ML20147C346

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Summary of 871210 Meeting W/Util in Bethesda,Md Re Full 40-yr OL & Status of Worker ALARA Programs at Plants.List of Attendees & Viewgraphs Encl
ML20147C346
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 01/06/1988
From: Jaffe D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-64245, NUDOCS 8801190189
Download: ML20147C346 (69)
v • d • e


Text

'

M8N 0 61983 o

Docket No. 50-213/336 LICENSEE:

Northeast Utilities FAC1 Lily:

Haddam Neck and l'illstone Unit 2

SUBJECT:

DECEMBER 10, 1987 MEE11NG WITH NEU 10 DISCUSS PATTERS RELATED TO THE FULL FORTY YEAR CPERATING LICENSE AND THE STA105 0F WORKER ALAP,A PROGRAMS AT HADDAM NECK AND MILLST0hE UNIT 2 On Decen;ber 10, 1987, representativcs of Northeast Utilities (NEU) and the NRC staff n;et in Room 6507 of the Paryland National Bank Euilding in Bethesda, Paryland. A list of attendees is contained in Attachnent 1, herein. The purpose of the teeting was to discuss the NRC questions concerning the programs at Faddan. fleck and Pillstone Unit ? for keeping radiation exposure to plant perscr.nel "As Lcw as is Reasonably Achievable (ALAPA)." The questions on Pillstone Unit ? were containtd in the Peeting flotice dated Cecer.ber 2, 1987.

Attachn.ent 2 contains a sonnary of information to be provided by NEU in the formal response to the NRC Staff's questions. The contents of Attachtrent P was the basis of a fornal presentation to the NPC staff. Attachn.ent 3, herein provides a request for aaditicnal information en worker ALARA at Haddam Neck.

With regard to the questions on Fillstone 2 and Haddam Neck, the requests fcr additional infornation affects fewer than 10 respondents; therefore, CMC clearance is not required under P. L.96-511. The hRC staff expressed satisfaction with flEUs approach to worker ALAPA.

At the conclusien of the neeting, NEU conmitted to respond to the RFC questions by December 18, 1987.

TEffil. $2SG BY:"

Cavid H. Jaffe, Project Manager Project Directorate I-4 Division of Reactor Project I/II Attachttent s :

As stated cc: w/attachn ents See next page f

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8801190109 080106 PDR ADOCK 050 3

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~NRC & Local PDRs SVarga BBoger Naffe CGC-Bethesda EJordan JPartlow ACRS(10)

HBClayton NRC Participants E. Branagan F. Congel L. Cunningham T. Essig C. HInson D. Jaffe

0. Lynch, Jr.

J. Minns M. Shanhaky J. Stolz A. Want J. Wiggington l

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UNITED STATES NUCLEAR REGULATORY COMMISSION g

WA5HINGTON, D. C. 20666

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Un e s sm Pecket No. 50-213/336 LICENSEE:

Northeast ' tilities FACILITY:

Haddam Neck and Pillstene Unit 2

SUBJECT:

DECEPBER 10, 1987 MEETING WITH NEU TO DISCUSS MATTERS RELATED TO THE FULL FORTY YEAR OPERATING LICENSE AND THE STATUS OF WORKER ALARA PROGRAMS AT HADDAM NECK AND MILLSTONE UNIT 2 On December 10, 1987, representatives of Northeast Utilities (NEU) and the NRC staff met in Room 6507 of the Maryland National Bank Building in Bethesda, Fa ryland. A list of attendees is contained in Attachment 1, herein. The purpose of the meeting was to discuss the NRC questions conceraing the programs at Faddam Neck and Millstone Unit 2 for keeping radiation exposure to plant personnel "As Lcw as is Reasonably Achievable (ALARA)." The questions en Villstene Unit 2 were contained in the Meeting Notice dated Cecember P.,

1987.

Attachment ? contains a su'rvary of information to be provided by NEU in the formal response to the NRC Staff's questions. The contents of Attachnent R was the basis of a forval presentation to the NRC staff. Attachment 3, herein provides a request for a 'ditional information on worker ALARA at Haddam Neck.

With regard to the quest.ons on Pillstone 2 and Haddam Neck, the requests 'or additional infomation affects fewer than 10 respor. dents; therefore, CPB clearance is not required under P. L.96-511. The NRC staff expressed satisfaction with NEUs approach to worker ALAPA.

At the conclusion of the meeting, NEU conmitted to respond to the NRC questions by December 18, 1987.

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6 Cavid.. Jaffe, Pro.iect Manager Project Directorate I-4 Division of Reactor Pro.iect I/II Attachments:

As stated cc: w/ attachments See next page 1

s Mr. Edward J. Hroczka Mi11stene Nuclear Power Station

  • Northeast Nuclear Energy Company Unit No. ?

cc:

Cerald Carfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Generation Facilities Licensing Ccurselors at Law Northeast Utilities Service Company City Pla:s Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D. C. Nordquist. Director Nuclear Operations Cuality Services Departr.ent Northeast Utilities Service Company Northeast Utilities Services Cerpary Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-027C Hartford, Connecticut C6141-0270 Kevin f'cCarthy, Director Regional Acministrator Radiation Control Unit Regior I Cepartment of Envirenrental Protection U. S. Nuclear Regulatery Cent,ission State Office Building 631 Park Avenue Hartford, Connecticut 06106 King cf Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen Energy Divisicn Town of Waterford Office cf Pclicy and Managerert Hall of Records 80 Washington Street 200 Besten Post Read

}lartford, Connecticut 0610E Waterford, Cenrecticut 063PE S. E. Scace, Station Superintendert W. J. Raywend, Resider.t Inspector M111 store Nuclear Power Statier Millstone Nuclear Power Statien hertheast Nuclear Energy Company c/o V. S. Nuclear Regulatery Cenrissicn Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 06357 J. S. Keenan, Unit Superintencent Charles Brinkman, Manager M111stene Unit No. 2 Washington Nuclear Operations Northeast huclear Energy Cerpany C-E Power Systers Post Office Box 1?S Combustion Engineering, Inc.

Waterford Connecticut 06365 7910 Weedmont Avenue Pethe:da, Paryland ECE14 l

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't ATTACHMENT __1 d

LIST OF ATTENDEES NRC STAFF NEU i

E. Branagan F. Dacirro F. Congel E. DeBarba L. Cunningham J. Klisiewicz T. Essig

- G. VanNoordeninen C. Hinson R. Rodgers 1

D. Jaffe F. Sears

0. Lynch, Jr.

J. Minns a

M. Shanhaky J. Stolz A. Wang J. Wiggington i

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-ATTACHMENT 2 1

4 DOCKET NOS 50-213 50-336 i

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J NORTHEAST UTILITIES 1

MILLSTONE NUCLEAR POWER STATION UNIT NO 2

1 HADDAM NECK PLANT l

FORTY-YEAR OPERATING LICENSE AMENDMENT '

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i DECEMBER 10, 1987

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_1 PURPOSE 1.

RESPOND TO NRC STAFF QUESTIONS ON OCCUPATIONAL EXPOSURE AT MILLSTONE UNIT NO. 2 AND CONNECTICUT YANKEE, 2.

REACH A FAVORABLE CONCLUSION TO ALLOW NRC STAFF ISSUANCE OF THE 7.0NNECTICUT YANKEE AND MILLSTONE UNIT NO. 2 FORTY-YEAR LICENSE AMENDMENTS IN DECEMBER 1987.

