ML20148F278
| ML20148F278 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/19/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011040738 | |
| Download: ML20148F278 (9) | |
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FEB 191976 Docket No. 50-29 Yankee Atomic Electric Company ATTN:
Mr. Robert H. Groce Licensing Engineer
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Westboro, Massachusetts 01581 pgGES t
centlement POOR Q RE:
YAAIKEE-ROWE on May 5,1975, the Commission published Appendix I to 10 CFR Part 50 which sets forth numerical guides for design objectives and. limiting conditions for operat. ion to meet the criterion "as low as practicabled regarding reisases of radioactive materials in effluents from lignt-water m oled nuclear reactors.Section V.B of Appendix I requires the holders of permits or licenses authorizing the operation of light-water-cooled reactors, for which application was filed prior to January 2, 1971, to file with the' Commission by June 4,1976:
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Such information as is necessary.to evaluate. the means employed for keeping levels of radibactivity in effluents to unrestricted areas as low as practicable, including all such information'as is required by paragraphs 50 34a(b) and (c) not already contained in his application; and 2.
Plans and proposed Technical Specifications developed for the purpose of keeping releases of radioactive materials in unrestricted areas during normal reactor operations, including expected operational occurrences, as low as practichble.
9 In a letter to you from D. Muller dated June 27, 1975, we indicated that the staff was in the process of developing guidance for licensees required to file information with the Commission under the provisions of Section V.B of Appendix 1.
This guidance is set forth in Enclosure 1.
< makes reference to proposed Regulatory Guides 1. AA, taru l.FF.
Tnese guides have been published in draft form and are available in the Commission's public document room.
Copies of these guides are being forwarded to you under separate cover. 'We are preparing additional guidance regarding the formulation of Technical Specifications to implement Appendix I which will be forwarded to you in the near future.
It is recommended that proposals to modify Technical Specifications related to Appendix I be deferred pending the completion of tnis guidance in order to obtain
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Form MC 3Is (Rev,9 53) AICM 0240 1'r u, s. eovsanushv raiwtime orrics ist4.sse ese
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.g FEB 101976 Yanxee Atomic 61ectric Company.
I provides a list of.information we will need to evaluate your facility.
The staff is in the process of determining whether plants for wnica application was filed pri5r to January 2. 1971, can be treated in a manner similar to the treatment given to later plants in the Commission's September 4,1975 Amendment to Appendix 1.
On this basis, the information called for by Enclosures 1 and 2 would be sufficient to determine
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compliance with the criteria set forth 'in Section II, paragraphs A, B and C of Appendix I and the design objectives set forth in the Concluding Statement of Position of the Regulatory Staff in Docket RH-50-2, which ia reproduced as an Annex to Appendix I as amended Septemoer 4, 1975.
It further information is required to satisfy a plant specific assessment under Section II.D of Appendix I, we will so inform you at a later time.
Within 30 days of the receipt of this letter, you snould inform us of the measures you intend to adopt or propose to meet the requirements of paragraph 50 34a.
We suggest that a meeting between your staff and tne NRC staff be arranged shortly thereafter to discuss the submittal of i
data and methods of evaluation.
Sincerely, t
Robert A. Purple, Chief Operating Reactors Branch #1 j
. Division of Operating Reactors Enclosurest 1.
Guidance to Holders of Permits to Construct DISTRIBUTION or Licenses to Operate Light-Water-Cooled NRC DPR DEisnhut Reactors for which Application was Filed Local PDR
/ VStello Prior to 1/2/71 to Meet the Requirements Docket File / ACRS (16) of Appendix I to 10 CFR Part 50 ORB #1 Reading KRGoller 2.
Additional Information 5eeded from Holders TJCarter i
of Permits or Licenses to Construct or 0 ELD Operate Light-Water-Cooled Reactors for OISE (3)
'Which Application was filed Prior to 1/2/71 RAPurple ABurger co: with enclosures SMSheppard See next page JCollins TBAbernathy JRBuchanan
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- : Mr. Donald G. A11ca, President Yankee Atomic Electric Co::pany 20 Turnpike' Road Westboro, Massachusetts 01581 Greenfield-Public Library 402 Main Street Greenfieldi Massachusetts 01581 1
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5 ENCLOSURE 1 Guidance to Holders of Permits to Construct or Licenses to Operate Light-Water-Cooled Reactors for Which Application was Filed Prior to January 2, 1,71 to Meet the Requirements of Appendix I to 10 CFR Part 50 1.
Licensees should provide an evaluation showing their facility's capability to meet the requirements set forth in Section II of
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Appendix'I to 10 CFR Part 50 2.
