ML20095E902
| ML20095E902 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/17/1992 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20095E905 | List: |
| References | |
| P-92162, NUDOCS 9204280064 | |
| Download: ML20095E902 (5) | |
Text
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April 17,1992 Fort St. Vrain Unit No.1 P-92162-U.S. Nuclear Regulatory Commission A'lTN: Document Control Desk
. Washington, D.C. - 20555 A'ITN:
Dr. Seymour H. Weiss, Director Non Power Reactor, Decommissicaing and Environmental Project Directorate Docket No. 50 267 GUBJECT:
REVISION TO TIIE FORT ST. VRAW PROPOSED DECOMMISSIONING PLAN
REFERENCES:
(see attached)
Dear Dr. Weiss:
The purpose of this letter is to provide a revision to Public Service Company of Colorado's (PSC's) Proposed Decommissioning Plan (PDF) for Fort St. Vrain,
= originally submitted to the NRC in: References 1 and 2.
This revision is forwarded in response to PSC's cammitment to update the PDP to incorporate additional information provided to the NRC in References 3 through 15. These submittals provided additional information, and in some instances revised
-information, to the plan that was originally submitted.
In addition, since the approved Decommissioning Plan will replace the Updated Final Safety Analysis Report as the licensing basis for Fort St. Vrain, PSC has incorporated the descriptions and design basis for existing plant systems and
~ components that will be used at various times during the decommissioning period.
With reference to-the new 10 CFR 20- program, PSC had originally indicated intent to implement the new program at the beginning of decommissioning. Now that the implementation of the revised 10 CFR 20 may be delayed, PSC
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P 92162 i
April 17,1992 Page 2 tentatively plane to implement the revised 10 CFR 20 no later than January 1, 1994. Depending on the projected status of the Fort St. Vrain decommissioning project as of January 1,1994, PSC may apply for an exemption of the implementation of the revised 10 CFR 20 requirements for the remainder of the deconmissioning project. However, PSC plans to implement the revised 10 CFR
' 20 for the 10 CFR 72 Independent Spent Fuel Storage Installation (ISFSI) by January 1,1994.
Attachment I to this k cr provides a summary of the changes incorporated into this latest revision of the Proposed Decommissioning Plan Attachment 2 provides
- the revised plan, together with instructions for entering the change to the Fort St.
Vrain Proposed Decommission!;; Plan. If you have any questions related to the contents of this letter, please contact Mr. M. H. Holmes at (303) 620-1701.
Sincerely, O M d {t h /
D. W. Warembourg 7
Manager, Nuclear Opera ions DWW:CRB/cb l
A'.tachment ee:
Regional Administrator, Region IV L
Mr. J.B. Baird l
Senior Resident inspector Fort St. Vrain l
l Mr. Robert M. Quillin, Director l
Radiation Control Division Colorado Department of Health 4210 East Ilth Avenue Denver, CO 80220 L
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s P-92162 AprR 17,1992 Page 3 REFERENCES 1.
PSC letter, Crawford to Weiss, dated November 5,1990;
Subject:
" Fort St.
Vrain I?oposed Decommissioning Plan" (P-90318).
2.
PSC lettec. Crawford to Weiss, dated July 1,1991;
Subject:
" Revision to the Fort St. "'ein Proposed Decommissioning Plan" (P-91217).
3.
PSC letter, Craw ;rd to Weiss, dated July 10, N91;
Subject:
" Supplement to the Environmental Report - Post Operating License Stage" (P-91219).
4.
PSC letter, Crawford to Weiss, dated July 26,199h S9bject: " Initial Site Characterization Program" (P-91240).
5.
PSC letter, Crawford to Weiss, dated July 30, 1991;
Subject:
"PSC Response to NRC RAI - DTS & Representative Cost Estimate" (P-91248).
6.
PSC letter, Crawford to Weiss, dated Auguct 28, 1991;
Subject:
" Verification of FSV Activation Analysis", (P-9127/).
7.
PSC letter, Crawford to Weiss, dated August 30, 1991;
Subject:
" Decommissioning Technical Specifications" (P-91278).
8.
PSC letter, Crawford to Weiss, dated December 6,1991;
Subject:
"PSC Response to NRC RAI (#13 & #16)" (P-91423).
9.
