ML18043A913

From kanterella
Jump to navigation Jump to search
Forwards Revision 3 to Steam Generator Repair Rept
ML18043A913
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/03/1979
From: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Ziemann D
Office of Nuclear Reactor Regulation
Shared Package
ML18043A914 List:
References
NUDOCS 7908070536
Download: ML18043A913 (68)
v • d • e


Text

..!

/

,. ~*

.~

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 August 3, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Brandi No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT ~ STEAM GENERATOR REPAIR REPORT - REVISION 3 JULY 1979 Attached is Revision 3~ dated July 1979 of the "Palisades' Plant Steam Generator Repait*Repcirt."

Thi~ Revision 3 contains responses to requests for additional inforn;iation transmitted by letter dated May 16, 1979.

I c.. i

..,. *~

~~~*-;~**

David A Bixel Nuclear Licensing Administrator cc JGKeppler, USNRC

CONSUMERS POWER COMPANY PALISADES PLANT STEAM GENERATOR REPAIR REPORT Docket 50-255 License DPR-20 At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits the "Palisades Plant Steam Generator Repair Report," Revision 3, July 1979, which describes the potential repair program based on complete replacement of the existing steam generators if major repairs become necessary.

CONSUMERS Pn By

/<.c, R C Youngdahl, Sworn 3rd day of August 1979.

~at<u:,~~

Jackson County, Michigan My commission expires March 26, 1983.

~**

.~.

1 CONSUMERS POWER COMP.~TI PALISADES PLANT STEAM GENERA.mR REP.\\m REPORT Docket 50*25.5 License DE'l:i-20 At the request of the Commission and pursuant to the Atomic Energr Act of.1954

.and the *~ergr Reorganization Act of 1974, as a.mended, and' the Commission's Rules a.c.d Regulations theretinder, Consumers Power Compa.ay submits the "Palisades Plant Steam. Genera.tor Repair Report," Revision 3, Jul7 1979, which desc~bes the potential repair program based on complete replacement of the existizlg steam generators if ma.Jar repairs become necess8,l"J'.

CONSUMERS POWER COMP Ai.TI By R C Youngdahl (Signed)

R C Youngdahl., Executive Vice President

. Sworn and subscribed to before me this 3rd day of August 1979.

Dorothy H Bartkus (Signed)

Dorothy H Ea.rtkus, Notar.r Public Jackson County-, Michigan

?ify' commission expires* March 26, 1983.

{)c.~I!?. 'S~ 1;11

-; q (j) 'ii (j) 7 (/) _g-3 6 IGf

. c T

PALISADES PLANT SGRR REMOVE INSERT vi*

Rev 2 vi Rev 3 vii Rev 2.

vii Rev 3

. viii Rev l viii Rev 3 x

Rev 2 x

  • Rev 3 Figure 3-3-2 Rev 0 Figure* 3-3*2 Rev 3 Table 4-3-*2 Rev 0 Table 4-3~2 Rev 3 (Sheet l to 2)

(Sheet l. to 2)

Appendix c C-l-l Rev 3 Table C-l-l (Sheet l to 12)

Table *c-1-2 (Sheet l to 3)

Table C-l--3 (Sheet l to 14}

Table C-l-4 (Sheet l to 3 )

Table C*l-5 (Sheet l to*3) c-2-1 Rev 3 C-3-l Rev 3 C-3-2 Rev 3 C-3-3 Rev 3 Figure C-3*1 Rev 3 Figure C-3-2 Rev 3 Figure C-3-3 Rev 3 Figure C-3-4 Rev 3 C-4-l Rev 3 c-s-1 Rev 3 c-s-2 Rev 3 C-5-3 Rev 3 C-6-l Rev 3, C-6-2 Rev 3 c-1-1 Rev 3 Table C-7-l Rev 3 c-a-1 Rev 3 c-a-2 Rev 3 c-9-l Rev. 3 c-10-1 Rev 3

,f.

PALISADES PLANT SGRR 8.6 REPLACEMENT OF STEAM GENERATOR

  • EVAPORATOR SECTIONS 8.7 MAN-REM CONSIDERATIONS a.a CONCLUSIONS 8-6 a-.6 8-7 9.0 COST BENEFIT ANALYSIS FOR THE DECONTAMINATION, 9-l STORAGE, AND DISPOSAL OF THE OLD STEA.a.\\f GENERATORS CONSIDERING ALARA 9.l INTRODUCTION

. 9.*2 STEAM GENERATOR IN-PLACE DECONTA.a.\\IINATION 9.3 STEAM GENERATOR STORAGE AND DISPOSAL 9.3.1 9.3.2 9.3.3 9.3.4

10. 0 REFERENCES LON~TERM STEAM GENERATOR STORAGE.

ONSITE IMMEDIATE SHIPMENT BY BARGE SHORT*TERM STORAGE WHILE UNITS ARE.

CUT UP FOR SHIPMENT (WITHOUT DECONTAMINATION)

CONCLUSIONS APPENDIX A -

RESPONSE TO NRC QUESTIONS OF 4/17 /79'

. APPENDIX B -

RESPONSE TO NRC QUESTIONS OF 4/19/79 APPENDIX C - RESPONSE TO NRC QUESTIONS OF 5/16/79 vi 9*1 9-l 9-2 9-2 9-2.

9-3.

9-3 10-l A-l(a)-1 B-l(a)-1 c-1-1 I 3 Revision 3 July 1979 2

TABLE NO.

2.1-1 2.1-2 2.2-1

  • 4.2-1 4.*. 2-2 4.2-3

'4.3-1 4.3-2 4.4-1 4.4-2 6.2-l 6.2-2 6.2-3 6.2-4 6.2-5 8.4-l' 8.8-1

  • B-2-1 B-2-2 c-1--1 c-1-2 C-l-3 C-1-4 c-1-s c-1-1 PALISADES PLANT SGRR..

LIST OE' TABLES.

TITLE.

STEAM GENERATOR COMPARISON DATA REPLACEMENT STEAM GENERATOR DATA STEAM GENERATOR MATERIALS ELECTRICAL EQUIPMENT.AND INSTRUMENTS TO BE TEMPORARILY REMOVED 480 V MOTOR CONTROL CENTER*S09 LOAD TABULATION TEMPORARY AND PERMANENT ELECTRICAL LOADS ASSOC.IATED WITH STEAL"1 GENERATOR REPAIR AND THEIR CORRESPONDING POWER SOURCE TYPICAL PORTABLE SURVEY INSTRUMENT SPECIFICATIONS MAN-REM ASSESSMENT FOR RE?LACEMENT ACTIVATED CORROSION PRODUCTS AFTER SHUTDOWN MAN-REM ASSESSMENT FOR OFFSXTE DISPOSAL ESTIMATES OE' AIRBORNE RELEASES TO ENVIRONMENT DURING STEAM GE~E:RATOR REPAIR EFFORT COMPARISON OF GASEOUS EFFLUFNT RELEASES ESTIMATED SPECIFIC ACTIVITY OE' LAUNDRY WASTEWlllTER ESTIMATED RADIOACTIVE LIQO!D EFFLUENT RELEASED DORING THE STEAM GENERATOR REPAIR COMP.~RISON OF.* RADIOACTIVE LIQtTID EFFLUENT RELEASES STEAM GENERATOR REPAIR ALTERNATIVE COSTS COMPARISON OF MAJOR REPAIR ALTERNATIVES GENERAL CORROSION' RATE IN FAULTED VOLATILE CHEMISTRY MODEL BOILER ENVIRONMENTS

. TUBE SUPPORT MATERIALS COMPARISON CCR..~OSION TESTING AT HEAT TRANSFER/SUPPORT LOCATION (MODEL BOILE.R TESTING)

MANUAL WELDING OF RC PIPE WITH MACHINE CLADDING I

SUMMARY

OF MANHOtm.S FOR ALL TASKS BY LOCATION MACHINE WELDING OF RC PIPE W!TH REMOTE VIEWING* *

SUMMARY

OF MANBOURS FOR ALL TASKS BY LOCATION MAN-REM ESTIMATE MAN-REM ESTIMATE (?REPARATION, INSTALLATION, REMOVAL, AND STORAGE) 2 3

vii Revision 3 July 1979

PALISADES PLAN'l' SGRR.

LIST OF FIGURES FIGURE NO*.*

TITLE 2.2-1 2.2-2 2.2-3 2.2-4.

2.2-s 2.2-6 2.2-7 2.2-a 2.2-9 2.2-10 2.2=11 3.1-1 3.1-2 3.3-l 3.3-2 3.4-l 3.5-1 4.1-l 4.1-2 4.1-3

  • 4.1-4 4.1-5 4.1-6 4.1-7 4.l-8 4.1-9 4.1-10 4.1-ll 4.l-12 4.l-13 4.1-14 4.1*15 4.l-16.

REPLACEMENT. STE.Ai.'-1 GENERATORS DELETED*

DELETED BOTTOM SLOWDOWN DOCT ASSEMBLY TOBE SUPPOR'l' TYPES EGGCRATE ASSEMBLY BEND REGION TUBE. SUPPORT TUBE SUPPORT OPPER ASSEMBLY STEAM GENERATOR -

FLOW RESTRICTOR NOZZLE PRIMARY HEAD DRAINS EXISTING SLOWOOw~ AND RECI?.CULATION SYSTEM MODIFIED SLOWDOWN A..~D RECIRCULATION SYSTEM EXISTING TURBINE ANALYZER PANEL FOR SAMPLING SYSTEM MODIFIED TURBINE ANALYZER PANEL FOR S&'!PLING SYSTEM PRIMARY HEAD DRAIN SYSTEM WIDE RANGE LEVEL TRANSMITTER SITE PLAN BARGE.SLIP OLD* STEAM GENERATOR STORAGE FACILITY PLAN VIEW OLD STEAM GENERATOR FACILITY SECTIONS AND DETAILS CONTAINMENT LAYDOWN AREAS GENERAL ARRANGEMENT PLAN VIEW, SHEET 1 GENERAL ARRANGEMENT PLAN VIEW, SHEET 2 GENERAL ARRANGEMENT SECTION A-A GENERAL ARRANGEMENT SECTION B-B DOw'"N-ENDING STE.Ai.~ GENERATOR ONTO SLEDS LOWERING STEAM GENERATOR FROM ELEVATOR PLATFORM ONTO TRANSPORTERS STEAM GENERATOR IN HOISTED POSITION, SECTION VIEW STEAM GENERATOR ON TRANSPORTER BETWEEN STORAGE AND CONTAINMENT STEAM GENERATOR ON TRANSPORTER BARGE TO STORAGE OFF LOADING STEAM GENERATOR FROM.BAR.GE, PLAN VIEW OFF LOADING STEAM GENERATOR FROM BARGE, viii 3

Revision 3 July 1979

4.2-4 4.2-5 4.2-6 4.2-7.

4. 2-8 :

4.3*1 4.3-2 4.3-3 4.3-4 4.3-5 4.3-6 4.3-7 A-l(b)-1 A-l(b)-2 C-3-l C-3-2 c-3-3 C-:3~4 PALISADES l?.LANT SGRR LIST OE' E'IGURES PRIMARY COOLANT PIPING CUT l?OINTS MAIN STEAM PIPING CUT POINTS FEEDWATER PIPING CUT POINTS BLOWDOw'"N PIPING _CUT POINTS STEAM GENERATOR UPPER SUPPORT DETAILS ACCESS CONTROL

(~L 590 1 -*0 11 AND EL 6ll'-0 11

)

ACCESS CONTROL.(EL 649'-0")

PRIMARY COOLANT PIPING CONTACT RADIATION SURVEY AVERAGE.RADIATION FIELDS 10 WEEKS APTER SHUTDOWN RADIATION SURVEY (EL 607 1-6 11 )*

MAX"IMUM DOSE.RATE INSIDE STEAM GENERATORS GENERAL RADIATION E'IELD NEAR STEAM GENERATOR PIPING STEAM GENERATOR REPLACEMENT SCHEDULE STEAM GENERATOR RETOBING PRI~.ARY COOLANT PIPING CUT POINTS MAIN STEAM PIPING COT POINTS FEEDWATER PIPING COT POINTS BLOWDOWN PIPING cuT POINTS 3

Revision 3 July 1979

PALISADES PLANT liTEAM GENERATOR REPAIR REPORT MODIFIED TURBINE ANALYZER

  • PANEL IW~: SAMPLING SYSTEH Figure 3. 3-2 Revision l.

