View source for NRC Generic Letter 78-39, Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent Technical Specifications, BWR, and NUREG-0133

{{generic letter-Nav
| gl id = NRC Generic Letter 78-39
| name = Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent Technical Specifications, BWR, and NUREG-0133
| issue date = November 15, 1978
| url = https://www.nrc.gov/reading-rm/doc-collections/gen-comm/gen-letters/1978/gl78039.html
}}

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November 15, 1978 
TO ALL BOILING WATER REACTOR LICENSEES 
Gentlemen: 
In a letter from B. Grimes, Assistant Director for Engineering and Projects, dated July 11, 1978, you were sent guidance and a submittal schedule which requested a license amendment application to be submitted to incorporate the requirements of 10 CFR Part 50, Appendix 1 into your facility Technical Specifications. Since that time, the staff has continued its efforts to simplify the specifications through clarification of intent and the removal of unnecessary requirements. In conjunction with these efforts we have had a number of discussions with the AIF and others concerning comments and questions they developed with respect to the specifications. As a result of our continuing review, we have made substantive revisions to the Draft Radiological Effluent Technical Specifications (NUREG-0472, PWR and NUREG-0473, BWR), which were forwarded to you in July. Although these specifications have been extensively revised they still incorporate the fundamental requirements and concepts contained in the original documents. The major difference in these specifications from the previous ones is the removal from the specifications of the equations for dose calculations, setpoint determination and meteorological dispersion factors. These items, along with some miscellaneous items, are now required to be included in an Offsite Dose Calculation Manual (ODCM) to be prepared by the licensee and provided to NRC for review and approval along with your proposed Technical Specifications.
To assist you in preparing your submittal, we have enclosed a copy of Revision 1 of the Draft Radiological Effluent Technical Specifications. We have also enclosed for your use a copy of NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants. This NUREG document describes methods acceptable to the staff for the calculation of certain key values required in the preparation of the proposed effluent Technical Specifications.
In order to provide additional time to address this guidance, you may use the revised submittal schedule shown in Table 1. The submittal dates are referenced to the date of this letter.In addition to the guidance noted above, the following general information is also provided:
: 1)    The format for the revised Technical Specifications may be that presently used for your existing Appendix A Technical Specifications, provided all applicable areas of the model Technical Specifications are acceptably addressed. Although the staff recommends the format of the model Technical Specifications, its use is not mandatory.
: 2)    It has been misinterpreted by several licensees that the Technical Specification submittal need only address the individual dose design objectives of Appendix I. The submittal request must implement 10 CFR Part 50, Section 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors which addresses the maintenance and use of radwaste equipment installed pursuant to Section 50.34a(a), Section 50.34a which addresses Appendix I (Design Objectives IIA, IIB, IIC and IID), 10 CFR Part 20, 10 CFR Part 50, Appendix A General Design Criteria 60 and 64 which address the control and monitoring of releases of radioactive material to the environment, and 40 CFR Part 190, Uranium Fuel Cycle Standard. Consequently, the NRC excepts the submittals to reflect these and other issues addressed in the Draft Radiological Effluent Technical Specifications enclosed with this letter.
: 3)    The submittal should consolidate the radiological effluent and environmental monitoring Technical Specifications in Appendix A of the Technical Specifications. Consequently, if your facility presently has radiological effluent or radiological environmental monitoring Technical Specifications in Appendix B, you should request that they be deleted upon approval of the new Technical Specifications in Appendix A. The submittal should resolve all duplicative Technical Specification requirements in the radiological area.
: 4)    The entire Administrative Controls Section (6.0) of the Standard Technical Specifications was included for information. Only those areas related to radiological effluents and environmental monitoring need be considered for inclusion into the license amendment request. However, if you desire to convert your entire Administrative Controls Section to incorporate the STS requirements and format the staff could handle this as a separate request.

.To further assist you in the preparation of your submittal the NRC will conduct a one-day seminar on the Draft Radiological Effluent Technical Specifications at four of our Regional Offices. The dates and locations of the seminars are shown in Table II. Representatives for the Office of Nuclear Reactor Regulation will make the presentation and the agenda will include an introduction and background on the effluent Technical Specifications, the development of the Standard Technical Specifications, and the method and schedule for implementing the specifications. A question and answer period will follow the prepared presentation. More specific information relative to these seminars will be forthcoming from our Regional Directors.
Sincerely,

Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors
Enclosures:
: 1. Tables I & II
: 2. Draft Radiological Effluent Technical Specifications - BWR
: 3. NUREG-0133
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TABLE I
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS LICENSEE SUBMITTAL DATES
30 Days          60 Days           90 Days              120 Days
Farley           Big Rock Point    Arkansas             Beaver Valley Hatch            Ginna             Brunswick            Browns Ferry Haddam Neck       Crystal River        Calvert Cliffs LaCrosse          Dresden              Cook Oyster Creek      Fitzpatrick          Cooper San Onofre        Indian Point         Davis Besse Surry             Millstone            Duane Arnold Yankee Rowe       Monticello           Ft Calhoun Nine Mile Point      Humboldt Bay Oconee               Kewaunee Peach Bottom         Maine Yankee Pilgrim              North Anna Quad Cities          Palisades Robinson             Point Beach Turkey Point         Prairie Island Vermont Yankee       Rancho Seco Zion                 Salem St. Lucie Three Mile Island Trojan

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TABLE II
REGIONAL SEMINARS ON DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS
November 28, 1978 - Regional III
December 1, 1978 - Region IV & V (In Region V)
December 5, 1978 - Regional II
December 8, 1978 - Region I
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