Text

Final Response to FOIA Request for Documents Re Replacement Piping at Facility.Forwards App a & B Documents.Documents Also Available in PDR
	ML20086P013
Person / Time
Site:	Nine Mile Point, Brunswick, Vermont Yankee, 05000000
Issue date:	02/03/1984
From:	Felton J; NRC OFFICE OF ADMINISTRATION (ADM)
To:	Bell N; EECNUCIR, NUCLEAR INFORMATION & RESOURCE SERVICE
Shared Package
ML20083L677	List: ML20083L674; ML20083L685; ML20083L692; ML20083L803; ML20083Q826; ML20084N257; ML20086P013; ML20086P024; ML20086P032; ML20086P034; ML20086P038; ML20086P042; ML20086P046; ML20263M566;
References
	FOIA-84-14 NUDOCS 8402240216
	Download: ML20086P013 (3)
	v • d • e

_

"Jyl - Q l Q j [

UNITED STATES g

NUCLEAR REGULATORY COMMISSION 5

E WASHING TON. D. C. 20555

...../

Docket No. 50-220 FEB 0 3 584 Ms. Nina Bell Nuclear Information and Resource Service 1346 Connecticut Avenue, NW 4th Floor IN RESPONSE REFER Washington, DC 20036 TO F01A-84-14

Dear Ms. Bell:

This is in final response to your letter dated January 5,1984 in which you requested, pursuant to the Freedom of Information Act, documents regarding the replacement of piping at the Nine Mile Point Unit %!

1 The documents listed on Appendix A already exist in the NRC Public Document Room (PDR) located at 1717 H Street, NW, Washington, DC.

The documents listed on Appendix B are being placed in the POR.

This completes action on your request.

Since ly,

/[

. M. Felton, Director Division of Rules and Records Office of Administration

Enclosures:

As stated 8402240216 840203 PDR FOIA BELL 84-14 PDR,

C

l Appendix A FOIA 84-14 1.

6-1-82 Ltr to D.G. Eisenhut from T.E. Lempges. 8206070363/PDR/ADOCK/50-220 2.

4-30-82 Ltr to D.G. Eisenhut from T.E. Lempges. 8205070114/PDR/ADOCK/50-220 3.

5-11-82 Ltr to D.G. Eisenhut from D.P. Dise.

8205170306/PDR/ADC0CK/50-220 4.

5-24-82 Ltr to D.G. Eisenhut from T.E. Lempges. 8206010310/PDR/ADC0CK/50-220 5.

8-06-82 Ltr to D.G. Eisenhut from T.E. Lempges. 8208130195/PDR/ADC0CK/50-220 6.

8-16-82 Ltr to D.G. Eisenhut from C.V. Mangan. 8208200049/PDR/ADCOCK/50-220 7.

9-27-82 Ltr to D.G. Eisenhut from C.V. Mangan. 8210010033/PDR/ADCOCK/50-220 8.

11-18-82 Ltr to D.G. Eisenhut from C.V. Mangan. 8211230330/PDR/ADCOCK/50-220 9.

3-31-83 Ltr to 0MPA from T.E. Lempges.

8305200383/PDR/ADCOCK/50-220 10.

12-15-82 Ltr to D.B. Vassallo from C.V. Mangan. 8212170266/PDR/ADC0CK/50-220 11.

Amendment to Facility Operating License. 825190430/CF/ADC0CK/50-220 12.

9-02-82 Memo to W.S. Hazelton from C.Y. Cheng. 8209230151/CF/ADCOCK/50-220 13.

9-13-82 Ltr to H.R. Denton from L.A. Drey.

8209170054/CF/ADC0CK/50-220 14.

5-12-82 Memo to T.M. Novak from R.W. Houston.

8205190430/CF/ADCOCK/50-220 15.

6-18-82 Notice of Issuance of Amendment to Facility Operating License and 8310060224/CF/ADC0CK/50-220 Negative Declaration 16.

6-08-82 Meme to T.M. Novak from R. W. Houston. 8206250092/CF/ADCOCK/50-220 17.

10-15-82 Notice of Issuance of Amendment to Facility Operating License and 8211060426/PDR/ADCOCK/50-220 Negative Declaration.

18.

3-04-83 Memo to B.D. Liaw from D.B. Vassallo.

8303160017/CF/ADCOCK/ 50-220 19.

5-26-83 Memo to G.C. Lainas from J.P. Knight.

8306030079/CF/ADC0CKJ 50-220 1

i.

l 1

-Appendix 8 FOIA 84-14 1.

4-30-82 Meeting Summary. DN 50-220.

2.

8-06-82 Ltr to D.G. Eisenhut from T.E. Lempges.

-3.

9-02-82 Ltr to D.P. Dise from D.B. Vassallo.

4.

Undated Schedule Plan - Safe - End Replacement.

5.

9-02-82 Memo to J.P. Durr from E.H. Gray.

6.

12-27-82 Ltr to G.K. Rhode from D.B. Vassallo.

7.

8-24-82 Task Interface Agreement.

8.

9-03-82 Ltr to R.C. Haynes from C.V. Mangan.

9.

Undated Resident Inspector Notes.

10.

6-07-82 Memo to D.G. Eisenhut from P.J. Polk.

11.

8-31-82 Note to Phil from M.G. Moseer.

l

Y NIAGARA NUMOHAWK NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE. N Y.13202/ TEL 1

I June 1, 1982 Mr. Darrel G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Re: Nine Mile Point Unit i Docket No. 50-220 DPR-63

Dear Mr. Eisenhut:

Our letter of May 24, 1982 provided plans for the mitigation of worker radiation doses during the safe and replacement outage. The attached contains additional information as requested by members of your staff.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION 17 p t.-

tw Thomas E. Lempges Vice President-Nuclear Generation MGM/ca Attachment i

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NINE MILE POINT UNIT 1 NIAGARA M0 HAWK POWER CORPORATION REACTOR RECIRCULATION N0ZZLE SAFE END REPLACEMENT SUPPLEMENTAL INFORMATION ON THE ALARA PROGRAM I.. MANREM EXPOSURE ESTIMATES Our letter of May 24, 1982 indicated that Niagara Mohawk was reanalyzing the manrem exposure estimates for the safe end replacement project. These analyses have been completed and are simnarized on Tables 1 and 2.

As shown in these tables, the current manrem estimates for the inlet and outlet nozzle replacements (i.e., ten nozzles in total) are approximately 533 and 2312 manrem, respectively. The primary inputs to the reanalysis were the decreases in source terms.

These decreased due to decontamination of the recirculation loops and measurements in the reactor lower support plate region.

In addition, th6 effects of leaving the control rod guide tubes filled with water were also f actored in.

Throughout t,he duration of the project, these. estimates will be.

continually updated to f actor in actual exposure data. Any significant,

changes in the total projected manrem exposure estimate will be reported to your staff.

II.

EXPOSURE REPORTS A report, sumarizing personnel exposures, will be distributed to site supervisors two times per day. The report will be available prior to the next operating shif t to assure close monitoring of radiation exposure.

An analysis of the manrem exposures for the project will be performed daily. This report will include exposure records by task and include such information as recirculation loop number, radiation work permit numbers, total l,

exposure, and total person hours.

III. RADIATION PROTECTION STAFF Figure 1 outlines the organization established for the safe end replacement project. Niagara Mohawk maintains ultimate responsibility for the project.

The radiation protection staff reports to the Superintendent, Chemistry and Radiation Management. As a result of a manpower study, it was determined that additional radiation protection personnel would be needed to augment R r.7.; Q.:' spec 1Cic'.' pro ~cidbreset?J.ecSMpeF.%responS' b;1e pogitilec station personnel. These additional. personnel will.r i

i ons:w.tlJ..nleet diup:3 g.. w'. e.,',.,,. g

qualif.ications of ANSI-18.1-1971. In addition,. professional. personnel froM Radiological and Chemical Technology Corporation will provide assistance, as hN.)).II.Y@ ppa,u with plant health physics and<hemistrye 4 Newport New r-

.. ~....;,needed

...s

u..

, qoordinator. for.eac.h shif t.. The'.radi.,rpMQ%er, MWRhippgikppiath,ip f

1.on.co.grdYn'ators YJll.have n.'. '

The drywell coordinators will meet the.;,

af,1 on,ptotyct:

experience in science or engineering.

qualifications of ANSI-18.1-1971.

j

~ ~ _ __ _ _ _.

Mr. Darrel G. Eisenhut Page 2 June 1,1982 An ALARA Committee has been established for the safe end replacement proj ect. The makeup of the ALARA Comittee is as stated in our letter of May 24, 1982.

The purpose of the Comittee 1.s to identify problem areas and develop recomendations for specific ALARA fixes in the below listed areas:

A)

Review Newport News Industrial Corporation procedures for ALARA censiderations.

B)

Assign ALARA tasks to comittee members for execution or tracking.

C)

Review impact of tasks, manrem and manhour data, as it is accumulated, and compare with manrem estimates and initiate appropriate action.

D)

Review other activities, as required by the Superintendent, Chemistry and Radiation Management.

These recomendations will be provided to the Superintendent, Chemistry and Radiation Management.

It is within the authority of the Superintendent, Chemistry and Radiation Management, and the General Superintendent, Nuclear Generation, to require solutions to ALARA problems.

An ALARA problem report methodology has been established to document the resolution of identified problems.

IV. ALARA PROGRAM Niagara Mohawk's occupational health program is in compliance with the intent of Regulatory Guides 8.4, 8.13, 8.26, 8.27, and 8.29.

Deviations from these guides are outlined herein.

A)

Regulatory Guide 8.13, " Instructions Concerning Pre-natal Radiation Exposure", outlines special instructions which must be provided to a

. female employee, her supervisors, and her co-workers relative to the potential risks 'of radiation exposure during pregnancy. Under the Niagara Mohawk Power Corporation training program, instruction is presented orally to the employee, her supervisors and her co-workers. Written instruction (copies of the Regulatory Guide 8.13 and the Appendix) is also presented to.the emp.loyee.and her M4/ :. ray : w.,.r..V' sipervitets'.ht compliance Witti.,,the5regth htoryrgu5 deb.;Copi'esf ar.e.' ade it". W.e.,

m available to co-workers.on request, but are not distributed.

s

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74,

r

Mr. Darrel G. Eisenhut Page 3 June 1, 1982 B)

Regulatory Guide 8.27, " Radiation Protection Training for Personnel

~

at Light Water Cooled Nuclear Power Plants", provides guidance regarding the appropriate instruction for both site and contractor personnel. The instruction is based on the level of radiation protection knowledge needed, and the manner in which trainees are to l

be evaluated. The Niagara Mohawk Power Corporation training program t

deviates from the guidance on several points.

Section 2.2 suggests that re-instruction occur whenever a worker is assigned to a new work area or job or has been absent from a job or work area f or a considerable length of time. Currently, the Niagara Mohawk Power Corporation training program does not specifically include job or work area specific instruction on special radiation problems. However, special instruction is being provided for the safe end project.

Section 2.4 suggests that non-site specific training might be eliminated from the radiation protection program for transient workers fcr whom it is documented that such training was recently received elsewhere. The Niagara Mohawk Power Corporation training program does not~ distinguish between site and non-site specific training. All individuals receive both types of training.

It is felt that from an ALARA standpoint, the reiteration of important health physics concepts is beneficial, since it can serve to increase the trainees awareness-of the importance of ALARA and improve retenti on. Detailed docm entation of training received is not It generally provided for the individual's use at other facilities.

is not a secondary objective of the training program to assure that training is not repeated needlessly at other facilities, as suggested in 3.1.

Section 3.2 suggests that trainees be given reference documents covering essential f acts, requirements, regulations, procedures, and plant organization. Currently, trainees are not informed in writing when and where reference docments are available, they are informed orally.

Section 3.2.1 suggests that self-monitors should acquire a detafled knowledge of sources of radiation and radioactive materials associated with all plant systems. Currently, each specific source of radiation is not. individually discussed in the self-monitoring g),Ib...,y...-ine ;. 9,$1%td.'Md'. ilioWeveMtr.aieees,.' ate; adeis$.toabgcpme 1,y. ;,3,3,.. g,e.;,.e"..'

familiar with past survey. data.beford entering' a radia' tion or'high.

radiation area.

In addition, station self-monitoring procedures

"..l?.. ??W,.

regu. ire perso'nnel to call radiation protection for a. survey if-dose.

@.'?.

.%cWW,.d%?..W, W. WPMW"..#Mn%Wmn Section 3.2.4 advises that on-site in... ~.. _..struction be given on emergency a

f acilities and equipment, emergency exits, escape routes, and safe assembly points. It has been found that time limitations of ten preclude bringing off-site personnel on site for this segment of training. However, familiarity with station alarms and assembly point locations are included.

L -._

m.

Mr. Darrel G. Eisenhut-Page 4

/

June 1, 1982

,l '

/

truction Concerning Risks from Regulatory Guide 8.29, "I C)

Occupational Radiation Esposure", provides guidance for presenting This the biological risks of occupational exposure to workers.

information is presented orally, as part of the Niagara Mohawk training program, but not in written form. Printed information is made available if an individual requests it.

Individuals are asked to acknowledge, in writing, that instruction has been received.

Tests are conducted and results used as an indication of understanding. Training generally covers the information contained in the appenoix to the regulatory guide. However, certain information considered not relevant to the objectives of the training program have been omitted in the interest of simplicity.

Regulatory Guide 8.4, " Direct Reading and Indirect Reading Pocket D)

Dosirceters", and Regulatory Guide 8.26, " Applications of Bioassay for Fission and Activation Pr, ducts", have been included in Niagara o

Mohawk Power ' Corporation procedures.

V.

PROCEDURES The following procedures will be developed, and reviewed and approved by the Site Operations Review Committee, by June 15, 1982:

An interf ace procedure which will define the authority and A) responsibilities of all crganizations associated with the ALARA aspects of the safe end replacement project.

B)

An overall radiation protection /ALARA program procedure, including responsibility and authority of the ALARA Committee.

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'A'M' 1.

REctRCULATinu No12LES

Pl9fP W CTION

' *

M?

, g..

_s

'M; ;

"y.

RR$

WORhERS MAN-HRS DOSE RATE MAN-REM MF.AS"JR f'D *

M RrWiiout. WITivour cR

. mas-prn WIT 1100T LOOP ESTIMATED SAVIMS d

./

, '*h,

[*.'.

LOOP DEcu4 DOSE RATE ESTIMATED FROM ORICIIIAL

.1, DECOM AFTER DrC04 MAN-REM ESTINATF.

- } '.4.

A.

PRELIMINARY MsJELL WORK

1. Install Loca195htelding (Blanketa),Upgir*. Deck & ',.*

tower Deck....;,.

, a 24 4

96

.350 31.6 0.061 -

58 27.8

s..

. _ eg

2. Open Shiel3,D'apro In stopteld 3

2 6

.300 1.8 1.8 opening

,7 5"

.'.,i..

i.*

f

3. Remove insele H on From i.

g Eltw o and R.iesire

' ' l.

24 4

96

.200 19.2 g.,

1 178 0.031 59 13.3 I

. v..

..r*

. W.

s.

