2 Pages
-Reactor Coolan: Punp 1RC 01 PD .
2 Pages
-Pressuri:cr Vessel 3 Pages , -Steam Generator 1RC 01 3A 5 Pages 1RC 01 BB 1 Page
. IRC 01 BC 1 Page t 1RC 01 BD 1 Page
-Residual Heat Exchanger 1R!! 02 AA 4 AB 1 Page c
i SECTION III INSPECTION ACCESS - SECTION IV ENA'!INATION EQUIPMENT
. Pipe Calibration Block Drawing M-1000
- J .
, 10-S1
A no L -. g r ....
- v. . . . ;m.a VOLUME 2 g SECTION V PROCEDURES
.ISI-QC-01 Rev 1 Control cf Nondestructive Exacination Status
.ISI-QC-02 Rev 2 Distributica and Centrol of Site PSI /ISI Procedures, Instructions and Drawings
..ISI-QC-03 Rev 1 Control of Senconfor:ances and Corrective Action
.ISI-QC-04 Rev 1 Preservice Inspection Records
.ISI-QC-05 Rev 0 Control and Certification of Nondestructive Examination Personnel
.ISI-QC-06 Rev 1 Control of Ultrasonic Tes: Calibratien 31ceks
.ISI-QC-07 Rev 2 Nondes:ructive Materials ?.eceipt Inspection
.ISI-QC-OS Rev 2 Marking and Identificatica of C::poncats for-- -
Inservice Inspection
.ISI-QC-09 Rev 1 Control of Ncada.i:ructive Testing Instruments
. ISI-QC-10 Control of Deficiency Reports
- .ISI-UT-S78-1 Rev 1 Ultrasonic Ensnination of Class 1 & 2 Piping Welds Joining Si=1lar and Dissimilar Materials
.ISI-UT-573-2 Rev 1 Ultrasonic M:nual Examination of Class 1 & 2 Vessel Welds Including Reactor Pressure Vessel '..* elds
.ISI-UT-578-3 Rev 1 Ultrasonic Enamina:ica of Class 1 s 2 Bolts & Studs
.ISI-UT-578 4 Rev 1 Ultrascnic Exa:In:cion of Plange Ligament Areas of Reactor Vessel
' .ISI-UT-S78-8 Rev 0 Ultrasonic Straigh Sea: Exa=ination
.ISI-UT-S78-9 Rev i Straight Sca: Ultraseni: Examinati:n of Piping Welds
.ISI-UT-S78-10 Rev 0 U1:rssenic Straign: 3ea Examina:ica of RPV Shell To Flange Weld y3) .ISI-MT-S7S-1 Rev 1 Magnetic Particle Examination of Welds and Bolting .
.ISI-PT-S7E-1 Rev A Liquid Penetrant Examination
.ISI-VT-578-2 Rev 1 Visual Examination of Bolting Components
.ISI-ET-S75-1 Rev 0 Multifrequency Eddy Current Exaninatica of Westinghouse Stca: Ocnera:Or Tubing
. Procedure No. 445.ISIOG0001 Rev B Citrasonic Exa inatica of Recc:or (?WR)
Vessel Shell (Cirth) Welds
. Procedure No. 445 ISICOCG02 Rev B ultrasonic Exa=ination of Reactor (?ZR)
Nozzlc to Vessel Ucids
.Prvuuduuu :L . 445 101 C0CO2 2c; O U1::csuni: E:::rin e ri-- "# 7m"-" (T 7) . Dissi=i-lar Mct:1 (Csic ;nd :: na :1-e)-ar.4 i_usr> rir LS'ds ,
(Safc :nd :: pipe)
. Procedure No. 445 ISI00000 Rev 8 Ultrasonic Examination of Reactor (?'/R)
Vessel, No :lc Radius SECTION VI ORGANIZATION AND QUALITY ASSURANCE
. Site Organi:stion Chart Ebasco Serviccs Section VII SCHEDULE SECTION VIII RECORDS AND REPORTS
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10-El
m _ f SECTION IX AS BUILT DRAWINGS
. Reactor Pressure Vessel No. IRC0lR 'IRPV 1 ISI
. Steam Cencrator No. IRC013A *
. Steam Generator No. IRC0133
. Steam Generator No. IRC01BC
.Steau Generator No. IRC013D
. Pressurizer No. 1RYO15
. Residual Heat Exchanger 1RH02AA & B3
. Primary Coolant System Loop 1 1RC-I-ISI SH 1
.Pri=ary Coolant Systen Loop 2 ~IRC-1-ISI SH 2
. Primary Coolant Systes Loop 3 .1RC-1-ISI SH 3
. Primary Coolant Systen Loop 4 1RC-1-ISI SH 4
. Reactor Coolant Line (S") Loop 1 1RC-1-ISI SH 6 -
. Reactor Coolant Line (3") Leop 1 1RC-1-ISI SH 8
.Reac' tor Coolant Line (S") Loop 2 1RC-1-ISI SH 9
. Reactor Coolant Line (3") Loop 2 1RC-1-ISI SH 10
