ML20211G667
| ML20211G667 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/30/1989 |
| From: | Sears P Office of Nuclear Reactor Regulation |
| To: | Frizzle C Maine Yankee |
| Shared Package | |
| ML20211G606 | List: |
| References | |
| FOIA-97-154 NUDOCS 9710030152 | |
| Download: ML20211G667 (5) | |
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Docket No. 50-309
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Mr. C. D. Frizzle, President C*
Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Q@
Dear Mr. Frizzle:
SUBJECT:
ACCEPTANCE FOR REFERENCING TOPICAL REPORT YAEC-1300P, VOLUMES 1
?, 3. "RELAP5YA: A COMPUTER PROGRAM FOR
'."..;T WAT:R REACTOR SYSTEM ' DERMAL-PYDRAULIC ANALYSI. '
By letter dated October 14, 1988, enclosed, the staff found the subject report to be acceptable fer referencing in licensing applications to the extent specified and under the limitations delineated in the subject report and in the associated NRC evaluation.
That evaluation is contained in the enclosure.
In the Idaho National Engineerinn Laboratory Repnrt (EGG-TFP-7933), " Technical Evaluation Report RELAP5YA Computer Program For Use In PWR Small Break LOCA Analysis" which is also part of the enclosure, it was stated that nothing was found in the code to preclude the application of RELAP5YA to Maine Yankee.
Thus, the application of RELAPSYA to Maine Yankee is approved to the extent specified and under the limitations delineated in the enclosure.
If you have any questions, centact P. Sears at 301-49?-1437.
Sincerely.
'M hf2_.
4w Petrick Sears, Project Manager Project Directorate I-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
NOTE: COMPI.ETc COPY LOCATED IN CORPORATE FILES.
See next page 4
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Mr. C. D. Frizzle Maine Yankee Atomic Power Company Maine Yankee Atomic Power Station Cc:
Mr. C. D. Frizzle, President Yankee Atomic Electric Company Maine Yankee Atomic Power Company ATTN: Mr. P. L. Anderson 83 Edison Drive Project Manager for Maine Yarkee Augusta Maine 04336 580 Main Street Bolton, Massachusetts 01740-139a Mr. Charles B. Brinkman Mr. G. D. Whittier, Manager Manager - Washington Nuclear Nuclear Engineering and Licensing Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc.
83 Edison Drive 12300 Twirbrook Parkway, Suite ??O Augusta, Maine 04336 Rockville. Md. 70852 John A. Ritsher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Dr. E. T. Boulette, Vice President Operations and Plant Manager Maine Yankee Atomic Power Company P. O. Box 408 Wiscasset, Mairie 04578 Mr. J. H. Garrity, Vice President Licensing and Engineering Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Regional Administrator, Pegion I
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U.S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset Municipal Building U.S. Route 1 Wiscasset, Maine 04578 Mr. Corneliue F. Holden Resident *.nspector c/o U.S. Nuclear Regulatory Comission P. O. Box E j
Wiscasset Maine 04578 l
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11 NRR ALLEGATION REVIEW BOARD MEETING e
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Coatset:
Bob PoDerd, Rich Hayes Monday, Deoseber 4,1995 (202)n2 0900 WR1%n.E BLOWER ACCUSES MAINE YANKEE OF FALSIFYIN(; DOCUMENTS AND JEOPARDETNC PUBl.IC SAFETY
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According io docum stetion anonymoudy peu,4 to the Union of Concerned Scientieta, samasanees et the Maina \\ ankee clear poww plant deliberstaly falsland computer e=hMama to
,i eswid declesing that the plant's cooling sysema are inadequate to mitigate a 'c 4=W accidas, f.
g ihcrossise the probebility da core mahdown The documerws also indicate that a f
?anvered up the fact that the reactor buihling may not rernain intas: aRor a mq)or pipe break.
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"Meins Yankee should not be pennkted to resume opwarion until a thoitush, thetual 0
hmmission s' compleand,* said Roben Ponant, Senior Nuclear Safay Engineer. *1fth are trus, ths Maine Yankee plant has been operating under dangerous condidons fbr years and ca penuwee the puhEc's satety.'
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a were purportedly sent by a longtime employee of the Yankee Atomic PJactric Compery. The individual claims that Maine Yanka management dehbcestely Ansited repor Nuclear Regulatory r aa=*=% in order to tocaive approval to increase the reactor's sumi:smo aDowable poww level.
