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Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning
	ML20082L928
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/30/1991
From:	Crawford A; PUBLIC SERVICE CO. OF COLORADO
To:	;
Shared Package
ML20082L926	List: ML20082L923; ML20082L928; ML20082L931;
References
	NUDOCS 9109040477
	Download: ML20082L928 (9)
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION in the Matter of the Facility Operating License)

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PUBLIC SERVICE COMPANY OF COLORADO )

Application for Amendment to the Facility Operating License License No. OPR-34 0F THE PUBLIC SERVICE COMPANY OF COLORADO FOR THE FORT ST. VRAIN NUCLEAR GENERATING STATION This application for Amendment to the Facility Operating License, License No. OPR-34, is submitted for NRC review and approval.

Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By A.-Clegg Crawford Vice President, Nuclear Operations KELLY, STANSFIELD & 0'00NNELL James K. Tarpey Mark A. Davidson ,

Public Service Company Building l Denver, Colorado 80202 Attorneys for Applicant I

9109040477 9109110 PDR' ADOCK 05000267 P PDR

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, i UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the Matter of the Facility Operating License) of )

Public Service Company of Colorido Fort St. ) Docket No. 50-267 Vrain Unit No. 1 )

l AFFIDAVIT A. Clegg Crawford, being first duly sworn, deposes and says: That he is Vice President, Nuclear Operations, of Public Service Company of Colorado, the Licensee herein, that he has read the foregoing Application of Amendment to the Facility Operating License and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his kno' ledge, )

information and belief. '

et A. Clegg" Tor Vice President,

, Nuclear Operations STATE OF COLORADO )

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COUNTY OF DENVER )

Subscribe and sworn to before me, a Notary Public on this 30th day of August , 199_1, f)r fn i s /Sm /u l Notary Public My commission expires January 6 , 19 93,

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o ATTACHMENT 1 t TO P-91278 1

SUMMARY

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Attachment 1 P-91278 Pago 1 of 4 MtiMARY OF PJ10EED_QRMlq]$_D1QH 1;X1sTllLQ_lICilRLCAL SPEcIF1cATLong G2.9112nn Doncriution__of chang 2

- racility Operating Licenso- Replaco_the Liconno and

- Appendix A - Technical Appendicos A and D in their specifications entirety with the Facility

- Appendix B ~ Environmental Liconno and Decommisaloning Protection Plan Technical Specificationo (llon-Radiological) (DTS)

Attachment 1 to P-91278 Page 2 of 4 Settigry_gf _ Charigen_from DecembgL2L 1990 Submittal 2f PSV DecolnJniDsloJ11ng. Technical Spes.ificaciona Spation Descripilon of Changg 2.7 Revised dofinition of Exclusion Area Boundary to reflect changes modo por the Decommissioning Emergency Rosponuo Plan, and to stato that the EAB is the same as the Emergency Planning Zone.

?>11 Revised dF anition of Process Control Program to irmlude the inplomonting proceduro and to doloto

- reference to 49 CFR 100. Regulatory references are as stated in Generic Lotter 89-01.

2.13 Revised definition of Unrestricted Arou to add reference to the Emergency Planning Zono for clarity, since the EPZ is identical to the Exclusion Area Boundary.

LC 3.1 Rovise Completion Timo from 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , as

, agrood to in P-91248, in response to NRC's request

for additional information.

Pago 3.1-5 Revised Basis for Action A.1 to reflect 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months completion time, por P-91248.

SR 3.2.1 Revised survoillance frequency from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , as agrood to in P-91248.

! Page 3.2-4 Revised Basis for Action' A. 3 to agroo with the wording in the Action statomont on page 3.2-1, as agrood to in P-91248.

, Pago 3.2-5 Revised Basis for SR 3.2.1 to reflect 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months j survoillanco frequency, as agrood to in P-91248.

Table 3.3-2 Revised Channel Calibration from 18 months - to 6

months, as agrood to in P-91248.

Page 3.3-3 Revised Basis Background for Radiation Monitors, to t doloto statement that offluent releases will La monitored by the ventilation exhaust stack monitors. Effluent monitoring will be performed in accordance with the Of fsite Doso Calculation Manual and may not necessarily include the existing stack monitors.

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Attachment I to P-91278 Pago 3 of 4 FE11RD DRE ClRtkRD LC 3.4 Revised Applicability for Tritium Concentration specification to stato that the specification applies whenever there is shielding water in the PCRV, as agreed to in P-91248.

SR 3.4.1, Revised tritium sampling frequencies ' .d on SR 3.4.2, concentrations, as agrood to in P-91248. In SR 3.4.3 addition, added monthly sample requiremont after tritium concentration decreases bel

1 0.01 microC1/cc.

Page 3.4-5 Revised Basis for survoillanco frequencies, to reflect changes based on measured tritium concentrations, as agrood to in P-91248, and as described above. Also added reference to Regulatory Guido 8.32.