July 1!179 r

I i I i

I I

fALISAJ>ES fl.ANT SGRR TABLE t.3.2

( SHEl:.'T 1, HAN-REH ASSESSMENT fOR REf LACEMENT (The manhour and man-rem eatimates have been revised refer Average Eutimated Ill Radiation Manhoura in

  • Field Work Areca

. Radication field*

(rem/hr)

1.

outsidis of power plant building but within uecurity fence

2.

Checking* in ;anli out tl'rough 11ecurity and hedl th pyuic11, aa W@ll o& time upcmt uui ting up, cleianing up, and*

111ov in\\I to iand

  • fl*o111 work ;areo for peclioruu:l working in radioactive areae
3.

lnuide contai1u11ent neiar now co11st1:11ction opening

4.

within 6 feet of outuido of reactor coolant pipe or bottom of *team generator before re111oval of &team geni:ratoru

!).

Within 6 fi:et of outuide of reactor coolant pipe after 11tea111 generator'u removal

6.

Within 6 feet of outside of ro;actor coolant pipe or bottom of 11tea111 genccatoru with p;u:tical expouuro to inuida of reactor cool;ant pipe.

befoce ateam generator*u removal

1.

Within 6 feet of outside of x*eactor coolant 1>ipe with pllrtial oxpo11uro to in11ido of reactor coolant pipe after uteam generator*o removal

8.

lnuide reactor coolant pip@

9.

Low radiation area within contaiD111ont 213,300

!)5,300 3,550 5,050 19,100 23,400 Al 750 ol,400 4,500 200 Al 300 A2 41,250 t,200 A2

.5x10*1

.0025 0.001 0.03 0.01 1.0 1.0 9.0 0.001

.005 A2 to'Table*C-1-1 Ai:ea Ill Man-Rem Dose (Han-Re111)

Unlihielded l.06 138.25.

3.55 151.5 191.0 234.0 Al 750.0 4,4100 40,500 1,800 Al 2,"100 A2 41.25 21.0 A2 to c-1-s.)

Reduction Factor (Shielding and/or Decontamination) 1.0 1.0 1.0 1.0 1.0.

0.05

. o.os O.l 1.0 Area Ha11-Re111 Dolie (Han-Re111) 1.06 138.25 3.55 151.5 191.0 234.0 Al 37.5 220.0 40*10;0 180.0 Al 270.0 A2 41.25 21.0 A2 Revision 3

Iuly 1979

-f

I

10.
11.
u.
u.
14.
15.
16.
17.

UL

19.

l'ALISADES l'LAHT SGRll TABLE t.3.2 (SllJ::ET 2)

~-REM ASSESS~J::NT FOJl RE~LACEHENT (The manhour and man-rem estimates have been changed reter to Table C~l-1 to C-1-5.)

Avercage Areil Ill Reduction Estimated 111 llAdhtion HAn-Rem i'Actor "anhouru in field

  • Dose (Han-Rem)

(Shielding and/or Work AreA Rodhtion Fiold (rem/hr)

Unshielded Decontamination)

Within 6 feet of top half of original stect111 generatore 1,100 0.005 5.5 1.0 Within 6 feet of top half of new liteaw yenercat:or11 8,050 0.001

&LOS 1.0 Operctting floor of contilinment 15,800 0.005 79.0 0.2 lnoide containment, above polar crane 1,150 0.001 1.15 1.0 Auxiliilry building neAr clean resin tank cand cooling wAtor tank 750 0.001 0.75 1.0 Auxiliary building no&r blowdown tank 6,700 0.001 6.7 1.0 S11e11t fuel pool floor 2,750 0.005 ll.75 1.0 Within 6 feet of tho bottom half of new 11tel:UI\\ generiltors J,700 0.010 37.0 1.0 Within 6 feet of tho outeido of the reactor ve1111el 50 1.0 50.0 1.. 0.

Next to the exiuting etoam gunercttora outi>ide of t:ho containment 1,000 0.02 20.0 1.0 Tot&l Al A2 Uote1 Are A Man-Rem Do lie (Man-Rem) 5.5 8.05.

15.8 1.15 0.75 6.7 13.75 37.0 50.0 20.0 4,993 1,666 1,193 111 The three 111An-reia estimate& given for-woi*k Area a (inside of reactor coolant pipe) are pi*eaerited becau11e of three welding teclmiquea under consideration.

Tho ALARA considerationa will be the fActor deton1ining which technilJUe iii eventually used.

'rho total time esti111cated for cutting, welding, and inlipecting in11ide \\:he reActor _coolAnt pipe& is 4,500 auanboun.

ones alternative (Al) ia ca technique, presently being investigated for fecaaibility, utilhing uianuill welding froau the outliido of the piping.

U11ing this method, only 200 u1ca11hou1*s out of A totcal of 4,500 would be i*equired

  • inuide priwa.i:y coolant piping.

'l'he remaining 4, 300 111a11boilr11 would be &pe1it within 6 feet 9! tho reactor coolant pipe (work At*ea 5).

Tho uecond alternative (A2) iu an auto111atic welding teclmique foi* the cladding from inliide the piping.

utili~ing remotts viewing~ Thia method requin:d 300. 111anhourli imiide the piping, and the remaining 4,200 11i.111houi*a would be 1ip1mt in a low radia.tion Aa:eA in the contai1u11ent (woi*k areA 9).

u~v1s1on 3 July 979

l SGRR C-1 PALISADES PLANT SGRR C-1 Provide the following additional information regarding ALARA considerations (Sections 1.1.S and 4.3.5):

RESPONSE

(l)

  • Duration of exposure associated 'with anticipated replacement/repair tasks (2)

Repetition rate of the*tasks

  • (3)

Numbers* o~ work forc:e exposed during each task (4)

Occupation~l exposures associated with antici-pated replacement/repair activities Tables (C-1-1 through C-l-5) provide ~~e requested additional information.

The manhour and corresponding man-rem estimates have changed from the original presented in Table 4.3.2.

The changes are based on modifications to the welding techniques, described as Alternative (A1 ) and Alternative (A2 ), and further development of work package~.

The new exposure estimates are as follows:

1,547 to 2,808 man-rem (A ), based on manual welding *the reactor coolant pipe carbon1steel port~on and machine welding the cladding (with remote viewing), and 1,537 to 2,663 man-rem (A) based on machine welding (with remote viewing) both the2carbon steel and cladding.

The man-rem range reflects two analyses, for 140 and 42 days after shut down for the commencement of primary system pipe cutting.

These estimates do not include a contingency.

It should be noted that Work Area 8, which represents manhours spent inside the reactor coolant pipe, has been expanded to appropriately differentiate radiation field levels before and after local decontamination.

c-1-1 Revision 3 July 1979

I.

PALI.

3 PLANT SGlUl TABLE C-1-1 (Sheet 1)

MANUAL WELDING.OF RC PIPE \\H'l'll MACHINE CLADDING NUMBER.

AVERAGE

. OF..

NUMHER TIMES*

TASK DURATION OF TASK NUMBER DESCRIPTION (HOURS)

PEllSONNEL

~LOCATION PERFORMED l

Scaffold. cut. and remove con-180 6

1 l

1>truction opening liner plate.

83 6

2 1

2 Install new line~ plate for con-233 6

3 1

structtpn opening, including 100 6

2 l

fttup, ecaf folding welding, etc.

3 Cover and uncover spent fuel pool.

270 7

16 0

(1>rotective cover).

116 7

2 0

240 7

l 0

4 Cut reactor coolant.pipe.

15 2

4 12 15 2

6 12 17 2

2 12 12 2

9 12 Machine weld preparution on ends 58 2

7

18.

of reactor coolant pipes.

35 2

2

18.

23 2

  • 9

.18 6

RJgj fitup, line up. und tack in 28 5

7 12 place reactor coolant pipe clo1>ure 17 5

2 12 spools.

11 5

9*

12

  • Refer to Table C-1-5

.MANllOUltS COMMENTS 1.000 498 1, 398 600 1.890 812 1,680 360 Inside radiation 360 control envelope 408 2H8 2,088 12 weld prep1>

1,260 would be."on decon-828 tamtnated pipe and 6 on pipe attached to reactor.

1,680 1~020 660

PALISI\\...*.> Pl.AN'l' SGRlt TABLE C-1-1 (Sheet 2)

MANUAL WELDING OF RC PIPE LH'l'll_ MACHINE CLADDING TASK NUMBER DESCRIPTION 1

Weld hot leg reactor coolant pipe (carbon steel).

8 Clad *hot leg reactor coolant pipe (etainlese steel) 9 Weld cold leg reactor coolant.

pipe (carbon eteel) *.

  • Uefer to 'fable C-1-5 DURATION (HOUR§)

131 2

131 113 2

50 30 89 2

91 17 2

45 -

28 22 2

22 20

. NUMBER AVERAGE OF NUMBER

. TIMES 01~

'fASK PERSONNEi.

  • t.OCATION PERFORMED 4

5 4

l 8C 4*

4 9

4 4

2 4

1 Sc 4

2 9*

4 2

2 4

4 5

8 1

8C a*

4 9

8 4

2 8

1 8C 8

2 9

8 2

2 8

4 5

12 l*

8C 12 4

9 12 4

2 12 MANllOURS COMMENTS-2,096 Manual welding 8c 8

level 2,104

~ j 1,800_

8 Utilizing machine 400 welding with re-240 mote welding 2,864 Manual welding 16 Manual welding 2,896 2,448 16" Machine welding 720 with remote 448 viewing

  • 1,056 24 1,056 960

PAL !SADES PLANT SGlUl TABLE C-1-1 (Sheet 3)

MANUAL WELDING OF RC PIPE Wl'fll MACHINE CLADDING.

TASK NUt-11.U~U DESCRIPTION 12 X-Ray ~nd NDT reactor coolant pipe.

13 Install cleanliness plugs in reactor coolant pipe prior to cutting pipe.

14 Clean inside of-reactor coolant pipe after welding.

15 Cover steam generator reactor coolant nozzles

. 16 Cover ends of reactor coolant pipe spools (temporary).

  • Refer to Table C-1-5 DURATION (HOURS~

1/2 4

3 1

1/2 1

1 1

1 1

4 1

2 1/2 1

3 l

AVERAGE NUMBER OF PERSONNEL.

1 2

2 2

1 2

1 4

4 4

2 4

4 4

4 4

4 NUMBER -

OF TJHES

'!'ASK

  • LOCATION Plm10RHED 8

48 5

120 2

120 9

120 8A 6

4 6

8C 12 8B 6

1 6

9 6*

7 6

BU 18 7

18 1

18 2

18 5

6 2

6 HANllOURS COMMENTS 24 I.eave plll guide i*

1.960 in place 8C when 720 possible in order

  • 240 to reduce exposure.

3 12 8

24 24 24 48 (Seal weld only) 72 1}14 36 72 72 24

11AI. ISl......; PLANT SGRR

'l'ABJ.E C-1-1 (Sheet 4)

MANUAL WELDING OF RC.PIPE Wl'fll MACHINE CLADDING

'l'ASK NUMBElt 18 19 20 21 22 23 DESCRIPTION Measure reactor coolant pipe clo1rnr,e spools.