. Reactor Coolant Line (12"56") Loop 3 1RC-1-ISI SH 11
. Reactor Coolant Line (S") Loop 3 1RC-1-ISI SH 12
. Reactor Coolent Line (4") Loop 3 1RC-1-ISI SH 14
. Reactor Coolant Line (14") Loop 4 1RC-1-ISI SH 5
. Reactor Coolant Line (S") Loop 4 1RC-1-ISI SH 15
. Reactor Ceolant Line (6") Loep 4 1RC-1-ISI SH 16
. Safety Injection (10") Loop 1 ISI-1-ISI SH 1
. Safety Injection (10") Loop 4 ISI-1-ISI SH 13
. Safety Inj ection (S") ,ISI-1-ISI SH 33 e
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S2ctita I Program Descrintion s
,, 1.0 SCOPE This docu=ent, the Byron PSI Program Plan, addresses those preservice examina-tions that are to be perfor=ed by Ebasco Services Inc. Specifically these ex-aulnations include Class 1 and Class 2 syste=s and co=ponents requiring volu-
- metric (including stem generator tubing) surface or VT-1 visual examinatiens in accordance with ASME Eoiler and Pressure Vessel Code *, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Co=ponents, 1977 Editica and Addenda through and including Su==er 1978. Perfor=ance of Class 3 exa ination and visual examinations, other than VT-1, of Class 1 and Class 2 cc=penents and pu=p and valve functional tests in accordance with sections IWP & !KV of the code are not included in Ebasco's secpe of work. However, these n:n-Ebasce scope ite=s are addressed in the Progra: Plan based on input frcs C:==onwealth Edison Co:pany (CECO).
2.0 IDENTIFICATION OF EXAMINATION REOUIRE"ENTS The piping system requiring exa=ination are identified on the Sargent & Lundy piping system flow diagrams of the a1000 series, copies of which are included in Section II of this docu=ent. Pertinent data for each line requiring ex-amination is provided in Section II of this docu ent. Also provided in Sec-tion II of this docu=ent is a list of exa inatiens re:uired for major equip-ment ite=s and the Inspection Plan for succ:atic ultrasonic exa inatica of the reactor pressure vessel. , qgg The locating and identification of specific ite=s, such as velds, bolted connections, pipe supports, that require examination was perfor:ed using as-built drawings and syste: valkdowns as described in Section IX of this doc-ument. 3.0 INSPECTION ACCESS - The plant design provided by Sargent & Lundy Engineers takes into acccunt, to the extent practical, the inspection access considerations described in Ik'A-1500 of the Ccdc. A nt=ocr ci prcblem areas were identified by Sargent
& Lundy during the design phase and specific co:ponents,which require relief from examination requireacnts are listed in Section !!I of this document.
Exclusions and exceptions that are found to be necesidry during actual per-formance of the preservice inspection, vill be incor orated in Section III of this docu=ent at the co=pletion of all examinaticns. 4.0 EXAMINATION EQUIPMENT N ' A listing of test calibration blocks is provided in section IV of this doc-u=ent. A description of the automated /=echanized test equip =ent used fer reactor pressure vessel and steam generator exa=inat_ n is provided in Sec-tion V of this document. Note: *From this point on the word Code will refer to the ASME Boiler and Pressure Vessel Code, Section XI Rules fer Inservice Inspecticn of 8 Nuclear Power Plant Co=ponents,1977 Edition and Addenda through and '8! including Su=mer 1978.
