ML20141K996

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Safety Evaluation Supporting Amend 89 to License DPR-34
ML20141K996
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 05/05/1997
From: Pittiglio C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20141K990 List:
References
NUDOCS 9706020230
Download: ML20141K996 (4)


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g t WASHINGTON, D.C. 20055-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS RELATED TO AMENDMENT N0. 89 TO FACILITY LICENSE NO DPR-34 FORT ST. VRAIN NUCLEAR GENERATING STATION. UNIT 1 DOCKET N0. 50-267

1. INTRODUCTION

. Fort St. Vrain (FSV) is a high-temperature, gas-cooled reactor owned and operated by Public' Service Company (PSC) of Colorado. FSV is located approximately 35 miles north of Denver and 5.6 km (3.5 miles) northwest of the town of Platteville in Weld County, Colorado. FSV had a capacity of 330 HWe. The PSC-owned site consists of approximately 11,320 me (2798 acres).

FSV was shutdown on August 18, 1989, because'of control-rod drive failures. The shutdown was made permanent because of a subsequent discovery of degradation of steam generator ring headers. About one-third of the spent fuel was initially removed from the core (the maximum capacity of the spent fuel storage wells). 1 PSC completed the construction of an independent spent fuel storage installation i (ISFSI) in August 1991 and received U.S. Nuclear Regulatory Commission approval (10 CFR Part 72 license) to store spent fuel in November 1991. PSC has trans-ferred all 247 elements of FSV fuel to the ISFSI.

The staff issued, on November 23, 1992, an Order Approving the Decommissioning Plan (PD) and Authorizing Decommissioning. The licensee _ selected the dismantlement / decontamination option as the decommissioning alternative, and l decommissioning is complete. PSC estimates that the FSV license will be terminated in 1997, and FSV released for unrestricted use.

The major dismantlement and decontamination activities performed during decommissioning were divided into three primary work areas: (1) decontamination and dismantlement of the prestressed concrete reactor vessel (PCRV); (2) decontamination and dismantlement of the contaminated balance-of-plant (B0P) systems; and (3) final site radiation survey. To support the FSV decommissioning activities, NRC conducted 24 inspections at FSV. The most recent inspections (inspections conducted from February 1996 through October 1996) focused on supporting the final radiation survey review, i

' The licensee conducted termination surveys to assess residual radioactive '

contamination levels at the facility. The termination surveys were conducted in a phased approach. The licensee completed 7.e final radiological survey in

! October 1996. The final survey report documented the level of residual i radioactivity remaining at the facility and affirmed that the residual

. radioactivity met unrestricted use criteria established by the NRC, and that the site was suitable for release for unrestricted use.

970602o230 97o505 PDR ADOCK 05000267 W PM .

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2. EVALUATION The proposed changes to the FSV Possession-Only License No. DPR-34 is administrative in nature and redesignates the approved DP, the approved

" Supplement to Applicant's Environmental Report - Post-0perating License Stage -

Decommissioning" and the approved Final Radiation Survey Plan as the License Termination Plan.

In summary, because of the procedural nature of the change, the amendment request does not create a new or different accident than previously analyzed in the DP.

All the accident scenarios previously analyzed in either the decommissioning technical specifications or the DP, and the offsite doses resulting from these accidents, were insignificant. The staff is approving the amendment based on the procedural nature of the changes and because the previously analyzed accidents in the DP were not changed.

3. ENVIRONMENTAL CONSIDERATIONS The amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
4. AGENCIES AND PERSONS CONSULTED In accordance with the Commission's regulations, the Director of Radiation l Control, Colorado Department of Public Health and Environment was notified of the proposed issuance of the amendment. The State had no comments on the proposed I amendment.

1

! 5. CONCLUSIONS The Commission has concluded, bas'.d on the considerations above, that:

(1) because the license amendment Joes not involve an increase in the probability nor consequences of accidents previously evaluated, nor create the possibility of a new or different kind of accident from any accident previously evaluated, and does not result in a reduction in a margin of safety, the amendment does not involve a significant hazard consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (3) such activities will be conducted in cotopliance with the

Commission's regulations; and (4) the issuance of the amendment will not be .

! inimical to the common defense and security, nor to the health and safety of the  ;

public. l l

Principal Contributor: Clayton L. Pittiglio, Jr.

Date: May 5, 1997

. 2

2. EVALUATION

' The proposed changes to the FSV Possession-Only License No. DPR-34 is administrative in nature and redesignates the approved DP, the approved

" Supplement to Applicant's Environmental Report - Post-0perating License Stage -

Decommissioning" and the approved Final Radiation Survey Plan as the License Termination Plan.