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CFS - 12/10/87 l

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2-NU PARTICIPANTS VICE PRESIDENT, NUCLEAR AND o

DR. C. F. SEARS ENVIRONKENTAL ENGINEERING KANAGER, RADIOLOGICAL o

DR R. C RODGERS ASSESSMENT BRANCH o

J. W, XLISlEWICZ SUPERVISOR, NUCLEAR KATERIALS AND CHEMISTRY o

F. R. DAtlM0 SUPERVISOR, MILLSTONE UNIT N0, 2 ENGINEERING o

E. A. DEBARBA SUPERINTENDENT, HADDAM NECK STATION SERVICES o

G. P. VAN N00RDENNEN SUPERVISOR, GENERATION FAtlllTIES LICENSING l

CFs - 12/10/87

' AGENDA 1.

NU Management - Overview C. F. Sea rs 2.

ALARA Overview Where Are Wa Now R. C. Rodg ers Where Are We Going Exposure Reduction Plan Exposure Goals / Budgets Station implementation Of Goals F. R. Dacimo 3.

Exposure Reduction Initiatives R. C. Rodgers 4.

Chemistry and Inspection / Repair J. W. Klisiewicz Ma*.erial Controls-Decontamination Chemistry Primary / Secondary 5/G Replacement Exposure Data 1980-1989 R. C. Rodg ers S.

Greater Than 10 Man Rem Jobs-MP 2 F. R. Dacimo 6.

Repetitive Jobs ALARA Data / Efforts F. R. Dacimo/

(Refuel, S/G,151, RCP)

Station System /Compontent Tracking 7.

Station ALARAImplementation ALARA Review Process F. R. Dacimo/

Post job Reviews E. A.DeBarba 8.

ALARA Screening inISAP G. P. van Noordennen

9. Additionalinformation on ALARA Savings R. C. Rodgers
10. Summary C. F. Sears i

CFS 12/10/87 i

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_4 FORTY-YEAR OPERATING LICENSE AENDMENTS REDUCTION OF OCCUPATIONAL EXPOSURE AT NU 1

MANAGEENT OVERVIEW o

IMPORTANCE c

o ATlTUDE CHANGES o

PHYSICAL CHANGES o

EFFECTIVENESS OF ALARA G0ALS l

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-s-i FORTY-YEAR OPERATING LICENSE AMNDENTS l

o NU HAS AN EFFECTIVE ALARA PROGRAM i

o SIGNIFICANT RESOURCES HAVE BEEN AND ARE BEING APPLIED TO CONTINUE TO REDUCE OCCUPATIONAL EXPOSURE o

TIMELY APPROVAL OF THE FORTY-YEAR OL AENDENT LOWERS COST TO OUR CUST0ERS i

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' NU ALARA PROGRAM CHRONOLOGY-ACHIEVEMENT e

ALARA part of routine operation Since Plant Start up e

Formal ALARA programinitiated 10/77 Mgmt. commitment, cost benefit, ALARA reviews,etc.

o Computerized exposure tracking by system 1979 component / job e

INPO NU ALARA Operating Experience Note-8A 9/82 o

Robotics in 5/G tube plugging /sfeeving CY 1987 MP2 Since1983 S/G channelhead decon

-CY 1986 (Industry First)

MP2 83/85/86 Mock up training, S/G, RCP, etc.

Since 1982 MP 1 Recirc. piping chemicaldecon 84/87 e

o NU Radiation Exposure Study 12/84 e

S20,000/ per man rem. Mgmt. initiative 7/86 e

NRC l&E findings in positive 1986 1987 New Exposure Reduction Program 12/86 three (3) year average goals, annual budgets exposure reduction initiatives e

MP 1 GEZIP 1987 1

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NU System hposure Data Compariscn to Industry Averages ytased on TLD Data)

Year pWR,Ay.

M P-1 PWR h M P-2 M P-3 CY

1. Total Man-Rem 1979 733 1,793 510 472 1,161 1960 1,136 2.158 578 636 1,353 i

1981 980 1,496 652 531 1,036 126 l

1982 940 929 578 1,413 1983 1,056 244 592 1,881 1,384 1984 1,003 836 552 120 1,216 j

1985 744(1) 608 442(1) 1,581 101 1986 622(2) 150 397(2) 894 25 1,567 1987(3) 719 180 447 792 1988(3) 159 633 29 200 i

1989(3) 464 640 419 796

2. Number of Workers with Measurable Doses E

1979 1,010 1,769 924 757 1,226 1,860 1980 1,311 3,024 1,101 892 i

. li 1981 1,340 2,506 1,076 890 1,554 1982 1,240 1,370 1,086 2,083 559 1983 1,287 309 1,065 2.383 1,645 1984 1,522 1,992 1,117 285 1,430 l*;

1985 1,378(1) 1,578 1,000(1) 1,057 381 1986 1,550(3) 489 1,050(3) 2,190 100 1,945

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3. Average Measured Dose Per Worker (Rem) 1979 0.726 1.014 0.552 0.624 0.947 1980 0.867 0.714 0.525 0.713 0.727 0.667 i

8 1981 0.731 0.597 0.606 0.597 1982 0.758 0.678 0.532 0.678 0.225 1983 0.821 0.790 0.556 0.789 0.841 i

1984 0.659 0.420 0.494 0.421 0.850 i

1985 0.540(1) 0.385 0.422(1) 1.496 0.265 1986 0.401(3) 0.307 0.378(3) 0.408 0.250 0.806 (1) - Based on preliminary NRC data 1

(2) - Based on INPO data (3) - Estimated I

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Three-Year Rollina Averaaes Usino PIC Data Years Q

g MP2 MP3 1981 1983 871 868 1,335 1982 1984 916 686 1,209 1

1983 1985 912 590 1,310 1984 1986 1,009 554 937 1985 1987 871 511 957 1986 1988 900 347 592 168 i

1987 1989 596 447 484 298 l

1988 1990 1990 + goals 525 580 525 250 i

INPO Goal 350 450 700 350 450 350 450 (Ann. Avg.)

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EXPOSURE REDUCTION PLAN Achieve Culture Chance Worker exposure reduction is same as reducing risk to publich health and safety e

e ALARA is mandatory Expcisure reduction is integral part of design, installation, and maintenance e

Exposure reduction is everyone'sjob - not just that of H.P.

o Evalua te and Implemen t Exposure Reduction Initia tives e

Reduce rad area work e

increase rad worker efficiency e

Reduce area dose rates Person Rem Goals e

Use three year average goals vs. annual goals Outage exposure goal set thirty to sixty days prior to start of outage o

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EXPOSURE REDUCTION INITIATIVES i

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Short Term initiatives - To be achieved in 1987-1988 l

Long Terminitiatives - To be achieved by the early 1990's e

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i EXPOSURE REDUCTION INITIATIVE!