, 5. 0 PROCEDURIS l ) Nondestructive exa=ination procedures required for code exstinations were de-veloped and are included along with administrati,ve procedures in Section V of this docu=ent. 5/
6.0 ORGANIZATION AND QUALITY ASSURANCE ~ An orgaa2zation chart showing responsibility and interfacing of Ebasco and Coc=onwealth Edison personnel is provided in section VI/of this document. - - Also included is a description of the Quality Assurahre progra= in effect for this progra=. . . .
- 7. 0 SCHEDULE ,
Two alternatives were offered with regard to the schedule of preservice in-spection activities as follows: Schedule A - Preservice exa:inations would start after co=cletice of cold hydrostatic testing of systems and components and continue for a period of
, approxicately 100 days.
4 Schedule B - Except for the vessels, preservice exa:inations would be per-forced before cold hydrostatic testing starting in the first quartcr of 1981 with completion scheduled for the first quarter of 19S2. This schedule
'A (B) was implemented and further infor=ation is provided in Section VII of this docu=ent. . .
8.0 _ RECORDS A';D REPORTS
-During the course of the preservice examinations records will be maintained in accordance with IL'A 6210 of the Code. Further description of the type of records to be =aintained is~provided in Section VIII of this docu:ent.
After completion of all examinations a final inspection report will be pre-pared using data for=s that are included in the nondestructive exa:inatiens procedures provided in Section V of this docu=ent. , .... 9.0 AS-BUILT DR.u?INGS . - As a supplement to the preservice exa=ination work scope, Ebasco was given the responsibility to aevelop as-built drawings for the ajor co:ponents and piping systems that were required to be exa ined by the Code. The scope of this service is discussed in Section IX,of this docu=ent.
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S3ctitn II 3 Id;ntifientien of Examination Rcouircmints The piping syste=s requiring examination are identified in Sargent & Lundy piping syste: flow diagrams of the M1000 series, copies of which are included in this section. Using the system flow diagra:s, in conjunction with the Byren Unit 1 piping line list, exasination requirements for each piping systes by line nu=ber, were identified. A tabulation of pipe lines showing their size; opera-ting and design conditions; safety classification; ASME Section XI exa=ination require =ents, exemptions and relief requests; and reference drawings, was pre-g , pared and is included in this section. A si=ilar tabulation was also prepared l listing examination require =ents for major equipsent items and is included in this section. Also included in this section is the inspection plan for auto =atic ultrasonic exa=ination of the reactor pressure vessel. A specific inspection plan for the reactor pressure vessel was developed because of the cc:plexity of this examina-tion and the fact that the examination is in the critical path schedule. (Th '
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04453 30000 23 445T!00C001 ti/ C 3 PacGR A?.1 TITLE Byron RPV Preservice Inspection DOCut. TENT TITLE Inspection Plan OOCUMENT TYPE KEY NOUNS Technical Infor.ation ISI, RPV, fiDT : ORIGINAL ISSUE DATE R E L. D ATE AFPHOVALS /~ DATE
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J 4. '/.a l t e r /,,, DEPT MAaL ACDR * ' PREPARED BY!7 ATE -
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W. R. I'cCurnin 731 T020 / '
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^"l This inspection plan describes the examin=tices to be R.G. Brencie LB03 -
pertorted on the cyron I reactor vessei using auto-
... D.P.Bueriin
- LSOS j C.V. DiPol LA42 mated ultrasonic test methods. These will be '
O.G. '!asen LA21 performed by Ea.u acting as subcontracter to W.R. McCurnin (10) TC20 T.G. Parker (a) fib 02 Ebasco :ervices 4r.ccrpcrated (Ebasco). The precedures.. A.W. Thiele f1Bla calibray.on blocx.s, and ultrasonic coveracc rry. iced ii J.H. Wal ter T005 R.S. Harcy T009 is intended to cc.civ with the reauire.ments of the W. P. . Jchnson T055 AS".E Boiler and Pressure Vessel Ccde, Section XI, 1977 Editicn ar.d Addenda througn Su=er 1973. f4 L $t H v t 0 r C 84 e' p 'J+ *O L i A M y t t G AL teO T IG L) l l 2 T
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Rockw:llintemittonal NO 445T!000001 Enerer symm. c,oup .. PAGE .2 ~ ~ ~
/(k TABLE OF CC::TE!!TS Jh , , ?
SECTICM Pace No. 1.0 INSPECTION REQUIREMENTS 3
. TABLE I.