"Whhoa access to internal Maine Yaakes documents, I cannot detenmine the accuracy
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anessticas,' saH Pollard. "However, it is appartse that this information was provkled by someons l
is h.w'49 of the subject matter and has accus to documents ther are act publicly avaBable *
' lie 19791hree Mile Island accident in Harrisburg, Pennsytvania was a loseo0 coolant musident that showed existing computer models wwe inadequate to predict core enski is Thorister, the NRC required na plaats to review sad, irascussary, revise the computer models used to cakndsee the effbetiveness of cmergency core coo 5ng systesns. While plants were esquired to complans these wasputer e=laMama by 19s3, Maine Yanicos did not submit their analysis until about 1999
" n% it appears that the NRC never reviewed Maine Yankee's e=ladasiaaa As a assuk, Maine Yankee opersed in na unssib ocodition bdore closing in Jarmary 1995 lbr unreissed staan 5
generenor repeien. Since them, the pism has been repairing corroded steam sencrator tubes by insertin mets stava inside tin tubea.
"Unfenuestely, i A ; 17,000 tubes forther degrades the ability of the emergency core cooEng i
systems to prevent a meltdown " said Pollard. *!t is necessary to detenmine, using a computer anodel that has act been falsl$ed, that the cooling systems are adequate to protect the pubGc."
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i-MAINE YANKEE ALLEGATION REVIEW TIMOTHY E. COLLINS REACTOR SYSTEMS BRANCH DIVISION OF SYSTEMS SAFETY AND ANALYSIS DECEMBER 18, 1995
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i-j ALLEGATION
SUMMARY
ECCS INADEQUATE FOR OPERATION AB0VE 2400 MWt
- POST-TMI HODEL EXCEEDS PCT LIMITS
- BEST ESTIMATES USED IN PLACE OF APP K CONTAINMENT INADEQUATE ABOVE 2400 MWt MISREPRESENTATIONS USED FOR POWER UPRATE TO 2700 MWt i
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\\9-George'Papanic, Jr.
S Senior Project Engineer 3
Licensing
- Q Yankee Atomic Electric Company 1671 Worcester Rd.
Framingham, MA 01701
Dear Mr. Papanic:
SUBJECT:
ACCEPTANCE FOR REFERENCING TOP: CAL REPORT YAEC-13MP, VOLUMES 1, 2, 3, "RELAP5YA:
A COMPUTER PR0f: RAM FOR LIGHT WATER REACTOR SYSTEM THERMAL-HYDRAULIC ANALYSIS" The Nuclear Regulatory Commission (NRC) st?ff has completed its review of
. Yankee Atonic Electric-Company (YAEC) licensing topical report YAEC-1300P, "RELAPSYA:
A Computer Program for Light dacer Reactor.Systen Thermal-Hvdraulie Analysis "
The staff finds the report to be acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the report.and the associated NRC evaluation (Enclosure 1).
The evaluation defines the basis for acceptance of the report.
Pursuant to 10 CFR 2.790, we have determined that the enclosed evaluation does not contain proprietary information.
However, we will delay placing the evaluation in the public document room for a period of ten (10) working days from the date of this letter to provide suu with the opportunity to coment nn the proprietary aspects only.
If you believe that any information in the cnclosure is proprietary, please identify such information line by line and -
define the basis pursuant to the criteria of 10 CFR 2.790.
The staff does not intend to repeat the review of the matters described in the report and found acceptable when the repart appears as a reference in licensing applications, except to assure that the material presented is applicable to the specific plant involved.
The staff's acceptance applies only to the matters described in the report.
In accordance with procedures established in NUREG-0390, it is requested that YAEC publish an accepted version of this report with the review questions and answers within 3 months of receipt of this letter. The accepted version shall incorporate this letter and the enclosed evaluation after the title page.
The accepted version shall include an -A (designated accepted) following the report identification symbol.
Should the staff's criteria or regulations change such that the conclusions as to the acceptability of the report are invalidated, YAEC and/or the applicant r;ferencing the topical report will be expected to revise and resubmit their Af g
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respective documentation, or submit justifi:ation for the continued effectivs applicability of this topical report without revision of theie respec,tive documeatation.