Remove insulation from steam generators.

Retnsulate new steam generator.

Remove and replace reactor coolant pipe insulation.

Cut, remove, bevel, erect, weld, stresu relieve, and insulate main steam llneu at top of steam generator.

X-ltay and NDT main steam line.

  • Refer to Table C-1-5 DURATION (HOURS) 4 1

38 32 25 32

  • rno 120 150 150 5

3 5

3 260 277 40 148 148 40 25 65 AVEltAG~

NUMBER

.OF PEltSONNEl.

3 3

4 4

4 4

4 4

4 4

2 2

2 2

3 3

3 3

3 2

2 2

  • LOCATION 5*

2 2

4 9

10 2

9 11 17 2

4 5

9 2

9 10 11 12 2

9 11 NUMBER OF TIMES TASK PERFORMED.MANllOURS COMMENTS 12 12 2

2 2

2 2

2 2

2 i2 12 12 12 2

2 2

2 2

2 2

2 144 36 304 256 200 256 1,440 960 1;200 1,200 120 72 120 72 1,560 1,662.

240*

888

.888 160 (6 weld) 100 260

PAL ISAUES l)LANT SGLUl TABLE C-1-1 (Sheet 5)

MANUAL WELDING OF RC PIPE W11'll MACHINE CLADDING

~UMBER AVERAGE OF NUMBER

'flHES

'l'ASK DURATION 01~

TASK NUMBER DESCRIPTION (UOURS)

PERSONNEL

  • LOCATION PERFOllMED 24 Cut, bevel, erect, weld 1 stress 162 2

2 2

reileve. and insulate feedwater 107 2

9 2

line.

25 2

10 2

245 2

11 2

25 X-Ray and NDT feedwater line.

20 2

2 2

45 2

11 2

26 Remove and replace miscellaneous 60 4

2 l

small pipe near steam generators.

50 4

4 l

/10 4

9 l

50 4

17

  • 1 27 Move component cooling water 75 4

2' 1

lank and clean resin tank out of 50 4

9 1

way and reinstall.

125

(

4 14 1

28 Install blowdown 1 tank. pwop 1 and 40 3

2 1

insulation.

20 3

9 1

67 3

15

1.

29 Install new blowdown piping 122 6

2 l

inside containment.

13 6

4 l

92 6

5 1

177 6

9 1

~Refer to Table C-1-5 HANllOUllS 648 428 100 980 80 180.

240 200 160 200.

300 200 500 120 60 201 732 78 552 1,062 COMMENTS (4 welds)*

I i

i

PALISAuc.S PLANT SGRR

,TABLE C-1-1 (Sl1eet 6)

MANUAL WELDING OF RC PIPE Wl'fll MAClllNE Cl.ADDING NUMBER AVERAGE OF NUMUER TIMES TASK DURATION OF TASK NllMUER DESCRIPTION (HOURS.)

PERSONNl.!:L

  • LOCATION PERFORMED 30 Install new blowdown piping 193 6

2

1.

outside containment.

128 6

9 1

322 6

15 1

31 Remove electrical inside con-37 4

2 1

tainment so steam generator can 63 4

4 1

be removed.

25 4

9 1

32 Reinstall electrical inside 90 8

2 1

containment.

60 8

9 1

75 8

11 l

75 8

17 l

If

. I 33 Install electrical for new 92 4

2 1

blowdown system.

12 4

9 1

173 4

15 l

32 4

17 l

34

  • Install and remove equipment 30 2

2

.l re'luited to monitor position of 10 reactor and steam generat~rs 130 l

9 l

during weldup of reactor coolant 20 2

17 1

(>ipe.

20 2

18 1

  • Refer to Table C-1-5 HANllOURS

.COMMENTS 1.158 768

1. 932.

148 252 150 720 480 600 600 368 48 692 1:28 60 130 40 40

PALISADES PLAN'f SGRR TABLE C-1-1 (Sheet 7)

MANUAL WELDING OF RC PIPE \\H'fll MACIUNE CLADDING NUMBER OF

'fl HES TASK TASK NUMBER DESCRIPTION DURATION (llOUllS~

AVE RACE NUMBER OF PERSONNEL

  • LOCATION PERFORMED HANUOURS 35 36 37 38 39 40 Mobilize, install cages.

1>>075 Re1uove *dome and buttress facia, relax tendons, remove tendons, chip concrete, cut rebar and

  • tendon sheathing for containment construction opening.

Replace opening on containment, 1,275 including the following:

R~place tendon sheathing, rebar, concrete and ~endons, stress tendon~ and replace dome and buttress facia, demobilize.

Construct and remove barge slip.

lloundatlons for rigging equip-ment, including sheetpiling, earthwork, concrete foundations and removal of foundations (at contaimuent building).

Mobile heavy lift rigger.

A1;;ae111ble 4 crawlers.

829 692 100 150

  • Ref er to Table C-1-5 20 l

1 21,500 15 l

1 19,125 14 l

1 11,606 12 1

1 8,304 15 1-1 1,500 10 l

l 1,500 COMMENTS

I I.

TASK NUMBER 41 42 43 44 45 lt6 47 48 49

  • Refer 1*

PALlb....; PLANT SGRlt TABU~ C-1-1

.(Sheet 8)

MANUAi. WELDING OF ltC PIPE Wl'fll M~ClllNE CLADDING NUMBER AVERAGE OF NUMBER TIMES DURA1'ION OF TASK DESCRIPTION (HOURS).

PERSONN!!:L

  • LOCATION PERl.i'ORMED Assemble jacking frame at barge.

62 12 1

1 Asoemble jacking frame at con-78 12 1

1 tainment.

Preassemble equipment for inside 78 12 1.

1 containment.

Install lifting equipment* inside 112 i5 2

1 containment.

158 15 12 1

105 15 13 1

Remove existing steam generatora 23 15 1

2 from containment (rigging).

26 15 2

2 44 15 4

2 19 15 19 2

Transport and store ex:l,sttng 31 10 19 2

steam generators.

Receive and ballast barge.

20 5

1 1

Offload, store, load, and trans-158 10 1

2 port new steam generatora.

Rertg as required to install.

16 15 1

2 to '!'able C-1-5

. HANllOURS COMMENTS 744 936 936

. 1,680 2,370 1,575 690 780 1,320 570 620 100

. 3,160 480

TASK NUMBER 50 51 I

52 53 54 55 56 57 TABLE C-1-1 (Sheet 9)

MANUAL WELDING 01.RC PIPE \\HTll MACHINE CLADDING NUMBER AVERAGE OF NUHIUUl 1'1MES DURA1'JON 01

TASK DESCRIPTION (llOURS)

PERSONNEL

  • LOCATION PERFORMED Install new eteam generatore.

19 15 1

2 21 15 2

2 37 15 12 2

12 15 17 2

Remove all external rigglng 225 15 1

1 equipment f row site.

Remov.e all rigging equipment 75 15 2

1 from containment.

105 15 12 1

70 15 13 1

Remove internal rigging. equip-63 15 1

1 ment from site.

Miscellaneous rigging 150 5

1 1

Steam generator storage building.

406 10 1

1 Cut and remove top support.of 8

5 10 I

  • 1 uteam generator.

5 5

2 1

3 5

9 l

Remove shims other steam 6

4 10 1

generator topeupport.

4 4

2 l

2 4

9 l

MANllOURS*

COMMENTS 570 630 1,110 360 3,375 1,125 1.575 1,050 945 750 4,060 40

  • 25 15 24 16 8
1.

l>AL !SADES PLANT SCRR

'fABl.E C-1-1 (Sheet 10)

MANUAL WELDING OF RC PIPE Wl'l'll MAClllNE Cl.ADDING NUMBER AVERAGE

  • OF NU.MBER TIMES TASK DUltATION OJ.t'

'l'ASK NUMHER DESCRIPTION (HOURS~

PERSONNEL

  • LOCATION PIUtFOllMED
  • 58 lleauove hydraulic snubbere.

4 5

10 8

3 5

2 8

1

.5 9

8 59 Unbolt existing steam generator.

4 3

4 2

3 3

2 2

  • 1 3

9 2

60 llemove shime at.ateam generator 15 3

4 2

base.

9 3

2 2

6 3

9 2

61 Holt down steam generators.

10 3

5 2

6 3

2

  • 2 4

3 9

2 62 lteshim bottom steam generator 50 3

5 2

(sliding base).

30 3

2 2

20 3

9 2

Ill 63 Replace top steam generator 120 3*

11 2

support.

72 3

2 2

48 3

9 2

64 lteshim top steam ge1_1erator 40 3

11 2

trnpporti;.

24 3

2 2

16 3

9 2

  • Uefer to '!'able C-1-S HANllOURS COMMENTS 160 120 40 24 18 6

90 54

36.

I 60 36 24 300

.180 120 720 432 288 240 144 96

PALJSAi._.:., PLANT SGRR TABLE C-1-1 (Sheet 11)

MANUAL WEI.DING 01~ RC Pll>E WITH MAClllNE CLADDING TASK Nlll1llER 65 DESCRIPTION Reinstall steam generator hy-drauli~ snubbere; 66 Miscellaneous pipe operations (welders tests, material hangling, scaffolding, training, hangere and supports, liue testing, cleanup, tents).

67 Distributables (startup, cleanup, scaffolding, welders tests other than pipe fitters, miscellaneous).

kRefer to Table C-1-5 DURATION (HOURS}

30 18 12 AVERAGE NUHliER OF PERSONNEL 4

4 4

""LOCATION 11 2

9 1

2 4

5 8

9 10 11 12

.15 17 1

2 3

4 5

6 7

8 9

llO u

NUMBER OF TIMES TASK PERFORMED HANllOURS 8

960 8

576 8

384 25,088 7,030 952 3,699 20 6,982 552 1,088 413 914 87 11,436 13, 298 1,003 1,526 4,883 131 1,613 51 9,766 567 2,921 COMMENTS Welders tests, training, material handling and fabri-cation of tents are in Location 1.

lte-mainder of manhours were allocated on the basis.of piping iuanhours in each location.

Welders tests and mJ.scellaneous in Area 1.

Rema i oder of manhours allo-cated on the basis.

of direct manhours excluding Area 1.

TASK NUMBER 67 (Continued) 68 Nonwanual DESCRIPTION

  • llefer to Table C-1-S PALI
I PLAN'l' SGRU TABLE C-1-1 (Sheet _12)

MANUAi. WELDING OF JlC PIPE Wl'J'll MACHINE CLADDING AVERAGE NUMBER DURATION 01

(HOURS)

PERSONNl~I. *LOCATION 12 13 14 15 16 17 19 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 l~

NUMBER OF TIMES.

TASK PERFORMED MANllOURS 2.6f6 1.090 218 1.526 785 1.090 480 99,160

6. 511.

53

~.uo 2.012 16 85 14

. s. 770 426 1,176 895 14*9 11

_l.143 141 401 67

'*I COMMENTS Office personnel and 50% of engineers and supervision's man-hours are* iii Location.

I

01.

Remainder of man-

  • houra by discipline wece allocated to the i)ropei location based on direct nianhours expended in that loca-tionby diacip:Une.

For example: *'l'he man-hours for electrical.