INITIATIVE #

INITIATIVE TITLE Short Term initiatives ST #1 Increase ALARA Awareness - All units ST #2 Job cancellation / scope reduction - All units ST 03 Work practice review - All units ST #4 Construction Work efficiency - A;l units ST #5 Decontamination - CY, MP-1, MP-2 ST #6 CET Grayloc flanges & reactor head stud tensioners - CY ST #7 Permanent neutron shield - MP-2 ST #8 GEZIP - MP-1 ST #9 Snubber reduction - MP-2, MP-3 ST #10 ALARA installation reviews - early stage -

All units ST 011 Cobalt reduction - All units ST #12 MP-3 project list ST #13 Hydrogen water chemistry - MP-1 Lono Term initiatives LT #1 Decontamination improvements - All units LT #2 Longer fuel cycles MP-2, Mp-3, CY LT #3 Steam generator inspection / plugging criteria - CY, HP-2, HP-3 LT #4 Primary chemistry conrols - CY, HP-2, HP-3 LT #5 Robotics - All units LT #6 Steam generator replacement - MP-2 LT #7 Cobalt material alternatives - All units

SUMMARY

MILLSTONE SITE ALARA INITIATIVES MILLSTONE UNIT 1 MILLSTONE 2 MILLSTONE 3 o

GEZIP PRIMARY S'(SIEB PRIMARY SYSTEM H WC o

DECONTAMINATIONS o

CONSTANT COOLANT PH 2

o o

DECONTAMINATIONS o

Co REPLACEENT o

Co REPLACEENT

I o

Co REPLACE E NT o

DISSOLVED H2 o

DISSOLVED H2 t

o CHEMISTRY CONTROL SECONDARY SYSTEM SECONDARY SYSTEM i '

l Y'

o CHEMISTRY CONTROLS o

CHEMISTRY CONTROLS l

l' MU WATER IMPROVEENTS o

SLUDGE LANCING

,l CPF OPTIMIZATION H3 B03 EVALUATION o

Cu ALLOY REPLACEENT MORPH 0LINE EVALUATION l

0 SLUDGE LANCING t

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CHEMICAL CLEANING o

Cu ALLGY REPLACEENT l

o MAIN CONDENSER REPLACEENT

e

SUMMARY

CONNECTICUT YANKEE ALARA INITIATIVES

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CONNECTICUT YANKEE I

i PRIMARY SYSTEM o

DECONTAMINATION 4

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DISSOLVED H2 H022 ADDITION o

o Co REPLACEENT p I' SECONDARY SYSTEM i!

o COMPLETED REMOVAL 0F ALL Cu ALLOYS o

COMPLETED RETUBE OF MAIN CONDENSER i

o ELEVATED SECONDARY SYSTEM PH i

o CHEMISTRY CONTROLS o

SLUDGE LANCING i

m - 12/10/87 i

ADDITIONAL ON-G0ING EFFORTS PROGRAM NORTHEAST UTILITIES IN CONJUNCTION WITH:

o STEAM GENERATOR TUBE PITTING UNIVERSITY OF MICHIGAN, AND COMBUSTION ENGINEERING o

STEAM GENERATOR SLUDGE PILE ALDEN RESEARCH LABORATORY (WORCESTER FORMATION POLYTECHNIC INSTITUTE) i o

STEAM GENERATOR CREVICE UNIVERSITY OF CONNECTICUT CONCENTRATION N0DELING QUALIFIED FOR CONNECTICUT STATE COOPERATIVE HIGH TECHNOLOGY RESEARCH AND DEVELOPMENT MATCHING GRANT s

7 CONSIDERED FOR NATIONAL SCIENCE FOUNDATION YOUNG PRESIDENTIAL INVESTIGATORS AWARD o

REGENERATION AND VOLUME REDUCTION UNIVERSITY OF CONNECTICUT OF SPENT CLEANING SOLUTIONS 00ALIF!ED FOR CONNECTICUT STATE COOPERATIVE HIGH TECHNOLOGY RESEARCH AND DEVELOPMENT MATCHING GRANT o

STEAM GENERATOR MAIN STEAM HYDROGEN NWT MONITORING Jwr - 12/10/87 A

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O ADDITIONAL ON-GOING EFFORTS (CONTINUED)

PROGRAM NORTHEAST UTILITIES IN CONJUNCTION WITH:

1 o

HYDROGEN PEROXIDE ADDITIONS ON INTERNAL TO NORTHEAST UTILITIES SHUTDOWN I

o STEAM GENERATOR CORROSION MODELING OTHER COMBUSTION ENGINEERING OWNERS GROUP PARTICIPANTS, AND COMBUSTION ENGINEERING

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0 EPRI PWR PRIMARY WATER CHEMISTRY OTHER PARTICIPATING UTILITIES GUIDELINES (REVISION) 0 EPRI BWR CHEMISTRY OTHER PARTICIPATING UTILITIES GUIDELINES (REVISION)

JWK - 12/10/87

19 i

MATERIALS AND CHiHISTRY ALARA INITIATIVES r

1.

HIGHER PRIMARY COOLANT PH:

ALLPWRS i

PRINCIPLE /0BJECTIVES:

- T0 INCREASE THE SOLUBILITY OF FUEL DESPOSITS I

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- TO MAINTAIN CLEAN FUEL SURFACES

- REDUCTION OF ACTIVITY TRANSPORT i

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- MINIM 12E SG CHANNEL HEAD DOSE RATES r

i STATUS:

TARGET

- TRIAL RUN AT MP3 FOR CYCLE 2 1988/89 i

- IF SUCCESSFUL, ASSESS FOR APPLICATION AT CY AND MP2 1990/91 t

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I JWK - 12/10/87

2, HYDROGEN PER0X1DE INJECTION DURING SHUTDOWN:

ALL PWRS PRINCIPLE /0BJECTIVE:

- T0 INCREASE SOLUBILITY OF CoS8/Co60 AT AN APPROPRIATE TIME FOR MAX. COOLANT CLEANUP

- REDUCE FUEL POOL DOSE RATES STATUS:

TARGET

- APPLIED FOR MANY YEARS AT CY

- BLING ASSESSED FOR APPLICATION TO MP2 AND MP3 1988 JWK - 12/10/87

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PARTIAL SYSTEM DECONTAMINATION:

ALL STATIONS PRINCIPLE /0BJECTIVE:

- TO CHEMICALLY REMOVE RADIONUCLIDES FROM SPECIFIC SYSTEM SURFACES PRIOR TO INSPECTION AND/0R REPAIR WORK

- REDUCE WORKER DOSE RATES STATUS:

TARGET

- UTILIZED AT CY AND MP2 ON SG CHANNEL HEADS 1983/85/86

- UTILIZED AT MP1 ON REACTOR RECIRC.,

REACTOR WATER CLEANUP, AND IN LOWER VESSEL ANNULUS 1984/87

- CONSIDERED ON A CASE BY CASE BASIS FOR EACH OUTAGE FUTURE i

l JWK - 12/10/87

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k, FULL SYSTEM DECONTAMINATION:

ALL PWRS i

PRINCIPLE /0BJECTIVE:

- TO CHEMICALLY REMOVE RADIONUCLIDES FROM THE ENTIRE PRIMARY SYSTEM (S) AND VESSEL (WITH OR WITHOUT FUEL IN PLACE),

- A REDUCTION IN WORKER DOSE RATES IN GENERAL AND/0R FOR MAJOR REPAlR OR REPLACEMENT (E.G. SG REPLACE?,ENT)

STATUS:

TARGET i

- AD H0C UTILITY COMMITTEE FORMED TO ESTABLISH A PROGRAM FOR PWRS COMMITTEE HAS NU REPRESENTATION AND NRC INVOLVEMENT

- PROGRAM TO BE DEFINED EARLY 1988

- PROCESSES OVALIFIED AND EVALUATIONS COMPLETED FOR GENERIC USE EARLY 1989

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JWK - 12/10/87 I

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5.