Sincerely, 5
Ashok C. Thadani, Assistant Director for Systems Division of Engineering & Systems Technologv Offi e of Nuclear Reactor Regulation
Enclosure:
Topical Report Evaluation DISTRIBUTION
- Central Files SRXB R/F A. Thadani N. W. Hodges ton H. Fairtile S. Sun S. Sun R/F
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%ooo ENCLOSUPE 1 SAFETY EVAltlATMM BY THE OFFICE 0' NUCLEAR PEACTOR REGULATION RELATING TO THE R:LAPSYA CODE FOR USE IN PWR SMALL BREAK LOCA ANALYSES FOR MAINE YANKEE AND Yt.NKEE R0WE ptANTS To satisfy the requirements of NUREG-0737, THI Action item II.K.3.30, Yankee Atomic Electric Company (YAEC) submitted RELAF5YA describTd in the topical report YAEC 13 COT, 'T.ZLATSYA:
A Computer Program for Light Water Rcactor System, Thermal-Hydraulic Analysis," for NRC review and approval as a licensing method for a small break loss-of-coolant-accident (LOCA) analysis.
NRC has used technical assistance by the Idaho National Engineering Laboratory (INEL) under contract FIN-B6039 in the review of the topical report.
The NRC has reviewed the Technical Evaluation Report (TER) on the' evaluation which is in Appendix.' ewf this Safety Evaluatin (SF).
The staff concurs in the recommendations made by INEL and finds that the RELAPSYA is acceptable as a licensing method for a SBLOCA analysis under the conditions stipula'ted.
The conditions are identified in Section 6 of the attached TER and are restated as follows:
1.
RELAP5YA is applicable for modeling LOCA events with the break sizes up to 0.7 ft.
If YAEC uses the code-for SBLOCA with break sizes larger than 0.7 ft, YAEC must ensure that the code. predicts important phenomena which may occur as discussed in Appendix A.
2 Use of RELAP5YA is restricted to analyzing SBLOCAs where the accumulators do not empty and the hydroges concentration remains above 5 cc H /kg of 2
water so that radiolytic decomposition of water is not a source of noncondensible gas.
Otherwise, additional justification must be provided in the plant specific applications.
3.
RELAP5YA overpredicts the condensation rate during a pressurizer insurge.
YAEC stated condensation of vapor in system high points and the pressurizer \\\\op01ortion of a SBLOCA ara refill beyond th' point of interest st 1t qg,
2 because the core i'. covered and there is no longer a question of plant safcty.
Therefore, RELAPSYA cannot be used to analyze SBLOCAs during periods of condensation of vapor in system high points and pressurizer insurge.
Otherwise, further justifier +1en must be provided in the p1"+
specific applications.
4 Due to the large interphase mass transfer coefficients used in RELAP5YA, the code is unable to calculate the presence of superheated vapor unle u the volume void fraction is 1.0.
Therefore, for any analysis where it appears the presence of vapor superheat would have a significant effect on the system response or the peak-clad temperatere, YAEC should justify that the model nodalization was detailed enough to account for vapor superheat.
This would include any SBLOCA analysis where the two-phase mixtt;re level dropped below the top of the core due to long term core boiloff.
5.
RELAP5YA also overpredicts the condensation rate when subeceled ECC is injected.
To mitigate the effects of inje.cting subemled ECC, YAEC developed ECC modeling guidelines. These guidelines'specify that the ECC water be modeled wi.h a temperatore of 2CO'F instead of the noHr.:' plant temperature of approximately 100'F.
This guideline is acceptable and any deviation from it must be justified.
In addition, the analysis used to justify that the cold leg nodalizatien at the injection point is sufficient to represent condensation induced by the ECC used 200'F water.
If colder ECC is used in a licensing analysis, the effect of cold leg nodalization on condensation must be reassessed and the results provided for NRC review.
6 The nine modifications reviewed in Section'2.2 that apply to pWR SBLOCA analyses are acceptable for use in ideensing analyses with the following restrictions:
6.
The Moody' critical flow model is correctly implemented.
- However, plant licensing analyses must use the model options recommended by
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l YAEC, i.e., the donor cell sta:ic pressure and enthal,sy as input to the Moody c*itical flow table (see Section 2.2.2 of Appe.1 dix A).
b.
The multiple surface radiation model is acceptable for licensing applications provided justification of the view factor matrix used is given or, if a code is used to generate the view factor matrix, the code should be submitted for NOC review and approval (see Section 2.2.7 of Appenoix A).
c.
The fuel behavior models are acceptable as implemented provided the rod internal pressure temperature offset is greater than 2'F (see Section 2.2.9 of Appendix A).
7 There are a large number of optiont available to the user in RELAP5VA.
To ensure that the code is used within its capability and with proper input, the licensee should provide future plant specific licensing submittals justifying all selected options and input data, including defaults.
8.