4. Rig In end Indkalt Scaff41 ding yj

.}', -

118 4

472

".08 37.8 0.045 22.0 15.8

)

,l

. S'*,p -

y 5.InstallTeepdprFLightej

,rj 18 2

36

.08 2.9 0.031 1.1

1. 8t s,w

+

.W j

6. Disconnect Sabblere anni,.

Replace vir.hyr'ntnickley.,

72 3

216

.08 17.3

.05 10.8 6.5

.g

s*

m*

J.

.2

7. Install Ptte Jestraintelr

R.-

.02

.75

(*'

25 6

150

.25 28.1

.03 4.5 24.4

. M. - -

8. Measuring E* Qting P!pe s d*.

15 2

30

.200 6.0 6.0 Loc a t t one -

y.

S..

..O.

p

{.-

9. Rig In Lead $1ejding

,~.i ~

I 80 8

640

.08 51.2 0.06) 39.0 12.2 1

10. Install Qurteine From Refdel T.*

' k**' '

12 3

36 07 2.5 25 Floct e.

- V, 7.

.W IiI';

11. Record Sprt% lunger Rea'dtage

-All RectresTaops I

'/

? *.

3 2

6

.08

.5

.05 0.3 0.2 l

t,

. w'

.h..

.:. dose irat'ds are to three dectml places.

Eatimates to tw> places.

Actual calcula t

es.

c;.

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jG*

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- s Tehle 1 Continued;*

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Evtukp* *

., g HR$ WORKERS MAN-Has DOSE RATE MAN-REM MEASUIEDa MAN-REN Rett / noire,WITHost? OR SAVINGS

, ag -

WITHOUT 1.00P ESTIMATED

]

. 4' -

LOOP DECON DOSE RATE ESTIMATED FRott ORIGINAL AFTER DECOM MAN-REM ESTIMATE

,*g'.

~

DECOM l

.J,r..

e *

12. Instalt tempotaryslead t

i Shtelding in Ansc' tor Shilfd 0

160.0

'l-Wall Opentes % 4 Suction,Stda fll-hetton.'*4,

1,' '

20 4

80 400 -

32.0

12-ketton T*.

20 4

80

.400-32.0

13-Sucttog*,$*1,

. 'h-20 4

80 400-12.0 2

14-ketion.T 20 4

80 400-32.0

15-hetton. 'I_

20 4

80

.400 32.0 4

(

etching-suc,t1 9 eide..; '

20 2

40

.500 20.0

.30 12.0 8.0 i

13. Flap all veldgior acid '.4,

.B-

. r.i

14. Estabitsh ennating welds' 20 2

40

.500 20 0

.30 12.0 8.0 using scid,.etiAin's-pump "i suction. :),$

}

.?:. 2 1

pump ouetten,b d4

d' 6

2 12

.500 6.0

.30 3.6 2.4 4

15. Scribe cut,145ss #1 & #1-

- g

. +

0.02 3.0 50 6

300

.250 37.5 0.029 8.7 31.5

16. Support rectifulation* 1 tees.

+

pumpe&c'therpulpeent,T

' N.s.

17. Install cosetypication equ.tp-meat & audio.deustequp 15 2

30

.100 1.0 3.0 eent

- *$y..

?C J,

36 4

144

.05 1.2 7.2 1

18. Remove tempecary;interlag-ences

. *F f

L*)n '

4*

24 4

96

.0M 7.7

.05 4.8 2.9

19. Set up rigstrig in Drywell

..>i

u.

a

l-

. A...* -

s l

u.

i.*

' ?

12 2

24

.08 1.9

.05 1.2 0.7

20. InetalI pneumatie pouec i

,(

l y

j

- ~..

21. Remove requisp! decking

.y2

. 4. '

12 3

36

.05 1.8 18

.?.j s

5:

y.

154.0 315.8 Subtotal-frepinary. ;

469.8

.i D.

2988 Drywe11 Work />.

3

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ti Y?.,.

.+

. :s.'s 4..

s Table 1 Centspeed.

.t I

.S.,

,?.

i HRS WOREERS MAN-HRS DOSE RATE M AN-Rfff MEASIIRF.D Rpt/ HOUR WITW1UT OR Mall-REM E

s' 6 b

WIT 1 TOUT Loota.

ESTIMATF.D SAVINr:S

{.

' *{.*

b*.

LOC DECON DOSE RATE

' ESTIMATED PROM ORIClltAL

.s d,.

3

..'r DLCON AITER DRCON MAN-REM ESTitt%TE

. p$a...tr.

+;;

4 R. REMOVAL OF EKTSTING SAPC; ENDS'AND ELSIBfS'

22. Rig in CettJ). Machines?,

J-

t..:.:

4 12 3

36

.08 2.9 2.9

^

. f.sth '

. U.*

f.

23. Set up CuttJ63 Machine (-

On Cut Line9 1*

N:

24 2

48

.350

,16.8

.20 48.0 36 fit-PungrSdetton ft2-Pump 48u't'on

?

24 2

4R

.150 16.8 ct

13-Pump l.Socaton

?.

24 2.

48

.350 16.8

14-Pump.Settion 24 2

48

.350 16.8 fl5-Pump.Sdtfen

.,f-24 2

48

.350 16.8

24. Make Cut Fij s

, a..

.f82

.2

y; 10 2

20

.550 2.5

.10 to 3.5

11-15:ap 'Sia's tion

.02

.2

..s'if l.'.

ft2-Pimp'Suhten 10 2

20

.250 2.5

.02

.2

y: *-

13-PuenSMtten.

S' 10 2

20

.?50 25

'.'t

.02

.2 U

14-Pump..S M.

1. .~.

10 2

20

.250 2.5 on

.n2

.2

.. tf

t*

15-Pump S delen r.

10 2

20

.250 2.5

25. Set up Cutt &cs Machine. for Cut #2 J --.

11-PumpSlk51on M-24 2

48

.350 16.8

.25 60.0 24.0

12-Puey Sveitpa

/,

24 2

48 153 th.8 24 2

48

.150 I6.8

.1

13-tump Sedian g

14-Pump' Seh ton 24 2

48

.350 16.8

15-Pump Snation N

24 2

48

.150 16.8 (Nearest Noz zle )

Cutj[if2 26.

Make 4

Note 6

.050

.5 i.i fil-Pump Sd tihn 10 2

20

.500 5.0

.25 25.0 2.5

.050

.5 a].*

f-10 2

20

.500 5.0

12-Pump Suction

~ E. '

.050 5

13-Punk M;y*ilan

.IJ 10 2

20

.500 5.0

.050

.5

p -

4*

14-Pump S g ton 10 2

20

.500 5.0

8. # ~4 :

.050

.5

15-Pump Suts ton *.<

10 2

20

.500 s.0

}7. Rig out ',Elh with.Saff End

Attached,

[.'

fil-Pump 5% tion

/4 ' "

12 2

24

.100 2.4 12.0 fl2-Pump Sgt,tton 12 2

24

.100 2.4 f!3-Pump Seetion 12 2

24

.300 2.4

14-Pump sehtten 12 2

24

.100 2.4

15-Pum'p S% tton 9-12 2

24

.100 2.4

. i.1 *

=

.* r.-

+

d:

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4

{ t,

.m+-,.

.%f*

.,5

h.,

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~

'h.

Tabla 1 Contiousd

,f,*f'.

.y

.s

'. '.# 1

.i '

HRS WORKERS MAN-IIRS DOSE RATE MAN-REM HEAS!!RI'D*

'tvEh" p*,

REM / HOUR WITHOUT OR v

a MAM-lWM

,j SAVIFES

.,,Q WITHOUT IJkW ESTIMATED

. g*,,

.,v LOOP DE(Wf.

DOSE RAff' EST! MATED PRON ORICillAI.

j-AFTER DF.(ON MAN-REM EST1 HATE DECON j

h *,

l

d;/.

11-Pump'Sueston-

7 2

2 4

50 20.0

.61 12 2 87.8 j

28. Install ehte&d.Pluss-r, 2

2 4

50 20.0

12-Pump'SM(ion 2*,

2 2

4-50 20.0 I

on i

13-Pump'Suct 2

2 4

50 20.0

14-Pump Sud lou 43 f

15-Pump Suetion 2

2 4

50 20.0

{

1 2

2 4

.350 1.4

.10 0.4 I.0 l,

29. Install covet tw Riser.;*

.j Ptye n (g.

~

.g. _.

2.1

30. Clean out Netztes 3

2 6

.350 2.1

! 'f4 e

'L

. : w* '

a All Inter.Mitssles 4

5 2

10

.500 5.0 5.0

]

31. Take ID 01msparons On'..,

j;

~

,.5

~.'*i.

..~

~~

1.0 i

32. Instalt cleas Plus in.*d 1

2 2

500 1.0 i

Nozzle *

,'g',

/i,.

'j

r_*.-

t.

t 2

2

.500 1.0 1.0

33. Etch Chedk. bid in Nozzle ID y.,5.,

.[,

f

.t

.N.

. 9*s E

34. Weld Prep the Riser Pige -

i fil-PumpSht' ton

, j' 5

2 10

.350 3.5

.I0 5.0 12.5 Pump Sueti.isjt2,

.5

12-Pump Sect' ton 5

2 10

.150 3.5 5

2 to

. 350

.1. 5

13-Pump,Saidion 2-5 2

to

.350 1.5

14-Pump'.Siidtt on f '.'_

5 2

10

.350 3.5 fl5-Pump'Sudt' ton 5

2 to

. 35 0 3.5

.10 1.0 2.5

35. Liquid Penepant Test,UT)

.t Weld Preps p Fiser Pipes h

.. W*

C

36. Mschtne ma4 Weld Prep Ealating

~

Safe End's Mump Suctton-

11-Pusf. Sipett'on 5

2 to

.350 3.5 17.5 fl2-Pusp. Suo61'on

[

5 2

10

.350 3.5 j

13-Pump'SNton 4

5 2

10

.350 3.5 5

2 to

.350 3.5

14-Pump, Suptbn s.

15-Pump Saktion

'i'a 5

2 to

.350 1.5

37. Liquid Peneqrapt Test-All Existing $ die End Stube-Pump suctfk

,y 5

2 10

.350 3.5 3.5 tu 5

2 10

.350 1.5

.in 50 12.5

38. Counterbor,4,;Riner Pipei fil-Pump SU6t' ion

12-Pungr Sstt ton

.a 5

2 to

.350 3.5

13-Pump Silition I,*

5 2

to

.350 1.5

14-Pum'p S~ulti,an

.[.".

5 2

to

.350 1.5 5

2 to

.350 5.5 f l 5-Pump,'. S.4t t an

.,5.

e i s Q..e 4

,p

i r.

I

.i.

8u m

..I 1

D N

50"!

e e.

e.

c.

r.

t I'.

o.

t o

n o

n ;g z

o u

n g

~

3.

aw o.

o.

"5 o

1.,

~

~.

N ee EEg

~

C u. b wk :

C o

o

.o O.

Em

.O.

m n a R

-w Im#$g 5

t cwc<

E$

n.. n. a. n.

e.

c.

nnnun n

aa kak

~

Ess8

.65 E

RRRRR R RRRRR 8

R R R R, R,

. R.R. R. R. R.,

Iw.S D 5

m. r.

o.

a.

e.. e..

c. m. o. m. o. e. o. m. e.,.

e p u EgsE E e

5

a g

=

a t

~~~~~ ~

m

~~~~~

~

nemme

~ n n

n u

o ee@@ d 4

4 4

C.

N HnNNN t

W4W g

an 1

1

.e 5

r 4. 3. "a :i.'...p.7 d.o8-Qli, ;;- < j :.r.. g. *33 j ', A.gi 3: g; /', n;c g:er, a" :,. :,,g,.;;.;,.g. g,,.,';y,j

,,..,'...,., g, g w

. a,g w

e h.

A.

A,,

.e e

.o..

o a.ooooo a

.a..

E..

Ea....,..

. { 1;...figIs. pushpi o

o o*

i oo

.o o

og

.E p~;.p:x.3;4c,pg.:qpi,.h

s@e j.a..,pi.v.e c

., !F-mg55,gg11 ale oo

9....wM.M I..:.r.a$zy4....A.M.

s eq,o v

a

.. p-.

tua U.i t.

., a...a.

E

.s e s j 1. z..x.

a a a.....

....a,-

e...

o,.

r

.z-

...o..

zz e. z c. z z c.zzaaz 3..Il..

1 3,.,

1 s-o o

es g e a M 4 em e N

m er.

.a 4

D* M.

aJ w we a 48 e en 8

N M em g

ed N

N 4

.N Q

D.

Q 4

4 4

m 4

%M***"'""MO

+'*1

- - 4 ri 4-e

=a 4

O 94 4

. Ff a -

t 7$p

t ~;

v

. D.

4,.

b a

g W"?.<

Tatt1] 1 Contissed g-IIRS.WOREERS MAM-HRS DOSE RATE MAN-PEM Mr.ASURED*

. gVE$g*

Mall-Rfli a 4.

f REH/ HOUR WITilOUT OR d.'.

WITHOUT 1.OOP ESTIMAfrD SAVIN 4:S i '_'j$.

'}

LOOP DECON

' DOSE RATE EST1 MATED FROM ORIC1 MAL DECON AFTER DF.COM MAN-RDf EST1 MATE y, e'r, ','

t-

'p..

46. Radiograph,(RTJ ' toot F2*.

11 Fump Suct{'on 7~

2 14

.08

.6

.10 7.0 8.5 w t *.

.350 2.5

12 Pump $*uc.$['en *

.V' 7

2 14

.08

.o

{*

. u. i

.350 2.5 f13 Pump SinctTon

[

7 2

14

.08

.6 y'-

M

.350 2.5 7

2 14 08

. fi

14 Pump Sue n,

15 Pump suces6*.

.2

.350 2.5

' -7 7

2 14

.08

.h

.1%0

2. 5_.

A*

47. Weld Out q"

. h,.

21 2

42

.05 2.1 10.5

11PumpSuc$$n" 21 2

42

.05 2.t l*

12 Pump Sectjen, l,.-

l 21 2

42

.05 2.1

13 Pump Sve(Jen j.

21 2

42

.05 2.t 814 Pump Sect 66n I

15 Pump Suc Qow 21 2

42

.n5 2.1 l1

48. NDE Weld 52

s'

'd.

O fit Pump suc't

/.

6' 3

18

.I 1.9 9.0 1

12 Pump Sdeggear, G.

6 3

18

.I 1. 75

1 6

3 18

.I l.4

13PumpStrct@}n

,l i

14 Pump Suet'l n' E

6 3

18

.I 1.M iti!

15 Pump SudYon, 6

3 18

.I 1.8 Il

49. Remove Weldi g Hachines[cin j'

Weld #2 - AIT*? ump Suctlpa 5

2 to

. 150 3.5

.10 1.0 2.5 j

a f!

+..A(*

I

50. Rig in Testplsfe - All Pimap Suction 9,

!. t.

3 2

6

.08

.4 0.5 l:

$.y 3-g d

c.

~

l 9

l+

51. Lift Templet447 All Pump' i

14.

J,.

5 2

to

.15o 1.s

.go 1.0 2.5 I

b Suction

'.f;-

Ii.