Reactor Vessel Preservice Inspection Plan 4
. _ 2.0 SUPPORT REQUIREMENTS . 6 3.0 CLOTHING 10 , '
i ._4.0 DOCUMENTATION . 10 i ,
~:
FIGURES 73, ,
.)
SKETCH A , 12
- l. Byron RPV Welds (As built) 13
- 2. Byron I Sottem Disc to Catcr.can :l eld Mao 14 -
- 3. Byron I Cutchman to Lower Shell-Course Weld "ao 15
- 4. Byron I Lower Shell Ccurse to U per Shell Course %eid "ao 16
~
- 5. Byron I Upper Shell Course to Noz:le Course Weld Map 17 .
- 6. Byron ! !:orzle to F1ance *. eld :*ap 16
- 7. Byron I Inlet No: le Weid Map 19 -
- 8. Byron I Outlet No::le '. eld 'ap ,
20
- 9. 426' Elevation Byron I Laycewn 21
- 10. Inservice Inspeciten cercuter Environmental Control Reca 22
- 11. Inservice Inspection Ccenuter Envircr. mental Centrol acc= 23 Sheet 2 l
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e- . Rockwelllnternational - NO . 445 TIC 00001 Energy systems Group PAGE . 3
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1.0 INSPECTION REQUIREitENTS . The welds to be ultrasonically examined by automated methods are listed in the attached Table 1, along with the applicable code categories, calibration biccks, and f:DE procedures. The snecific areas expected to be scanned are defined in the attached Figures 1 - 8 The actual areas scanned , and any areas not scanned due to obstructions will be docuiented on the
. examination reports for the individual welds. ,
Figure 1 shows the welds to be inspected using autcmatic ultrasonic equipment. Reference drawings 1 through 6 were used to generate this figure. The weid maps shown in Figures 2 through 3 were generated frca reference drawings 7 thrcugh 12. ,
;;)
The calibration biccks listed in Table 1 are referenced to Sketch A and reference drawings 13 thrcugh 19. e G 6 t C
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i f. TABLE 1 . REACTOR VESSEL PRESERVICE INSPECTION PLAN
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,1 -AUT0ffATED ULTRAS 0ft!C EXAtllflATI0flS- [$
I CODE TEST
- CALI!1RATI0ft WELD 3I
; PART EXN'.IflED CATEGORY PROCEDURE !!0. BLOCK fl0. Il0'S. WELD MAP ga l ,q
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3 S!! ELL UELDS 0-A 44SISI000001 9"t x 6"u WR 34 Fig. 5 ej CIRCU'1FEREt!TI AL WR 18 Fig. 4 j e 8 LOUER llEAn UELDS B-A 44515I000001 5"t x 6"w t!R 16 Fig. 2 9. IlR 29 Fig. 3 SilELL-TO-Fl.A!!GE MELD B-A 445ISIO00001 II"t x 6"w llR 7 Fig. 6 REPAIR !! ELDS B-A TBD TBD TBD IOZZLE-TO-VESSELllELDS B-D 44515I000002 II"t x 6"w Fig. 8 Ou{let flozzle A0 E
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' Fig. 7 Inlet
.. flo2.zle
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Inlet flozzle B Fig. 7 C p n a g a
- Typical examination volume is defined for each welt!/ component geometry in the appilcabic test procedure,
Flockwdlintemstfonal NO 425TI000C01 4* Erwrsy srutems creuo PAGE .5
'b2 1.1. REFERE.'CE DRM:I:GS
's . Babcock & Wilcox 145069, Location of Welds For In Service Inspection.
- 2. Westinghcuse 7245031 Sheet 2 of 9, CAE (As Built) Reactor Vessel Instrumentation Penetration Coordinates and Elevations.
- 3. Westinghouse 7245031 Sheet 3 of 9, CAE (As Built) Lfpper Barrel Seating
. Surface and Keyways.
4. Westinghouse 7245DS1 Sheet 4 of 9, CAE (As Built) Clevis.
- 5. Westinghouse 7245081 Sheet 6 of 9, CAE (As Builts) Wall size, inside diaceter of cutlet no::le ano no::le orientation.
- 6. Westinghouse 72?5D81, Sheet 5 of 9, CAE (As Built) Succcrt Locations, Radii of outlet no::le to internals seating surface.