YAEC noted that the following items will be performed on a plant specific basis and documented in the plant submittal:
time step sensitivity studies; break size sensitivity studies; a list of metal heat slabs used at various nodes including justification of any metal structures not represented in the analysis; clarification of how the multiple surface radiaciun model is used in EH analyses; justification that clad geometry changes during a SBLOCA do not change the radiation model view factors, justification of any nonzero value for the direct moderator heating fraction; and justification of the pressurizer nodalization used in SBLOCA licensing analyses.
9.
YAEC will also provide justification of the steam generator nodalization in SBLOCA licensing analyses on a p. ant specific basis with the plant submittal. The steam generator nodalization will be determined based on
A sensitivity studies to show convergence cf the PCT.
In order to calc. slate low flow and reflux cooling conditions any nodslization propsied by YAEC should have at least eight nodes to represent the U tubes (see Section 5 of Appendix A).
10.
The analyses that assessed RELAPSYA's ability to calculate the core thennal-hydraulic response during core uncovery and recovery had nodalizations that used at least six volumes in the core.
Therefore, YAEC is required to use at least six volumes in the core for its plant licensing ana1"ses.
More detail may be needed if calculating vapor superheat is *.Aortant in the analysis.
The complete nodalization used in a plant licensing analysis should be consistent with current modeling guidelines or the nodalizations used in the assessment calculations.
Any differences should be justified.
11.
Certain models, as discussed in Section 4 of Appenoir A, are not acceptable for use in licensing applications, inese models include known errors and YAEC chose not to incorporate available uedate corrections.
12.
In several of the i tegral assessment calculations, the system at: sure was underpredicted and, as a result, accumulator injection began earlier than in'the experiment. The system depressurization rate was calculated better when a discharge coefficient less'than 1.0 was used.
The effect of discharge coefficients on the calculated results is the same as varying the br6ak area, Therefore. YAEC is required to perfonn a break size study to include the worst SBLOCA case for the plant specific licensing applications.
Bas d on its review of the YAEC's submittals and INEL's TER, the staff concludes that RELAPSYA is acceptable for use in SBLOCA analyses and licensing applications when above conditions are satisfied.
s..,.
egg ec/.r EGG.TFM.7933 TECHNICAL EVALUATION REPORT RELAP5YA COMPUTER PROGRAM FOR USE IN PWR SMALL BREAK t.0CA ANALYSES C. P. Fineman May 1988 p
Idaho National Engineering Laboratury EG&G Idaho Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Comission Washingten D.C. 20555 Under 00E Contract No. DE AC07-761001570 FIN No. 06022
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ABSTRACT A review was completed of the RELAP!/A computer program developed by Yankee Atomic Electric Company (YAEC) for - -forming oressurized wa6er reactor (PWR) small break loss-of-coolant accident (SBLOCA) licensing
- .1alyses.
The review consisted of an evaluation of the RELAP5YA computer orogram as well as the modifications made by VAEC to the RELAP5/M001, cycle 18, computer program from which the licensing version of RELAPSYA originated.
Separate effects and integral assessment calculations were reviewed te evaluate the validity and proper implementation of the modifications and added models.
The review found that RELAP5YA met the recuirements of 10CFR50.46, Appendix X, and NUREG-0737, item !!.X.3.30, and it is recommended the code be acce:ted fo use la PWR SBLCCA licarsing analyses on the basis that suggested conditions and recuirement-are followed.
The largest break size YAEC used to assess RELAP5YA was ecuivalent to a 0.7 ft2 break in a PWR.
RELAP5YA may be used to analyze breaks larger than this if the important onenomena for the 'arger creak sizes are similar to that assessed for the 0.7 ft2 and smaller breaks.
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Sul94ARY This report documents the review and evaluation of the Yankee Atomic Electric Comodhy (YAEC) computer program RELAP5YA for use in performing oressurized water reactor (PWR) small bevak loss-of-coolant acc Hent (58LOCA) licensing analyses.
RELAP5)A is capable of analyzing the steady state and transient thermal-hydraulic response of a light-water reactor.
The code has features that allow compliance with the requirements of 10CFR50.46 and Appendix K.
RELAP5YA was cased on RELAP5/M001, cycle ao, developed at the Idaho National Engineering Laboratory (INEL) under Nuclear Regulatory Conniission (NRC) sponsorship.
The code was submitted to the Office of Nuclear Reactor Regulation (NRR) for approval as a licensing method.
NRR requested assistan:o from tne INEL in reviewing RELAP5YA.
Assistance in ti.e review was limited to those aspects related to f'nR steady state and $8LOCA transient spolications.
The RELAP5YA code was reviewed and tssessed as well as the model additions and modifications made by YAEC to RELAP5/M001, cycle it,.