COBALT SOURCE REMOVAL:

ALL STATIONS PRINCIPLE /0BJECTIVES

- TO REPLACE Co CONTAINING COMPONENT MATERIALS WITH ALTERNATIVE ALLOYS

- TO SPECIFY LOW Co CONTENT FOR MAJOR CONTRIBUTION COMPONENT MATERIALS (E.G. SG TUBING)

- REDUCE Co CONTENT IN COOLANT WATER AND COMPARABLE REDUCTION IN WORKER DOSE RATES STATUS:

TARGET

- PROJECT ASSIGNEMENT IN PLACE TO REPLACE SPECIFIC Co CONTAINING VALVE SEATING ALLOYS (STELLITE) WITH ALTERNATIVES 1988/89/90/91

- STELLITE REPLACED WITH T420SS IN FW REGULATOR VALVES AT MP1 1986 l

- LOW Co CONSIDERED FOR IMPROVED i

SG TUBING AT MP2 1987 i

- STUDY TO BE PERFORMED ON EFFECTIVENESS OF REPLACING OTHER IN CORE Co CONTAINING COMPONENTS (E.G.

CONTROL R0D DRIVES, GRID SPACERS) 1988/89 i

JWK - 12/10/87 I

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SURFACE PASSIVATION PROCESSES:

ALL STATIONS PRINCIPLE /0BJECTIVE

- TO CHEMICALLY (OR ELECTR0 CHEMICALLY) TREAT COOLANT COMPONENT SURFACES IN ORDER TO REDUCE RADIONUCLIDE l

RETENTION ON METAL AND/0R OXlDE l

f J

STATUS TARGET

- GEZIP (ZN INJECTION) TESTED AND IMPLEMENTED AT MP1 1987 i

- STATE OF THE ART IN ELECTR0 POLISHING AND/0R HIGH TEMPERATURE (STEAM / AIR)

SURFACE TREATMENTS BEING FOLLOWED ON-G0ING 1

i i

i i

1 1

m - 12/10/87 7

i l

t

~:

4 7.

HYDROGEN COOLANT CHEMISTRY:

BE PRINCIPLE /0BJECTIVE:

I TO CONTINUOUSLY INJECT H2 INTO THE FEEDWATER IN ORDER TO LOWER THE ELECTRODE POTENTIAL OF SS AND INCONEL COMPONENTS TO PREVENT AND/0R MlTIGATE IGSCC A REDUCT10N IN BOTH REPAlRS AND INSPECTIONS WITH SUBSEQUENT DECREASES IN PERSONNEL EXPOSURE l

STATUS:

TARGET

- H2WC TESTED AT MP1 1987 1

I

- IMPLEMENTATION AT MP1 NOW BEING ASSESSED 1988/89 m - 12/10/87

... _ 1. -.

MILLSTONE 2 STEAM GENERATOR CHANNEL HEAD DECONTAMINATION FXPERIENCES AUGUST 1983 o

0Z0X-A PROCESS AVERAGE VALUES 181IJAL (R/HR)

POST DECON (R/HR)

POST HYDR 0 (R/HR)

DE 18 10.5 6

3.0 KAY 1985 o

DlLUTE CITR0X PROCESS AVERAGE VALUES INITIAL (R/HR)

POST DECON (R/HR)

POST HYDRO (R/HR)

DE 14 4

3 4.6 0CTOBER 1986 o

0Z0X-A PROCESS AVERAGE VAlllES INITIAL (R/HR)

POST DECON (R/HR1 POST HYDR 0 (R/HR1 DE 11 5

5 2.2 i

JWK - 12/10/87

__g--

. -. ~..

.~

~~.

MILLSTONE 2 STEAM GENERATOR INSPECTION PRACTICES NOVEMBER 1986 o

SM4 o

FOUR STEAM GENERATOR PLENUMS IN PARALLEL o

STEAM GENERATOR DECONTAMINATION o

MOCKUP TRAINING o

VIDEO TAPING PROBE ENTRY o

SHIELDED STEAM GENERATOR MANWAY DOORS o

DATA ACQUISIT!0N OUTSIDE CONTAINMENT JANUARY 1988 o

GENESIS ARM (ZER0 ENTRY) o NO TUBESHEET TEMPLATES o

4WD PROBE PUSHER o

ANALYST TRAINING o

M0CK UP TRAINING o

FOUR STEAM GENERATOR PLENUMS IN PARALLEL o

FINANCIAL INCENTIVE / PENALTY CLAUSE REGARDING MAN-REM EXPOSURE JWK - 12/10/87

7 t

~.

MILLSTONE 2

SUMMARY

OF STEAM GENERATOR CHEMISTRY CYCLE PARAMETER LIMIT 5

6 Z

'B' CHLORIDE LESS THAN 20 PPB 57 29 23 1

S0DlVM LESS THAN 20 PPB 26 15 13 1

CAT. COND.

LESS THAN.8 US 1.5 1.1 0.6 0.1

  • END OF CYCLE 8: JANUARY 1988 l

i

  1. K 12/10/87

MILLSTONE 2 ESTIMATED NUMBERS OF STEAM TUBE REPAIR EXISTING INDICATIONS ClCLE BECOMING.2 40%

OTHER TOTALS E0C8' (1/88) 350 30 380 E0C9 70 20 90 E0C10 70 15 85 E0Cll 70 15 85 E0Cl2 60 10 70 E0Cl3 60 10 70

  • END OF CYCLE 8 JWK - 12/10/87

... = -. _

_30 MILLSTONE 2 STEAM GENERATOR IMPROVEMENTS ON-G0ING EVALVATION OF FOLLOWING DESIGN CONSIDERATIONS:

o ALLOY 690 (LOW COBALT) o FERRITIC SUPPORT SYSTEMS o

ENHANCED BLOW DOWN RATE o

ELECTRO POLISHING 0F CHANNEL HEAD CLADDING o

INSTALLATION OF FIXTURES ON DIVIDER PLATES TO FACILITATE SHIELDING INSTALLATION o

MORE/ LARGER HAND HOLDS AND MANWAYS o

SEALED DIVIDER PLATES TO FACILITATE CHANNEL HEAD DECONTAMINATIONS o

IMPROVEMENTS IN N0ZZLE DAM DESIGN JWK - 12/10/87

.~

I

-n-MILLSTONE 1 DECONTAMINATION EXPERIENCES APRIL 1985 o

CAN DECON PROCESS o

REClRCULATION SYSTEM ayERAGE VALUES INITIAL (MR/HR)

FINAL (MR/HR)

E 238 41 5,8 SEPTEMBER 1987 o

LOMI PROCESS o

REClRCULATION SYSTEM AVERAGE VALUES INITIAL (MR/HR FINAL (MR/HR)

E 285 77 3,7 o

REACTOR WATER CLEANUP SYSTEM AVERAGE VALUES I"lTIAL (MR/HR)

FINAL (MR/HR)

E 155 57 2,7 JWK - 12/10/87

1

==

-l ~

s MILLSTONE 1

SUMMARY

OF REACTOR AND FEEDWATER CHEMISTRY CYCLE PARAMETER LIMIT 11 12' REACTOR WATER CHLORIDE LESS THAN 20 PPB 5

5 FEEDWATER OXYGEN LESS THAN 200 PPB 20 20

  • CYCLE 12 STARTUP AUGUST 1987 l

'i JWK - 12/10/87 1

-.-i

9 MILLSTONE 3 STEAM GENERATOR INSPECTION PRACTICES NOVEMBER 1987 o

SM10 o

NO TUBESHEET TEMPLATES o

4WD PROBE PUSHER o

VENDOR REVIEW 0F BASELINE DATA o

TWO STEAM GENERATORS IN PARALLEL o

ANALYST TRAINING JWK - 12/10/87

I i

MILLSTONE 3 l

SUMMARY

OF STEAM GENERATOR CHEMISTRY PARAMETER LIMIT CYCLE 1 CHLORIDE LESS THAN 20 PPB 5

S0DIUM LESS THAN 20 PPB 11 l

.l CAT. COND.