- 7. Babccck and Wilcox IC96933 Rev. 2. Lower Head CTR Disc.
- 8. Babcock and Wilcox 125:30C Rev. 2, Lower Head Dutchman Forging.
M J 9. Babcock and Wilcox 125'29C Rev. 1, Lower Shell Forging. '
- 10. Babcock and Wilcox 125222C Rev.1, Upper Shell Fcrgirg.
- 11. Babccck and Wilcox 12E 29C Rev.1, : cz:le Belt Forgir.g.
- 12. Babccck and Wilcox 1095953 Rev. 1, Yessel Flange Forging.
- 13. Westinghcuse 1679C95,Shee: 1 of J. Calibration 31ock Inter ediate Shell.
- 14. Westinghcuse 1679096, Sheet 2 cf 4 Calibraticn Block Closure Head.
- 15. Westinghouse 1679C96, Sheet 3 of 4, Calibration Block Ecttem He:d.
- 16. Westinghouse 1679C96, Sheet 4 of 4, Caitbraticn Block Upper Sheil.
- 17. Westin:heuse Tc800CS,
- Loop Calibration 31cck Flange Lig:r.ent.
- 18. Westinghcuse Sketch 20, Calibration Block Details Safe End. -
- 19. Westinghouse 16 SIC 46, Calibration Block.
- 20. Sargean; and Lundy Engineering Drawing 1-171 Rev.H
- 21. Sargeant and Lundy Engineering Drawing i1-172 Rev. H .
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Rockwellintemat!ond NO . 445TI000001 En.cer sa. . cravo PAGE . 6 6 b ' 2.0 SUPPORT RECUIRE"ENTS - l 2.1 Laydown and Ecuicment Assembly Areas
" A packing list will identify container numbers in the vans used to ship the Rockwell International ISI system. A sequencing sheet and instructions
- will be provided by the Rockwell crew manager at the Byron site for unloading ' and laydown of equipment. 2.1.1 Control Rocm The laydewn area for the control and electronic console peri;:horals will be gridlines@ to O (Owg.14-171) and@ to@with portions of @ to @ceir.g to line @and(9to Ogcing to line@(see Fig.11). Three quarter in. thick ply-
. must be 1e"~' 'n"n over tne grating in this area to allcw sealing of the control roon ualls to the ficor and to provide a barrier to the environment.
Outside the centrol roca there will be the two electronic power su;;olies (2'xa 'x 4' high) and Oeitec (3' x 2' x 4-1/2' high) with 30' of cable available from the end of the control room. There^is a 78' cable from the po..er supplies to run to the source of 450V 3D power. There is available 50' cf cable frca the end of the control rc0m to the source of 4S0 V single O power. The packages into this area will be the centrol console (5* x 11' x 7'high)
-2700 pounds, par console (2-1/2' x 4' x 6' high) '1,500 pcunds, taca and dis:
drives (2-1/2" x 3' x 7' high), printronex teleprinter (3' x 3' x 4' high), a four file cabinets 15" x 30" x 4' high) and several varicus size boxes of supplies and diagnostic equipment. e
'9 F O R Ae 710 P R t v.
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NO 445T100000) hoRockw:llintemat'onal . Enem sprems Group PAGE . 7
/s A control room (see Figure 12) will be built around and over the control censoles, electronic peripherals and file cabinets.