52. Remove Template,From la

,*[4

?.

3 2

6

.08

.5

.5 1

.~

Dryvell l

d

?*[*

,' E

53. Set up Weldtp H.ichtnesr,4ar Weld #1 sed.141d #3

11 Pump Suc2)on

-l, 24 2

48

.150 16.8

.10 24.0 60.0 24 2

48

.350 16.8 19 fl2 Pump Suc'(foe

13 Pump Suc1} ion 9.

24 2

48

.350 16.R e

14 Pump Suc)(nn

>1.

24 2

48

.150 16.8

15 Pump Sucflaw

J 24 2

4R

. 350 16.8

54. Remove Shtel4 Plups - Akt Tump 10 2

20 5.0 100

.61 12.2 87.8 Suction

.g,

l- 'h).

-j,.

p.

s-r.

.y -

,sv..

"e.

.*:. J

hl~

'4.* e*I

.', g*.

+

r s

5l

.&,[

I 4 ~ (.

.r.,

E*

b fi.

o.

?.

Table 1 Contimmed -

4 L '

Mt.-

. I Isas W0aKERS P AM-IIRS D01E RATE MAN-REM-HEASURrD*

g.

r..

. IhrEsit."

4.****.

0*

REN/tio0E WITn00T on Mall-t r.M SI WITil0UT IDOP ESTIMATED SAvitCS

3*

i

L'1

?*

LOOP l> ECON DOSE RArt ESTIMATED P90M URIC 11141.

Y*

4*

DECON AFTER 14. CON MAN-REM EST1 HATE

. 5;-

. 's

55. Estabilmin Furge

12 Pump suct "

'.N, '

2

.2 4

.10

.4 2.0

11 Pump Suc((ok

-1 2

2 4

.10 4

13 Pump su sn-2 2

.10

.4

[

14 Pump Sec p n gj 2

2

.10 -

.4

15 Pump Suc_t{da L

2 2

4

.10

.4

56. Fit Up 4 TAthElbow into Place 16 3

48 10 48

.20 48.0 192.0

11 Pump Section

.~ p,-

h

12 Pump SecVien-16 3

48 1.0 48

13PumpSuc%n 16 3

48 10 48 t

14 Pump Suetaden f.,

16 3

48 1.0 48

15 Pump kett'un

't 16 3

48 1.0 48 e

57. Weld in Root.fi 4

2 8

.08

.3

.le 4.0 4.4 l

711 Pump Sucitati

.350 1.4

.e..-

w i.

f12 Pump Sues ~tpa 4

2 8

.08

.3

13Pumpdue%;."'

,' f.

4 2

8

.08

.1

.350 1.4 9

n

- !3

.350 1.4

14 Pump Suedon.

".y 4

2 8

.08

.3

.. S',

p.

.350 1.4

15PumpsuoKa,n

..I 4

2 8

.08

.3

'N.

.350 1.4 3,

58. Radiograpig Root;#1 7

2 14

.08

.6

.10 1.0 8.5

11 Pump Suci.fovi

. y" #.

.150 2.5

'.". G

12 Pump suctioni C'

7 2

14 08

.6 FT

- 'k

.350 2.5

13 Pump Sudiod

.4'*

7 2

14 09

.6

}

./I

.350 2.5

14 Pump Soh,uin n 7

2 14

.08

.6

.350 2.5 7

2 14

.09

.6

15 Pump.Su6tf og

,g.

i

_ W.

.h

.350 2.5

- 59. Weld Root.f) *.

ill Pump $ ire'dkon' 4

2 8

.08

.3

.10 4.0 4.5

.350 1.4

- - p",

l

12 Pump Suc$lan 4

2 8

.08

.3 l

.350 1.4

-r 4

2 8

.08

.3

13 Pump.Supfen g

.150 1.4

'f 4.,

14 Pump S,c,T.jon 4

2 8

.08

.3 u

.350 1.4

.p; t

15 Pump Sucsh>n F

4 2

8

.08

.3 l

16..

.350 1.4 s-i%..t 1*

..f. -

r*.

i*.

' 1 **,

.?.

.s s

S

_..D.,

,G.

.'t

.4 5{'. I n

v.

.6.

.y.,

..~.

'. %. e

.s.

R

(- -

g

..,.5

%- = -

y

.p.

b 1 Cond SV 5

HRS WORKERS MAN-HRS DOSE RATE M A?-R Dt HEASUREI)*

MAN-REM '

. i*.

REM / HOUR WITHOUP OR WITHOUT LOOP ESTIMATED SAft:N:S 5..-

,.5 1.00P DECliN DOSE RATE ESTIMATED PROH ORICINAL f

.I '

DECON AFTER DECON MAN-REM ESTINATE

,.I*

'.y

60. Radiograph IhMPt #3 j,l.

11 Pump Su, n

7 2

14

.08

.5

.10 7.0 8.5

.350 2.5

./.

P

.t.*

.S' 7

2 14

.0A

.6

12 Pump $u on

.350 2.5 j

).

y

13 Pump 'Suegl6n 7

2 14

.08

.6 g

.350 2.5

..'.4,g..

4

,s..

14 Pump Suus1=n 7

2 14

.08

.6 i

Tj.

.350 2.5

15 Pump Sugr$on f..

7 2

14

.08

.6

. r!.

e.',

.350 2.5

61. Weld Out.fl i64

,1.

21 2

42

.05 2.1 10.5

.\\

fil Pump Sdetton 21 2

42

.05 2.1 I

f12 Pump Suedon

13 Pump iu4tjon 21 2

42

.05 2.1

14 Puep;SucT, ton 21 2

42

.05 2.1 s

?

15 Pump 1uditioe*i 21 2

42

.05 2.1

62. Weld Out /3 /'.

i fitPump.SuNio'n

*j 21 2

42

.05 2.1 10.5 z

12 Pump.Jo $ en 21 2

42

.05 2.1

13 Pump Sue' sten 21 2

42 05 2.1 4

14 Pump SucYto'n 21 2

42

.05 2.1 21 2

42

.05 2.1

15 Pump Suefton

63. NDE Welde FL-)n.1 F3

.4

11 Pump *Su'citon 6

3

.I8

.100 1.8 9.0

12 Pump.Sidt' ton

i 6

3 1R

.100 1.8

13 Pump.'Suffida 6

3 18

.100 1.8 6

14 Pungs.Sultlon

I-6 3

18

.1n0 1.8 2

6 3

18

.t00 1.8

15 Pump Stielfon I

2108 f>87.3 211.5 47**.8 SUBTOTAL-REP'NhMTOFSAhENDS

s

. A D. POST REPAtt -ORYWELL WORK.

64. Remove Tempqy,sry Shielding in Bioshield 0)pninge l

11 Pump'Substp[n 1*,

10 4

40

.400 16 0

80 10 4

40

.400 th

12 Pump'6acQon

'l*

10 4

40

.400 i f>

13 Pump'Subtida

14 Pump,Sugtton

.l.

10 4

40

.400 16 10 4

40

.400 I t.

15 Pump 50aftlon

65. Remove Temps,r'ary Shtelyng on PectrculdtlIer System tipper Deck

(.$'l 24 4

96

.200 19.2*

.In 9.6 9.6

. i;:

66. Replace & Rurord Spring -

Hanger ReaddiRe' 5

2 10

.08

.5 0.5 5;

$*).

,h.

' ir ~..

SUBTOTAL - P'OS'TWECDING DWTWET.I' 9 3, y 10.1 8'b fi woRxc j.

.C

/

TOTAL - RECIRCJft'ATION SYSTFJt PUMP n02 i..f,a. 2 594.7 iOr i.7 Sucrtnii-ainE Nonis.s

,..y a..

,3,.

~

s

., y

.s y.

U et '

(*,h I M:.

- O Table 2

... /* -

1,i,'

REC 1RCULAT10N N02tLES - Pt#fP DISCIIARCE

'fr

...r; EVE;f6 *. *

'.. HR$ WORRERS. PERSON REM /l!R PERSON MEA $ TIRED *

.d

y.".

HOURS NO REM OR HAN-REf1 DECON NO EST1 HATE SAVINGS

.; f.g.*

j y.

DEC0f3 DOSE RATE ESTIMATED FROM ORIGINAL

=,

AFTER DECON MAN-REM ESTIMATE

. 4, -

t 3,g.

A.

PRELIMINARY, unsww.Lt. WORA.]

o..

, 1.

Install Tempopery;ShieIdihg j

in Bloshield @Wninfo y

~

11

.1 20 4

80 0.4 32 160.0 20 4

80 0.4 32

12

!.41.

13

,t

4e, 9

20 4

'80 0.4 32 20 4

80 0.4 32

p*

14 a

15 20 4

80 0.4 32 2.

FispWelds,fo(.,14cidEtchlag 20 2

40 05 20

.25 10.0 10.0 l

,. :g'

? :.

3.

Estabitsh Entaling Welds by AcidEtchthg,,$,.

',i, 20 2

40 0.5 20

.25 10.0 10.0 A

,g,

.g 4.

Scribe Cut 4.ines 1, 2 & T i

.s 6

2 12 0.5 6

.25 3.0 3.0 0.*l.

]..; t t

t DRYWELIMRK 412 206 183 23 SUBTOTAL PRELiljl 1.

8.

REMOVAt. OF*EXTSTING - "i SAFE ENDS ANDeh ROWS

. ;Y?

Y.

5.

Rig in Cuttin& N chines *.-

12 3

36 0.05 18 1.8

.s

.,p.,

a 6.

Set Up Cutting.%rchine-Cut Line 14 ' T.*

I' 24 2

48 2

96

.5 120.0 360.0

11

12

ST.

24 2

48 2

96

13 k:,

.?-

24 2

48 2

96

14 I,.7!

24 2

48 2

96

15

'.R *.

24 2

48 2

96 Set Up Cuteingl(M.nchine opt 7.

2 Cuttine *.*

'/ !

fitPumpDischrg,e 24 2

48 1.0 48

.50 120 120 1

12 Pump Discherg'e 24 2

48 1.0 48

13 Pump DischgTge 24 2

48 1.0 43

14 Pump Discharge f.

24 2

48 1.0 48

.=-

24 2

48 1.0 48

15 Pump Disch'erge 9

8.

Make Cut F1

-l.

.t.

4,

11 Pump Die

'rge

s 10 2

20 1.0 20

.50 50 50

12 Pump Disc 1eirte

'.e.

10 2

20 1.0 20

13PumpDfeelistge 10 2

20 1.0 20

14 Pump D{sclattge 10 2

20 1.0 20

15 Pump Discisrge 10 2

20 10 20

- 6.*

Actual calcu14td.d.ose ratesf are to three decimal places. Est ta.ites to tw places.

W. *

%g

(

., a[5 ',..f

. =.

. is:.!

' i.'-

g.'

e*o

7 *,F.

C

+ -n

F'.

s-*

>J}'

.*(

Table 2 Cantimmed q%

h -

y O HR$ WORKERS PERMMI RDl/HR PERSON.

MEASILEDS EVENT.

,. (

'l -

HOURS NO REM OR MAN-REM

*g **

DECON NO ESTIMATED SAVINCS

,. g-

.

hl-DECnN DOSE RATE ESTIMATED PROM ORIGINAL AFTER DFftwf MAN-REM ESTIMATK

,...r.

h.

4'

11 Pump Dio.c Q;,9 Make cut #2 ;.

,q.

.,5 to

-2 20 1.0 20

.50 50 50 9.

12 Peep Disch&sdef s* "

10 2

20 1.0 20

13 Pump Diechsitge J.s

10 2

20 1.0 20

14 Pump Dimetonste.

.f., 10 2

20 1.0 20

15 Pump Dise", L.

-V to 2

20 1.0 20

10. RIG Out Etter *p

~. "

Fil

M-

Of 12 2

24 1.0 24

.50 60 60 s

12

..f,

,4 12 2

24 1.0 24

13 12 2

24 1.0 e 24

14

%'(.

G.,'

12 2

24 1.0 24 fl5

-V.

12 2

24 1.0 24

11. Set Up & Instan Sbield Plag

11

.g

'f 12 2

24 5

120 3.5 420 180 12 2

24 5

12n i

12

.M-

. -h%

A.% - 12 2

24 5

120

13 i

12 2

24 5

1.0

.. ', [.

14

15

? i.f*

N 12 2

24 5

120

12. Install Fluge osr Rteer Pipee 2

2 4

1.0 4

.n%

0.2 3.8

, K.}

y.

13. Remove Cuttingfflechtne Frot cut 2 & Ineraltion Cut!!ng*f3 24 2

48 0.5 24

.10 24.0 96.0

11 ' Pump Disch7brge-t 24 2

48 0.5 24

12 Pump Disichaftpe

+,,

L

13 Pump Diec@ge, 24 2

48 0.5 24

14PumpDischs,rpe 24 2

48 0.5 24

15 Pump DiselleVat 24 2

48 0.5 24 e.

13a. Make Cut #F

(

10 2

20

.35 7.0

.20 20.0 15.0 I

f!! Pump Disc ge

12 Puep Dischasse 10 2

20

.35 7.0 10 2

20

.35 1.0

13 Pump DiaghArge' 10 2

20

.35 7.n

14 Pump DischMae

15 Pump Disch.ftge 10 2

20

.35 7.0

14. Rig Out Safe-1361s filPumpDiech'aje' 12 2

24 0.2 4.8

.30 12.0 12.0

12 Pump D!ich4tge 12 2

24 0.2 4.8 12 2

24 0.2 4.8 II) Pump Disch4sie i

14. Pump Diecidige' 12 2

24 0.2 4.8

15 Pump DischMe:

12 2

24 0.2 4.M l

15. Clean Out NdaM interford; (Includes Ptapptig) 10 2

20 10 20 20.0 Q

16. Take 1.D. Messaarguents of,/-

12 2

24 1.0 24 24.0 Nosale

17. Weld Prep Piemp Ote' charge g Nasslee IT,

.s ill

j';

5 2

to 0.35 3.5

.20 30.0 7.5 5

2 10 0.15 3.5

12

. ),.'

13

' w* '

5 2

to 0.35 3.5 5

2 to 0.35 1.5

14

.b'

15 5

2 to 0.35 3.5 b.

N',

...w. -.

,,to g 3

3z 1:

4 1

l b

N O

- e.

I f

I Gw o

K as v.

od o.

e.

en.

t s

.N t

l 8

N N

m o

4

N t.

E >*

E 9. C W

D

'U E o.

o.

e.

o.

o o.

o.

2..

o

. e.

N e

o N

e o.e e.

o.

g e

.3 e

9 e

g E

A g E h!

h!

<L o

o o

C C

o.

g4

.c' at

.J E

sd M.

N.

e.

H.

N.

m

-w

>= e g 4

l'ED84

=

e.

$.5 5

e c. o. c. e.

c. e. r. r. e.

e.

r. e. c. r. e.,

N N N

N e-u

.o o.

.E w

i.

<++-e e

+ee<s

+++<e e

e.

o.

e. n. e. e.,.

n. n.. m. e.

N.

. n. e.,. e.

e.n.