LESS THAN 0.8 US

. 0. l4

.:n - 12/10/87 1

/.

CONNECTICUT YANKEE STEAM GENERATOR CHANNEL HEAD DECONTAMINATION EXPERIENCE JANUARY 1986 o

CAN DECON PROCESS o

ONLY STEAM GENERATORS 1 AND 3 AVERAGE VALUES INITIAL (R/HR)

(POST DECON (R/HR)

POST HYDRO (R/HR)

DE 27 5

6 4.5 JWK - 12/10/87

~~

CONNECTICUT YANKEE STEAM GENERATOR INSPECTION PPACTICES JANUARY 1986 o

SM10 (REMOTELY OPERATED ROBOTIC ARM) o NO TUBESHEET TEMPLATES o

4WD PROBE PUSHER (MINIMlZED NUMBER OF PROBE CHANGES DUE TO PROBE WEAR / BREAKAGE) o VENDOR REVIEW 0F 1984 INSPECTION RESULTS o

MOCK UP TRAINING o

TWO STEAM GENERATORS IN PARALLEL AUGUST 1987 o

SM10 (UPGRADED) o NO TUBESHEET TEMPLATES o

4WD PROBE PUSHER o

VENDOR REVIEW 0F 1986 INSPECTION RESULTS o

ANALYST TRAINING o

MOCK UP TRAINING o

TWO STEAM GENERATORS IN PARALLEL o

CUT HOLE IN STEAM GENERATOR SKIRT (TOOK ADVANTAGE OF EXTRA SHIELDING) o TUBE MARKING FORM SM10 JWK - 12/10/87

e

-n-CONNECTICUT YANKEE I

SUMMARY

OF STEAM GENERATOR CHEMISTRY CYCLE PARAMETER L]31I 11 12 H

B CHLORIDE LESS THAN 20 PPB 56 28 10 10 S0DIUM LESS THAN 20 PPB 68 7

7 6

CAT, COND, LESS THAN 0.8 US 1.2 0,5 0,4 0.3 JWK - 12/10/87 t

s i

CONNECTICUT YANXEE 1987STEAMGENERATORINSPECTIONRESU[TS' A TOTAL OF 353 TUBES PLUGGED:

289 FOR PWSCC AND ROLL TRANSITION CRACXING; 64 FOR OTHER REASONS (E.G. PITTING)

SAMPLE OF TUBES WITH PLUGGABLE INDICATIONS IN 1987, WHEN COMPARED T0 1986 RESULTS, REVEALED THAT ESSENTIALLY ALL INDICATIONS WERE PRESENT IN 1986 DATA REDUCTION STILL UNDERWAY PRESENT CONCLUSION, 1987 DEFECTS REPRESENT OLD NOT NEW INDICATIONS, WITH MINIMAL DEFECT PROGRESSION RATES

'\\

l m - 12/10L_BZ

_ 3 9 _ _u - - --

_=

_a MP2 SIG EXPOSURE HISTORY Ou.tage Total For S/G S/G Year Outage Projects Total

% S/G 1980 486 ECT 49 63 13 %

Tube Plugging (2) 8 Sec. Side inspection 6

1981 82 1689 ECT 155 1098 65%

Nozzle Dams 296 Plug (1492) 584 Tube Sample 56 Sec. ',. Inspection 7

! 1983 84 1989 ECT 148 1289 64 %

Sludge Lanc.

67 Decon 130 Sample 26 i

Tube Sleeving (2022) 572 Plug (386) 61 Tube Repair 57 Radiography 13 Nozzle Dam 208 Sec. Side Inspec.

8 1985 1547 Sleeve (2926) 526 1026 66 %

ECT 198 Decon 58 i

Chem Clean.

96 l

Tube Sample 17 Lanc.& Radio 13 ea.

Nozzle Dams 46 Plug (132) 13 1985 127 N/A

. RCP Motor i

1986 872 Plug (56), Sfeeve (226) 138 351 40 %

Nozzle Dam 92 I

ECT 50 Sludge Lanc.

16 Decon 47 I

Radiography 8

!1987 82 Plugs (162), Sleeves ( 1) 60 60 73 %

. Tube Leak i

1988 544 ECT 60 267 49 %

Plugging 67 Radiography 8

Tube Pull 10 Sec. Side inspec.

25 Nozzle Dams 60 S/G Platfrm/ Stage 22 Misc. Support 15 1989 562 ECT 60 252 45%

Plugging 30 Radiography 11 i

Sec. Side Inspec.

30 Nozzle Dam 84 S/G Platfrm/ stage 22 i

Misc. Support 15

_...m...

CY SIG Exposure History Outage Outage i!xposure

% S/G Year Total Steam Generator Projects S/G Total Exposure 1980 1005 ECT 52 74 7.4 Tube Plugging (4) 8 Sec. Side (Lance /inspec.) 14 1981 878 ECT 130 238 27 Tube Plugging (50) 38 Tube Pull Attempt.

47 Sec. Side 23 1983 1260 ECT 117 335 27 Tube Plugging (440) 177 Sec. Side 41 1984 1108 ECT 182 348 31 Tube Plugging (104) 67 Tube Removal 48 Sec. Side 51 1986 1506 Chemical Decon.

115 361 24 (Refuel)

ECT 100 Tube Plugging (122) 72 Tube Removal 41 Sec. Side 33 1986 106 ECT 10 106 100 (July)

Tube Plugging (248) 95 Sec. Side 14 1987 638 ECT 61 122 19 (11/24/87) Tube Plugging (706) 47 Sec. Side 14 1989 716 ISI SG4 Welds 5

118 16 ECT 59 i

Tube Plugging 45 Sec. Sluge Lance 13 1

I

e'

~.

_ QUESTION NO.1 MP 2 JOBS GREATER THAN 10 MAN REM 1980 A tual Acutal Job Manhours Man Rem Refueling 7467.79 100.410

  • NRCIE Bulletin 79 02 7405.22 51.150 Reactor Head Cable Project 9185.00 36.900
  • Reactor Head Vent 3510.75 15.945 Modification CEDM Guide Cone Insp.