In summary, because of the procedural nature of the change, the amendment request does not create a new or different accident than previously analyzed in the DP.

All the accident scenarios previously analyzed in either the decommissioning technical specifications or the DP, and the offsite doses resulting from these accidents, wen insignificant. The staff is approving the amendment based on the procedural nature of the changes and because the previously analyzed accidents in the DP were not changed.

3. ENVIRONMENTAL CONSIDERATIONS The amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
4. AGENCIES AND PERSONS CONSULTED In accordance with the Commission's regulations, the Director of Radiation j Control, Colorado Department of Public Health and Environment was notified of the l proposed issuance of the amendment. The State had no comments on the proposed j amendment. '
5. CONCLUSIONS The Commission has concluded, based on the considerations above, that: .

(1) because the license amendment does not involve an increase in the probability l nor consequences of accidents previously evaluated, nor create the possibility of a new or different kind of accident from any accident previously evaluated, and does not result in a reduction in a margin of safety, the amendment does not involve a significant hazard consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (3) such activities will be conducted in compliance with the Commission's regulations; and (4) the issuance of the amendment will not be inimical to the common defense and security, nor to the health and safety of the public.

Principal Contributor: Clayton L. Pittiglio, Jr.

Date: 5/5/97 TICKET: N/A DISTRIBUTION: Central File NMSS r/f DWM r/f JGreeves MFederline GHill(2) SGa MafMSmalRB@@gner/0PA i In small Box on "0FCi"'line@ enter:dnTC0ifd;ud pslBl.;ecQQ((jhMDisR]tjiit^f;bnICdp~

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l

. 2

2. EVALVATION

' ' The proposed changes to the FSV Possession-Only License No. DPR-34,is administrative in nature and redesignates the approved DP, the ap

" Supplement to Applicant's Environmental Report - Post-0perating License S age -

Decommissioning" and the approved Final Radiation icense Survey Termination Plan.

In summary, because of the procedural nature of the change, the amendment request does not create a new or different accident than previously analyze 4/in the DP.

All the accident scenarios previously analyzed in either the dep6mmissioning technical specifications or the DP, and the offsite doses resul ng from these accidents, were insignificant. The staff is approving the amend t based on the i procedural nature of the changes and because the previously a.n lyzed' accidents in the DP were not changed. j 1

3. ENVIRONMENTAL CONSIDERATIONS l The amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prep'ared in connection with the l issuance of this amenoment. l l
4. AGENCIES AND PERSONS CONSULTED In accordance with the Commission's regul ions, the Colorado Official was notified of the proposed issuance of the endment. The State Official had no comments on the proposed amendme .
5. CONCLUSIONS The Commission has concluded, based / on the considerations above, that:

(1) because the license amendment Mes not involve an increase in the probability nor consequences of accidents prgviously evaluated, nor create the possibility of a new or different kind of pcident from any accident previously evaluated, and does not result in a reduction in a margin of safety, the amendment does not involve a significant hazard nalysis; (2) there is reasonable assurance that the health and safety of the ublic will not be endangered by operation in the proposed manner; (3) such activities will be conducted in compliance with the Commission's regulation , and (4) the issuance of the amendment will not be inimical to the common efense and security, nor to the health and safety of the public.

Principal Contribut r: Clayton L. Pittiglio, Jr.

Date:

TICKET: N/A l DISTRIBUTION Central File NMSS r/f DWM r/f JGreeves MFederline GHill(2). SGagner/0PA

, MRSmal , 03(EsiiniCdni:ErrinEe] Bl os kit 5[0lf.i.hM 0is t fi bu t'ibn TCbpyl Pfife^re nc e; In small ox on "0FC:" line enter: C = Cover E = Cover & Enclosure N = No Copy 0FC LLD E LLDP ,,, LLDP OGC/ LLDP RIV NAME dikiglio JCopelknd/Eh TJohnson SLNis JHickey BSpitzberg h

DATE /h97 4/$/97 / /97 5 // /97 / /97 / /97 Path & Fi e Name:S:\DWM\LLDP\CLP\FSVAMEND OFFICIAL RECORD COPY In small Box on "DATE:" line enter: M = E-Mail Distribution Copy H = Hard Copy R: YES NO Category: Proprietary or CF Only ACNW: YES NO Delete file after distribution Yes No IG: YES N0