N.

b.

o.

e. m. e. r.. :

E s

ooooo ooooo o

oooco ooooo o

o o

o c c o o:

I,g B.

N o

o o

ooooe o

ococo NNN,, N;

m..

E 4

m.

N N N N pg f'

.0 N

N NNNNN NNNNN N

NNNNN NNNNN N

N m

S N N N_

N_.:

m e

e ememe e

macee NNNNN e

N-g-

$,*' 6..A 6 'A 4 tt I. -$ 0.6..!.4. 'K% w k Y.W: -. I..N 1.-.3,*

ct.

t>

6 si< n-l),1..r. ;ij g.,, t.M..? Yjt. n g.

.L..

t g

u E

.t.

2 2

t g

'g-

s..

.a.#. t... s.. *..

B 2

d..Q,%QvM,k.*.O a

2 a

i e. s.

c

'~-

M'k.dNMkE.S,#NM.j lh',3pf'jkjj}gjj:f.n.f jfYQji f.)j.j{3,pj:j%j[.Q:. y?y-

.. 2...,.... m

.u. 3.... 4. n. m. -... u.. u.n.o.s.

3o..a. a.n... n.

o

.e

.u 2

f 7

3 00000 JDOOQQ w

a 00000 0D000..

3[ 2 A

J tt 2

a mauss 'sa cat

.....d as.aa..

3 E"2 3

EEEEE EEEEEE E. E.EEEEE

EEEEE E$

5

! d.'

2

.a 5.

.-No.e --Ne4e,-

.-N e 3.-Nm e t.

-Nr.r.

p g.

453 32 iC:: 2 3 C23: 33 32:22: 38 :::: 53

-3 2 2

C::::::

P k

W

.f'%

P4 8

e' N

N N

N U

N e4 N

o.

G

.4

J'*;t f<..

.~.

p, a

. -i"..

' W:r;.*.

,1 w ps TablJ 2 Contipoed

.,gy h,

HPS WORRERS PERSON REM /HR PERSd3 MEASURtDe (I,.

.,.1p, fl0URS NO RtM DR MAN-REN

.'

s..'

DECON NO ESTIMA1ED SAVINCS

=

( h',,

, h*

DECON DOSE R4TE ESTIMATgD PROM ORIC1 MAL AFTER DECON MAN-RDI ESTlH4TE

,*J

_' Td.

29. Pit Up and T4ck Safe-End Into Placi $['*

331'

~.

[.

16 3

48 0.5 24

.10 72.0 48.0 16 3

48 0.5 24 I.h.

. if 16 3

48 0.5 24 ft2

13

't.

f.**

.16 1

48 0.5 24 Q.

'{?

14 16 3

48 0.5 24

15 3 '*.p.

30. Establish,rorge for Alk*

Nogales tC 10 2

20

.215 4.1 0.1 2.0 2.3

,y*

31. Weld Root.'f2@-!.

4 2

8

.55 4.4

.35 14.0 8.0

11

.j%

'e 4

2 8

.55 4.4

12 e

L; 4

2 8

.55 4.4

13 f14

'..YP

4 2

8

.55 4.4

15 ff *

'h*

4 2

8

.55 4.4

32. Radiograph Bappt, #2

' E*r 7

2 14 0.05 0.7 3.5

11

. )

7 2

14 0.05 0.7

12 7

2 14 0.05 0.7 813

- %f

(*,

f

14 j 4y,..

j.

7 2

14 0.05 0.7 7

2 14 0.05

_0. 7

15

. u 1

33. Weld Out (Logtton #2.

21 2

42

.62 26

.40 84.0 46.0

11 Pump)Diesharge

12 Pump Dial /Rarge 21 2

42

.62 26

13 Pump.Dio%arge.. */.

21 2

42

.62 26 CJ' 21 2

42

.62 26

14 Pump %Iidharge

15PumpD'14arge S.

21 2

42

.62 26 4*

1

34. NDE #2 Wel(Nharge h..

8 2

16 0.5 8.0 fit Pump DI 8

2 16 0.5 8.0

.30 24.0 16.0 l

12 Pump *; Dip harge -,.. -

'c C

8 2

16 0.5 R.0

13 Pump

Die' harge e

14PumpDIMMrge 8

2 16 0.5 8.0 8

2 16 0.5 8.0 815 Pump'D(ectuitge 35.RiginSpoobPlece fit Pump Df' th' ayre ft 12 2

24 0.05 I.2 6.0 s

h 12 2

24 0.05 1.2

12 Pump,Drog.arge 12 2

24 0.05 1.2

13 Pump lDieharge

14 Pump DSTiarge s'a*

12 2

24 0.05 1.2 S

15 Pump'Dik hdrge.

J*'

12 2

24 0.05 1.2

36. Set Up Weld 4pg Jtachine Weld #1

11 Pump.;Dfesharge

.A."

24 2

48 0.5 24

.30 72.0 48.0

12 Pamp Dtihharge b-24 2

48 0.5 24

13 Pump,D(meharge* ".

24 2

48 0.5 24

14 Pump, Dip'e!hkrge

.f 24 2

48 0.5 25 1^

15 Pump *.DMharge

7 24 2

48 0.5 26

37. Fit Up and,Teck New Spoo,1 Piece into flace i ^

fil Pump;D(herge 16 3

48 0.5 24

.3n 72.0 48.0

12 Pump.btidharge 16 3

48 0.5 24

13 Pumpr 014stwrge lg 16 3

48 0.5 25

14 Pump *Dftei4stge. f*j 16 3

48 0.5 2n l,

l-

15 Pump D1 h., rge

.~

I6 3

48 0.5 24

it

. '.{.'

l sy, '

=l

.g. t.t. 3

[

il m

t N.

Jt t- ~

t-g.$.

c e

Table 2 CaetteIsed, t i. :

e "gTN.

[,

'HR$

WORKERS ' PERSoft REM /IIR PERSr3 MEASUREne man-mi

. ;;c '.

.~.

nouRs un aEM OR SAVIf* 3 DECON SK)

ESTIMATED

'(

DECON TOSE RATE ESTINATED

. PROM ORIC115At.

,,N,

.*hh.-

AFTER IWCON MAN-ILEM 35Titt4TE

,-jf,g

.p'

,3

38. Estabiteh.Pugige for Welds

*Q.

l 20 2

40 0.5 20

.30 12.0 8.0 I

39. Weld Root <#1*.

4 2

8 0.55 4.4

.35 14.0 8.0

.fil Pump Dibs krge. i.

'A T

j.

12Pumpythtse 4

2 8

0.55 4.4

h ree t

r '.*

4 2

8 0.55 4.4

~~

.fl3 Pump

}

14 Pump,Di @ rge

E[*

.T...

4 2

8 0.55 4.4 s.

4 2

8 0.55 4.4

15 Pump D1betarse

y

.9.

l:

40. Itadiograph Sot 1 7

?

14 0.05 0.7 35 f

11 Pump Di M arge 7

2 14 0.05 0.7

12 Pump Dt' rge l

ft) Pump St.,. rge

.e 7

2 I4 0.05 0.7 1

2 14 0.95 0.7

14 Pump Diesharge

15 Pump *Disch wge 7

2 14 ti.05 0.7

^

41. Weld Out'fl,. p uplete Weld)

11 Pump Disiharge 21 2

42 0.05 2.1 10.5

[

12 Pump Di @ rge.

-s.

21 2

42 0.05 2.t d

13 Pump aldt$arge gl 21 2

42 ti.05 2.t i

21 2

42 0.05 2.1 i

14 Pump.Didc%4rge

15 Pump. ' ISarge h

21 2

42 0.05 2.t D

i

42. NDE #1 fil Pump

Die'ib'rge

7"..

6 3.

18 0.5 9.0

.30 27.3 III.0 I

12 Pump '. Die (harge 6

3 18 n.5 9.0 l

6 3

18 0.5 9.0

13 Pump Diseharge arge 6

3 18 0.5 1.0

14 Pump;DtM'6Arge.[P l

6 3

18 0.5

'). D

15 Pump' Dies J

43. Rig in Temp]#tes i"

,1 ' '

..]

3 2

6 0.05 0.3 0.3

,9 9

. ri:.

a.

Il

44. L1ft Templ4te,e 5

2 to 0.5 5.0

.30 30 2.0 l}

. f.S

..j.

s **-J l-

45. Rig to ElboWr.

d fit Pump!Diipdhdrge

.y 12 2

24 0.05 1.2 6.0 hl

12 Pump'DtMarge 12 2

24 0.05 t.2 12 2

24 0.05 1.2 lI

13 Pump *D%egharge

14 Pump"Dtwyharge 12 2

24 0.05 1.2

15 Pump'.06 Marge 1

12 2

24 0.05

1. 7..

46. Set Up Wdidfe4 mchine,,Jor Welde fi k $

f11 Pump Dischdrge

.T 24 2

48 0.5 24

.30 72.0 48.0

12 Pump.'Dtisiharge

'N 24 2

4ft 0.5 24

13 Pump;Dtisi.harge i*

24 2

As 0.5 24 o

24 2

48 0.5 25

14 Pump'Di'c!hirge Y'

15 Pump Dideharge 24 2

48 0.5 24

,, 6,..

.1*

7, e

.y.,.

.s

n.2.t e

'A

= _ _ -__

-__._a..-

J' j~ r eg *..'}p} U

,f,-

+

QFE%.

+

~-.

~

N 2

I a

e t g.,

-).

s

.(

,/

., /

.8 l,. ; *,

, // - ' g.$.,;i

[,' *[ '.

o g/

3'.

' * ;,;l 3 l

.'p r

EV$:,. -,

+~J*.

ggongs geo REM trR

' MAN-l!EM

l, HR$, WOgKER$

PERSON rot /HR PFRSON MEASUMED*-,'/.

Tab 1) 2 Centlassed

.. s.

-5 DeiCON 10 0 ESTIMATED f 5AVIf4 f

k K..'

DECOM-DOSE RATE.

ESTIMATED FROH nRfCIIIAL 4f, y

a n-

-j.9 a s y..

y -

AFTF.R ITCON.

MAN-Rut EST! HATE 1

. g..

.47. Remove SdteY4 Plus 12 2

24 1.0 24

.6n 72 0 48.0

-T*

fil Pum/Df) charge 12 2

24 '

1.0 24'

.I

12 Pump'-D!scha'rge

13 Pump Die 4 barge 4,

12 2-24 1.0 24 12 2

24 1.0 24

)

. #14 Pump *DIVdairge

15 Pump D M rse 2.

^

12 2'

24 1.0 24

,'^

4 7a. Remove.RIs9.g.,{1us

g.

2 2

4-

0. 5.

2.0

.30 1.2 0.8 5

(s.

'..T.

48. Isetent furge,. Dame in.9p.out Piece & 646)

.*2 10 2

20 5

100 3.50 70.0 30.0

'*i..

49. Pit Up 4.Tect.W id #3*

11' '

fN-

"J.

16 3

48 1.0 48

.60 144.0 9(,.0 f*[

9 16

'3 48 1.0 en i

f12 16 2

48 1.0 ed '

13

,l.% %

)3

)

14

.. l.g 16 3

48 1.0 4R i

e!S

/*

16 3

, 48 1.0 4R

. eld #4 * -

]

50. F1r Up 4.Teeg# W

.g*,

16 3

48

.43 20.6

.25 60.0 43.0

11 1

12

. 7 *.

3 16 3

48

.43 20.6

13

p,

,.~

16 3

48

.43 20.6 i

14

,,./

A 16 3

48

.43 20.6

~4 16 3

48

.43 20.6

15

. h -

. "e

51. Establish-PGge in alf.Eblows fil Pump >D%sfeharse 2*

4 2

8 0.1 0.8

.06 2.4 1.6 f t2 Puupr Df1sEharge. G 4

2 8

0.1 0.8

13 Pump ptligharge 4

2 8

0.1 0.8

14 Pump Dfecharge,i:

4 2

8 0.1 0.8

15 Pump. Dfekharge - r' 4

2 8

0.1 0.8

52. Weld Root FT.,

11 Pump-D, herge... '

4 2

8 1.05 M.4

.60 24.0 1R.0 j

12 Pump.D1 Mharge 4

2 8

1.05 8.4

'.1 -

13 PumpeDietharge d

4 2

8 1.05 8.4 j

14 Pump D Niharge.;i.'

4 2

8 1.05 8.4 l

815 Pump pfbcharge 2*

4 2

8 1.05 8.4

53. Radiograph-Weld #3 Rock Paae

11 Pump Dideharge ~ h*;

7 2

14 0.05 0.7 3.5 f!2 Pump,Disi;h' rge 7

2 14 0.05 0.7

,a

13 Pump ofeitshrge 7

2 14 0.05 0.7

14 Pump-Di'aiharge e.

7 2

14 0.05 0.1

15 Pump *D b harge

'*7 7

2 14 n.05 0.7

54. Weld Roa.t p u,

c

.I

11 Pueg Dh7 charge

~ * '.

4 2

8 1.05 8.4

.6u 24.0 18.0

12 Pump MMbarge

e.

4 2

8 1.05 8.4

13 Pump plopharge *

-p.

4 2

8 1.05 8.4 4

2 8

1.05 8.4

14 Pump Dibcharge

15 PumM Dt,$ charge

4 2

8 1.05 9.4

' *h,b -

'(.'

y

^*

f.

...4-

s.,

O.s.

4.-

.n

v*

4,.

y-

Nh '

M m

s --

~

i

..g

- w*

i

,t s;.

f. TE.s I

i w.

3 PE2 SAN HEASURCu'

',RT.M/flR gVEs%*.

Has WORKERS PER50st nann

,a Rm cR

[r'

:y

.c

,,mS SATIra;5 DF.r04 NO ESTINATED DECDPI DOSE BATE ESTt*.ATED PROM ORICIIIAL

[

- (b

s* t.f.

AFTER DF.C0ri MAN-RDt ESTIM%fE 1*. ?

A

d:* *

e fit Pump $leDihrge.

5 7

2 14

.05 0.7 3.5

{'

55. Radiograph FL. Root Pase.'

12' Pump Disikerge 1

2 14

.05 0.1

?

2 14

.05 0.7

13 Pump Ote Serge c'.

7 2

14

.05 0.7

14 Pump *DtEgberge

15 Pump Die @ rge. i.

I 2

14

.05 0.7 l

, f.

21 2

42 0.05 2.1 10.5

56. Weld out,.D 4 f J

fil Pump Dishbar,ge

f.

]

12 Pump Dier3afse d-21 2

42 0.05 2.I

13 Pump'bts' charge f

21 2

42 0.05 2.1 l

14 Pump Ot M rge p

21 2

42 0.05 2.1

15 Pump bid $arge 21 2

42 0.05 2.1

~

57. Weld out Di b rae

~

10.5 F 4 * *-

28 2

42 0.05 2.1 fil Pump

12 Pump.htui afge 21 2

42 0.05 2.1

13 Pump'.Dt rae tr.

21 2

42 0.05 2.1 1

i f14 Pump Diednerse 21 2

42 0.05 2.1

+

l

15 Pump *Diebras t

21 2'

42 0.05 2.1 6

3 18 0.43 7.1

.25 22.5 16.0

58. NDE Weldg.3*4~4' b;.

fit Pump VtIs$afge 6

3 18 0.43 7.7

12 Pump.bikclarge

5*.