engineers and supts

  • were allocated based on the electrical dJrect hours expended on each task at each location.-*

TASK

!!!h__ ---=~=~l :~-=~-I. -*-*- l 4

I 1

4!111 1,000 2-61111 l,198 I

l I, t.1111 1112 4

4011 160

!i 1,2611 6

1,1120 1

1,81111 2,096 I

8 240

!I 2,440 2,1164 10 41,9 I I 11

!1611 1,056 12 720 960 ll 12 14 l!i 24 16 12 17 24 12 18

}(1 144 19

  • 1114 256 211 1,440 21 IW 72 120 22 l,!i60 21 160 24 11411 25 110 26 240 200 21 11111 l

811HHAllY Ot' HAllllOllllS mn Al.L 1'ASKS llY l.OCA'l'lllll HANllAI. Wl!l.lllNG 01' ttf.AC:'l'Oll COOi.ANT C:.S. l'll'H Wl'l'll HAClllNK c:u1ioi111: AND llt:HllTI! u ll!WlNI:*

6 1

___ _1c.:.~-* g 10 ---1r::::=1L 160 288 2,1188 828 1,680 660 8

2,104 8

4110 16 2,1196 16 120 24 I,O!i6 24 240 l

8 48 24 24 144 12 200 256 960 1,200 12 1,662 240 11118 111111 JOO 2611 428 JOO 980 180 160 2110 n

14 15 16

  • -u~.:::=-=1!!.*~---*19*----

l,090 1,200 2011

!iOO

'i'ii.sK

!!~:

2 20 1211 29 1:12

]jl I, 158 ll I '*8 12 no

])

]68 34

(>II 15 21,5011 16 l'J, 125 11 11,60(.

]8 8,:1111,

]IJ 1,500 411 1,500 41 1411 42

'J:lt.

41

  • nt.

44 1,1180 45 6')11 IRO 46 41 IOU 48

i, H.o 49 4811 511 5111 6'.10 51
  • 1,:IVi 52 l,125 5'.I

'J/15 18 252 1,320

'l'AIJU,; C-1-2

.. (i;ii;!.,t 2)-

SlltlllARY 01'" HANllOllllS **cm. Al.I. 'l'ASKS bV Ull:A"l' IUN tlANllAI. Wt:l.lllNCi lW lll'AC"l'Ull C:OOl.AH'f C.S. 1'11'1( Wl'l"ll HAClllNli Cl.AlllllNG AND Rlitton: VIEWING

... ~ ~.::=~:~*10 ___ -=.*: ! !

12

!L~=~~-14~=*:*: !~--:-1,_*:~--~-*!L

.. !~..

60 l,1162 166 150 460 48 no 6611 20l I, 9:12 692 2,llO 1,515 6110 128 40 I, 1111 "1(10 1,515 l,11511 jij. -.....

  • riisii NII.

54 5~,

5(,.

51 58 59 611 61 (12 (11 64 65 l'nl al llin*rl11 61 60

'l'ot11I

'1'1\\111.F. C-1-2 i i;j,..(. i j) *-

lllllllARY OF 111\\NllllllllS t'llll At.I. l'ASKS PY l.IJCA'l'IOll tlAlllll\\I, Wf.1.111 NG Of' llf.Al:'l"llll COOi.ANT C. S. I' ll'E Wl'l'll llACll I Nii Cl.Allll INll ANll REtlO'fE V lf.W I NG

.1.. 11 I

2

'i

~-~=:: 5 9 ------rn*-- *-*ii i -*-*.-----*.. **. -...... -*

i 1. -----.! r_~--~---1~.=_-.:.=:. l L----~-- J~.. ***rn**** -*-*--*-

1211 18

~,,.

1011 1112 51(,

2~ ** 111111 1,0111 24 90

(,(I

'11111 1111,0LI 12,114 2,478 1,640 11,921 II,lt"ll1 l'I, Z1lR 1J1J, l(,o

<* /i 11 1,111n 1,526 4,881 5:1 1;uo 2,812 211,65/ 52,141 1,514 6,216 llJ,610 DI 16 1,611 85 507 5,658 15 8

40 6

]6 24 120 288 96 184 211

'**'182 40 24 160 1211 240 960 552 l,086 lol 1 221 21,662 1,112 1,116 6,156 2,625 51 IJ,166 I lo 5, 110 561 2,921 2,616 426 1,116 895 1,0911 11,9 268 19,llJ8 2,165 11,211 9,861 l,864 1.6 914 61 5110 l,139 1,906 2,615 218 1,526 11 1,141 185 141 I, ll'Jll loll I 129 6_,408 2,812 4, 1116 40 I, 1911 480 61 1,0 I, Ul

TASK NUMBER 1

2 3

4 5

6

~Ref er l'AL!SADES PLAN'f SGRR TABLE C-1-3 (Sheet 1)

MACllINI( WEI.DING OF R. C. PIPE Wl'l'll REMOTE VIEWING NUMBER AVERAGE OF NUMBER TIMES

DURATION, OF TASK DESCRIPTION (HOURS)

PERSONNEL

~LOCATION PERFOltMED Scaffol4, cut, and remove 180 6

3 3

construction opening liner plate.

. 83 6

2 1

Install new liner plate for con-233 6

i 1

struction opening, includJng 100 6

2 1

fitup, scaffolding, welding, etc.

Cover and uncover spent fuel 270 7

16 0

pool (protective cover).

116 7

~

0 2110 7

l 0

Cut reactor coolant pipe.

15 2

£,

12' 15 2

6 12 17 2

'I..

12 12 2

9 12 Machine weld prep on ends of 58 2

i' 18 reactor coolant* pipes.

3~

2 2

18 23 2

~*

is*

II lUg, fit up, lineup and a:ack in 28 5

12 place reactor coolant plpe 17 5

2 12 closure spools.

11 5

9 12 to 1'able C-1-5 MANllOUllS COMMENTS 1,080 498

. i i"

1,398 600 1,890 812 1,680 360 Inside radiation con-360 trol envelope 408 288 2,088 12 weld preps would 1,260 be on decontaminated 828 pipe ~nd 6 on pipe*

attached to reactor.

1,680 1,020 660

PALJSADES PLANT SGRR TABI.E C-1-3 (Sheet 2)

MACHINE WELDING OF lt.C. PIPE WI'fll REMOTE VIEWING NUMBER AVERAGE OF NUMBER TIMES TASK DURATION*

OF TASK NUMBER DESCRIPTION (HOURS)

PERSONNEL

  • LOCATION PERFORMED 7

Weld hot leg reactor coolant 4

2 7

4 pipe (carbon steel).

3 1

BC 4

234 1

5..

4 146 3

2 4

273 3

9 4

8 Clad hot leg reactor coolant 2

1 BC 4

pipe (stainless steel) 50 2

9 4

30 2

2 4

9 Weld cold leg reactor coolant 4

2 7

8 pipe (carbon steel).

2 1

8 8

160 1

5 8

100 3

2 8

186 3

9 8

10 Clad cold leg reactor coolant 2

l 8C 8

j)ipe (stainless steel).

45 2

... 9 8

28 2

2 8

11 Stress relieve reactor coolant 22 4

5 12 pipe.

2 1

8C 12 22 4

9 12 20 4

2 12

  • Refer to 'fable C-1-5 HANllOURS COMMENTS
  • L

.32 Utilizing machine 12 welding with remote 935 viewing.

~;753

  • 1.276 8

Utilizing machine 400 welding with remote 240 vie.wing.

64 16 1,280 2,400 4,464 16 Machine welding 720 with remote Viewing*

448 1,056 24 1,056 960

PALISADES PLANT SGltR 1'AHLE C-1-3 (Sheet 3)

MACHINE WKLDING OF a.c. PIPE WI1'll REMO'l'.E VIEWING NUMBER AVERAGE OF NUMBER

'rIMES TASK DURATION I

OF TASK NIJMBl!:R DESCRIPTION (HOURS)

PERSONNEL

8C 48 llipe.

4 2

5 120 3

2 2

120 1

2 9

120 13 Install cleanliness plugs in 1/2 1

BA 6

reactor coolant pipe prior to 1

2 4

6 cutting pipe.

14 Clean inside of reactor coolant l

l 8C 12 pipe 4fter welding.

15 Cover steam generator reactor 1

4 88' 6

coolant nozzles.

1 4

l' 6

1 4

9

6.

4 2

7 6

16 Cover ends of reactor coolant 1

4 88 18 pipe spools (temporary).

l

.4 7

18 1/2 4

1.

18 l

4 2

18 17 Rig reactor coolant pipes to 3

4 5

6 decontamination area.

1 4

2 6

  • Refer to '!'able C-1-5 HANliOURS COMMENTS 24 Leave pill guide in 1,960 place 8C when poss!-:-

720 ble in order to re-

.240.

duce exposure.

3 12 i

8 24 24 24 48 (Seal weld only) 72 I

144 36

.. 72 72 24

i>AI.ISADES PLANT SGRR TABLE C-1-3 (Sheet 4)

MACHINE WEI.DING OF a.c. PIPE WITH REMOTE VIEWING NUMBER AVERAGE OF NUMBER TIMES TASK UURA'fION

  • OF TASK NUMBl!:R DESCRIPTION (HOURS)

PERSONNEL *LOCATION PERFORMED 18 Measure reactor coolant pipe 4

3 5

12 closure spools *.

. 1 3

2 12 19 Remove insulation from steam 38 4

-2 2

gene rat ors.

32 4

4 2

25 4

9 2

32 4

10 2

20 Re insulate new steam generator.

180 4

2 2

120 4

9 2

150 4

11 2

150 4

17 2

21 Remove and replace reactor coolant 5

2 2

- 12 pipe insulation.

3 2

4 12 5

2 5

12 3

2

-9 12 22 Cut. remove. bevel,_ erect, weld 1 260 3

2 2

stress relieve. and insulate main 277 3

9 2

steam lines at top of steam 40 3

10 2

generator.

148 3

11 2

148 3

12 2

  • Refer to Table C-1-5 I

HAN HOURS COMMENTS 144 -

36 304_

256 200 256 1.440 960 1.200 1.200 120 72 120 72-1,560 1,662 240 888

-888

PALISADES PLANT SGlUt TABLE C-1-3 (Sheet 5)

MACHINE WELDING 01 R.C. PIPE Wl'fll llEMOTE VIEWING NUMBER AVERAGE OF NUMBER TIMES TASK DURA'flON OF TASK NUMIUm DESCRIPTION (HOURS)

PERSONNEL

40 2

2 2*

25 2

9 2

65 2

11 2

24 Cut 1 bevel, erect, weld, stress 162 2

2 2

relJeve 1 and insulate feedwater 107 2

9 2

line.

25 2

10 2

245 2

11 2

25 X-Ray and ND'r feedwater line.

20 2

2 2

45 2

11 2

26 Remove and replace miscellaneous 60 4

2

50 4

4 l

40 4

9 1

50 4

17 l

27 Move component cooling water 15 4

2 1

tank and clean resin tank out* of 50 4

9 l

way and reinstall.

125 4

14 l

  • Refer to Table C-1-5 MANHOURS*

COMMENTS

160 (6 welds)
100 260 648 428 100 980 60 (4 welds) 180 240 200 160 200 300.

