ML18078B168

From kanterella
Jump to navigation Jump to search
Responds to NRC 781115 & 781116 Requests for Radiological Effluent Tech Specs.Requests Extension of Time Until 790430
ML18078B168
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/28/1979
From: Librizzi F
Public Service Enterprise Group
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 7904100349
Download: ML18078B168 (11)
v • d • e


Text

{{#Wiki_filter:Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 March 28, 1979 Director of Nuclear Reactor Regulation

u. S. Nuclear Regulatory Conunission Washington, D.C.

20555 Attention: Mr. A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Gentlemen: PROPOSED RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS SALEM NUCLEAR GENERATING STATION UNITS NO. 1 & 2 DOCKET NOS. 50-272 and 50-311 Your letters of November 15 and 16, 1978, requested that Public Service Electric and Gas Company submit proposed Radiological Effluent Technical Specifications for Salem Units l and 2, incorporating the principles of 10CFR50 Appendix I, within 120 days. The proposed Technical Specifications have been prepared and are undergoing'final internal review. In.this regard, PSE&G respectfully requests the time for submittal of these proposed Technical Specifications be *extended to April 30, 1979. Should you have any questions, please do not hesitate to contact us. Attach. Very truly yours, F.hrm-General Manager - Electric Production 790410031\\~ ~\\ GH 2 The Energy People 95-0942

t* TO ALL UNITED STATES NUCLE~,R.REGULATORY CO~MISSION LICE\\ ~'llASHtNoroi-J.' o: c~'2o5ss LICENSING ANO Uivi._._...... ~** 1 \\ R. !J:i!JGh{J.;1mbe'r 15, 1978 NOTED ~. \\ / NOV 301978 4.,.t-:r ~ PRESSURIZED WA ERf!REACIOR-L-lGENSE-ES-I J.,,.

