ML20095L037

Forwards Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning

ML20095L037
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1992
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20095L043	List: ML20095L037 ML20095L067
References
P-92181, NUDOCS 9205060200
Download: ML20095L037 (5)

Text

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Public Service

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16805 WCR 191/2, Platteville, Colorado 80651 .

f April 30,1992 E Fort St. Vrain Unit No.1 P-92181 Director,  ;'

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267 E

SUBJECT:

SUPPLEMENT TO APPLICANT'S ENVIRONMENTAL REPORT - 2 POST OPERATING LICENSE STAGE

REFERENCES:

1. PSC Letter, Crawford to Weiss, dated July 10,1991 (P-91219)

2. PSC Letter, Warembourg to Weiss, dated March 20,1992 (P-92123)

3. NRC Letter, Erickson.to Cuwford, dated November 19, 1991 (G-91246)

4. PSC Letter, Warcrabourg to Weiss, dated April 17, 1992 -

(P-92162)

Gentlemen:

This letter sub:.4 the revised Supplement to Applicant's Environmental Report (ER)

- Post Operating License Stage. Public Service Company of Colorado (PSC) submits this ER Supplement to address the enviroamental impacts of decommissioning the Fort St. Vrain Nuclear Generating Station.

The attached ER Supplement has been up<jated from the initial submittal (Reference 1), to reflect current decommissioning plans and to incorporate additional information that PSC provided in Reference 2, in response to NRC questions identified in Reference 3, Information from the recently updated Proposed Decommissioning Han a(PDP, Reference 4) has also been incorporated in the attached ER Supplement, g I

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P-92181 April 30,1992 Page 2 Changes frcm the initial ER Supplement (Reference 1) have been marked in the margins on the attachment to facilitate your review. A brief description of these changes is included as Attachment 1. The ER Supplement, included as Attachment 2, has been extensively re,ised and is intended to completely replace the ER Supliement provided previously.

The attached ER Supplement evaluates the environmental impacts associated with alt reasonable decommissioning alternatives. The environmental impacts of decommissioning Fort St. Vrain, by use of the Early Decontamination and Dismantlement (DECON) alternative selected by PSC, are not signi6 cant when compared with accepted consequences of operating and decommissioning Light Water Reactor plants. No sit: specific chaiacteristics were identi6ed that would result in environmental impacts that would be significantly different from those stuaied generically by the NRC. The attached ER Supplement demonstrates that the impacts of decommissioning the Fort St. Vrain facility do not significantly affect the human environment.

In accordance with 10 CFR 51.55(a), forty-one (41) copies of the attached supplement are included with this letter. Additional copies have been retained by PSC for distribution to other parties or organizations at a later date, if so instructed by the NRC.

If you have any questions regarding the attached information, please contac: Mr ii.

H. Holmes at (203) 620-1701.

Sincerely,

/b yl]r(Kima J w Donald W. Warembourg g7 Manager, Nuclear Operations DWW/SWC/Img -

Attachments

t P-92181

-April 30,: 1992 -l Page 3 -

cc: Regional Administrator, Region IV .

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Mr J. B. Baird Senior Resident Inspector Fort St. Vrain Mr. Robert M. Qaillin, Director Radiation Control Division Colorado Department of I!ealth Dr. Seymour H. Weiss, Director Non-Power Reactor, Decommissicning and Environmental Project Directorate U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l

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A1TACHMENT 1 TO P-92ERS REVISIONS TO JULY 1991 SUPPLEMFNT TO APPLICANT'S ENVIRONMENTAL REPORT - POST-OPIMATING LICF,NSE STAGE SECTION 1:

• Updated to reflect current spent fuel shipping status.

• Updated to reflect recent submittals of Proposed Decommissioning -

Plan (PDP) and Decommissioning Technical Specifications.

SECTION 2:

• Updated to reflect Activation Analysis Verification efforts, Site Characterization surveys.

• Updated to include tritium leaching information from revised PDP.

SECTION 3:

• Updated schedules to reflect information in recent PDP submittal.

• Added discussion about evaporated tritium vapor being released as gaseous effluent.

SECTION 4:

• Updated tritium release plans consiaent with recent PDP submittal and PSC -response in Reference 2 (P-92123) to NRC Request for Additional Information (RAI).

• Revised dose projections consistent with revised pathways analysis provided in RAI response; dose estimates were funher revised from those provided in- ' RAI response in P-92123 to incorporate additional conservatisms and to enhance the discussion or doses resulting from a postulated release of 8000 Curies of tritium.

• Added dose estimate due to inhalation of tritiated water vapor from

- evaporated PCRV Shield Water.

• Updated Radiation Protection Program description based on revised PDP.

• Identified chemicals for release based on RAI response.

Attachment 1 to P-92181 Page 2 SECTION 5:

• Revised heavy load drop and added steam generator drop accident analysis, based on revised PDP.

• Deleted discussion of lifetime fatal cancer risk contribution, as accident consequences are adequately analyzed in terms of doses.

• Deleted statement that no in-leakage has been observed in the Reactor Building sump. Water out leakage from the sump is precluded by the high water table. 1 SECTION 6:

e Updated description of SAFSTOR and ENTOMB alternatives per RAI response.

SECTION 7:

• Ircorporated analysis of decommissioning alternatives from RAI response.

SECTIOM 8:

• Added EPA Safe Drinking Water Standard, 40 CFR 141, based on RAI response.

SECTION 9:

• Updated document summary to incorporate changes in previous sections.

APPENDIX 1:

• Added new Appendix to address 10 CFR 51.45 (b) considerations, as was provided in RAI response.

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