200 500

i

.1

- )

I I

l

' j I I I I I

1 i

I

' i I

PALISADES PLANT SGlut

'fA8LE C-1-3 (Sheet 7)

MACHINE WELDING 01 R. C~ PIPE WI'fll REMOTE VIEWING TASK NUMBER 34 35 36 37 DIJRA'flON DESCRIPTION (llOUltS)

Install and remove equi~nent 30 required to monitor positimi of reactor and steam generators dur-130 ing weldup of reactor coolant 20 pipe.

20 Mobilize, install cages.

Remove 1,075 dome and buttress facia, relax tendons, remove tendons, chip concrete, cut rebar and tendon sheathing for containment con-struction opening.

Ilea>lace opening on contairunent, 1,275 including the following:

Replace tendon sheathing, i:ebar, con-crete and tendons, etrese ten-dons and replace dome and butt-ress facla, demobilize.

Construct and remove barge slip.

829

  • Rder to 'fable C-1-5 NUMBER AVERAGE OF NUMBER TIMES OF TASK PERSONNEL
  • l.OCA'l'ION PERFORMED*

2

2.

1 10

  • 1 9

1 2

u 1

2 18 1

20 1

1

' 15 1

l 14 1

1 MANllOIJltS COMMENTS 60 130 40 40 21,500

I

-I ij PAl. ISADES PLAN1' scnn TABLE C-1-3

  • (Sheet 8)

MACHINE WELDING-o~* a.c. PIPE Wl'l'll REMOTE VIEWING NUMBER AVERAGE OF

_ NUMBER TIMES 1'ASK DURA'fION.,

OF TASK NllMBElt DESCRIPTION (HOURS)

PERSONNEi.

  • l.OCA'flON PEllFORMED -_

38 Ii'oundatioos for rigging 692 12

-1 l

equip111ent, including sheet:-

piling, earthwork, concrete foundations, and removal of foundations (at containment building).

39 Mo bi le heavy lift rigger 100 15 l

1 40 Assemble 4 crawlers.

150 10 l

1-41 Assemble jacking frame at barge.

62 12 1

l" 42 Assemble jacking frame at con-78 12 l

1 tainmeot.

43 l'reassemble equipment for to-78 12 l

1 side containment.

44 Install lifting equipment in-112 15 2

1 1::1ide containment.

158 15 12 l

105 15 13 1

  • llefer to 'l'able C-1-5 HANllOUllS COMMENTS 8,304

- I 1.500

- ~.soo 744-936 936 1,680

- 2.110 1,575

I I.

I I

I i

I I

I I

I

~

J>ALISADES PLAN'l' SGRll

'fABLE C-1-3 (Sheet 9)

MACHINE WELDING OF R.C. PIPE WI'l'll UEMO'fE VlliWING NUMBER AVERAGE OF NUMBER TIMES TASK DURATION OF TASK.

NUMBEll DESCRIPTION (HOURS)

PERSONNEi.

2 from con~ainment (rigging).

26 15 2

2 44 15 4

2 19 15 19 2

46 Transport and store existing 31 10 19 2

steam generators~

47 Receive and ballast barge.

20

  • 5 1

l 48 Offload, store, load, and trans-158 10 l

2

(!Ort new steam generators.

49 Uedg as required to install.

16 15 1

2*

50 Install new steam generators.

19 15 1

2 21 15 2

2

37.

15 12 2

12 15 l.7 2

51 Remove all external rigging 225 15 1

1 equipmen~ from site.

  • Refer to '!'able C-1-5 HANllOURS COMMENTS 690 780 1,320 570 620 100 3,160 480 570 630 1,110 360 3,375

PALISADES PLANT scarn TABLE C-1-3 (Sheet 10)

MACHINE WELDING OF R.C. PIPE Wl'fll REMOTE VIEWING NUM.BER AVERAGE OF NUMBER TIMES

'fASl<

DURATION OF TASK NUMllER DESCRIPTION (HOURS)

  • PERSONNEL
  • UlCATION PER~'ORMED HANllOLJRS COMMENTS 52 llcmove all rigging equipment 15 15 2

1 1,125 from containment.

105 15 12 1

1,575 70 15 13

.1 l*,050 53 Uemove internal rigging equipment 63 15 1

1 945 from site.

54 Hlscellaneoua rigging.

150 5

1 1

750 55 Steam generator storage building.

406 10 1

1 4,060 56 Cut and remove top support of 8

5 10 1

40 steam generator.

5 5

2 1

25 3

5 9

1 15 57 Uemove shims other steam generator 6

4 10 1

24 top support.

4 4

2 1

16 2

4 9

1 8

58 Uemove hydraulic snubbers.

4 5

10 8

. 160 3

5 2

8 120 1

5 9

8 40 59 Unbolt existing steam generator.

.4 3

4 2

24 J

3 2

2 18 1

3 9

2 6

  • Uefer to 'fable C-1-5

I

-I 1

  • i PAl:ISADES PLANT SGRR TABLE C-1-3 (Sheet 11)

MACHINE WELDING OF R.C. PIPE HI'l'll REMOTE VU~WING NUMBER AVERAGE OF NUMBER TIMES TASK DURATION 1 OF TASK NllHBER DES CR I P1'10N (HOURS)

PERSONNEL

4 2

base.

9 3

2 2

6 3

9 2

61 Bolt down steam generators 10 3

5 2

6 3

2 2

4 3

9 2

62 Reshim *bottom steam generator 50 3

5 2

(sliding base).

30 3

2 2

20 3

9 2

63 lleplace top steam generator 120 3

11 2

support.

72 3

2 2

48 3

9 2

64 Reshim top steam generator 40 3

- 11 2

supports.

24 3

2 2

16 3

9 2

65 Reinstall steam generator hydraulic 30 4*

11 8

snub be rs.

18 4

2 8

12 4

9 8

  • Uefer to 'fable C-1-5 HANHOUltS COMMENTS 90 54 36 60 36 24 300-180 120 720 432 288 240 144 96 960 576 384
  • PALISADES PI.ANT SGRR TABLE C-1-3 (Sheet 12)

MACHIN!! WELDING OF Ll.C. l1IPE WITll UEMO'J'E VIEWING TASK NllMIHHl DESCRIPTION 66 Miscellaneous pipe operations (welders tests, material handling, scaffolding, training, hangers and supp~rts, line testing, cleanup. teste).

67 Distrlbutables (startup, cleanup, scaffolding, welders tests other than pipe fitters, miscellaneous).

  • Refer to Table C-1-5 AVERAGE NUMBER UURA1'ION OF (llOURS) 1 PERSONNEL
  • LOCATION NUMBER OF TI HES TASK PERFORMED MANllOUltS 1

25,058 2

6,993 4

1,0~4 5

1,954 7

217 8

20 9

8,358 10 543

-u 1,107 12 434 15 933 17 87-1 11,400 2

13,385 3

1,003 4

1,526-5 3,052 6

131 7

1,744 6

COMMENTS Welders tests, training, material handling and fabri..,.

~ation of tents ~re in l.ocation I.

Re-mainder of manhours were allocated on the basis of pip'ing manhours in each -

location.

i I

TASK NllMllER 67 (Conti~ued) 68 Noumanual DESCRIPTION

  • Refer to Table C-1-5 PAI.ISADES PLANT SGRR TABLE C-1-3 (Sl~eet 13)

MACHINE WELDING OF ll.C. PIPE WI'fll lU:MOTE VIEWING AVERAGE NUMBER OF NUMBER OF TIMES TASK DURATION' (HOURS)

PERSONNEL

  • LOCATJON-PERFORMED MANllOURS 9

11,466 10 567 11 2 '921.

12 2,616 13 1,090

. *I 14 218 15 1,526 16 785 17 l,090 19 480 1

99,160 2

6,431 3

53 4

1,191 5

1,648.

6 16 1

238 8

61 9

6,753 10 420 11 1,191 12 911 COMMENTS Office pereonne 1 +50%

of engineers a~d supervision manhours are Jn Location 1.

Remainder of manhours by discipline were allocated to the proper location *based on direct manhours expended in that location by discipline.

TASK NUMBER 68 DESCRIPTION (Continued)

  • Refec to Tuble C-1-5 PALISADES PLANT SGRR TABLE C-1-3 (Sheet 14)

MACHINE WEI.DING OF R.C. PIPE WI'l'll llEMOTE VIEWING AVERAGE NUMBER OF NUMBER TIMES OF TASK DURATieN (HOURS)

PERSONNEi.

  • LOCATION PERFORMED MANllOURS 13 149 14 11 15-

. 1,158 16 141 17 401 18 19 67 COMMENTS For example:

The manhours for elec-trical engineers and supts were al-located based on*the electrical direct hours expended OQ each task at each location.

-i *

~------------------~

TASK

!!!!:____ -----..-----2*--* ]

4 5

I 498 1,080 2

600 I, 198 1

1,6110 812 4

1106 160 5

1,260 6

1,1120 1

  • 1,1n 915 8

240 9

2. 41111 1,260 JO 446 11

%0 1,056 12 no 960 I) 12 14 15 24 16

.16 12 17 24 12 18 16 144 19 104 256 20 l,440 21 120 12 120 22 1,560 21 160 24 648 25 HO

'l'Alll.E C-1-4

-(Shccti) lillHHAllY 01' HANllllUllS 1'1111 Al.L TASKS llY l.OCA'l'IUN 6

160 WIU.()fNI; m* ltl!AC'l'CIR COOi.ANT 1*1rl! llY HAClllNE Wl'l'll Rt:H01'1! vu:w1N1:

1 8-9 10 II 12 266 2,068 828 1,680 660 12 u

1,276 8

400 64 16 4,464 16 120 24 1,056 24 240 1

6 48 24 24 144 12 200 256 960 1,:wo 12 1,662 240 868 888 100 260 428 JOO 9110 1110 I'

ll 14 IS 16 11

. 10 19 1,090 1,2011

I j

l I

I I l

  • I TASi( -----------

110.

2 26 2411 27 100

.!II 120 29 112 10 I, 1511 11 148 l2 7211 ll 160 14 60 35 2 l,5110 36 19, 125 17 11,606 lit 8,104 19 1,5011 40 I,5011 41 744 42

!H6 41 916 44 1,680 45 li90 780 46 47 ltlll 48 J,160 49 4011 50 570 6111 51 l,H5 52 I, 125 51

!J4'i l

4 5

200 70 552 252 1,120 SlltlHAllY 11~* HANllllllllS **mt Al.L TASKS llY l.OCATION 6

WKl.lllNI: 011 R~:AC'l'OR CUlll.ANT P ll'K UY HAClllNK wnu aEHO'l'E I/IE.UNG 1

8 9

10 11 160 200 60 1,062 768 150 480 600 48 no 12 2,110 l, I Ill 1,5H ll 1,575 1.0~0 14 IS 16 11 18

!~

2011 500 201 1,912 600 692 l:.!8 40 40 570 li:.!O 1611

TASK ________________

NO, 2

l 4

5 54 HO 55 4,060 56 25 57 50 120 5!1 10 24 60 54 90 61 16 60 62 180 100 61 4l:l 64 144 65 516 Subtotal 82,02 I 25,2119 2,470 2,664 5,479 66 25,0Sll 6/Hl1 1,064 l,!154

'l'otal llhllClli 1111,1119 12,202 2,418 1,128 7,411 67 11,400 11,'J85 1,001 1,526 l,1152 60 9!1, 1611 6,411 51 1,191 1,648 1*oral 211,6'J') ')2,018 1,5'J4 6,445 12, lll 1

I

  • I TAUi.i! C-1-4 (Sheet l)

SllHHAllY OF HANlllllllUl FOR Al.I. TASKS BY l.tll:A'l'lOll 6

160 160 Ill 16 5!11 Wl!l.lllHH llt' llt:AC'l'Oll GOOl.AllT 1'11'1! llV HAGlllHF. Wl'l'll lll!HO'l'B VIEWINll 7

8 9

10 II 15 40 8

24 40 160 6

16 24 120 200 no 96 240 104

%11 4,056 2111 19,451 820 6,020 211 20 8,158 541 1, I07 4,27l 221 27,811 1,161 1,115 1,744

- 11,466 567 2,9:1.1 218 61 6,751 420 1,191 6,255

UIO 46,0lO 2,150 11,241 12 5,941 414 6,171 2,616

!Ill 9,904 ll 14 1S 16 17 18 J9 16

-2,6iS 500 2,825 1,!106 2,528 40 1,190 91i 61 2,625 500 1,758 l,!106 2,615 411 l, 190 l,090 218 1,526 785 1,090 480 14!1 11 1,158*

141 4111 67 l,864 12!1 6,422 2,812 4, 1116 411 1,117

Work Arca (I.neat. Ion)

l. 011L11lde of 1111wl!r plant l>Ul1Jl1111 Lul within llllCll( 1l y f CllCI!.