PSC letter, Crawfrd to Weiss, dated January 9,199'2;
Subject:
"PSC Response to NRC RAI (#11 & #38)" (P-92014).
l-10.
PSC letter, Warembourg to Weiss, dated January 15, 1992;
Subject:
"Results of Final Structural Evaluation of the PCRV" (P-92012).
I1.
PSC letter, Crawford to Weiss, dated January 20, 1992;
Subject:
"Contirmation of PSC's Selection of the "DECON" Decommissioning j
Alternative" (P-92029).
12.
NRC letter, Weiss to Crawford, dated January 27, 1992;
Subject:
"FSV Decommissioning Funding Plan" (G-92015).
13.
PSC letter, Warembourg to Weiss, dated February 18, 1992;
Subject:
"PSC Response to NRC RAI (#9, #12 & #14)" (P-92064).
14.
PSC letter, Crawford to Weiss, dated March 19, 1992;
Subject:
" Decommissioning Technical Specifications" (P-92115).
15.
PSC letter, Warembourg to Weiss, dated February 5,1992;
Subject:
" Initial j
Site Characterization Program Results" (P-92036).
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A'lTACllMENT 1 TO P-92162
SUMMARY
OF REYlSIONS TO Tile FSV PROPOSED DECOMMISSIONING PLAN i
APRIL 17,1992 SECTION
_ PROPOSED REVISIGE 1.0 o Minor revisions to Sections 1.1,1.2,1.4 and 1.5 to reDect chang s made in later PI'P sections.
2.1 o Incorpora,ed PSC selection of the "DECON" decommissioning alternative.
2.2 o Incorporated description of Reactor Building louvers and crane.
Incorporated RAI discussion of core barrel and core support floor, o
Added' FSAR design basis descriptions of systems or structures that o
may be vsed during portions of the decommissioning period:
Elot Service Facility, Systems 62,63,73 and 93.
o Additional description and figure of liquid effluent release paths and
. water supplies.
23 o Incorporated information from PCRV Structural Analysis.
.o Incorporated RAI response on PCRV Shield Water System (formerly the PCRV ~ Water ' Cleanup and Clarification System) design information, Deleted requircraent to sample the PCRV at %-core increments during o
- the core fill process.
o-Incorporated RAI responses for. the PCRV top head, component removal, core barrel and CSF removal, and steam generator removal, o Incorporated -information from initial site characterization survey results into the descriptions for. contaminated balance of_ plant (BOP)
. equipment, o incorporated latest detailed project schedule, o Minor corrections to Table 2.3-1.
Minor revisions to the PSC Organization, including addition of-
-2/ -
o Deputy Project Director and Project Controls Manager.
2.5_
o - Updated Figure 2.5-1 to reflect management reporting responsibilities.
r
, to P-92162 April 17,1992 Page 2 2.6 o Deleted emergency preparedness and fire. protection training requirements.
Revised to incorporate results of initial site characterization study.
3.1 o
o Incorporated latest revision to activation analysis and last submittal to NRC on activation verification activities, Incorporated RAI response on tritium source term from the graphite.
o o Incorporated revision of plateout analysis based on end of reactor life.
at G90 EFPD and revised tables accordingly.
Revised commitment to implement new 10 CFR 20 by January 1993.
2 o
o Moved ORE discussion to Section 3.2.5.2 and added Table 3.2-1, Provided current defueling plans to the ISFSI and deleted discussion 3.3 o
of shipments to DOE.
Incorporated tritium and effluent release description as per RAI c
responses.
o Identified effluent release criteria consistent with Environmental Report - Post Operating Phase.
o Moved LLRW discussion from Section 5 to 3.3.3.1.
o Minor revisions to tables.
3.4 o Added steam generator drop accident description.
e Updated heavy load drop accident to account for largest (rather than average) permanent side reflector.
o Incorporated updated activation and plateout analyses results, ar '
revised accident consequences accordingly, Added discussions related to natural gas concerns in the vicinity of o
-Fort St. Vrain and containment tent fires.
4 (No revisions) 5 o Added referenc: to NRC approval of PSC's Decommissioning Funding Plan.-
Added reference to recent Technical Specification submittals to NRC.
6 o
-7 o Updated reporting responsibilities.
8 o Deleted reference to conversion project.
9/10 Deleted sections; plans submitted separate from Decommissioning Plan.
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