6 3

18 0.43 7.7 f13 Pump

Die b rae

]

14 Pump.St*stikerge * ::

6 3

18 0.43 7.7

15 Pump Drydbarge

'v 6

3 18 0.43 7.7 2

1 4.

.s ",

s C.

SUBTOTAL-RE' CEMEW offSAFE-ENDS 3608 t590.4 984.3 596.1 t). POST REPAtt JRYwE*L womsr.

59. Remove Comesn'icationg.to Resote Y!aualEhtgIpest j?

7 2

14 0.1 1.4

.06 0.8 0.6

[-

s..b".

j.

60. Besove Teepoh ry Shielde Proe l!

Bloshield $ 1nge

/

l~

11 Pump.Diistharge 20 4

80 0.4 32

.25 100.0 60.0

12 Pump Clyharge 20 4

80 0.4 32 20 4

80 0.4 32

13 Pump D1,4phirge 20 4

80 0.4 12

14 Pump.Di @ rge ej

15 Puep* Discharge *.

20 4

80 0.4 32

61. Remove Support-From ;Regisc Systee

E**

25 6

150 0.05 1.5 7.5

,E:.

.m

62. Remove Turnpischles & Replace 72 3

216 0.05 10.8 10.8 Snubbero# 1.(;*

T.

63. Remove Tempgary 1.tghting 9

2 18 0.05 0.9 0.9

.~t.,.

64. Besove PipeJeetraints:-

O

(.

12 2

24 0.1 2.4

. 0#.

1.4 1.0

S*2...

65. Remove Locejdhleidini;..on sectre LineeZ'

?.

12 4

48 0.175 8.4

.10 4.8 3.6

, e *

66. Instatt InadIntion 24 4

96 0.1

P. 6

. De, 5.8 t.M

. _ i4....

3! *1 9

A

}*

x

.m..

-w.

' s-1.

6'

,f'.

'4s.

b e

Table 2 captioned

1..

n

7. '

NRS u0stEa5 FERSON REMim. rtssoss HE43URrt

Eptht *.

MiniRS No ssat 08 M

FFM

f-SAVilF3 DECOsf NO ESTIMATFD

,* *[.

term

'tiosE RATE ESTIMATED FROM l'RICINAL

. ;;J. --

AFTFR IWCON MAN-REN ESTittATF.

' f? '

4

'.. h* -

T.

67. Replace IAer.forences ~,.

T 36 6

144 0.05 1.2 7.2

.4.

65.RemoveSea,ffpo,

.=

e, e,.

~*w*

J 60 2

120

.05.

6.0 6.0 N

69. Replace Deck M*

12 3

36 0.05 t.8 1S y

.'gg

p.

12 2

24 0.05 1.2 1.2 N

70. Restore Dr 1 ' Interior.,q *

. f;.,.

e*

. e;

. 't:".

- M-D.

Poet Repett Spyuell Work

1290 217.2

,148.2 69.0

. /.p*.

-..s Seabt otal '

r

'g t.

Total - Decfeti Pump. *2' 7024 3981.4 2311.5 1669.9 Discharge.51 6

\\

1.

Y*

...T-l Total - Becithi.Fump J

l Suction SI'de'7*-

6502 1668.2 594.7 1073.5 r _<

'a' 4*

caANDTOTAI.S.1,*

13526 5649.6 2906.2 2743.4 r.

l

/*.

.k l

1..

.c..

+

fs-l

. ig' 4

k

.r3..

3

.y s

i.

yg.

s7

s s.s. -

.g s

P.

j

. ". *s t.

4.

..r's -

<.o.:.

r 1.

t',t.

I.Y.

s'

'me.g.

e V

'..4 e

8

',a.-C **

,{**'

s**

,. r.s 8

- - =;-

..j.

.. q.. -

..x.

~

.a.

4.

.g**

0.P '

g.

C. *

.*2 s

v..

.. i$;s

..,r.'

f n.

/

y :.

e f'

,,(..

i

? t.

,e, e

. F.

c

.%. *y 0-

,-A,

'+j ".

, 6 e-

.r

../

E IIQlRF 1

',I i.

9

gy l

-.J

?4 NINE fille POINT UMIT 1

. f $*..?.

-SAFE END REPL ACEt1ENT GtrAN!/ATION C-

^

d

.f

' ')

r.*

,. v.

CINERAL SUPfR!nTENDENT.NUCLFAR l.

..'1*

)

7.$-

.: q~ y y.

,,s STATIC'l ',UPfRINTENDENT s...

}'

-.,?

r.

(

s.(.

7 Ii 3

l i

- f* -

PROK CT MANAGER SUPERINTENDENT,g CHEMISTRY l;

.M. SAFE Ea0 REPLACEMENT AND RADIATION MM!AGEMENT

(<

. w.- -

:I o

- 4,.

l

.t 6

l l

'I N'e

.~rD l

l RADIOL 0GICAL &

l SUPEitVISOR l

i!

COST V.

NOdPORT NEWS CONSULTANTS CIIEMICAL TECIN EOGT SUPPORT CHEMISTRY &

ALARA CONTROL SCHEDilidhG lN005 TRIAL CORP.

li LGE.MPR.EPR I.ETC. )

CODP02ATION STAFF RA0!ATION PROT.

CINetITTEE l

~.fA

- )1 l

\\'

't

' n..

L*

"3 c ASSISTANT Il

- i. -

4 SUPERVISOR 1

-..r,

}

I I

. p *-

Ll

.- :y(.*

fWC CONTRACT TECH.*;!CIANS TECHNICIANS n.

+.

.y;.

.ap;

.c 3

i

+

.*s y

_.s s

i

. A,.

d.

F.

i

... k,*d.*

r

' f. ~

f

..s..

.f s

,I t

4 5...

. f.**.

b

. p.'

.p-

1-t

.i.-

s e

- '*R. >

1 4 -

.,s h

N':

8 o

g.

~

e. gi*.

Q

.T*

)

4,

+

p.g.

..'s.

- x e..

p

. s.*s..

a y

p*

(

.t

', 6 as y gc Ny

.V

NIAGARA MOHAWK PoYtER CORPORATION /300 ERIE BoulEVAAD WEST. SYRACUSE. N.Y.13202/ TELEPHONE e 74-1511 e

t <a, '\\

v'.

v* < L

'~Q W',

C-Y b.f'?=b m{3 April 30, 1982

.\\

...y k\\.d,d w

Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Ei unhut:

In accordance with your letter of April 21, 1982, Niagara Mohawk submits herein our plans for the Phase I decontamination of the reactor recirculation loops at Nine Mile Point Unit 1.

Phase I consists of decontaminating from the pump discharge valves to the recirculation outlet nozzles. The Phase II decontamination plan, which will apply to the remaining portion of the recirculation loops, will be provided at a later date. A seal plug will be installed in the reactor vessel annulus region to provide a boundary between decontamination fluid and the reactor water. In addition, a four inch hot tap will be placed in the elbow for a flow path.

Figure 1 attached shows a typical recirculation loop configuration. This figure includes all of the piping penetrations into the recirculation loops, the material and the line sizes. Figure 2 is a detail of the hot tap to be u sed.

The method of decontamination to be used on these portions of the loops has previously been described to the Nuclear Regulatory Commission.

In a meeting on August 27, 1981, a proprietary report entitled "Information Requested by NRC Re: Decontamination of Recirculation Pumps at Nine Mile Point Unit 1, March 18-April 14,1961" was provMed to the Nuclear Regulatory Commission by London Nuclear Services, Inc. Section 1(c) of that report is a description of the decontamination process which includes oxygen removal and the passivation step.

7 The only specific item not addressed in that report is flushing af ter i

decontamination. However, Niagara Mohawk believes that the water

/

purification, which is the final steo in the decontamination process, will s((

actually eliminate any concern relative to decontamination fluid in crevices or pipe ends. As can be seen from Figure 1, there are no extensive crevices or long runs of dead end piping, so that removal of decontamination fluid is not-anticipated to be a problem.

lNDNK O

4 xP pop

-_ _~

1 Mr. Darrell G. Eisenhut Page 2 April 30, 1982 The previ'ously mentioned report also contains the range of concentration and composition of the decontamination fluid. The specific range of concentration to be used in Phase 1 is 0.15-0.20 weight percent of reagent

-LND-101A. The temperature range will be 80-900C, and the process will take 12-24 hours per loop. The passivation will take approximately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Niagara Mohawk has investigated the effects of the decontamination process on the recirculation system. The review of appropriate data indicates that the clean surfaces will not be more susceptible to stress corrosion cracking nor will there be increased susceptibility to intergranular attack than now exi st s.

A portion of the test data, which forms the basis of our review, is included in the report provided to the Nuclear Regulatory Connission on August 27, 1981. This data includes crevice corrosion, galvanic corrosion, general corrosion, material condition' (i.e., sensitized, cold worked, etc.),

consequences of long term exposure and the effects of thoroughly decomposed decontamination solutions.

In addition, the fracture mechanics tests which have been performed are summarized in that report.

Niagara Mohawk-has performed an ALARA review comoaring not decontaminating to decontaminating. Assuming decontamination factors of 5 and 10, Niagara Mohawk expects to save between 700 and 800 person rems exposure by decontaminating. Therefore, the benefits of decontamination clearly outweigh the costs.

The overall volume of the decontamination solution for Phase I for each individual loop is approximately 1600 gallons. The volume of the waste resins generated by the decontamination process is estimated to be 15 cubic feet per loop.

The waste resins generated by the decontamination process will be dewatered and placed in high integrity containers. Niagara Mohawk estimates that 15 cubic feet of waste resins, which contain 30-50 curies of activity, will be generated per loop. Since the anion resins portion of the waste (about half the total) contains approximately 2 weight percent of chelating agents, disposal will be in accordance with ' proposed rule 10 CFR 61.55 (i.e.,

Niagara Mohawk will_ discuss with the proposed burial site the concentration of the chelant in the resin and determine acceptability prior to shipping of f site).

A safety evaluation in accordance with the provisions of 10 CFR 50.59 has been performed for this decontamination phase. It is scheduled to be reviewed by the Site Operations Review Committee on May 3,1982 and is available for your review at the site. That safety evaluation concludes that no unreviewed safety issues exist for the process, including hot taos and material. The safety evaluation also states that the conductivity of the reactor water, near the seal plug, will be monitored to assure that decontamination fluid does not leak into the vessel and that no chlorides are leached into the reactor water.

In addition, chlorides will be monitored in the decontamination fluid during the process.

t

~~

o Mr. darrell G. Eisenhut Page 3 April 30, 1982 The only alternative to decontaminating is to effectively shield all the radiation sources. However, evaluating the quantitias of shielding required, it appears to be a cumbersome task at best.

Your expeditious review of this phase of the decontamination effort is reque sted. Tentatively, the elbows are scheduled to be hot tapped beginning May 1,1982, a d the decontamination will begin as soon thereafter as possible.

Please not$ that this letter does not address all of the issues raised in your April 21, 1932 letter. The remainder of the information required to respond to all of those issues will be provided at a later date.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION t

Y T. E. Lemoges Vice President Nuclear Generation GJG:ja Attachment s e

.,__.___T__.

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NuY N,e NIAGARA AtoHAWK PhWER CORPoRAT10N/300 ERIE BoVLEVARo WEST SYRACUSE. N.Y.13202/ TELEPHO May 11, 1982 N ! '"

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Darrell G. Eisenhut, Director

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Division of Licensing

'S Office of Nuclear Reactor P.egulation 7,

U. S. Nuclear Regulatory Comission sg b Washington, D.C. 20555 s

4 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Eisenhut:

Your letter of April 21, 1982 requested that Niagara Mohawk provide plans and schedules for 1) reactor decontamination, 2) mitigation of worker radiation doses, 3) removal and replacement of the safe ends, and

4) justification for resuming operation. This letter is in response to that reque st. The following is a discussion of each of these items:

1)

Reactor Decontamination Niagara Mohawk plans a two phase decontamination of the recirculation loops. The first phase (outlet nozzles to the pump discharge valves) was described in our letter of April 30, 1982. The second phase will address decontamination from the pump suction valves through the vessel inlet nozzles. In order to accomplish the phase II decontamination, an inflatable seal plug, which is being designed at this time, is planned to be utilized. The decontamination process to be used will be similar to that described in our April 30, 1982 I

letter. When the phase II seal plug design and all other details have been finalized, Niagara Mohawk will submit them for your review.

2)

Mitigation of Worker Radiation Doses Mitigation of radiation doses is provided by 1) effective decontamination, 2) maximum justifiable shielding and 3) overall ALARA control. The decontamination process described above, which is a prime mitigation tool, eliminates as much radiation source as is reasonably achievable. Shielding designs, both internal and external, were based upon providing at least equivalent shielding to that which was there from the water prior to cutting. All other specialty shielding (i.e, lead blankets Gver piping, etc.) will beA team J,

reviewed to assure maximum efficiency.

contractor personnel have been assigned the responsibility of maintaining doses as low as reasonably achievable throughout the j[

project. Sufficient workers will be trained and utilized to ensure that individual radiation doses will be minimized.

3 9051? N

.m.- r.u Darrell G. Eisenhut, Director 4j Page 2 May 11, 1982 3)

Removal and Replacement of Safe Ends J

In 1978, Niagara Mohawk realized the potential for intergranular i

stress corrosion cracking in the furnace sensitized safe ends.

Therefore, a contingency project was developed for recirculation safe i

end replacement. That contingency project consisted of developing a 1

replacement specification and draft procedures and the procurement of certain hardware. A portion of the software must now be updated to i

reflect new techniques, such as automatic welding. When the procedures have been finalized, they will be provided to the Nuclear

]

Regulatory Consnission for information.

The planned sequence for removal and replacement of the recirculation outlet nozzle safe ends is as follows:

1 j

1)

Install shield curtains and nozzle shielding - Figure 1 2)

Support the piping system i

3) ' Make two cuts on the outlet elbow - Figure 2 4)

Install internal nozzle shielding - Figure 3 5)

Remove internal shielding 6)

Install new elbow with safe end attached - Figure 4 Due to continued ALARA and/or technical considerations, there may be revisions to this sequence. For example, the safe end may be welded to the nozzle prior to installing the elbow, rather than welding the safe end to the elbow outside of the drywell.

The planned sequence for removal and replacement of the recirculation inlet nozzle safe ends is different than the outlet nozzle safe ends, due to geometry. Following is a list of that planned sequence.

1)

Install external shielding - Figure 5 2)

Cut and remove the inlet elbow - Figure 6 3)

Install shield plug - Figure 7 4)

. Remove the spool piece - Figure 8 5)

Install new spool piece - Figure 9 6)

Remove the shield plug - Figure 10 7)

Install a new elbow - Figure 11 As mentioned in the previous discussion of the outlet nozzle safe ends, this sequence is also subject to change due to ALARA and/or technical considerations.