104.70 18.670 and Repair

  • RCP Oil Collection System 1210.00 10.820 Health Physics Blanket 7600.15 31.590
  • Special Maintenance Jobs

j QUESTION NO.1 MP-2 JOBS GREATER THAN 10 MAN-REM 1982 Actual Acutal JM Manhours

_ Man Rem Refueling

  • 5978.71 84.400
  • Steam GeneratorTube 247.37 55.710 Sample
  • Incore instrument 2872.25 31.550 Modification Class 1 In-Service Inspection 1281.00 34.520 (ISI)
  • Replacement of "C" 1803.85 11.355 Charging Pump
  • Health Physics Blanket 16734.30 69.450 Operations Blanket 1767.79 21.520
  • NRC IE Bulletins 79 02 and 22414.92 223.160 7914 (Hangers ) *
  • Special Maintenance Jobs l

-4'3_

QUESTION NO.1 MP 2 JOBS GREATER THAN 10 MAN REM 1983 1984 Actual Acutal Job Manhours Man Rem Refueling 10134.75 77.215

  • Steam GeneratorTube 29387.33 572.290 Sleeving
  • Steam GeneratorTube 2352.33 61.075 Plugging
  • Steam GeneratorTube 1621.92 56.665 Repair
  • Steam GeneratorTube 982.42 13.020 Radiography
  • Steam GeneratorTube 1000.58 26.460 Sample
  • ThermalShield Removal 57281.33 135.585
  • Class 1 In Service Inspection 2795.42 24.025 (151)
  • Class 2 and 3 ISI 1913.00 14.100
  • Reacotr Coolant Pump Seal 608.25 13.855 Replacement Preventative Maintenance 1565.75 31.160 Miscellaneous Component 1267.58 11.470 Repairs
  • RCS RTD Connector Head 2084.33 46.635 Replacement
  • Wide Range Nuclear 2582.08 29.640 Instrumentation Mods.
  • RCS Loose Parts Monitor 248.92 10.200 System Installation
  • Pressurizer Loop Seals 1885.92 14.545 Replacement NNECO Personnel Blankets 40125.67 168.525 Contractor Personnel 4345.33 16.775 Blankets Radwaste Work and 130.17 21.390 Personnel Blankets
  • Special Maintenance Jobs l

= -. -. - - -

=.

=..

v QUESTION NO.1 MP-2 JOBS GREATER THAN 10 MAN REM * [^'

1985 Actual Acutal Job Manhours Man. Rem Refueling 6796.75 101.535

  • Steam GeneratorTube 12924.17 525.520 Sleeving Steam Generetor Eddy 4072.17 243.235 Current Testing (ECT)
  • Steam GeneratorTube 373.17 16.490 Sample
  • Steam GeneratorTube 156.92 13.145 Plugging
  • Steam GeneratorTube 759.09 12.580 Lancing
  • Class 1 In Service inspection 4705.00 118.055 (ISI)
  • Corrective Maintenance 5029.42 47.870
  • Inadequate Core Cooling 1856.50 38.450 Modification
  • Refuel Cavity Drain Une 1067.58 21.410 Hanger Modification Reactor Coolant Pump Seal 405.43 13.595 Replacement
  • Preventative Maintenance 732.67 11.170
  • Incore instrument Stalk 610.50 17.595 Repairs Trash & Laundry Pick up 816.92 12.840 NNECO Personnel Blankets 597.84 52.700
  • Special Maintenance Jobs o.-

~

. ~ _. _

QUESTION NO.1 MP 2 JOBS GREATER THAN 10 MAN. REM 1986 Actual Acutal Job Manhours Man Rem Refueling 4034.25 82.220

  • Steam GeneratorTube 4317.92 137.830 Sleeving and Pluging Steam Generator Nozzle 607.00 92.265 Dam instellation/ Removal Steam Generator Eddy 1020.91 50.235 Current Testing (ECT)

Steam Generator Channel 2463.34 47.430 Head Decontamination Steam Generator Sludge 292.83 16.095 Lancing Containment Staging and 7831.67 122.115 Shielding Class 1 In Service inspection 2305.33 61.285 (ISI)

Corrective Maintenance 2602.58 33.475 Preventative Maintenance 1693.33 31.065

  • Appendix "R" Modifications 3237.92 23.385 "C" Reactor Coolant Pump 895.84 17.860 (RCP) Motor Replacement RCP Seal Replacement 504.50 15.305 Regen. Heat Exchanger 156.58 10.185 Shield Installation Component inspections for 843.91 10.090 E EO Qualifications NNECO Personnet Blankets 1616.75 24.265
  • Special Maintenance jobs 1

)

I

m 46-MILLSTONE UNIT 2 EXPOSURE TRENDS FOR REPETITIVE JOBS EXPENDING MORE THAN 10 PERSON REM Refueling -This job includes reactor disassembly, fuel shuffle and reactor reassembly Year 1980 1981 82 1983 84 1985 1986 j Person Rem 101 84 77 101 82 Exposure Controls 1980

1. Worker briefings on radiation conditions and "hotspots"
2. Equipment decontamination
3. Audio communication eqdpment
4. Local shielding
5. Spare tensioner used for training
6. Reactor head studs cleaned with machine 1981 82 As above plus:
1. New graylock flanges facilitate in Core instrumentation (ICl)
2. More experienced work crew used relative to prior outage 1983 84 As above plus:
1. Reactor Head laydown area shielding,this saved about 8 man rem 1985 As above plus:
1. An improved shielded cavity drain filter sysem was used 198,@

As above plus:

1. A new cleaner was used for post refuel stud hole cleaning l

l

Reactor Coolant Pump Seal Repairs Year 1980 1981 82 1983 84 1985 1986 Person Rem 20.7 5.6 13.8 13.6 15.3 Seals 4

1 2

2 3

Exposure Controls 1980

1. The RTD connectors were modified to facilitate removal and replacement
2. The seals are disassembled under water which provides shielding and eliminates the need for decontamination 1981 82 As above plus:
1. New seal cartridge used for training 1983 84 As above plus:
1. Shielding was installed between the "B" RCP seal area and the pressurizer auxiliary spray line 1185 As above 1986 Asabove

j An.

j

... l l

Class 1 inservice inspection Year 1980 1981 82 1983 84 1985 1986 Person Rem 19.9 34.5 24.0 118 61.3 E_xp_osure Controls 1980

1. Coordinated 151, where possible, with other jobs to exploit staging and shielding already in place
2. Localdecontamination
3. CCTV was used for reactor vessel 151 1981 82 As above plus:
1. Hi jackers and ladders used instead of staging where possible
2. Localshiefding used where possible 1_983 84 As above plus:
1. Used automated ISI equipment on the reactor vessel 1985 As above plus:
1. RCS piping was prepared and inspected with water level above the centerline.

This saved about 6 person rem

2. A new RCP rotating device allowed inspection of the flywheel without having to remove the spool piece coupling the pump and motor 1986 As above plus:
1. Master slave ultrasonic testing equipment was tried but did not work well

f Steam Generator inspection & Repair This job includes manway removal and replacement, nozzle dam installation and removal, decontamination, eddy current testing, tube plugging, sleeving and sampling (i.e. tube pulls), radiography and sludge lancing.

1980 1981 82 1983 84 1985 1986 ECT 49.3 154.5 147.9 197.5 50.2 296(1) 207.9 45.6 92.3 Nozzle Dams 129.8 58.1 47.4 Decontamination Tube Plugging 8

584.2 61.1 13.1 137.8 572.3 525.5 Sleeving 56.7 Plug Repair 13.0 13 7.5 Radiography 55.7 26.4 16.5 Tube Sample 66.8 13 16.1 Sludge I.ancing Chem. Cleaning 96 I Sec. Side Inspec.

6 7

8

! Total 63 1098 1289 1026 351.3 (1) Initial Modification Exposure Controls 1980

1. Used manway cover shield
2. Had alljumpers mockup trained
3. ECT controls set up in low dose rate area 1981 82 As above plus' i
1. Manway diaphragms were shielded
2. CCTV used for remote observation
3. Shielded waiting areas were constructed. These saved about 40 person. rem

_1983 84 As above plus:

1. The channel heads were chemically decontaminated (DF = 3). Exposure savings are estimated as follows:

Task I.oop Area Shielding Decontamination ECT 61 30 Plug Repair 11.1 260 Tube Sample 5.7 130 l

l 1

. _., Steam Generator nspect on & Repair (Cont'd.)