Radioactive Source Terms used in the evaluation should be consistent with the paraceters and ecthodology set forth in Draft Regulatory Guides 1.BB or 1.CC (as appropriate).
Note: For BWRs gaseous releases from the. containment building and auxiliary building should be cocbined to form reactor building release for pre-BWR/6 Mark III Containment
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Meteorology / Hydrology information used in the calculation of doses should be consistent with Draft Regulatory Guides 1.DD and 1.EE.
4.
Dose Calculations should be consistent with Draft Regulatory Guide 1.AA.
5.
Effluent Release Data from previous reactor operation should be provided, if available, for use in evaluating the source term calculations.
Such data should include at least one full year of effluent release data tabulated by effluent release point, month, mode of operation (e.g., full power operation, refueling shutdown),
excluding the first, year of reactor operation.
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The above evaluations should be accompanied by the infor=ation requested in Enclosure 2 Exceptions from the information requested will be considered on a case-by-case basis.
7.
The staff is preparing standard Technical Specifications and will issue further guidance'to licensees regarding changes to Technical Specifications to i=ple=ent the Appendix I objectives.
Proposed revisions to Technical Specifications by licensees based on the limiting conditions for operation set forth in Section IV of Appendix I should~ be withheld pending further guidance fro: the staff.
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Additional Information Needed' from Holders of Permits or Licenses to Construct or Operate Light-Water-Cooled Reactors for Which Application was Filed Prior to January 2, 1971
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.1.
Provide.the infomation requested in Appendix D of Draft Regulatory Guide 1.BB or 1.CC, as appropriate.
2.
Provide, in tabular form, the distances from the centerline of the first nuclear unit to the following for each of the 22-1/2 degree radial sectors centered on the 16 cardinal compass directions.
a) nearest milk cow (to a distance of 5 miles) b). nearest meat andral (to a distance of 5 miles) c) nearest milk goat (to a distance of 5 miles) d) nearest residence (to a distance of 5 miles) e) nearest vegetable gaden greater than 500 ft2 (to a distance of 5 miles) f) nearest site boundary For radioactivity releases from stacks which qmlif'y as elevated releases as defined in Draft Regulatory Guide 1.DD, identify the locations of all milk cows, milk gcats, meat animals, residences, and vegetable gardens, in a similar manner, out to a distance of 3 miles for each, radial sector.
3 Based on considerations in Draft Regulatory Guide 1.DD, provide estimates of relative concentration (X/Q) and deposition (D/Q) at locations speci-fled in response to item 2 above for each release pofnt specified in response to item 1 above.
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Provide a detailed description of the meteorological data, models and parameters used to detemine the X/Q and D/Q values.
Include info ration 1
.concerning the validity and accuracy of the models and assumptions for your site and the representativeness.of the metecrological data used.
5 If an onsite program comensurate with the reccmendations and intent of Regulatory Guide 1.23 exists:
a) Provide representative annual and monthly, if available,, joint frequency distributions of w1nd speed and direction by atmospheric stability class covering at least the most recent one year period of record, preferably two or more years of recond. Wind speed and
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direction should be measured at levels applicable.to release point elevations and stability should be detemined from the vertical temperature gradient between measurement levels that represent con-ditions into which the erfluent is released.
b) Describe the representativeness of the available data with respect to expected long-tem conditions at the site.
6.
If recent onsite meteorological data are not available, or if the meteorological measurements program does not meet the recomendations and intent of Regulatory Guide 1.23:
a)
Provide the best available meteorological data in the fonrat described in item 5.c above.
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b) ' Describe the representativeness of the available data with respect to onsite and near site atmospheric transport ard diffusion conditions, and with respect to expected long term conditions at ard near the site.-
c) Provide a description of the meteorological measurements used for collection of the data presented. This description should include the locatien of the sensors with respect to the pcwer plant (s) and other prominent topo p aphic features (including buildings) and accuracy of the instrumentation.
d) Provide a ecmitment to establish a pregam to meet the reccmendations and intent of Regulatory Guide 1.23, or provide sufficient justifi-cation to allow the present program to remain unchanged.
7 Describe airflew trajectory regimes of importance in transperting effluents to the locations for which dose calculatichs are made.
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Provide a map showing the detailed topographical features (as modified t
by the plant, en a large scale, within a 10-m11e radius of the plant and a plot of the maximum toperaphic elevation versus distance from the center of the plant in each of the sixteen 22-1/2 degee cardinal ccd: pass point sectors (centered on true north), radiating from the center of the plant, to a distance of 10 miles.
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Provide the dates and times of radioactivity releases from intemittant sources by source location based on actual plant operation and, if l
'available, appropriate hourly meteorological data (1.3., wind direction and speed, and atmospheric. stability) during each period o.' release.
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