DF 4.1 Revised Site description to reflect that the Emergency Planning Zono is the same as the Exclusion Area Boundary, for clarity.

DF 4.3 Added section on PCRV Water Leakago Provention, as agreed to in P-91248.

Figure 4-1 Revised FSV Site Map, to reflect now Exclusion Area Boundary and Emergency Planning Zone, in accordance with the revised Decommissioning Emergency Responso Plan.

AC 5.3.5 Revised DSRC responsibilities to include revick of proposed changes to decommissioning work specifications that affect Radiation Safoty, and any now work specifications. The decommissioning work specifications are the Proposed Decommissioning Plan first level implementing documents, and are comparable to the administrativo proceduros identified in AC 5.3.5.a. Subparagraphs in AC 5.3.5 were renumbered as required.

AC 5.3.7.a Revised decommissioning program audit frequency from once per 2 years to once per yonr, as agreed to in P-91248.

AC 5.4.2 Revised requirement for DSRC review of procedures to only include those proceduros that affect Radiation Safety, to be consistent with AC 5.3.5.a.

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Attachment 1 to P-91278 Page 4 of 4 Section Rescriotion AC 5.4.4 Revised Radioactive Effluent Controls Program subparagraphs a.2, a.3, .and a.7 to require conformance to 10 CFR Part 20, without citing specific sections of that regulation. Section designations in the neti?y revised 10 CFR 20 are different from the previous version, and this revision avoids commitment to the previous version of the rule.

AC 5.5.1 Revised Annual Radiological Report requirements to delete reference to specific paragraphs in 10 CFR 20, for the reasons cited in AC 5.4.4 above.

AC 5.8.1 Revised High Radiation Area citations to specific paragraphs of 10 CFR 20, for the reasons cited in AC 5.4.4 above.

AC 5.10 Revised Offcite Dose Calculation Manual paragraph a.2 to delete reference to a 7pecific paragraph in 10 CFR 20,. for the reasons cited in AC 5.4.4 above.

AC 5.11 Revised Ni Jral Gas Restriction to be consistent with .,.e <

g uirements imposed by the NRC in the PosseMioD Only License, Amendment 82-to the FSV license. The second part of the POL restriction dealing with connection of the 6 inch line to the 16 inch line was not included in AC 5.11, because design modificetions to allow this connection will be in placc by the time the DTS are implemented, and this part of the natural gas restriction will not be necesse.ry.

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i ATTACHMENT 2 ,

TO P-91278 i

4 j PROPOSED FACILITY LICENSE h

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Fort St. Vrain Decommissioning Technical Specifications License Information Page 1 of 2 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267 FACILITY LICENSE License No. DPR-34

1. Facility License No._DPR-34 is hereby issued to- the Public Service Company of C:-lorado to read as follows:

A. This license applies to the Fort St. Vrain Nuclear Generating Station, a high temperature gas-cooled nuclear reactor and asscciated equipment (the facility) owned by the-Public Service Company of Colorado. The facility is located near Platteville, in Weld County, Colorado, and is described in the Decommisstoning Plan as supplemented and amended and the Environmentil Report _as supplemented and amended.

B. Subject to tha conditions _ and requirements incorporated herein, the Comnisiion hereby licenses the Public Service Company of Colorida:

(1) Puriuant te Section 104b of the Act and 10 CFR Part 50,

" Domestic Licensing of Production and Utilization Facilities," to possess but not operate the facility at the desigrat ed location near Platteville in Weld County, Ctilorado, and to decommission the' facility as described n the ' licensee's -Decommissioning Plan, as j supplement'!d anS amended. '

(2) Pursuant to the Act and 10-CFR Parts 30, 40 and 70,-to_

receive, posiess, and use at any time any byproduct, source ara special nuclear material as sealed sources for radintion monitoring equipment calibration, in amounts as required; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70,_to receive, po,sess and use in amounts as required any byproduct., source or special nuclear material without l restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

Fort St. Vrain Decommissioning Technical Specifications License Information Page 2 of 2 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as were produced by the operation of the facility authorized herein.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and the appropriate sections of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in effect; and is subject to the additional conditions specified or incorporated below:

(1) 01conmissioning Technical Specifications The Decommissioning Technical Specifications contained in Appendix A, as revised through Amendment No. __, are hereby incorporated in the license. The licensee shall decommission the facility in accordance with the Decommissioning Technical Specifications.

(2) Applicability This Facility License and the Oecommissioning Technical Specifications implement the Decommissioning Plan and will be effective after all nuclear fuel has been removed from the Fort St. Vrain Reactor Building and the NRC has approved the Decommissioning Plan.

D. This license is subject to all Federal, State, and local i

standards imposed pursuant to the requirements of the Federal Water Pollution Control Act of 1972.

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2. This license is effective as of the date of issuance and shall expire at midnight, September 17, 2008.

FOR THE NUCLEAR REGULATORY COMMISSION 4

Attachments:

Appendix A - Technical Specifications Date of Issuance: December 21, 1973

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ML20082L928

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SUMMARY

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