This review was made using the information provided by'YAEC in the RELAP5YA cede manuals, Volumes 1, 2. and 3, and in the utility's aesponses to euestions submitted by the NRC to YAEC.
The code was also reviewed to ensure that known updates and corrections to RELAP5/M001, cycle 18, were included in RELAP5YA by YAEC or appropriate justification given if excluded.
- Finally, the code was reviewoi for compi sance witn NRC requirements.
Base'd on this review, it is reconenended that RELAP5YA be accepted for performing PWR 58L0CA licensing analyses, including the calculation of paak clad temperature, provided that suggested conditions and requirements are followed.
The largest break size Y EC used to assess RELAP5YA'was equivalent te a 0.7 ft2 break in a PWR.
RELAP5YA may be used to analyze
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breaks larger than this if the idiportant phenomena for the larger break sizes are similar to that assessed for the 0.7 ft2 and smaller breaks.
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CONTENTS ABSTRACT....................
SUMMARY
1.
INTRODUCTION.....................................................
4 2.
RELAP5YA CODE DESCRIPTION AND ASSESSMENT...................'......
3 2.1 Genera 1 Code overview.............. *.
2.2 Model Description and Assessment...........................
5 2.2.1 Interphase Drag Models for the Vertical Flow Regime............................................
5 2.2.2 Moody Critica1 Flow Model.........................
7 2.2.3 Accumulator.......................................
9 2.2.4 Forced Convective Boiling
..l......................
9 2.2.5 Critical Heat Flux................................
10 2.2.6 Rowet and Quench Models...........................
12 2.2.7 Mul tiol e Surf ace Radiation........................
14 2.2.8 Heat Transfer Logic Options.......................
15 2.2.9 Fuel Behavior Models..............................
15 2.3 Assessment Calculations.............................. '
17 2.3.1 LOFT Sma11 Break Assessment Calculations........'..' 17 2.3.2 LOFT Intermediate Break Assessment Calculation....
25 2.3.3 Semiscale Assessment Calculation..................
35 2.3.4 THTF Assessment Calculations ;...............;....
44 2.3.5 Assessment Summary................................
44
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2.4 Phenomena'Important to PWR SBLOCA........................
a6 2.4.1 Noncondensible Gas................................
46 2.4.2 Condensation Heat Transfer........................
30 2.4.3 Natural Ci rcul ati on...............................
33 2.5 Calculation of S-UT-6 Phenomena...........................
58 3.
COMPLI ANCE WITH NRC REQUIREMENTh '................. '.........'.....
59 1
4 RELAP5/M001 CODE UPDATES.;;......;.;............................
61.
s 5.
SYSTEM MODELING TECHNIQUES. ; ; i.. :... ;. '..... '.. '...... '..............
62 6.
CONCLUSIONS.....................................................
66 7.
REFERENCES..............................-
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g OI Mr. George Papanic, Jr.
Senior Project Engineer-Licensing Yankee Atomic Electric Company
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580 Main Street Bolton, Massachusetts 01740-1398
Dear Mr. Papanic:
SUBJECT:
m*EG-0737 ITEM II.K.3.31 - PLANT SPECIFIC CALCULATIONS TO SHOWCOMPLIANCEWITH10CFR50.46(TACNO.48213)
By letter dated J&nuary 23,198F Yankee Atomic Electric Company..com{tted to w..
submit,the Yankee Nuclear Power Station plant specific small break LOCA g
analyses by the end of 1989. Ik consider this.comitment to be acceptable in regard to !! K.3.3b and are closing out the review performed under our TAC No.48213.
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Morton B. Fairtile, Project Manager Project Directorate I-3 Division of Reactor Projects 1/11 cc: See next page gob
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Mr. George Papanic, Jr.
Yankee Atomic Electric Company Yad ee.Nud m Power Station CC:
Dr. Andrew C. Kadak, President and Chief Operating Officer Mr. George Papanic, Jr.
Yankee Atomic Electric Company Senior Project Engineer-Licensing 580 Main Street Yankee Atomic Electric Comp!!ny Bolton, Massachusetts 01740-1398 580 Main Street Bolton, Massachusetts 01740-1398 Thomas Dignan, Esquire Ropes and Gray 225 Franklin Street Boston, Massachusetts 02110 Mr. N. N. St. Laurent Plant Superintendent Yankee Atomic Electric Company Star Route Rowe, Massachusetts 01367 l
Chaiman i
Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Resident inspector Yankee Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Adrinistrator, Region I U.S. Nuclear Degulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 7th Floor Boston, Massachusetts 02111 i
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