2. Clu:cldnQ 111 anti out lhL*o1111h 11ecur hy and health phy11lc11 a11 well a11 t Ju1c s11c11t 1111JtJ1111 up, cleanlnu up and u1ovJ1111 lo and fn11u woa*k 11re1111 foa: 11crouuncl wocldua tu riulJoact Jve urcua.
l. 11111Jdc <:1111laJ11111c11L near nllw co1111tr11cl Ion 011c11 l1111.
4. WILhJn 6' of nutolde of reactor coolant pipe or bottom of olcaw ucuerator prior to rcmuval of 11lemu

.acncratol*u.

5. \\Hlhln 6 1 oulsJde of reaclur cool1111l pJpc after sh:11111 geucrator'e rc111uval.

6, \\llthln 6' uf outuldl! of re11ctor coolant 1>lpc or lwllo111 o(

11tcum ll<~ncratua:u w I Lh part 111 l e1<a*u111u*u to lnultle uf reactor cuol11111. plpu 1*rlur to t1tcu10 l.Jt!ncrutor 1ti i*t!umval.

1. W!lhln 6' of outlilde of reactor cuol1ml 11lpc wllh p111*tl11l ux11u11ure tu l1111J1lc of reactor coolant pt11e after ute;uu g,cncrulor 1e L*crnuvul.

(I) l'AJ.ISAllES Pl.ANT.SGl\\ll

'l'Alll.E C-1-5 (SllEE'I' lf HAN-llt:H ES'l'ltlATE Avernue Radiation field

( a:-em/lu:)

Eutlluated H1mho11re (tlauunl Welding)

Al I

-5

.5 x lO

.0025

.001

.010 -

.050

.OlO -

.010

.050 - 0.100

.050 -

.100 217659 5ll43 1514 6216 19618 501 5658 In 1111.llntlon Field (H1;*:blne Weldtu11)

A'/.

21761!.I 52010 121)]

507 6255.

(:.!)

Area H1111-ll<*u1 lln"c (H;111-lleo1)

(Hanuel Welding)

(tlachlne WelJlug) 1.1 1.1 llO.l llO

]~5

.** 5 188.3 - lll.6 l!.11.1 - 12:!.l 196.8 -

5!.10.1 121.l - 164.0 25.4 -. 50.7 25.4 -

50.1 281

- 454.8 112.8 - 625.5

(I)

Aveuge lladllltlon Hork Arca (l,ocaLJon)

(mm/hr)

8. a) lnuldc of reuclur cnolant pipe hcfure decontamination, 9.0 -

Ii) OuLstJe of pipe w/parttal cxpo1111rc lnu l1le luifore decontamlnalion.

1.0 -

c) lnulde of reactor coolunt 1*l11c uhcr Jccout111ulnaLton.

.015

9. I.ow ruJtatJou arcu wtlhln conlaJu111cul

.005 I

JO. \\Hlhlu 6 1 uf to1* hil If of orlll,lnal utcnu1 ll,cnerutora (Jnatallc1l Jn placo).

.005

11. WJLhln 6 1 of top half of new atcam acncratoru (fostallcd in place).

.001

12. 011cr11l lnll f Joor or cont a J11111ent,

.005 -

13. lnuJde con ta l11111cnt, at polar crane elu11atlu11.

.001

14. Aul<ll lary lrnll11ln11 uc1tr clean rcuJn tank 111111 cool 11111 water lank.

.001

15. AuxHtary bnll*llus 11e11r blowJown tank.

.Olll

16. S1urnt fui!I pool flour.

.00!)

11. WHhln 6' u{ l h" hottom. hat f of UC\\.I Ul:CUlll BCIH!l'UtUC'li (tu place).

.OIO -

l'Al.ISAUES l'l.ANT SGllH

'l'ADl.E C-1-5 (SllEl~'f 2) tlAN-llEtl E.'l'l'ltlA'l'E l~st Jwated Hanhouru

    • teld (tlanual YeldJng)

Al 12.0 4.l 2.0 116 148 19198 2365 lUll

.OIO 9861

JU6"1 J'l.9 6408 2832

.1110 4106 Jn lluJlatlon Field (t111cl1lne lluldlng)

'~1

,, _____ _L__

4.2 114 150 46010 2150 112111 9904 lllM 729 6442

.11n2

/a11)6 (2)

Area H11n-ltc111 II"'"'

(tlan-llcm)

(Hanual We_ldJnc)

(Hach Inc Welding) 38.1 -

51.6 11.U -

50.4 ll6 212.0 134 26U.O 5.2 5.1 1°96 2jo.2 ll.8 11.U 11.2

11. 1 49.l - 98.7 49.5 -_99.0 l.9 1.9

. 0.1 0.1 6.4 f>.4 14.2

14. :.!

4l. I - 121.2 1, 1.1 - 121.2

i

  • 1 I

Wod1. Arca (l,11cutlo11)

18. WJthln 6 1 of the outlllJc of the r&!ilCtor vcaa1ll *
19. Next to the 1:xl11tlnu 11te11111 8"n.:r11ton1 011t11lde uf the co11-t11l11111l!nt 211. lnaLalluLiou of 11hlel*ll11u and l111:al J.,i:outmuluaLlnn.

tlOl'I!;

I (l) l'Al.lSAllt::i l'l.AN'l' SGRR

'rAlll.H C-1-~

(lllllm'I' 1)

  • llAN**lll;ti l\\!l'l'IHA'l'E Averogo Radlatlon field

( ce1u/hr)

Hut !milted H1111h111u-s 01111111111. Weldlng)

Al

JOO 40

.020 -.010 1111 (1)

(l)

(I) lll!Jucllun fucloa-11 aurlbuted to shJelJJng 11nd/oa-decont11111ln11tau11 have been Jncut*p11a-atllll lnlo tluiue field estl111ates aud wlll not be 11a-enc10ed here all 11 ue11aralc cohi11111.

(.2)

Furthl!t reduct Ion In area 11um-a-em duoe 1:011IJ oc1:11r 011 woa-k auu:kugeu and Al.AllA otndh:o cuutlnuc.

'l'he eulJ11111tcs aa-e baucd on co1111ervutlve 1111suwptJom1.

(l)

'l'hc u111nlu111r e11tl111ilte11 fol: place111e11t of 11hlcldlng 11nd local ilec1111tamln11tto11 are te11tat J ve 1lue to Lhe cl'mtlnuut Ion uf Al.ARA una ly11J11 1md work packaae Jevelo11111cnt.

'l'he 1111111hcr11 presented here aru an e11t l111ate nml ru11re11uut a 11urcu11L1111.: of the tutu I 111a11-re111.

In* 11.:ulla~ 1011 llJ4ild (t111d1l11.: UelJJna)

--- _______ Al_ ___ _

40 11H

0)

(:.!)

A.-"a *tlnn-Ri:m llnee (tl1111-ltl!IU)

Ct1011~al Weldln!J)

(tlachlue Welding) 4.0 14.1 -

52.I 165. 1 - 1!!!!.:.!!

lS41. -

28111. 6 4.0 Vt.1 -

52. I IH1
.!662.9

PALISADES PLANT SGRR C-2 Describe the designated contamination control* envelopes and your plan to maintain occupational exposure within these envelopes "AL.ARA."

Include also dose rates, exposure times, and numbers of workers involved in the tasks (Section 4.3~3).

RESPONSE

The contamination control envelopes will be used for the cutting of reactor coolant piping (Task. 4).

Although the design of the envelopes has* not been finalized,* the envelopes will ~elude a high e~ficiency filtration system.

The flow of air within the envelopes will preclude the escape of contaminants through the tent openings used for entering and exiting the area:

Each of the 12 cuts on primary coolant piping will require two workers approximately 15 rnanhours.

It is estimated that 720 man-holirs will be spent within the control envelopes, with an average radiation field of 30*50 mr/hr.

This results in an estimated 21-36 man-rem of occupational exposure.

As described in. the Repair Report, Section 4.3-1, personnel in-volved in work within areas with a high level of contamination will wear two sets of protective clothing.

Respiratory protection will be required in accordance with Palisades health physics procedures.

Sheet lead, lead wool blanket, or other shielding will be used where possible in accordance with ALARA guidelines.

c-2-1 Revision 3 July 1979

PALISADES PLANT SGR.."q, C-3 Provide a diagram. showing tjle radiation surveys around the steam generator replacement/repair activities.

Include s~milar rad.iation surveys for E'igures 4. 2-4 through 4. 2-7.

Include a table showing the whole body dose received during the inspection and plugging of the degraded steam generator tubes for 1976, 1977, and 1978.

RESPONSE

1.

Figures 4.3-3, 4.3-4, and 4.3-5, which are included in the Steam *Generator Repair Report, show radiation surveys around the steam generators at various*times after shutdown.*

The fields specified are representative-of those expected for the replacemen_:t repair activitie*s *. It *should *be noted that the".fields specified in Figure 4.3-5 a:e expected to decrease significantly at the time that pipe cutting begins, considered to be 42~l40 days post-shutdown for

. study purposes.

The decrease will follow _the ge_neral radiation field near the steam generator piping shown in Figure 4.3-7.

Figures 4.2-4 through 4.2-7 have been modified to include general field information in areas where replacement/repair activities will occur and are now designated as Figures C-3-l through C-3-4.

2.

As reauested, Tables C-3:,_l and C-3-2 show the whole body dose received for inspection and plugging steam generator tubes during 1976 and 1978, respectively.

TABLE C-3-1 PALISADES ~LANT -

RADIATION DOSE

SUMMARY

STEAM GENE~TOR WORK 1976 Activity l..

ECT Personnel Inside steam generator (without shielding)

Outside steam generator Total (received over a period of 21 days}

2.

Insert and remove shielding Inside steam generator Outside steam generator

'rotal

3.

Insert templates Inside steam generator Outside steam generator total

4.

Brushing and rolling Inside steam generator Outside steam. generator

'rotal c-3-l 1976 Exposure a

16.5R l9.3R l7.8R 2.0R 25.3R 2.8R 37.6R 4.3R 35.SR 19.SR 28.lR 4l.9R Revision 3

  • July 1979

SGRR C~3-2.

PALISADES PLANT SG~

Activitv 1976 *Exoosure 5~

Insert plugs Inside steam gene,rator Outside steam generator Total.*,

28.SR 2.9R 31.7R

6.

Weld plugs Inside* steam generator Outside steam generator Total 54.4R 15.3R 69.7R

7.

