ML19319E054
| ML19319E054 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/18/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8003310520 | |
| Download: ML19319E054 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMimilON ej..
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WASHINGTON, D. C. 20555 t
February 18, 1976
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Docket No.: 50-312 l
Sacramento Municipal Utility District ATTN:
Mr. J. J. Mattimoe Assistant General Manager G Chief Engineer 6201 S Street P. O. Box 15830 Sacramento, Califernia 95813 Gentlemen:
RE:
RANCHO SECO 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 operation to meet the criterion "as low as practicable" regarding releases of radioactive materials in effluents from light-water-cooled 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; 1.
Such information as is necessary to evaluate the means employed for keeping levels of radioactivity 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 operation-al occurrences, as low as practicable.
In a letter to you from D. Muller dated June 17, 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 I.
This guidance is set forth in Enclosure 1.
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- Sacramento Municipal Utility District'
- makes reference to proposed Regulatory Guides 1. AA, through 1.FF.
These 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 reBarding'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 -codify Technical Specificatiens related to Appendix I be deferred pending the completion of this guidance in order to obtain a con-sistent format for radiological effluent release Technical Specifications. provides a list of information we wi:1 need to evaluate your facility.
The staff is in the process of determining whetht r plants for which appli-cation was filed prior to January 2,1971, can be treated in a manner e
similar to the treatment given to later plants in the Commission's September 4, 1975, Amendment to Appendix I.
Cn this basis, the infoi ation called for by Enclosures 1 and 2 would be sufficient to determine compli-ance with the criteria set forth in Section II, I aragraphs A, B, and C of Appendix I and the design objectives set forth in the Concluding State-ment of Position of the Regulatory Staff in Dock (t RM-50-2, which is reproduced as an Annex to Appendix I as arcended Septenber 4 1975.
If further informatica 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 should 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 the NRC staff be arranged shortly thereafter to discuss the submittal of data and methods of evaluation.
Sincerely,
{
l origha: C;c Sy Robert W. Reid, Chief Operating Reactors Branch #4 1
Division of Operating P.cactors
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Enclosures:
See next page i
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f DISTRIBUTION:
Sacrarento INnicipal Utilit'y NRC PDR DEisenhut L PDR District TBAbernathy Docket File JRBuchanan
Enclosures:
Guidance to Holders of Perr,;its to Construct VStell VRooney llGoIIer or Licenses to Operate Light-l'later-Cooled TCarter Reactors for tlhich Application was Filed OELD Pricr to 1/2/71 to ?:cet the Requirements OIGE (3) of Appendix I to 10 CFR Part 50 RReid RIngram 2.
Additional Inforcation Needed from Holders JCollins, ETSB of Permits or Licenses to Construct or Operate Light-tlater-Cooled Reactors for tlhich Application was Filed Prior to 1/2/71 cc w/ enclosures:
David S. Kaplan, Secretary and Genera 1 Counsel 6201 S Street Post 'Of fice Box 15S30 Sacramento, California 95S13 Busir. ass and Municipal Department Sacramento City-County Library 828 I Street Sacramento, California 95S14 ORB #4
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ENCLOSURE'1 Guidance to Holders of Per=its to Construct or Licenses to Operate Light-Water-Cooled Reactors for Which Application was Filed Prior to January 2, 1971 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 Appendix'I to 10 CFR Part 50 2.
Radioactive Source Ter=s used in the evaluation should be consistent with the paraceters and =cchodology set forth in Draft Regulatory Guides 1.BB or 1.CC (as appropriate).
Note: For BWRs gaseous releases from i the containment building and auxiliary building should be co=bined to form reactor building release for pre-BWR/6 Mark III Contain=ent designs.
1 3.
Metectolozy/H.drology infor=ation used in the calculation of doses should be consistent with Draft Regulatory Guides 1.DD and 1.EE.
a4 Dose Calculations should be consistent with Draft Regulatory Guide 1.AA.
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Effluent Release Data from previous reactor operation should be i
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provided, if available, for use in-evaluating the source ters calculations.
Such data should include at least one full year of effluent release data tabulated by effluent release point, =onth,
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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 infor=ation 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 implement 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 from the staff.
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Additional Informaticn Needed frem Holders of Pemits er Licenses to Construct or Operate Light-Water-Cooled Reactors for hhich Application was Filed Pricr to, January 2, 1971 1.
Provide the infomatien requested in Appendix D of Draft Regulatory Guide 1.BB or 1.CC, as appropriate.
2.
Provide, in tabular fom, 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 di ections.
a) nearest milk cow (to a distance of 5 miles) b) nearest meat anLTal (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 ganien greater than 500 ft2 (to a distance of 5 miles) f) nearest site boundar"/
For radioactivity releases from stacks which qmNy as elevated releases as defined in Draft Regulatory Guide 1.DD, identify the locations of all milk cows, milk goats, meat animals, residences, arri vegetable gardens, in a similar manner, out to a distance of 3 miles for each romp 1 secter.
3 Based on considerations in Draft Regulatory Guide 1.DD, provide estLTates of relative concentration (X/Q) and deposition (D/Q) at locatiens speci-fled in response to item 2 above for each release point specified in response to item 1 above.
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Provide a detailed description of the meteorob.ogical data, models and parameters used to detemine the X/Q and D/Q values.
Include information concerning the validity and accuracy of the models and assumptions for your site and the representativeness of the metecrolo5 cal data used.
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If an onsite program conr::ensurate with the reccanendations and intent of Regulatory Guide 1.23 exists:
a) Provide representative annual ard monthly, if avniinhle, joint frequency distributions of wird speed and direction by atmospheric stability class covering at least the most recent one year period of record, preferably two or nr:re years of record. Wird speed ard direction should be measured at levels applicable to release point elevations and stability should be detemed from the vertical temperature gradient between measurement levels that represent con-ditions into which the effluent is released.
b) Describe the representativeness of the available data with respect to expected long-tenn conditions at the site.
6.
If recent onsite meteorological data are not avMkhle, or if the meteorological measurements program does not meet the reconnendations and intent of Regulatory Guide 1.23:
a) Provide the best avnihhle meteorological data in the fonnat
, described in item 5.a above.
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b) Describe the representativeness of the avniinhle data with respect to onsite and near site atmospheric transport and difDision conditions, and with respect to expected long tem conditions at and near the site.
c) Provide a description of the meteorological measurements used for collection of the data presented. This description should include the location of the sensors with respect to the power plant (s) and other prominent tcpegraphic features (including buildings) and accuracy of the instrumentation.
d) Provide a comitment to establish a progran 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 airficw trajectory regtr.es of ir:portance in transporting effluents to the locations for which dose calculatichs are made.
8.
Provide a map showing the detailed topographical features (as Irodified by the plant, on a large scale, within a 10-mile radius of the plant ani a plot of the maximum topographic elevation versus distance frcm the center of the plant in each of the sixteen 22-1/2 degree caniinal ce pass point sectors (centered on true north), radiating from the center of the plant, to a distance of 10 miles.
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4-9 Provide the dates and times of radioactivity ' eleases frem intermittant r
sources by source location based on actual plant operation and, if available, appropriate hourly meteorological data (i.e., wind direction
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arxi spe'ed, and atmospheric stability) during each period of release.
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