I i

1983 84 (Cont'd.)

2. New manway stud tensioner employed
3. Use automated ECT equipment
4. The honing device, used in the sleeving operation, filter was remotely located and shielded
5. The decontamination skid was shielded
6. Automated tube plugging, equipment was tried but didn't work well, thus requiring a manual operation 1985 As above plus:
1. Decontamination Factor-4.6
2. Exposure savings are as follows:

Task Loop Area Shielding Decontamination Sleeving 120 1200 Plugging 2

82 Radiography 4.5 37 Tube Sample 4,5 55

3. Special robot, ROSA, used for sleeving cold leg tubes. Manual method used on hot leg
4. New honing machine didn't cause high contamination exposure problems as prior model did
5. New robot, Genesis,was tried for radiography. It was unsuccessful 1986 As above plus:
1. Chemical decontamination factor = 2.2
2. Special robot (ROSA) was used for plugging as well as sleeving. Using ROSA saved about 170 person rem
3. New manway shields permitted ECT with shield in place
4. Changesin sludgelancing equipmentsaved 40 4S person rem
5. Radiography was performed, this time successfully with Genesis and saved 7 person rem
6. Other exposure savings are:

Task Loop Area Shielding Decontamination Plugging & Sleeving 28.0 57.3 ECT 1.5 12.5 Studge Lancing 3

Radiography 4.2

. =

- :=. -..

ALARA IMPLEMENTATION AT MILLSTONE UNIT 2 ACP 6,02, MAINTENANCE OF OCCUPATIONAL RADIATION EXPOSURE ALARA TO PROVIDE THE METHOD, ESTABLISH THE AUTHORITY AND DELINEATE RESPONSBILITIES TO ENSURE THAT ALARA EXPOSURE CONTROLS ARE EXERCISED AND DOCUMENTED ON JOBS WITHIN RADIOLOGICAL CONTROL AREAS AT MILLSTONE STATION THROUGH A SYSTEMATIC PROGRAM 0F PLANNING WORK SIGNIFICANT PART OF STATION, UNIT AND DEPARTMENT G0ALS; BASED ON CORPORATE G0ALS EXPOSURE REDUCTION PROGRAMS (4 ITEMS)

VIG0ROUS APPLICATION OF PERMANENT AND TEMPORARY j

SHlELDING DURING OUTAGES (ACP6,10)

ALARA COORDINATOR INVOLVEMENT WITH APPLICABLE UNIT DEPARTMENTS BEFORE AND DURING REFUEL OUTAGES UNDER ACP6.02 Eno - 12/10/87

i,

ALARA REVIEW PROCESS 1.

PERFORMANCE OF WORK - ACP 6.02 IF ESTIKATED EXPOSURE BETWEEN 1-5 MAN / REM, UNIT EVALUATES THE NEED FOR AN ALARA INSTALLATION REVIEWS, IF ESTIMATED EXPOSURE GREATER THAN 5 MAN / REM, AN ALARA INSTALLATION REVIEW IS IMPLEMENTED BY JOB TASK LEADER ON SF847 AND 848, 11.

DESIGN CHANGES - ACP-0A-3,10 IF ESTIMATED EXPOSURE MORE THAN 1 MAN / REM, APPLICABLE SECTIONS OF SF338 ARE REVIEWED, i

i FRD - 12/10/87

ROUTINE MANAGEMNT INVOLVEENT IN ALARA CONCERNS OUTAGE ALARA REPORT PROMULGATED BY ACP6,13 (SEE EXAMPLE)

FORMAL STATION RESPONSE TO ALARA OUTAGE REPORT RECOMENDATIONS (SEE EXAMPLE)

STATION SERVICES SUPERINTENDENT (H HAYNES) INVOLVED WITH CORPORATE EXPOSURE REDUCTION INITIATIVES STATION G0ALS DIRECTLY RELATED TO G0ALS ESTABLISHED BY CORPORATE RADIOLOGICAL ASSESSMENT BRANCH INCREASED ALARA STAFF ASSIGNED FOR OUTAGES INCREASED ALARA AWARENESS DURING OUTAGES:

ADMINISTRATION LETTER, OUTAGE METINGS, VISUAL AIDS,

ETC, SIGNIFICANT EMPHASIS ON TEMPORARY AND PERMANENT SHIELDING (NON-REGENERATIVE HEAT EXCHANGER, STEAM GENERATOR PLATFORM SHIELDING CAPABIL1 TIES, ETC,)

DAILY STATUS REPORT (SEE EXAMPLE) l FRD - 12/10/87_

j j

_ ~.

.. _ _....?..-

4 EXPOSURE REDUCil0N PROGRAMS S

M0CK UPS t

PHOTO BOOKS / COMPLETE VIDE 0 DOCUMENTATION OF C0hlAINMENT DURING 1988 REFUEL OUTAGE DURING 1988 REFUEL OUTAGE i

CHEMICAL DECONTAMINATION I

CONTAINMENT DECONTAMINATION t

i l

l i

l I

FRD -12/10/87 I

l

_.. ~.-, -..,__

ISAP ANALYTICAL RANKING ETHODOLOGY PERSONNEL SAFETY ATTRIBUTE l

0 PERSONNEL SAFETY ATTRIBUTE COMPOSED OF TWO CHARACTERISTICS l

- OCCUPATIONAL RADIATION EXPOSURE

- INDUSTRIAL SAFETY o

IMPACT MEASURED BY COMBINATION OF QUANTITATIVE AND QUALITATIVE FACTORS

- DOLLAR VALUE PER MAN-REM h

- COST PER LOST WORK-DAY GPVN - 12/10/87

=.

l ISAP ETHODOLOGY INTEGRATED IMPLEENTATION SCHEDULE o

EVALUATION OF SCHEDULING FOR POTENTIAL PLANT MODIFICATIONS AND ENGINEERING STUDIES i

o FACTORS IN THE FOLLOWING:

I

- EXTERNAL IMPACTS

'I

- ARH RANKINGS

- ALARA G0ALS/0CCUPATIONAL EXPOSURE h

l

- CAPITAL AND EXPENSE BUDGETS

- EQUIPENT/ MATERIAL AVAILABILITY

- PERSONNEL RESOURCES

- OUTAGE DURATION l

- REGIONAL POWER NEEDS l

0 END PRODUCT IS UNIT IMPLEENTATION SCHEDULES sevu - 12/10/87

e r:--... --

. ~ ' - -... =. - - - -

i MILLSTONE UNIT 2 EXPOSURE SAVINGS THRU' ALARA (man-rem) 1981 82 Sheilded Waiting Areas 40 1983 84 Task Channel Head Decon loop Area Shieldino F

30 61 Plug Repair 200 11 Tube Sample 130 5.7 1985 Task Channel Head Decon loop Area Shieldina Sleeving 1200 120 Plugging 82 2

Radiography 37 4.5 Tube Sample 55 4.5 1986 Ta,s_k Channel Head Decon loop Area Shieldin_q Plugging & Sleeeving 57.3 28 ECT 12.5 1.5 Studge Lancing 3

Radiography 4.2

~E

-58 Haddam Neck (Connecticut Yankee) 1986 Exposure Savings Realized by ALARA Controls Estimated Savings ALAR A Control (Person Rem) 1.

Shielding for RCS temperature element mod.

137 2.

Monitoring abovejobwith CCTV 21 3.

Shielding for hanger work 24 4.

CCTV monitoring for steam generator work (primary side) 32 5.