QC inspection of-a.J:Jove operat:ion Inside steam generator Outside steam generator Total 23.6it l.6R 25.2R l0.7R

a.
  • Engineers support qf above operations Exposure accumulated inside steam generator*..

Exposure accumulated outside steam generator 204.0R NOTE:

48.2R TOTAL ACCUMULATED EXPOSURE 262.9R The exposure designated inside and outside steam generator are only estimates (al.though the total for each operation is accurate), since inside steam generator data is extracted from high radiation dose summary sheets which also include some outside steam

. genera'Gar work.

The net result is that the inside steam generator data reads. slightly higher and the outside steam generator data reads slightly lower than actually* occ:Urred.

Radiation exposure to engineers is not included in this breakdown.

TABLE C-3-2 PALISADES PLANT ~ RADIATION DOSE StJMl.'f.ARY STEAM GE~RATOR WORK 1978 Organization/Activity'

  • 1978 Exposure (Level. 9* R/hr 3. 5 R/hr)
1.

Consumers Power Company* Repairmen

a.

Manway cover removal/vacuuming

b.

Dam installation

c.

Surge line shielding + miscellaneous

d.

F1oorin.c;/RSS hot legs e *. Flooring, struts, tracks, bridge c-3-2 A cold leg B cold leg 5.6 45.0 5.5 8.5 14.3 22.5 Revision 3 July 1979

2.
3.
4.

NOTE:

PALISADES* PLANT SGRR

. Activitv

f.

Track~, bridge

g.
h.

General maintenance

  • Tube plugging A hot leg B hot leg
i.
j.

. A cold leg A hot leg B cold leg B hot leg Equipment removal/leg cleanup Dam. removal

k.
l.

Manway cover replacement Cont* cleanup HP coverage NDT lab/contractors CE - Setup Deplugging Sleeving A cold leg A_hot leg

' SGRR c-3..;.3*

  • 1978 Exposure 6.l 6.3 l.9 3.l l.6

. 3.9 l.8 6.8 4.6 4.9 2.6 145.0 6.0 44.3 2.4 7.4 4.3 14.9 29.0 Total exposure

  • 224.3 Man-rem
    • These exposures are based on dosimeters and TLDs.

Source is containment entry logs.

These numbers should only be considered* close approximations.

C-3-3 Revision 3 July 1979

General Field 20-30 mr/hr CVT POINT-~

I I l STM. 6N. E 0 SOA

( G'Sa*a IS IYP. J a l.)i.

CJPPOSITE WPND).

42 *I.£). Pl..P/N~-.~*-. ----

cur POINT NEAR SIDI:;

F'ARSJDE.

3 5 '=-""""°'-~--

General Field 3o "'/.a~ 1=1?1Na---LL NEARSIDE' ~

~

35 mr/hr eneral Field FAR.SIDE

-.-..-r G'L~VATION CIJT POINT N~ARSll)E" ~

-AR.SIDE' PALISADES PLANT STEAM GENERATOR REPAIR REPORT

?RIM.ARY COOLA..'TT

__R;:t:PING CUT POINTS Figure C-3-l Revision 3 July 1979

FU TUR~ 1.0CAl/ON

--_,..-.. ~

I PRESGNI !.OCAT!ON General Field CUT POINT-...;-~ s-io mr/hr C/JT POINT I

~ 3~ MAIN STE'Alvl ELeVAi!ON I

I I

i I

I I i if. SIM. G~N.

. 5-SOA

( E'-S08 IS iY~

av r OPPOSl"i~

HAND)

PALISADES PLANT STEAM GENERATOR REPAIR REPORT

' MAJ:N STE&'\\! PIPING CUT POINTS Figure.C-3-2 Revision 3 July 1979

/

.... /

~ STU. 6EN. E* SOA T ( c*so e 1s TYP.J I

8J.JT OPPOS/7E

  • J.IAND)

General Field s-10 mr/hr CUT POIN/

Cl.)/ P01Nr PL.AN PALISADES Pt.ANT STEAM. GENERATOR REPAIR REPORT FEEDWATER PIPING CUT POINTS

. Figure. c-*3-~3 ---- --

Revision 3

  • July 1979

General Field s-10 mr/hl:

CUT POINT 2.. S lJR /:".4C c

~== <l !3J. OWDOW.iY 1.JNE General Field 5-lO mr/hr t SIM. ~~N ~-.SOA ELEVATION i

L'VA /ION STM. GGiV. E-SO.PJ JS "TY P. I 2'* U 7" OP POS/7£ HAN/;

CUT POINT z.. eo-rraM 81.0WOOWN' LINE 35 mr/hr General.Field with Manways Covered

~OiAT£90 ~o* C'-OCKWIS=

PALJSAOES PLANT STEAM.GENERATOR REPAIR REPORT BLOWDOWN PIPING CUT PQ_n..t~_s __ _

Figure C-3-4 Revision 3 July 1979

SGRR c-4 PALISADES PLANT SGRR C*4 Discuss briefly how you would avoid imbalance of the permanent ventilation systems due to the additional construction -related ventilation equipment (portable fans, hoods and filters, etc).

RESPONSE

Additional construction - related.ventilation equipment will be* used to supplement the permanent ventilation system and will remove fumes associated with welding and cutting operation as well as*ventilating temporary enclosures.

Significant imbalance of the permanent ventilation system is not expected since the construction related ventilation equipment will exhaust inside the*containmerit after filtration, and/or have

  • relatively low flowrate.

However, should imbalance of the permanent ventilation system occur., balance can be restored by controlling the dampers on the permanent ventilation sys.tem.

Revision 3 July 1979

SGRR C-5 PALISADES l?LANT SGRR c-s Your description.of compliance with Regulatory Guide a.a,

  • "Information Relevant to Ensuring that Occupational Ex-posure at Nuclear Power Stations Will Be As Low As Reasonably Achievable", Revision 3, June 197a, states that the follow-ing considerations were not implemented:
l.

Radiation zones in the containment work areas, identifying.

the *exposure levels in each work zone. c. 2.* ('a) "

2.*

Streaming or.scattering of *radiation from installed shielding, such as plugs in open ended pipe lines following cutting.

C.2.b.(4)

3.

Outleakage of airborne co~tamination from the contain~

ment due to steam generator replacement/J:epai,r activities:

when the equipment hatch is open.

4.

Operating experiences should be recorded, evaluated, and reflected in the selection of replacement instrumen-tation.

C.2.(~)(3)

5.

Provision to be implemented to* minimize exposure of station personnel in performing code inspection, such as removable insulation, smooth welds, etc.

(C.2.(i)(ll)

6.

An adequate emergency lighting system can reduce potential exposu?:es of station personnel by permitting prompt egress from high radiation areas if the station lighting system fails.

7.

.A staff member who is a specialist.in radiation protection assigned the responsibility for contributing to and coor-dinating ALA.RA efforts in support of operation that could result. in substantial individual and collective dose levels.

8.
. ** Station work areas to limit the average concentration of radioactive material in air to levels below *** in Appendix B, Table l, Column of 10 CFR l?art 20.

C.2.d Provide justification for not implementing these provisions of Regulatory Guide a.a, and demonstrate that alternative precautions you have taken will provide.comparable levels of protection.

C-5-l Revision 3 July 1979

---,.---.,,._,...=.,,.---~

SGRR C-5-2 PALISADES PLANT SGRR

RESPONSE

The philosophy of the radiation protection group is to maintain the occupational dose to all personn~l as low as is reasonably achievable (ALARA) *.

Th.is has been stated as a policy in the Palisades Plant Radiation Protection Manual.

In order to ensure that* the various provisions of Regulatory Guide 8. 8 are. evall,lated adequately,.. a. third par.ty ALARA review of the repair efforc has

~een utilized.

The re~iewers' responaibilities are to devel6p ALAR.A nchecklistsn to be used in conjunction with the work pack-age descripti"bns for each of the repair tasks.

The "checklists" will ev.aluate and recommend any measure. found appropria~e to maintaining the personnel exposure ALARA as defined in Regulatory Guide 8. 8 (Revision 3)

  • Al'though the detailed work packages are presently in the develop-ment stage, each of the following specific provisions will neces-sarily be given complete consideration for use during any re-placement/repair activity:
l.

The*identification of exposure levels in any work zone is presently implemented per Palisades Plant health physics procedures.

The. Repair Report Section 4.3.5.4 describes the low background radiation waiting areas

  • that will be used near each containment work area.

As specified, special signs, tape, or rope-off areas will be utilized to designate these zones.

Inter-mediate zones could be utilized, if found ALARA, as individual work packages are developed.

2.

The effective streaming or scattering of radiation from installed shielding, such as plugs in open ended pipe lines, can be minimized through ~~e use of local decontaminating of pipe stubs, use of temporary

.shielding, or exposure control by controlling ingress or* egress to work areas.

(See Repair Report Sections 4.3.5.2 and 4.3.5.3).

All of these ALARA techniques are being evaluated for use with the individual work packages per third party ALARA review described above.

c-s-2.*

Revision 3 July 1979

SGRR C-5-3 PALISADES PLAN'I' SGRR

3.

In addition to the temporary enclosure on the construc-tion opening, airborne radioactivity inside containment during the steam generator repair effort will be con-trolled, monitored, and ultimately released via the plant vent stack.

The air will be drawn through the hatches and construction opening and exhausted.by the purge system. via the plant ventilation stack, thuS precluding airborne radioactive particles or gases from leaving containment openings utilized for construe*

tion* activities.

(See Repair Report Section 4.3.3}. *

.4.

continuous air monitors, area radiation monitors, and.portable survey instruments will be used in.ac-cordance with Palisades Plant health physics procedU.res.

,Daily and weekly operational checks, calibration, and*

response settings will be implemented and recorded as required per Palisades Plant health physics procedures.

S.

Appropriate provisions'will be implemented to minimize exposure of station personnel in performing code in-spection, such as removable insulation~ smooth welds, etc.

Design features to improve maintenance and in-spection are discussed in the Repair Report Section 2.2.2. '.

6.

An emergency lighting system will be available for the steam generator replacement activities~

7.

A staff member who is a specialist in radiation protection will be assigned to the responsibility for coordinating AL.ARA efforts.

8.

Special measures will be implemented to minimize and control the average concentration of radioactive material in air to below those specified in Appendix B*,

'I'able l, Column l of 10 CFR Part 29.

In addition to temporary enclosures in areas where cutting will occur, containment air will be conditioned for the removal of airbo:ne radioactivity by use of filters.

c-s-3 Revision 3 July 1979

SGRR C-6 PALISADES PLANT SGRR c-.6

'Explain what s.teps you plan to. take to help main-tain doses ALARA in this project.

Indicate what use will be made of. contaminations tents, lead wool. blan.l(ets, gloveboxes,. remote cutting and welding equipment, temporary shielding and venti-lation systems.

  • Also indicate what equipment will be mocked-up for training. purposes.

RESPONSE

An independent ALA.RA review of the.steam generator repair effort has been utilized to ma.l(e recommendations for maintaining doses ALARA' (see question c-.5).

The ALARA recommendations made will be incorporated into the various work packages.

Each of the. following items will be used where appropriate to maintaining doses A.I.;...RA.

l.

Contamination Tent~ - The cutting of primary coolant piping will be contained within specially designed contamination control envelopes.

The envelopes will be provided with high efficiency

. filtration.

2.

Temporaty shielding in the form of:

  • lead wool blankets, lead shield plugs and sheet lead will be used where effective to maintaining* doses ALARA.

Experience has shown that lead wool blankets can effectively reduce streaming around shield plug and sheet lead fittings.

3.