4)

Justification for Continued Operation Furnace sensitized material cracking has been experienced throughout the industry since the early 1970's. At Nine Mile Point Unit 1, 24 of the original 34 furnace sensitized safe ends on the reactor vessel have been replaced. Unresolved safety issue A-42 has addressed intergranular stress corrosion cracking and determined that this does not create a significant safety hazard to the public. However, it is advantageous to minimize the effects on piping system and thus j.

improve plant reliability.

l

.a Darrell G. Eisenhut, DirIcter Page 3 May 11, 1982 All replacement recirculation material (i.e., safe end, elbows, and spool pieces) will be 316 nuclear grade stainless steel or equivalent. This material has proven to be the most resistant to intergranular stress corrosion cracking. Therefore, all five recirculation systems will be more crack resistant than originally con structed. This is consistent with NUREG 0313, Rev.1.

In addition, the riser to elbow weld will be a heat sink weld. The procedure is currently being qualified.

Attached figure 12 shows the schedule plan for replacing these safe ends.

As indicated, the first decision point is relative to decontamination, which was addressed in our letter of April 30, 1982.

Very truly yours, NIAGARA MOHAWK POWER' CORPORATION

{

D. P. Di se Vice President Engineering GJG:ja 4

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State of New York )

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County of Onondaga )

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DONALD P. DISE, being duly sworn, says:

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I am Vice President - Engineering of Niagara Mohawk Power Corporation. I have read the foregoing letter and the facts contained in the letter are true to the best of my knowledge, information and belief.

I e,dA (2 did Donald P. Dise Sworn to before me on

. this u day of 1982 LA (L.h L Notary Public CYNTHIA A. PffTA won e en. se.

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i i. N3M MIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE. N.Y.13202/ TELEPHONE (315) 4741511 May 24, 1982 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Eisenhut:

In accordance with your letter of April 21, 1982, Niagara Mohawk submits herein our plans for mitigation of worker radiation doses during the safe end replacement outage. Very truly yours, NIAGARA M0 HAWK POWER CORPORATION i / 8Y uw" V>(;~,ypp 2 _ Thomas E. Lempges Vice President - Nuclear Generation SSM:bd Attach. =g y ^^^- ' o a u o (.% 0 -= = L y a. _ 1

NINE MILE POINT UNIT 1 ~ ' NIAGARA MOHAWK p0WER CORPORATION REACTOR RECIRCULATION N0ZZLE SAFE END REPLACEMENT ALARA PROGRAM -~' I. Manrem Exposure Estimates During an April 22, 1982 meeting, Niagara Mohawk provided NRC with manrem exposure estimates for the safe end replacement project. Since that time, Niagara Mohawk has pe'rformed additional analyses to better define these earlier estimates. Our analyses to date indicate th&t the original manhour estimates for certain tasks may be low. This would increase the previously projected manrem estimates. Additionally, radiation measurements taken on May 20, 1982 at the outlet nozzles indicate that the original dose rate projections may be hich by a factor of ten or more. This would decrease the previously projected manrem estimates. Other dose rate estimates, such as those at the inlet nozzle area, are also conservative, since tne original estimates did not consider the current plan of leaving the control rod guide tubes filled with water. Currently outlet nozzle mockup training is being performed. Accurate time and distance estimates will be available from this training. Additional inlet and outlet nozzle radiation dose measurements will be taken to better define the radiation fields. This data will be used to provide bases for more accurate manrem exposure estimates. Based on the aforementioned, revised manrem estimates factoring in the latest manhour estimates, actual dose rates, and recently developed shielding techniques will not be available until June 15, 1932. II. Radiation Protection Staff The radiation protection staff will be increased to accommcdate the needs expected.!uring the safe end replacement outage through the use of contract persornel. Additionally, as outlined below, contractor specific health physics staf fs will also be utilized. Radiological and Chemical Technology Corporation will provide onsite consulting services for the duration of the outage. They will be used to: A. Review source terms for shielding design, designate in vessel confinning measurements required to validate design, and document impact of the results of these measurements on shield design or safe end replacement. B. Rcview ALARA procedures for safe end replacement and related activities. C. Review dose rate measurements and/or calculations and advise site personnel regarding adequacy of procedures and recommend changes when required. D. Perform any other activities related to health physics and chemistry on request. l

g Newport' News Industrial Corporation will provide a radiation protection staff to support their work on the safe end replacement project. A Tdescript. ion of.their ALARA Program, which includes a job description for "the radiation protection coordinator, is provided as Appendix 1. In addition'to'the, radiation protection coordinator, the staff will include an ALARA clerkjand a drywell coordinator for each shift. The ALARA J clerk will tabulate hours and exposures for all jobs. This data will be f - tracked to.a'ssure exposure guidelines are not exceeded. The drywell b+ coordinator will check for correct protective clothing, serve as a timekeeper / time study coordinator, and keep a record of areas where improvement is possible. Additional clerical personnel will be assigt.ed to perform dosimetry activities. Exposure reports will be issued twice a day and 24 hour coverage will be provided fcr thermoluminescent dosimeter readings. III. ALARA Comittee Tha ALARA Committee will detennine the costs, both in exposure and ,w ' dollars, and the benefits of all dose rate reduction options (i.e. c C shielding, decontamination, or not doing the erk). They will provide guidance and recomendatious on alternatives.a further reduce manrem expowre s. The Comittee consists of the Superintendent of Chemistry ar.d Radiation Management, the Radiological Engineer, the Dosimetry '~. Coordinator,~ the Corp 0 rate Health Physicist and representatives from Radiological and Chemical Technology Corporation and Newport News Industrial Corporation. Additional staff personnel (Supervisor, Chemistry and Radiation Protection or assistant, Respiratory Protection ' Coordinator, etc.) will be included when required. 10 Additional Equipment Utilized to Reduce Radiation Exposure Mock-up training will be used to reduce the in drywell manhour i requirements and ensure that procedures, tools and equipment will function efficiently during actual work. Appendix 1 summarizes additional infc sation on mock-up training. Audio-visual communication equipment will be utilized at the job location so that supervisors can direct work activities from low radiation areas. Automated equipment such as pipe cutting machines, welding equipment, recirculation inlet nozzle plug installation tools, and weld crown reduction tools will be used in the drywell. Appendix 1 sumarizes ? - ' ' additional infonnation on these tools. + 3 )\\ Respirators (both full, and half face mask) with neck microphones will be r, O utilized to facilitate comunication in the drywell. Half face respirators will be~ utilized when conditions warrant. These devices m will reduce the encumberance associated with respirators and improve .Thorkerefficiencyinthedrywell. Respirator fit test reports will be issued to the drywell coordinators so they can check that all persons 4 required to wear respirators have passed the fit test. W. i. % .I. 4 7 m -

For tasks which could result in airborne radiation, portable ventilation equipment will be used. Shielding will be used to reduce exposure in the drywell. This shielding will include: A. Specialty shieldi.ng such as inlet and outlet plugs and shield curtains. B. Guide tubes filled with water. C. Exterior shielding such as between the biological shield wall and the nozzle. D. 0ther shielding as recommended by the ALARA Committee. Ot'her ALARA options under consideration include: A. Using a seal plug in the inlet nozzle. This is being reviewed by the ALARA Committee.

8. Keeping the annulus filled with water while working on the inlet nozzles.

C. Utilizing decontamination as much as possible. At present it is expected that decontamination'will be performed on the outlet and inlet piping by use of decontanination connections at the pumps. The actual decontamination will be accomplished by raising and lowering the level of the decontamination solution in each recirculation line. V. ALARA Program Niagara Mohawk's Radiation Protection Training Program and Procedures were developed using regulatory guides 8.4, 8.8, 8.10, 8.13, 8.26, 8.27, and 8.29 as a basis. 'Due to the length of these documents, a line by line comparison between the regulatory guide r2quirements and Niagara Mohawk practices and procedures is not provided. Specific areas of concern will be discussed with members of your staff during the upcoming site visit. e ?g 9 1 u.

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h 5 9 r . ~ m[p su,,s. t- -= ./ +Q "-W 4 AJ m., e ?d?~ .6?$ Vi??$d ~$Y ~*:. NUMSER ALARA ?ROGRAM DESCRIPTION FOR REFLACDfENT OF RECLRCULATION ' SAFE ENDS AT NINE MILE POINT 1 NUCLEAF. GENERATING PLAhT [ '. i ,,g i,s

m. g f J!--....:.a asj REVISION DATE vv 9-tce a

PREPARED BY t 'r cn==" #a ~ REVIEWED BY APPROVED BY AUTHORIZED BY dUSTO MER APPROVAL Newport News industrial Corporation Subsidiary of Newport News Shipbuilding 6 ATerwisco Correony

I. -INTRODUCTION All efforts to perform a task in a'n ionizing radiation environ =ent with a minimum total exposure to personnel can collectively be called ALARA eff. orts (As Low As Reasonably Achievable). The ALARA program, does not impose quantitative limits on exposure but rather establishes a philosophy to try to maintain exposures as low as possible by examining all possible alternatives and deciding upon the best solution. However, the maximuL reduction in radiation exposure cannot be the only criteria to establish the best ALARA Program. The " reasonably achievable" repect of the ALARA Program must take into account other parameters such as etct, time, and final quality required of the finished product in order to make tha ALARA Program realistic and workable. The following description of the ALARA Program will describe planning, pr:paration, and implementation efforts which will be used fcr the modifications to,the Niagara Moha'sk.Nine Mile Point 1 Recirculation System. irs t '-'5 44.i1. in\\. 2; .II. PLANNING AND PROCEDURES 7, N 4 t ! a (,i g y,. . 4 .a . >=e g. A. Selection of Methods, Processes and Techniques Prior to establishing written procedures, a selection of various methods, processes and techniques will be discussed and evaluated for several factors, four of which are discussed below. The four groups responsible for review (Field Service, Design Engineering, and Quality Assurance) will = = 4ne the various alternatives presented, point dut the advantages and disadvantages of each alternative and decide the most desirable choice. Four parsmeters considered in deciding the most desirable choice are: 1. Radiation Exposure - Any technique being discussed should be evaluated on the basis of the collective radistion expended as well as individual exposure estimates. These estimates of radiation exposure should be compared to the ther alternatives exposures estimates. A technique that causes excassive exposures compared to other equally acceptable alternatives will be discarded as not meeting ALARA objectives. 2. Cost - The cost of a particular choice must be considered in any analysis. Excessive costs to save a little exposure may not be a " reasonably achievable". alternative. Previces experience on major repair and maintenance outagea, at nuclear plants generally shows that reasonable raji > logical control procedures are cost effective in the final analysis. 3. Time - The tf% spent to complete a specific technique or method can be apprcached from tvo viewpoints. The first viewpoint looks at the length of time a, particular technique will take overall (i.e. how long it will extend the outage as compared with other alternatives). The second viewpoint looks at the length of time a particular technique requires personnel to remain in high radiation areas. The more time a method or technique can save, the more attractive it may be from an ALARA standpoint. 2 a- -~ -+ .----,,--n~-- n

'4. Quality Control - The quality control aspects of a particular technique may be of utmost importance if there is a direct impact on plant safety or integrity. On the other hand, if items worked on will be scrapped, quality control may be of little or no significance. B. Procedure Development once the techniques, methods. or processes have been decided upon, detailed procedures are written by the appropriate planning or technical group. Each procedure is intended to be a complete document in itself and should contain a minimum of references to other control procedures. Special precautions, prerequisites and radiological protection requirements will be as explicit as possible and clearly merked or identified. Each completed procedure is then reviewed by the appropriate groups. Each review group shall be responsible for determining that the procedure contains adequate information in its field of responsibility. A final review of the procedures will be performed once all comments from review groups have been completed. Signoffs shall be done at this time as appropriate. All procedures developed by the contractor will be submitted for review by the Site Operations Review Committee or SORC. which includes a Quality Assurance Review and ALARA Reviet.. +s e III. ADMINISTRATIVE CONTROL {., , g,,, ). ;-,;\\ ; An NNI Radiation Protection Coordinator is assigned by the contractor-to serve on the Project Manager's staff. One of his major functions is to discuss ALARA objectives with personnel. A.The NNI Radiation Protection Coordinator will call pre-planning meetings at logical points during the outage to discuss ALA1A objectives and radiological probicas associated with the job. Meetings of this type will be called whenever: 1. A major task is about to be undertaken. 2. A recirculation line is about to be breeched. 3. Radiation Levels in the work areas have significantly changed. The meeting will be held in order to discuss ways to reduce exposures. Major points covered will be: 1. Identifying targets where exposures could be reduced. 2. Dividing the job into smaller. easier to handle work packages. 3. Identification of High and Extremely High Radiation Areas around work areas. 4. Assigning responsibilities for actions to be taken. 5. Review of particular job assignments to insure everyone understands their job functio'n. Af ter completion of work, a post-task ALARA review will be held. The radiation Protection Coordinator will schedule and chair this meeting. This meeting will discuss the success of the actions taken as a result of the pre-job meetings and suggests improvements that could have lowered exposures even further. 3 \\

B. In addition, the NNI Radiation Protection Coordinator's other job functions are: 1.- Maintain an overall kncwledge of work in progress and the general radiological conditions associated with this work, / 2. Attend Plan-Of-The-Day meetings and serve as liason between' functional groups on matters of radiation safety. / 3. Provide technical assistance on radiological safety problems.

4.. Keep project manager informed of radiological safety problems and the action being taken to resolve these problems.