  • I

~----- Gentlemen: General Manager liccn~ing and En11i1unment RL.~L

~~~;f~.

WER 1J_ ~j !WJ EJM (~ !;?!) Jo~OK JCi1 CJPl(S --- FIL£---- In a letter from B. Grimes, Assistant Director for Engineering and Projects, dated July 11, 1978, you were sent guidance and a submittal schedule vJhi ch requested a 1 i cense. amendment app 1 i ca ti on to be submitted to incorporate the requirements of 10 CFR Part 50, Appendix I into your facility Technical Specifications. Since that time, the staff has continued its efforts to simplify the specifications through clari-fication 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 conmen ts and quest i ans 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, Pt,.JR 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 do.se calculations, setpejnt deter-mination 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 Techni~al 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 preparatio1; 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 I. The submittal dates are referenced to the date of this letter. In addition to the guidance noted above, the following general informa-tion is also provided:

1)

The format for the revised Technical Specifications may be that presently used for your existing Appendix A Technical Specifi-cations, provided all. applicable areas of the.. model Technical Specifications are acceptably addressed. Although the staff recorrrnends the format of the model Techni-cal Specifications, its use is not mandatory.

2)

It has been misinterpreted by several licensees that* the Technical Specification submittal need only address the indi-vidual 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 Stand~rd. Consequently, the NRC expects 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 Specifica- . *-- tiofis-in Appendix*B, you should requ.est that they.be delete'd

  • upon approval of the new Technical Specifications in Appendix A.

The submittal should resolve all duplicative Technical Speci-fication requirements in the radiological area.

4)

The entire Administrative Controls Section (6.0) of the Standard Technical Specifications was included for informa-tion. 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.

i 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. t_he seminars are shown in Table II. Representatives from the Qff i c~:--of Nuclear Reactor Regulation wil 1* make the presentation and the agenda*w*f1,1 :i*ncJude an introduction and background on the effluent Technical Sp.~cJfications, the development of the Standard Technical Specificatt6n~, and the method and schedule for implementing the specifications. A question and answer period will follow the pre-pared presentation. More specific information relative to these seminars will be forthcoming from our R~gional Directors.

Enclosures:

1. Tables I & II
2.

Draft Radiological Effluent Technical Specifications -

3.

NUREG-0133 PWR /"7 Q' Sincerely, ~- ~-<~.. ~ Brian K. Grimes, Assistant Director __ for Engineering and Projects Division of Operating.Reactors - . ------ --*----------~--.

  • ~. l- -

~ 1:

  • ~r--**.
  • -. :~

TABLE I RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS

  • .;.:-::';:[.. ~---

.*.~~~*"1£',:. -30 Days

60. *oays Farley Hatch Big Rock Point Ginn a Haddam Neck La Crosse Oyster Creek San Onofre Surry Yankee Rowe LICENSEE SUBMITTAL DATES 90 Days Arkansas Brunswick Crystal River Dresden Fitzpatrick Indian Point Millstone Monticello Nine Mile Point

-- Oconee Peach Bottom Pilr:rim Quad Cities Robinson Turkey Point Vermont Yankee Zion 120 Days Beaver Valley _ Browns Ferry. _ Calvert Cliffs Cook Cooper Davis Besse -Duane Arnold Fort Calhoun Humboldt Bay. -- -Kewaunee Maine Yankee North Anna Palisades Point Beach Prarie Island Rancho Seco Salem St. Lucie Three Mile Island Trojan /_

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

( \\ c _UNITED STATES NUCLEAR REGULATORY COMMISSION '.ASHINGJ:ON~ D. C. 20555 LICENSING MANAGEf~ 1 LICENSING AND ENl/IRONi\\N:dvember 16 I 1978 R. P. DOUGLAS NOTED 41fff~-- 0ocket No. 50-31 1 NOV 2 81978 REFER TO /JC-A __ _ LETTER TO OL A~PtlC~NJS-A~:t-tSTED IN ENCLOSURE 1 j Gentlemen: I t.01'icS 0 -k~A&,----F-ftE--{~/t) c<-tja(tiiN~-f f.CfER TJ FILE ) I B rn.1 Jc~~:' _COPJ[:S -~ Fl~:: F.~L JCi~. !~ a letter from D. B. Vassallo, Assistant Director for Light Water Reactors, dated July 26, 1978, you were sent guidance and a submittal schedule which requested that you submit proposed effluent Technic~l Specifications to implement the requirements of Appendix I to 10 CFR

~ ~- -

Part 50. 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 \\<Jith these efforts - we have had a number of discussions with the AIF and others concerning comme.-,ts and questions they deve 1 oped with respect to the specifi ca ti ans. As. a result of our continuing review, we have made substantive r~visions 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 incorpor-ate 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 dis- -persion* 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. Nuc1ear Power...., _ _."if** Plants. This NUREG document describes methdds 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 Enclosure 1. The submittal dates are referenced to the date of this letter.

\\ e*** In addition to the guidance. noted above, the following general informa-tion is also provided:

1)

The enclosure uses the format of the Standard Technical Specification. If your facility is not currently scheduled for Standard Technical Specifications, your submittal may be made in the format of Appendix A Technical Specifications, provided all applicable areas of the model Technical Speci-fications are acceptably addressed.

2)

It has been misinterpreted by several applicants 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~ Tech-. nical Specifications on Effluents from Nuclear Power Reactors

  • -which addresses the maintenance and use of radwaste equipment installed pursuant to Section 50.34a(a), Section 50.34~ which

. :addresses Appendix I (Design Objectives IIA, IIB, IIC and JID), 10 CFR Part 50, Appendix A, General Design Criteria 60 and 54* which address the control and monitoring of releases of radio-* active material to the environment, and 40 CFR Part 190,

  • Uranium Fuel Cycle Standard.

Consequently~ the NRC expects

  • the submittals to reflect the~e*and other issues addressed in the Draft Radiological Effluent Technical Specifications

.enclosed with this letter.

---- 3)

The submittal should consolidate the radiological effluent and enyironmental monitoring Technical Specifications in* ____ -* --~-. _:__ ~.Appendi~ _A of. the Technical. Speci.fications or _the Standard Technical Specifications, whichever is applicable to your facility._

4)

The entire Administrative Controls Section (6.0) of the Standard Technical Specification has been included in the model specification. If your facility does not have Standard

  • Technical Specifications, then those areas related to radio-logical effluents and envircnmental monitoring need.to be included with your submittal.

If y6u have any questions on this matter, please contact us. _ _ Sincerely/.

  • ~~a--

D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management

( c

Enclosures:

1. Submittal Schedule
2. Draft Radiological Effluent Technical Specifications
3.

NUREG-0133 cc: See next page - 3.. I*.

\\f.~~**:. ~* ~: ~. *. I' Mr. I{. L. Mittl General Manager - Projects Engineering and Construction Department Public Service Electric and G_~s Company 80 Park Pl ace, Newark, New J~i"Sey. 07101

/**=~if:~:~****:... :*._

.:,.~. cc: -. *.. *=* ~i~.':~:.. **.~.:\\:.. _./:' : Ri.chard* Fryli°H~~:'Jr., Esq. Assistant General Counsel Public Service Electric & 80 Park Place Newark, New Jersey 07100 Mark Wetterhahn, Esq. Conner, Moore & Caber Gas Company 1747 Pennsylvania Avenue, N.W. Suite 1050 Washington, O.C. 20006 Mr. Leif J. Norrholm U. S. Nuclear Regulatory Corrmission .Region I Drawer I Hancocks Bridge, New Jersey 08038 l"'- 1

---~-*---**... -*-* 1,., ~ \\,.., / \\

  • \\

,1 c*; ENCLOSURE I APPENDIX I TECHNICAL SPECIFICATIONS SUBMITTAL DATE SCHEDULE 30 DA l's. J~~;~~~~o DAYS 120 DAYS . McGuire l

  • North Anna 2 Zimmer.l Arkansas 2 Sequoyah 1/2 Salem 2 Diablo Canyon.

6 Months Pr.ior to Scheduled OL Issue - Date Fermi 2

  • San Onofre--2/3
  • Shoreham Watts Bar 1/2 La Salle 1/2 WPPSS-2 South Texas 1/2 Susquehanna 1/2 Comanche Peak 1/2 Bellefonte 1/2 McGuire. 2
  • Grand Gulf 1/2

_______ c.. ---~M.id.land-1/2 - 180 DAYS Summer l Farley 2}}

Retrieved from "https://kanterella.com/w/index.php?title=ML18078B168&oldid=5014896"