Gloveboxes -

As yet, there are no repair/replace-ment.activities desc::ribed, which can effectively use glovebox enclosures for maintaining doses ALA.RA. As work procedures develop, glovebox techniques will remain a viable option.

4.

Remcte cutting and welding equipment - Automatic welding machines with remote viewing will be used for welding operations made to interior located stainless steel cladding.

Measuring equipment for determining the location of reactor vessel and steam generator during weld-up and cutting opera-tions will utilize remote indicators.

Although the cutting techniques have not been finaiized, the AI.ARA considerations will be one of t..i.ie determining factors for final selection.

C-6-l Revision 3 July l9i9

PALISAGES PLAJ.'fl' SGR..~

S.

Ventilation Systems - Local constrtiction related ventilation equipment will be used to supplement the permanent ventilation syste~ and will remove fumes associated with welding.and cutting operation as well as controlling the airbqrne contamination existing in the temporary enclosures.

6.

Mock-Ops of reactor coolant.pipe, and the steam generator primary head as well as the actual cutting*and welding equipment will be utilized for training and work planning.

c-6-2 Revision 3 July 1979

r SGRR C-7 PALISADES PLANT SGRR c-7 Provide a table shewing the occupational col-lective whol'e body dose esti."ttates for the fol-lowing phases of the steam generator replace."nent repair acitivities: (1) preparation, (2) removal, (3) installation and (4) storage.

  • RESPONSE:

Discuss briefly your procedure for calculating these doses, taking.into account the* dose reduc-tion measures proposed*to maintain doses as low as

  • r~asonably achievable {AL.ARA)., including local decontamination, temporary lead shielding, pre-job planning,* pre-job training and use of remot~ too*ls where practicable.

Table C-7-l provides the requested.L.~for:nation.

The table groups the various tasks into preparation, removal, installation, and storage phases of the replacement/repair

  • effort.

The man-rem is the product of (man-hours) X (average radiation field) for each task. It should be noted* that each task consists of man~hours accumulated in several locations, and each location has a correspondi~g radiation field.

A description of locations and average radiation fields is presented in Table c-1-s, credit taken for decon-tamination and.temporary shielding is incorporated into the radiation field estimates. Reduction factors for shielding and/or decontamination are presented in the repair rep~rt, Table 4.3.2.

c-1-1 Revision 3 July 1979

'.*----.----~

i

.J PAl.ISAllllS 1'1.AIU SGllR

'l'Alll.I~ c:-7-1 HAtHll!tl ES'l'UIA'l'B (l'rep11r11tlun 1 J1111l11l latlo11, Reiuov11l 1 11i1J SLon1gl!)

ll<!IUOVlll hullnl lat Ion

. !~;k H~ * -----~.:-::*:~.fu!i~~- H11-11-Re11

__ Sto!!'.ll!:!.. -*----*-*-***- ___ _

Taak Ho:.

-*- _ !Ula __...

Ha1!.:!l"U1

__.!'.!~1'.!!!!!l!!!!!... _.. -*. ----*--

J:aek~~

__,_JI..!!!!. ---

~Re111 T1111k No. -

~ Ht!i==-* ~ll.:ji.,;;;

1 l,51R 2.12 1

1,416 11.26 1

4,l8:t 11.58 ll 15 21.16 14 HO 2.60 u

120 26.52 15 21,500 o.u 16

.124 19.JR 11 11,6116 0.06 19 1,016 I0.12 18 8, '1114 0.01 21 115 1.02 19 1,500 0.01 22 416

.912

  • 40 1,500 0.01 24

'j1]

1.91 41 144 0.01.

26 240 4.01 42 9')6 0.01 21 100 1.110 4'1 9l(o 0.01 ll 550 8.6R 44 5,625 11.62 45 1

I 1,'160 s;,ds 41 1110 0.01 56 80

. '14 411

'i, 160 0.01.

51 48

.:.!4 4!J 480 0.01

'j8 120 I. *10 59 48

.19

a __.. ________ J5.82 __ M_._ ____ ~ ___ 11 561, _______.i,R 1'utal Plrect11 U1,~i4'.I 215.48 I0,169 2";11.10 lllot.-lbutu"1*:11 61 22,597 124 2, 11!J 15.28 tl1111m111111u I _!!._ ___. __.. 1~.!!!L --*- ___.. JJ.86 ______ !.~~L----**-*!!::2t!. Total 159.441 411~14 19,612 202.16 (I) llci:1111La111l11111. l1111/Sh lolJ 11111 lnetallat Ion 2 5 6 1 8 9 10 ll 12 l4 J1 18 20 2l 22 21 24 25 26 21 28 29 10 l2 ll 14 16 so 51 52 51 54 61 62 61 64 65 66 1,991 2.!JO 4,116 111.69 1, 160. 89.85 6,0118 12.ll MH 2.86 8,224 44.86 1,104 'j.26 1,096 19.06 1,944 11~44. 12 .42 96 .18 180 1.51 4,81111 9.60

.!69 1.00 4,162 14.21 5:.!11 1.16 1,519

}. 2(&1) 16.16 %0 5.11 100 1.25 1111 .80 ~.424 15.00 1,850 8.61 2,1,00 10.8 l,:.!16 l.ll DO 2.6 19,12') 0.09 2,670 10.12 l,lH .01 1,750 11.11 !W> 0.01 1511 0.01 120 0.81 6110 4.05 1,440 1.24 480 l.06 4/1 55 (r20 4,060 u.4 0.0:.! _____ !.~~!! ----**-***-i.:.H. 09,980 454.09 l1,6HO 12.112 20 au. 60.94 110, U16 51S.0) 4,680 12.42 20,416 156.1 1,2011 6.64 --**-!~.Oil!! ______ 2!:~1... 1 ______ _

.! 6]5 1.95 2011', 522 161.66 8,521 21.01

SGRR c-a PAL:ISAD~S 'PLANT SGRR c~a Discuss your cutting and welding operations and cleanup of surface contamination in.respect to "AI.ARA" guide-lines (Section ~.3.3). . RESPONSE: We note that a definite *schedule has not been set for the* cutting and welding, that experi.ence is being gained by way of similar operations at other plants, and that'detailed w()rk plans have not been completed. The final operations will reflect applicable experience, and AL.ARA consider-ations. The following is an outline of operations under consideration at this time. *

l.

Cutting of Reactor Coolant Pioe Since the Palisades reactor coolant pipe is carbon steel w/stainless steel cladding, a plan.is to utilize a track mounted oxygen-acetylene torch to cut the pipe. Consideration is also being given to mechanically cutting the pipe in orde~ to minimize the pipe lost during the cutting process and to facilitate the machining operation. The cutting operation will be accomplished in an enclosure to limit spread of contamination.

2.

Handling of PiPe to Decontamination Area After the pipe has been cut, temporary shield plugs will be secured to each open end of the reactor coolant pipe and the short pieces of pipe moved to a dec*ontami-nation area. The tempora_""Y shield plugs will be mechanically attached to the pipe in order to reduce the number of welding and cutting operations.

3.

Field Machining of the RC Pipe Attached to Reactor and Reactor coolant p*umps Temporary shield plugs will be inserted a short distance into.the pipe. The.pipe between the shield plug and the end of the pipe w.ill then be decontaminated to the extent practical. The pipe weld preparations would then be field* machined. C-8-l Revision 3 July 1979 --**--*-~-*--*---*-***--- ---*--- ---*-****- **-*- *-~-. *- *- -* -- -- **- --- **-- *- --- .SGRR c-a..:.2 PALISADES PLANT SGRR

  • 4.

eield Machininq of the Short Pieces of Reactor C~olant Pipe After the new steam generacor has been placed, the dimensions between the. existing reactor coolant pipe and the new steam generator nozzles will be transferred to the short pieces of reactor coolant pipe and the pipe weld preparations machined.

s.

Welding Of RC Pipe After set-up of.th.e reactor coolant pipe the joints may

  • be welded by. one of the* following.methods:
l.
  • Manually weld the carbon steel portion.of the reactor coolant pip~ and utilize an automatic welding machine with remote* viewing for welding the ~tainless ~teel interior cladding.
2.

Utilize an automatic welding machine with remote viewing to weld both the carbon steel and s *::ain-less steel interior cladding.

6.

Clean-up of Surface Contamination Loose surface contamination will be removed mant.;:i.lly from the outside of reactor coolant pipe pieces, prior to cutting operations and again, prior to remo~ra..J. from contamination control envelopes. Plastic or other impervious sheeting will be used to cover pipe pieces before relocating to decontamination area. c-a-2 Revision 3 July 1979 \\ C-9

  • RESPONSE:.

PALISADES PLANT SGR.~ Your estimated dose range of 1,200 to* 5~000 man-rem for the steam.generator replacement/ repair activities is too wide to assure that occupational exposure. will be as low as reasonably practicable. Justify the high end of the range as being ALARA. Experiences with other designs indicate* the feasibility of performing such.work with substantially lower total doses. than the high.end of range you have predicted. As presented in.the task description (Question C-1),. there are two welding techniques being considered for .reactor coolant piping. One technique utilizes manual welding of reactor coolant carbon steel pipe with a machine weld-up of the stainless steel cladding. This technique would result in an estimated l,547-2,808 man-rem for the repair~ The second technique utilizes a machine weld-up of both carbon steel pipe and stainless steel cladding. This alternative results in an estimated l,537-2,663 man-rem for the repair effort. The high end of the range presented in Table 4.3.2, 5,000 man-rem, resulted from a manual weld-up of carbon steel pipe and cfadding entirely from the inside.* Due to the technical feasibility of the two welding techniques described above, this third alternative is no longer con-sidered ALARA and has since beeri eliminated. C-9-1 Revision 3 July 1979

~------.. **----....

,/ .,.~-'!..... (,,.,....., I SGRR C-lO PALISADES PLAN~ SGRR C-10 P~ovide a rough breakdown of the activities, person-hour occupancies, and projected dose rates which are used in deriving the esti-mated total of 40,250 man-rems per unit for retubing in place (Section 8.7).

RESPONSE

Refer to Appendix A of as transmitted* to the iJSNRC letter dated June ll, 1979. reevaluation. the SGRR response to Question A-2, by the Consumer Power Company That analysis is currently under C*lO-l aevision 3

  • July 1979
    • llt*&.A L.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE.THE ADMINISTRATIVE.LAW JUDGE In the Matter of CONSUMERS POWER COMPANY (Palisades Nuclear Power Facility) ) ) ) } ) Docket No. 50-255 (Civil Penalty) CERTIFICATE*op*sERVICE I hereby certify that copies of ~RC STAFF'S SUPPLEMENTAL ANSWERS TO CONSUMERS POWER COMPANY'S SECOND ROUND OF I'NTERROGATORIES and NRC STAFF'S REQUESTS FOR ADMISSIONS BY CONSUMERS POWER COMPANY in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or as indicated by an asterisk, through deposit in the Nuclear Regulatory Coll1Tlission~s internal mail system, this 7th day of November, 1980. Hon. Ivan W. Smith* Administrative Law Judge Atomic Safety & Licensing Board. U. S. -Nuclear Regulatory Comnission Washington, D. C. 20555 Michael I. Miller, Esq. Alan Bielawski, Esq. Isham, Lincoln~ Beale One First National Plaza Suite 4200 Chicago, Illinois 60603 Paul Murphy, Esq. Isham, Lincoln & Beale One First National Plaza Suite 4200 Chicago, Illinois 60603 . Judd Bacon, Esq.

  • 212 W. Michigan Avenu~

Jackson, Michigan 49201 Docketing & Service Section* Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. c. 20555 Atomic Safety & Licensing Board Panel* U. S. Nuclear Regulatory CoTTDllission Washington, D. C. 20555 Atomic Safety & Licensing Appeal Panel* U. S. Nuclear Regulatory CoTTDllission Washington, D. C. 20555 ,~G~

  • Stephen G. Burns Counsel for NRC Staff

\\ -}}

Retrieved from "https://kanterella.com/w/index.php?title=ML18043A913&oldid=5026257"