Using robotic equipment for steam generator (secondary side inspection (ECT) 86 6.

Shielding used for cavity seal replacement 48 7.

Shielding for valve operator work in loop area 19 l

8.

Shielding for in serviceinspection 10 9.

CCTV monitoring for RCP seal repairs 10

10. Shieldir.g for RCP seat repairs 6
11. Shielding for various Appendix R modification 10 l

I i

g.

J.

MILLSTONE UNIT 1 1984 Exposure Savings Realized by ALARA Controls Estimated Savings ALARA Control (Person Rem) 1.

Flush concentrator prior to repair.

5.0 2.

Replace lower head of'B' concentrator 4.7 with a better designed one.

3.

Use a better grade material to retube 5.2

'B' co ncentrator.

4.

Worker familiarization for hose installation 2.1 into the spent resin tank.

5.

Removal of corrosion ring from fuel pool 23.7 to reduce general area dose rates for clean up work.

6.

Coordinating down power operations 1.0 with condenser bay work.

7.

Shielding CRD saw.

2.0 8.

Modify chain hoist so one man can handle 2.0 radwaste drums.

9.

Chemicaldecontamination of the recirculation system a.

Pipe Repairs 600.0 b.

Class 1 In service Inspection 100.0 c.

Hanger Modifications 25.0 d.

Other Drywell Work 575.0 Total 1345.72 I

C

< i i

MILLSTONE UNIT 1 1985 Exposure Savings Realized by ALARA Controls Estimated Savings ALAR A Contr_'

(Person Rom) _

1.

Fuel poo " st rine" decontamination for LPRM 19.8 and control rod blide disposal.

2.

Replacement of the refaciing mast take up cable 31.2 3.

Shielding for hanger work 2

l l

1 1

. 'n-d MILI. STONE UNIT 1 1986 Exposure Savings Realized by ALARA Controls Estimated Savings ALAR A Control (Person. Rem) 1.

Improved material logistics for turbine 5

building roof repairs.

2.

Shielding for hanger work 3

3.

Decontamination 10 I

J I

~

-. =

.i.

,=

FORTY-YEAR OPERATING LICENSE AMENDHENTS o

NU HAS AN EFFECTIVE ALARA PROGRAM o

SIGN!FICANT RESOURCES HAVE BEEN AND ARE BEING APPLIED TO CONTINUE TO REDUCE OCCUPATIONAL EXPOSURE o

TIMELY APPROVAL OF THE FORTY-YEAR OL AKENDMENT LOWERS COST TO OUR CUSTOMERS J

I i

CFS - 12/10/87 l

^

1."

ATTACHMENT 3 REQlEST FOR ADDITIONAL INFORMATION o

HADDAM NECK LICENSE EXTENSION:

1.

The staff notes that Haddam Neck has one of the highest cumulative ave. age exposures of any operating pressurized water reactor (PWR) in the United States.

In addition, the average exposure for the three most recent years (i.e., 1984 - 1986) has remained relatively high. Given the magnitude and persistency of these exposures, the staff requests that NNECO provide a more detailed breakdown of the annual occupational exposures for Haddam Neck for every year from 1978 to the present.

As part of this breakdown, NNEC0 should identify and describe, to the extent feasible, every job performed during this period in which more than 10 person-rems were expended. NNEC0 should provide its definition of "special mainte-nance" work and, for each job listed, should state whether this work was classified as being a special maintenance job.

2.

For those jobs described above that are of a repetitious nature, provide a table listing each of these jobs along with the correspond-a.

ing exposures expended for each of the years from 1978 to present (similar in format to the table on page 5 cf the 1986 Refueling and Maintenance Outage ALARA Report).

b.

Describa the measures th6t NNEC0 has taken to eliminate or reduce the frequency of perfoming these jobs, or parts of these jobs; Describe the measures that NNECO has taken to reduce exposures re-c.

^

ceived from performing these jobs. For those jobs listed where the

, ye:r.ly exposures have increased or remained the same;over'the. la_

several yea.rs exposures m1,d, describe why efforts have been unsuccestful in reduc

' 7 g' ed to theiMdebs.

a.

If these jobs are being performed 'n the'same or similar equipment or d.

o components, identify the components, the nature of the work (repair, maintenance, or replacement), and what is being done to avoid repetition.

.3.

Describe the steps that.NNECO has taken.over the preceding years to

' prevent these relativelych'ighl exp6sures from steam generatoi i.pspections 1

and repair projects.' "Specifically,"provide t'he.following informaticn: -

J Identif sures (y and describe the steps that NNECO has taken to reduce expo-a.

e.g., use of rutemation, robotics, etc.) during steam generator inspection and repair projects. Note the time periods in which these steps were taken and describe their degree of success in reducing exposures.

Describe what further steps NNECO plans' to take to reduce steam generator work-related exposures.

b.

Identify and describe NNECO's efforts to lower dose rates (e.g.,

through decontamination and/or shielding) in and around steen genera-tors prior to maintenance.

Describe the success of these efforts in reducing area dose rates.

'2

  • ^.,_

' c.

Identify and describe the steps that NNECO has taken to minimize the l

need for steam generator repairs.

For example, describe any changes in water chemistry control made to minimize steam generator tube corrosion. Have condenser tube leaks contributed to degradation of the steam generator tubes, and, if so, what has been done to alleviate this problem?

d.

Describe NNECO's plans, if any, and time schedule to replace the steam generators at Haddam Neck.

Describe what steps will be taken to ensure that NNECO will not have similar problems with the new steam generators, State what jobs other than steam generator-related work are large e.

contributors to the annuel dose at Haodam Neck on a repetitive basis.

What efforts have been made to minimize the exposures related to these jobs.

4.

Provide NNECO's exposure goal for Haddam Neck and the time frare for meeting this goal, and describe the specific steps that NNEC0 will take to reduce exposures at Haddam Neck to 500 person-rems per year, or less.

Describe how you plan to enforce these exposure goals and yhat steps you plan to take when these goals are exceeded.

5..

Describe NNECO's criteria for perfoming ALARA reviews over the time

' period 1978 through the present.

If the criteria is the same as for Millstone-2, merely state that is the case.' In particular, state NNECO's cutoff exposure above which an ALARA review must be performed. Provide, to the extent feasible, the percentage of jobs receiving ALARA reviews for each of the years 1978 through present. An, integral part of any ALARA

.y' f.r.eview is,the post-j)b review.'.. diffe:rences tistwieWestiMted Tand a' This i'eview consists.-ofi.compar.ing.

better ways'to perforin the task in.the future (e.g.. use of mockups and testing for operability of equipment prior to'initiatins the job, use of different equipment, use of shielding, changes to job procedures, erection of pemanent staging and/or platfoms, use of experienced workers) that would result in even lower overall exposures. Describe NNECO's procedures for evaluating and implementing post-job review ALARA recomendations which may result in lower future exposures for perfoming repetitive jobs.

'6' Provide any additional-inforstati'on that NNECO thinks is relevant for the staff to reach'a favorable conclusien rega'rdintj the license

  • extension' at this time, rather than deferring consideration of HNECOs request to allow NNECO additional time to identify root causes of, correct, and reduce occupational exposures at Haddam Neck.

7.

Provide a copy of the ALARA program appraisal conducted by the corporate staff of Northeast Utilities (NU) of the Millstone and Connecticut Yankee sites. The report describing the finding is dated December 18, 1986.

Include the "Outage ALARA Reports for 1983, 1984, 1986, and 1987.

_

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