5. Review radiation surveys performed by plant personnel so that general exposure levels and local hot spots in the work area can be identified. At this cdme, shielding and other methods of reducing radiation levels can b.e discussed with plant Health Physics personnel. 6. Discuss most efficient ingress and egress routes for personnel at work sites. 7. Review work on a continuing basis. He shall work closely with plant Res1th Physics and craft foremen to be sure they are aware of Man-Rea budgets and actual totals for the various portions of the work being performed. 8. Keep track of individual and collective exposures on a daily basis. Work with craft foremen to utilize craft labor in order to equalize exposures as much as possible. IV. TRAINING AND ORIENTATION P~ "' ' - a s -r t A. Radiation Training-3 All personnel will be required to attend the Radiological Safety Class at the Nine Mile Point Training Center before being allowed to work on site. B. Specialized Equipment Pipefitters and welders will be given extensive training on specialized or unfamiliar equipment such as pipe cutting machines and automatic welding equipment. Training will concentrate on set-up and removal operations for the equipment. Since the set-up and removal times are usually very time consuming, significant radiation exposure savings can be achieved by performing these operations as efficiently as possible. Once personnel have become familiar with the machines and their operations, training vill move to the mock-up facility. C. Mock-up Training A sock-up facility will be fabricated in order to simulate the work area around the recirculation pump suction and discharge no::les as closely as possible. The training in the mock-up will include the use of anti-contamination and respiratory equipment which will be prescribed for work in the drywell depending on which operation is being performed. In general, the mock-up training is intended'to accomplish the following objectives: 1. Familiarize trade workers with che physical orientation and 4 l

rccccinto of tha work crcs. 2. Confirm that tools and equipment will function as intended and no additional items are needed. 3. Identify possible ways of improving or simpl>fying the task from the standpoint of job performance, quality control and radiological control. 4. Determine that temporsry shielding or contamination control arrangements will function as intended and will not be counter productive with respect to ALARA objectives. V. RADIATION EXPOSURE CONTROL y , y; jc 3 r' A. Man-Rem Estimates and Applications 2 W'LiG h '.! 1 l An estimate of the collective radiation exposure for the recirculation safe-end replacement will be made in order to establish manpower needs in crucial areas of high radiation levels where skilled personnel must work. This attimate will also assist management in determining areas of emphasis for the use of temporary shielding. The conective estimated exposure win be measured in units of Man-Rem and win consist of a summation of an individual tasks. Man-Rem subtotals for each task will also be used as a guideline figure for comparing actual Man-Rem accumulations to the estimated Man-Rem during the course of the project. Variation.s win occur from the original job scope and these must also be considered when comparing cetuni and estimated Man-Rem totals. Periodic evaluations will be perfor=ed as a planning aid to determine the adequacy of craf.c manrover available to perfor'm skin ed work in high radiation treas. B. Radiation exposures will be measured daily and added to previous accumulations in order to control individual exposures within established limits for each calendar o.uarter. Daily exposures win also be grouped under various job categories so that cumulative Man-Rem exposures can be measured against estimated Man-Rets. This win help to evaluate the effectiveness fo the ALARA Program. C. Temporary Shielding will be used in those areas where it can be shown to be effective in minimizing radiation exposures. When temporary shielding is being considered, it must be shown that shielding installation, maintenance and removal will not exceed the projected Man-Rem savings. The decision in any particular area must include the following factors: 1. Detailed radiation surveys of the work areas are needed to identify general background radiation levels; radiation levels about 1 foot from the surface of the radioactive component and radioactive component surface radiation levels. " Hot Spot" accumulations of radioactivity shottid also be identified in these surveys. 2. An estimate must be made of the number of individuals who will -~ occupy a particular work area and the length of time to be spent in these areas. 3. The number of skilled craf tsmen needed t6 complete a job in certain areas deserves special considerations. Shielding may be required in certain locations in order to protect a limited number of skilled workers. S 1

4. Some areas with low radiation levels may be shielded if it can 'be shown that this area will be occupied by large number of people for unusually long-periods of time. 5. Shielded work spaces may be more desirable in some instances when the background radiation is coming from all directions rather than trying to shield an entire work area. 6. The flushing of " Hot Spots" will be considered as an alternative to shielding. If flushing is a feasible operation, it will be attemnted before shielding is erected. Nozzle Shield Plugs will be inserted in the recirculation nozzles (pump suction and pump discharge) as soon as the elbows are severed and removed from the area. The plugs will reduce the " beam" of radiation eminating from the lower core support plate at the pump suction nozzles and from the activated core structure at the pump discharge nozzles. These plugs will be removed just prior to fitting up of the new recirculation elbows. D. Designated " Stand-by" areas should be established for the purpose of minimizing radiation exposures for people who are "on-call". These stand-by areas will be selected ;-imarily on the basis of the lowest backgound radiation levels. Personnel on-call will remain in these stand-by areas dressed in anti-contamination clothing until they are needed in the work area. This will reduce delay in the job due to a change in shifts or personnel requirements. E.Special controls vill be applied to all areas which are classified as high radiation areas (greater than 100 millrem per hour). Access to such areas will be restricted to keep personnel from receiving inadvertent exposures. P.As much pre-installation work as possible on the recirculation loop will take place in non-radioactive areas. 1. Weld preps and oth:r machining on the safe ends, spool pieces and elbows will be don < outside radiation areas. 2. A template will be used to measure for the spool piece between the riser pipe and safe end. The template will be removed from the dry-well following templating and will be used to machine the spool piece in a non-radiation area. This practice will minimize the pipe fitting time spent in the radiation area. ? VI. CONTAMINATION CONTROL

' w.d d if h3 6.li.,, j A. Anti-contamination clothing and equipment will be worn routinely for entry into the containment and other areas designated as contaminated.

Additicnal protective equipment will be prescribed on the Radiation Work Permits f,or unusual contamination conditions which may be encountered. B.The recirculation loop will be chemically decontaminated ati the beginning of the outage in order to reduce radiation and contamination levels. Since the recirculation loop is a major con ributor to general background levels in the drywell, the chemical decontamination is expected to. contribute to the -sadriation of these levels. s rEducth 6 e

C. Portable filtered exhaust ventilation will be used as a control measure to reduce the possibility of airborne contamination from any operation which cocid cause particulatas to become' airborne. t D.Ageneral policy of wrapping cone==4nated materials, items, components or tools in plastic bags or sheets will be followed. This practice is sinactive in minimizing the spread of radioactive particulates when these contaminated items are being transported from one area to another. Clean items brought into the vessel an'd removed again shall also be wrapped while in the cone==4nated area to prevent uneccessary contamination of the item. E. Emphasis will be placed on good housekeeping practices throughout the project to maintain a reasonable state of cleanliness. This will help to keep cont==4 nation from spreading and also assist in keeping background l radiation as low as possible. h, t,; u y VII. TOOLS AND EQUIPMENT & 6 %ggg,g g y Tools and equipment used in the drysall were all designed and/or selected to function simply and efficiently with a minimum of difficulty. Some examples of the specialized equipment and tools include: A. Automatic Welding Equipment will be used in the drywell to help reduce exposures. The welding equipment used is intended to =4n4=fwe operator exposure and produce a high quality weld which should need little or no repair effort. B.. Pipe cutting machines will be used to cut the recirculation pipe in the drywell. Cutting machines are designed to cut, weld prep and counterbore from the same basic set-up. This eliminates the-set-up and disaaembly times for separate machines plus produces an accurate we1d p?.ep and counterbore since all operations are ~ made from the same set-up. The cutting machine feeds automatically whcih allows the ciarator to move to a lower radiation area while the machine is running. C. Pump Discharge Shield Plug Installation Tool - Used to install shield plug automatically in the pump discharge nozzles. Ensbles workers to move away from the radiation beam coming from the core. ) VIII. REFERENCE A."Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low As Reasonably Achievable t (ALARA)", U. S. Nuclear Regulatory Commission, Office of Standards Development, Regualtory Guide 8.8 7 9

i'- p ' M V NIAGARA s ' RUMOHAWK NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE. N.Y.13202/ TELEPHONE (315) 474-1511 I August 6, 1982 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Eisenhut:

On May 11, 1982, Niagara Mohawk provided information on the replacement of the recirculation safe ends at Nine Mile Point Unit 1. That letter was in resoonse to your letter of April 21, 1982. The purpose of this letter is to confirm previous verbal communications with members of your staff that we plan ~ to replace all the 28-inch recirculation system piping. The basis for Niagara Mohawk's decision to replace the recirculation Diping is provided herein. Chronology and Conclusions On March 23, 1982, through wall cracks were detected in two of the ten recirculation safe ends. On March 26, 1982, ultrasonic examinations were performed on these two safe ends and one other. The results of those examinations confirmed crack indications. Based uoan that information, Niagara Mohawk decided to reDlace all ten safe ends. In mid-Aoril, 1982, two boat samples were obtainea from one of the safe ends in the vicinity of the through wall cracks. One each of these samoles was sent to General Electric and Battelle Laboratories for evaluation. The results of those evaluations in mid-May confirmed the presence of intergranular stress corrosion cracking. Prior to receiving the results of the avaluations from Battelle and General Electric, other Dhenomena were evaluated by Niagara Mohawk as potential mechanisms for crack initiation. These evaluations were used on a qualitative basis to determine high stress areas of the recirculation piping system under various ooerating scenarios (i.e. locked Dumo snubbers, etc.). Based on these evaluations, it was accided to examine by ultrasonic methods the pumo discharge casting to riser elbow weld. Using normal ultrasonic methods, it was determined that two of the five welds had coae reportable indications. When increased ultrasonic transducer gain was used, the remaining three welds exhibited indications. 06( .gf6h130195 820806 PDRADOCK05000g e c<.-- \\

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Au' gust 6, 1982 Page 2

-The two pump discharge casting to riser elbow welds with normal ultrasonic indications were later examined by dye penetrant methods on the inside ciameter. The results of those examinations indicated the presence.of cracks. In early May,~1982, a replicattor, process (i.e., obtaining a negative of the crack with a piece of #11340 celluose acetate tane) was implemented. The results of General Electric and-Niagara Mohawk's review indicated the presence .of intergranular stress corrosion cracking. A boat sample of that same region (taken en June 13, 1982) _was evaluated by Sylvester Associates and confirmed the presence of intergranular-stress corrosion cracking. -Based upon the confirmation of cracking at the safe ends and the pump discharge casting to riser elbow welds, it was~ decided to ultrasonically inspect all of the remaining welds, where the radiation fields permitted. The results of those examinations indicated cracking in a large number of welds. In most cases, these indications could only be obtained when using the increased gain _ ultrasonic technique procedure. Attached Figures 1 through 5 outline the location of all welds in the recirculation loons. Table 1 summarizes the examinations and results of the examinations. Based on the results of our examinations and investigations, it was decided to replace the 28-inch recirculation piping. Preliminarily, it appears that it will be advantageous to replace branch piping also. However, all of the technical issues have not yet been resolved. Therefore, no final ~ decision nas been made to replace this branch piping. Replacement Program All replacement material will be 316 NG or equivalent, with a carbon content of less than 0.02 percent. This material is of the grade which does not require augmented in service inspection per NUREG 0313, Revision 1. The replacement safe ends were manufactured in 1979 to the 1977 ASME Boiler and Pressure Vessel Code Section III_ (adcenda through sumner 1977). The rernainder of the piping was ordered and is being manufactured to the 1980 code through winter 1980 Addenda. The actual replacement will be accomplished in accordance with IWA4000 and IWB4000 of ASME Boiler and Pressure Vessel Code, Section XI, 1977 addition (addenda through suruner 1978). All welding will be in accordance with Section IX,1978). The fit uD requirements Will be in accordance with ANSI B31.1-1977 (wich addenda through winter 79) code for preisure piping. Since the configuration of the: system will be the same as the original design, Niagara Mohawk does not intend to redo the existing stress analysis. The seismic design criteria are as specified in Section III of the Final Safety Analysis Report.

..u e o Au' gust 6, 1982 Page 3 Nondestructive examination requirements for field welds which are applicable to this replacement are as follows: Radiograohic and Dye Penetrant Section III of ASME Boiler and Pressure Vessel 1977 Summer 1978 addenda Ultrasonic Section XI 1977 Summer 1978 addenda The replacement methodology is in the orpcess of being develooed. Preliminarly, the method of replacement is to dismantle all of the oiping in all five loops. from the pump uo.The loop furthest from the equipment hatch would be rebuilt, and fit up, on both inlet and outlet sides of the loop.The uppermost elbows Rebuilding of the loops would continue until the final 1000 (closest to the equipment hatch) is completed. A revised occupational dose estimate for the expanded scope of work will be included with the next quarterly repair program status as required by paragraohs 2.D.(6) c ano d of our coerating license. Very truly yours, NIAGARA M0 HAWK POWER CORPORATION 7 T. E. Lemoges Vice President Nuclear Generation GJG/kmb - ~.: O mca .yg__,_ -am m ~

( o TABLE 1 Ultrasonic Dye Penetrant Examination Examination Weld No. (UT) (PT) Results(I) No. 11 Recirc.-Loop P32-FW-1-W Not Inspected P32-SW-1-W Not Incpected P32-SW-2-W ~~ X -~ UT Indications (Increased Gain) P32-FW-2-W X UT Indications (Increased Gain) P32-FW-3-W X UT Indications (Increased Gain) P32-SW-3-W X UT Indications (Increased Gain) P32-FW-4-W X UT Indications (Increased Gain) P32-FW-26-W X UT Indications (Increased Gain) P32-SW-17-W Not Inspected P32-FW-2 5-W Not Inspected P32-SW-16-W Not Inspected P32-SW-15-W Not Inspected P32-FW-23-W Not Inspected P32-FW-22-W Not Inspected No. 12 Recirc. Loop P32-FW-5-W Not Inspected P32-SW-4-W Not Inspected P32-FW-6-W X UT Indications (Increased Gain) P32-FW-7-W X UT Indications (Increased Gain) P32-SW-5-W X UT Indications (Increased Gain) P32-FW-8-W X UT Indications (Increased Gain) P32-FW-31-W X UT Indications (Increased Gain) P32-SW-20-W Not Inspected P32-FW-30-W Not Inspected P32-FW-29-W Not Inspected P32-SW-19-W Not Inspected P32-SW-18-W Not Inspected P32-FW-2 8-W Not Inspected P32-FW-27-W X Code UT Indications Plus Leaks (1) Where increased gain is indicated, the normal code ultrasoni: examination showed at least one reco-dable defect indication. However, using an increased gain, intermittent indications were observed along the circumference of the inside diameter.

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~ ~ ~ ~ _. - ,,_., y.m y. y,. .._. y _m, _._. __ m __.1.. .c. .a, .m..m V TABLE 1 (Continued) Ultrasonic Dye Penetrant Examination Examination Weld No. (UT) (PT) Results(l) No. 13 Recire. Loop ^' P32-FW-9-W Not Inspected P32-SW-6-W Not Inspected UT Indications P32-SW-7-W X (Increased Gain) UT Indications P32-FW-10-W X (Increased Gain) UT Indications P32-FW-11-W X (Increased Gain) P32-SW-8-W X UT Indications (Increased Gain) P.',2-FW-12-W X UT Indications (Increased Gain) P32-FW-36-W X X UT Indications (Increased Gain) PT Indications P32-FW-35-W Not Inspected P32-FW-34-W Not Inspected P32-SW-22-W Not Inspected P32-SW-21-W Not Inspected P32-FW-33-W Not Inspected Code UT Indications P32-FW-32-W X No. 14 Recirc. Loop P32-FW-13-W Not Inspected P32-SW-9-W Not Inspected UT Indications P32-SW-10-W X (Increased Gain) UT Indications P32-FW-14-W X (Increased Gain) UT Indications P32-FW-lL-W X (Increased Gain) P32-FW-11-W X UT Indications (Increased Gain) UT Indications P32-FW-16-W X (Increased Gain) UT Indications P32-FW-41-W X (Increated Gain) P32-SW-26-W Not Inspected P32-FW-40-W Not Inspected P32-FW-39-W Not Inspected P32-SW-25-W Not Inspected P32-SW-24-W Not Inspected P32-FW-38-W Not Inspected P32-FW-37-W Not Inspected

l TABLE 1 (Continued) Ultrasonic Dye Penetrant . Examination Examination Weld No. (UT)- -(PT)- Results(l) No. 15 Recire. Loop P32-FW-17-W Not Inspected ~~ P32-SW-12-W X X UT Indications (Increased Gain) PT Verification After Removal P32-SW-13-W X UT Indications (Increased Gain) P32-FW-18-W X UT Indications (Increased Gain) P32-FW-19-W X UT Indications (Increased Gain) P32-FW-20-W X UT Indications (Increased Gain) P32-SW-14-W X UT Indications (Increased Gain) P32-FW-21-W X UT Indications (Increased Gain) P32-FW-46-W X X Code UT Indications PT Indications P32-SW-30-W Not Inspected P32-FW-4 5-W Not Inspected P32-FW-44-W Not Inspected P32-SW-29-W Not Inspected P32-SW-28-W Not Inspected P32-FW-43-W. Not Inspected P32-SW-27-W Not Inspected P32-FW-42-W Not Inspected Through Wall Crack (Leakage) mm - n,. ,p_ - -.., - ~. ~ - - -... = -, - ~