2'1.2
. Soarec and Recair Recm ,
An area 200 ft2 is needed for a workbench, tool lockers and spare parts. The area between R2 and R3 was offered and would be suitable with , a wire cage enclosure. 2.1.3 Calibration Area An area near the reactor flange will be required to calibrate and service the ultrasonic transducers. An immersion tank (2' x 5' x 2-1/2 high) will be used to hold the calibration biccks and calibrate transducers. A tcol box (2' x 5' x 2-1/2' high) will contain the S'.!RI accessories and tcols. A table area by 8' is needed for layou,t. A floor space of 3' x 10' shculd be contigucus with tank, tool box and table area. 2.1.4 par Laydnwn
- The PAR manipulatcr legs will be in a crate 4' wide by 3'4" high
- by 12'8" long 1,500 lbs. This will be moved using the rail car into containz.cnt. A crane will*be re;uired to remove the crate from the rail
- car and placed on or near the end of the rail car platfom. The tcp of the
~
box will be removed and the bolts and wood restraints removed frcm the legs. o . T Foneen?=ntv.: o
-- h[h Rockw;llint:rnananal NO 445 TIC 00001 o
enerer vu. . crous s PAGE .8 N
)
) . The pap. manipulator will be in a crate 23' long 4' wide and 5-1/2' high
'5,000 pounds. This will be moved using the rail car into contain.ent. The crane will be required to re. move the crate from the rail car and placed on the end of the rail car platform. The sides and tcp of the box will be remoted and the bolt and wood restraints released frcm the manipulator and box ,
bottem. The manipulator will be removed from the box bottcm and placed on the rail platform. The manipulator is ecuipped with a trunion and casters to allow ease in uprighting using a crane. Upright the =aniculator and remove trunion and casters. The legs will be attached and then the maniculator
'placed over the reactor flange. ,
2.2 UTILITIES 7
~
2.2.1 Electrical l 15 Amp 40 Voi: 30 within 70' of the pcwer sucplics. 1 20 Amp 40 Volt 13 with 50' of gridline G and 1 or H and 2. 2 20 Amp 22CV 1 0 at the con:rol consele recm. 4 15 Amp 1107 at the control console roo.a. I 15 A.T.p ll0V at the spaies ar.d repair rocm. , 1 15 Amp 110V at the calibration area. 2.2.2 t'itrogen 100 psi dry nitrcgen or dry cir at the control room. C 2.2.3 Self Extiruishire Fire 5es'.ca - A Halon self extinguishing fire system. d , FOW 11%P setv. $3
{ R:ckw;illaternational NO . 445T1000C01 4A Energy Syuems Group PAGE .g I . 2.2.4 Telenhores - Two outside telephones are required in the control rcen. 2.2.5 Drinking Water.. , 2.2.6 Refuse nisnosti. 2.3 CRAFT SUPPORT
. The folleuing craft support will be required. -
Electrical - Halon Installers Fitters Riggers Heavy equiprent operators Carpenters g Banders & Craters - 2.4 CRANE
' Cranes and handling equipment will be required to unload two vans and move to operating areas. In the opera kng area ready access (within I hour) to use the crane is required.
2.5 0FFICE AREA An office area with a desk with locking drawers and an outside phene. 2.6 EOUIF"E"T CO'UAINER STOR'3E The folleuing reusable con:siner: require storage . cut of weather and secure from damage: 6' romu tu e arv. 2 eo l ~ ~ ~ ~ . - _ _ . .
, , , . . , . . . , ;..,,,....-- Q- - --,----.--- -- -- -
- EOckwelllntZrnati2nal NO 445TICC0001 Energy Systems Group PAGE , 10 p) . a) The par manipulator crate 4'-1/2" wide by 5'6" high by 23' long, b) par manipula or leg crate 4'-1/2" wide by 3'4" high by 12'8"long.
c) Portable building crate 5' x 5' high x 11' long, d) pap. cansole skid 4'2" by 10" high by d'S" long. e) Perte & mag tap skid 3'3" by 10" high by 3'8" long. , f) Co.m.puter skid 4'8" by 10" high bf 11' long. g) Two Printronix skids 2' by 10" high by 3' long. 3.0 CLCTHI'ai Rockwell Internaticnal coveralls will be worn by all Rockwell operations personnel in contairrent. The coveralis are blue and made of durable press 65% Kodel polyester /35 cembed cotten fine line twill. When. required plant industrial gloves (305X-10) will be worn. These are made from medium weight blea:hed jersey material processed to be chloride-free. Canvas shoe covers will be worr. By all Rockwell personnel descer.dir.g the ladder to the flange of the reactor pressure vessel. The shoe covers are -ade of of heavy grade B arr:y duct with exerciser closure to P.ii spec. C5650A. 4.0 DOCU:'E!!TATIO! The results of the exanination will be documentej in a report which will contain as a minimum:
- Equipment Description Examination Su= aries Procedures h,i -
I roau m e ns :eo. l
- - . - - . ._ l l
ROCkWCllIntirnation::1 NO 445TICCC001
. Energy Systems Group PAGE j) s.
J . Personnel Certifications Material Certifications Equipment Certifications
- Equipment Calibraticns
. Weld Maps -
Summary of reportable ' indications Calibration Data Magnetic Tape Record . Exanination Data
) .
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