FIGURE I RECIRCULATION LOOP NO.11 MATCH LINES \\N [ \\ s P32-FW-1 -W l l J [~-- ~~ P32-SW - t -W /[ '.A (l SAFE END I P32-SW-2-W/ P32-FW-22-W t C P32.- FW W ~ ,J 1 r P32-SW W I l REACTOR REClRC SAFE END P32.- FW-2 -W

PUMP NO. I'l t

P32-SW W E / T I --~ P32-FW-3 -W g 'l P32 - FW W I l [ P32-FW W g P32 - SW w 1 ] [ REACTOR VESSEL if 'g r P32-SW-3 -W g 4 't x \\ P32-FW-26-W '~ P 32 - FW W t T E E N_N ' M -v r1 % v-~.w,r-, w, %,,,,, _,

1 FIGURE 2 } RECIRCULATION LOOP NO,12 MATCH LINES X 7 P32-FW-5 -W P32-SW-4 -W h 1 SAFE END I P3 2-FW-27-W l P32-FW W y P31-SW -I B-W l \\ EAFE.END l REACTOR RECIRC . PUMP NO.12 t 232-SW W P 32-FW W C / h 1; --~ P 32-FW W l \\~ A 4 > P32 -FW W \\ f 9 ~ P32 - F W W P32 - SW W g --l h l cc P32-SW W l {y x i \\ P32 - FW-31 -W ( P31-F W-8 -W l --m - r_~ r_m_ re_m_, ._.m_ m _,,,,,.

n__.._-------;----- FIGURE 3 ~ RECIRCULATION LOOP NO,13 MATCH LINES [ \\ ' P32-FW-9 -W P32-GW-6 -W i l SAFE END l P32-FW W P32-SW-7-W l h P32-FW W A y P32-sw-21 -W l \\ I R'EACTOR. RECIRC SAFE END . PUMP NO.13 c P32-SW W P32-FW-IO-W / \\ 'C '"~ P32-FW-i l -W 'l A i P32-FW-34-W I h P32-FW-3 5-W \\ IP32-SW W i i j [ REACTOR VESSEL i i y I P32-SW-8 -W l [t A \\ P32-FW-36-W k P32 - FW W e% - - ~ w ; m m m _-_- r g _ _+ - m m - - - -..r-m- - ~~-

~ FIGURE 4 ~ RECIRCULATION LOOP NO,14 MATCH LINES [ N P32 - FW-13 -W .P32-SW W [l SAFE END l P32-SW-10-W/ P32-FW W l P31-FW W 1 r P32-SW W j \\ 1 l REACTOR. REClRC SAFE END ~ ~ ~ ~ P32-FW W h 'G P32-FW-15-W l P32-FW W l I k P32-FW-40-W I \\ !P32-SW-26-W j g REACTOR VESSEL y P31-SW -il -W l C -- - - 3 \\ \\ P32-FW - 4 l-W N i P3 2.- FW W . v::.,... wn m,, cr:n-or~ v v:ve =~ -.-~---,-:.~ --

A =- .x FIGURE 5 ~ RECIRCULATION LOOP NO.15 ~~ MATCH LINES 7 \\ I P 32 b FW-17-W l y _r e ~~ -~ P32 -SW-12 -W l h [ h u l SAFE END P32-SW-13-W 1 h (~ P32-FW-42-W I , P32-FW-18-Wf '~ P32-SW-27-W A 1 r P32 -FW-43 -W I \\ l -s N i sgpp_. ggt R~EACTOR. RECIRC P32-SW-2 8-W

FUMP NO.15

( \\ P32-FW-19-W c' P31-SW W -~ P32-FW-20 -W c l g k A i P32 -FW-4 4 -W l V Q ~ P32 - FW-4 5 -W i y i 7 P32 -SW-30 -w i f [ REACTOR VISSEL P 32 -SW-14-W l { -- h 1 \\ P32 - FW - 4 6 -W N] P32-FW W s k --..--r. n.= -., - - e --.. n -,,., - ..---=~--c-.--...-----.-..,

d* u. _.7a._.._... u _ :_ u. m n _... a.; 2 - m __._....__u_.2 =a j _.w 1 N M eiN& NIAGARA MOHAWK POWER CoRPORAT1oN/300 ERIE BOULEVARD WEST. SYAACuSE. N.Y.13202/ TELEPHONE (315) 4741511 August 16, 1982 Mr. Darrell G. Eisenhut, Directo'r Divi sion of Licensing Office of Nuclear Reactor ReQulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket NO. 50-220 DPR-63

Dear Mr. Eisenhut:

Our letter of August 6,1982, provided informa' tion regarding preliminary plans for replacing all of the 28-inch recirculation system piping during the current outage at Nine Mile Point Unit 1. During a meeting of August 13, 1982, members of your staff requested additional information regarding piping repl acement. The requested information is provided herein. ALARA Prooram Our letters of May 24 and June 1,1982, provided plans for the mitigation of worker radiation doses during the safe end replacement outage. These plans were reviewed by your staff and found acceptable as described in your letter of June 18, 1982. This transmitted Amendment No. 49 to our operating license and your Safety Evaluation Report. This ALARA Program will also be utili7ed for the mitigation of worker radiation doses during the 28-inch recirculation system piping replacement. Use of this pre-approved ALARA Program for this additional portion of the project will assure worker radiation doses will be kept as low as reasonably achievable. Man Rem Exoosure Estimate Our letter of June 1,1982, provided a man rem exposure estimate for the safe end replacement project. The total man rem exposure estimate projected for the 28-inch recirculation system piping replacement is currently being developed. Provided on Table 1, Task Person-Rem Summary Report, is the man rem exposure estimate for the disassembly of Number 15 reactor recirculation loop. This will be the first loop to be disassembled. hof 6 0816 PDR ADOCK 05000220 P PDR

r t.a.x.210.a : NN N ,...he *

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>.a { >.' h*- - Mr. Darrell G. Eisenhut Page Two Man rem exposure estimates for the remaining loops will vary due to the unique attached piping arrangements of each loop. These man rem exposure estimates will be provided prior to the disassembly of the remaining loops. Although the total man rem exposure estimate for the 28-inch recirculation system piping replacement has not been finalized, it is anticipated that the total man rem exposure estimate provided for the safe end replacement project will bound this additional work. This is expected since the existing recirculation piping, which is a large source of radiation, will be removed from the drywell. This will decrease the prior man rem exposure estimate for the safe,end replacement project. The man rem exposure estimate for the 28-inch recirculation system piping replacement is expected to be less than the man rem savings associated with the elimination of the recirculation syste'm piping in the drywell. Therefore, it is anticipated that the total man rem exposure estimate for the safe end replacement project will bound both the safe end and 28-inch recirculation system piping replacements. .Upon completing your review, disassembly of number 15 reactor recirculation loup will commence. As indicated above, the remaining man rem exposure estimates will be provided to you for review prior to the disassembly of the remaining loops. Very truly yours, NIAGARA M0 HAWK POWER CORPORATION C. V. Mangan Vice President Nuclear Engineering & Licensing SWW:od i PNhaau%'.gpo.,mem powemmenmeer see =e> * -==e--

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~~SUMMARY~~
REPORT DATE 08/16/82 PAGE 5 '. .j s TASK DESCRIPTION PERCENT ACTUAL TOTAL EST CURR EST CUR EST ACTUAL TOTAL EST CURR EST PERSON YASK COMPLETE PERSON PERSON PERSON MINUS PERSON PERSON PERSON HOURS '[* REM REM REM ACT HOURS HOURS HOURS DIFFERENCE,,- g PERS-REN 4.. j S 4, ' !' l GRAND TOTALS sessssssssssssssssssssssssssssa 1.978 120.290 .000 . 978-55.50 1643.00 .00 55.50, ..J. .l t =, n 4 f, il i' se, m...., m .%e e. =q....v.**.g* t 4*- 9e.. a=*
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(A ~. p.3 3 N U MOHAM: Y NIAGARA ? 1 NIAGARA MOHAWK PoiNER CORPORATloN/300 ERIE BOULEVARD WEST. SYRACUSE. N.Y.13202/ TELEPHONE (315) 474-1511 1 al, d September 27, 1982 l 'i Mr. Darrell G. Eisenhut, Director 'j Division of Licensing Office of Nuclear Reactor Regulation a l U.S. Nuclear Regulatory Commission j Washington, D.C. 20555 d Re: Nine Nile Point Unit 1 Docket No. 50-220 DPR-63
~~Dear Mr. Eisenhut:~~
Our letters of August 6,1982, August 16, 1982 and August 26, 1982 1 provided information regarding our plans for removal and replacement of the 2] reactor recirculation system piping. During a meeting on Septembet 22, 1982 members of your staff requested additional infonnation regarding the replacement program. The requested information is provided herein. 1 Man-Rem Exposure Estimate Our letter of August 26, 1982 provided a man-rem exposure estimate which addressed safe-end replacement and disassembly of the five reactor recirculation loops. At that time, the man-rem exposure was estimated to be approximately 2036 man-rem, excluding exposure associated with recirculation pipe replacement. That estimate has been revised based on actual dose rate, man-hours and exposure incurred to date. The current estimate is provided below: Item Man Rem Man-Hours August 26, 1982 Estimate 2,036 43,475 (less recirculation pipe replacement) Current Estimate 1,565 56,921 (less recirculation pipe replacement) 28" Recirculation Pipe Replacement 258 11,042 COI 12" & 14" Branch Pipe Replacement 45 1,145 7 ~i j 6" Branch Pipe Replacement 40 1,61 0 Total current estimate 1,908 70,718 a 7 ,] -4vu1uva; 620907 g DR ADOCK 05000220-PDR ay L
c n e ~ w = m u m. m a m.:: m -c m n a w o M & u n. ._ m _ ;_ _ :n _e s w y. &.. y .I , Mr. Darrell G. Eisenhut j Page Two t d ^ As shown above, the combined man-rem exposure estimates for the recirculatio1 piping replacement as well as the safe-end replacement are bounded by the original estimate of 2906 man-rem. _ y .q -3 Replacement Program w 3 ' $9" Our letter of August 6,1982 provided general design criteria related to the replacement program. At that time it was indicated that the fit up aT'. requirements would be in accordance with ANSI B31.1-1977 (with addenda through 1j winter 79) Code for pressure piping. Our current plans are to follow the fit ,4 up requirements of the 1980 Edition of the ASME B&PY Code, Section III through . j winter 1980 addenda. -y 3 5 k) In addition, it was indicated that the stress analysis would not be redone a since the new system configuration would be the same as the original design. 2i However, our current plans are to redo the stress analysis using the as-built configuration. This reanalysis will be consistent with the requirements of f, the 1955 Edition of the ASA B31.1 Power Piping Code as stated in our FSAR. IU The reanalysis will be performed using the equations presented in the 1977 = 5d Edition of the ASME B&PV Code, Section III, subsection NC, subsubarticle - {g NC-3650 for sustsined loads, occasional loads, thermal ?oads and stress - a range. However, the allowable stress values, "S", will L9 extracted from the t !! 1955 Edition of ASA B31.1 for comparable materials and will be consistent with 9 :j FSAR allowable. stresses. The seismic response spectra, will be that -; j originally submitted in our FSAR. h This method of analysis t's consistent with the approach used for the q analysis required in IEB 79-07. 1, _!--y replace the reactor recirculation piping. Namely, ultrasonic examination Our letter of August 6,1982 provided the basis for our decision to ?! usir.g increased gain techniques of a large number of welds indicated the i presence of cracking. Analysis using a replication process, and evaluation of -ri boat samples confimed the presence of intergranular stress corrosion cracking i / at several weld locatfora. The original material utilized in the reactor c - recirculation system is now classified as non-conforming material within the v0 contents of MUREG-0313, Rev.1 dated October 1979. The non-conforming 1 material;is attr5buted to ba the principal cause of the presence of the { observed cracking. -.j. =- Vent truly yours, . 3.j 1 NIAGARA MOHAWK POWER CORPORATION - 1 y -e; MW%'> c A D-3 is ' C. V. Mangan 7 1 _ 4; Vice President Nuclear Engineering & Licensing -g - RJP:bd _' /7 J{ m, A
M Y NIAGARA RUMOHAWK NBAGARA MOHAWK POWER CoRPoRAT1oN/300 ERIE 30VLEVARD WEST. SYRACUSE N.Y.13202/TELEPHcNE (315) 474-1511 November 18, 1982 ~ Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Nile Point Unit 1 Docket No. 50-220 DPR-63
~~Dear Mr. Eisenhut:~~
On June 21, 1982 Niagara Mohawk notified members of your staff of a miscut made during repairs at Nine Mile point Unit 1. The cut on number 15 recirculation safe end penetrated the edge of the nozzle material as shown on Figure 1. The purpose of this letter is to describe the method and schedule to be utilized for the nozzle repair. The repair on number 15 recirculation nozzle will be accomplished in accordance with the AS!1E Boiler and Pressure Yessel Code, Section III, Division 1, Article NB-2549, " Repair by Welding". Article NB-2549 invokes requirements of Article NB-2539. These in turn require that welding and weliers must be qualific-d per Article NB-4000 and Section IX of the Code. Also, the repaired area must be examined by magnetic particle or liquid penetrant and then radiographed. In addition, the nozzle must be heat treated in accordance with Article NB-4640. o/ mnemih P
= s ^ The man-rem dose estimate for this repair is expected to be low and will be included in our next quarterly report. The following is a milestone schedule for accomplishing the repair. Milestone Date Weld Procedures ard Welder Qualification 12/01/82 Demonstration on Mockup 12/10/82 Begin No.15 Nozzle Repair 01/03/83 Complete Repair 01 /31 /83 In conjunction with this repair, both a stress and thennal analysis will be perfonned and available at the Nine Mile Point Unit 1 site for your review. Sincerely, y Met $W C. V. MangaM Vice President - Nuclear Engineering and Licensing MGM:bd E
~~v o w o-~~
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FIGURE 1 e i E b Ia TO 132, INCOMEL WELD 11 3 STRESS REUEVED _ lit o15 _ T l IMCOMEL WELD ~ METAL yoo SAFE END PORTION ORE E I.06f- / \\ a n 3 l.+s t TO I u 1.9 Bb u a g ( k TO k STAIMLESS STEEL CLAD 2 6.17. 5 DI A li2 'O I B To 26.150 DIA o ACTUAL F RS" CUT ACTUA,L ME ASUREMENTS t . - _ - _}}

ML20086P013

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Dear Ms. Bell:

Enclosures:

Dear Mr. Eisenhut:

Dear Mr. Ei unhut:

Dear Mr. Eisenhut:

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Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

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Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

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ML20086P013

Text

Dear Ms. Bell:

Enclosures:

Dear Mr. Eisenhut:

Dear Mr. Ei unhut:

Dear Mr. Eisenhut:

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L

Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

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SUMMARY

Dear Mr. Eisenhut:

Dear Mr. Eisenhut:

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