ML20095K406
| ML20095K406 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/26/1995 |
| From: | Borst F PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20095K410 | List: |
| References | |
| P-95122, NUDOCS 9512280326 | |
| Download: ML20095K406 (7) | |
Text
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h Public Service' 24" L 16805 WCR 19 1/2; Platteville, Colorado 80651 4
December 26, 1995 Fort St. Vrain Unit No. 1 P-95122 U.
S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
Annual Fort St.
Vrain Decommissioning Plan Update submittal
REFERENCES:
(See Attached)
Gentlemen:
This letter transmits Public Service Company of Colorado's (PSC) third annual update of the Fort St. Vrain (FSV) Decommissioning l
Plan (DP).
Enclosed are ten copies of Revision 3 to the FSV DP.
The FSV Decommissioning Order (Reference 1), states the following:
"The Decommissioning Plan replaces the licensee's Updated Safety Analysis Report.
Accordingly, a license condition has been added allowing the licensee to make changes to the Decommissioning Plan after performing a review based upon criteria similar to the criteria of 10 CFR 50.59 to ensure that such changes do not involve an unreviewed safety question."
In addition, the FSV Decommissioning Order requires PSC to submit to the NRC a quarterly report containing a brief description of any changes, tests and experiments, including a summary of the safety j
evaluation of each.
References 2 through 5 are the quarterly reports of changes, tests and experiments submitted during 1995.
The enclosed DP has been updated to reflect the changes discussed in these quarterly reports.
Brief descriptions of the principal changes to affected sections of the DP, Revision 3, are included in the Attachment to this letter.
Revisions entered since the Decommissioning Plan was last updated j
(Reference 6) are identified with a bar mark in the margin adjacent to theg ortion actually changed.
' O L ()O y J
9512280326 951226 PDR ADOCK 05000267 W
P-95122 l
December 26, 1995 l
Page 2 If you have any questions concerning this report, please contact Mr. M. H. Holmes at (303) 620-1701.
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Sincerely, bile -
Sc P Frederic J L Borst Decommis ohing Program Director FJB/JRJ i
i Attachment Enclosure i
i cc:
Mr. Michael F.
Weber, Chief Decommissioning and Regulatory Issues Branch f
Regional Administrator, Region IV l
Mr. Robert M. Quillin, Director Radiation Control Division
(
Colorado Department of Public Health and Environment i
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P-95122 December 26, 1995 Page 3 REFERENCES 1)
NRC Letter dated November 23, 1992, Erickson to Crawford (G-92244) 2)
PSC Letter dated -March 14, 1995, Fisher to NRC Document Control Desk (P-95021) i 3)-
PSC Letter dated June 8, 1995, Fisher to NRC Document Control Desk (P-95057) 4)
PSC Letter dated September 14, 1995, Fisher to NRC Document Control Desk (P-95081) 5)
PSC Letter dated December 21, 1995, Borst to NRC ^7cument Control Desk (P-95119) 6)
PSC Letter dated December 27, 1994, Warembourg to NRC Document Control Desk (P-94115) l 1
ATTACHMENT P-95122 December 26, 1995 Descriotion of Principal Chanaes Incorocrated in Revision 3 of the Fort St. Vrain Decommissionina Plan Section 2 Deleted statements regarding plans to rig each of the twelve steam generator primary modules to the Reactor Building crane prior to unclamping the modules from the lower plenum floor near the bottom of the Prestressed Concrete Reactor Vessel (PCRV).
Included results of the evaluation which determined the modules would be adequately supported by the floor and penetration seal studs at the bcttom of each module, without being connected to the crane.
The DP originally stated that the nine fuel storage wells would be decontaminated to below the release criteria, surveyed, and left in place.
Revised this discussion to state that the fuel storage wells were removed and disposed of as radioactive waste.
Updated the discussion on removal of the core support floor (CSF) to reflect that the CSF lift involved a weight of approximately 345 tons, instead of the 270 ton weight previously referenced in the DP.
The additional weight was the result of three inches of steel plates installed on top of the CSF for shielding, the monorail spider assembly was attached to the bottom of the CSF during the lift, and to account for water absorbed in the insulation remaining on the sides and bottom of the CSP.
Revised the description of the lifting system from a " strand" jacking system to clarify that the hydraulic jacks used steel jackrods.
The DP originally stated that the beltline concrete segments removed from the area that used to be adjacent to the core would be approximately 40 ft. long, 8 ft. wide, and a minimum of 27 inches
- deep, with vertical back cuts made between every third inner vertical tendon tube.
Revised this to indicate that the segments were approximately 43 ft. long, 8 ft. wide, and a minimum of 31 inches deep, with vertical back cuts made between every inner vertical tendon tube.
In addition, included a discussion of plans to remove an additional 26 ft. of beltline concrete from the PCRV lower plenum area, in order to meet the release criteria of the final survey plan.
Updated the DP to reflect the following modifications involving systems for processing and releasing radioactive liquid effluent:
- Installation of additional demineralizers in the drain line of the PCRV shield water polishing demineralizers to provide increased flexibility in processing water prior to release; e Installation of a " tee" connection to permit water to be pumped from the Radioactive Liquid Waste Sump, through the additional demineralizers noted above, to the Reactor Building Sump / keyway;
- Installation of the PCRV lower plenum and penetration drain
ATTACHMENT P-95122 December 26, 1995 system to permit isolating the shield water system so it could be decommissioned, and permit draining and processing water from the PCRV bottom head penetrations.
Identified the presence of a self-contained, mobile, wet wash respirator cleaning trailer on the FSV plant site.
Revised the description of the PSco organization to eliminate the Decommissioning Program Deputy Director position, and to change the title of PSco's Facility Support Manager to the Radiation Protection Manager, section 3 4
Updated the discussion in Section 3 regarding the onsite processing of radioactive liquid wastes to reflect the effects of the modifications identified above.
Revised Section 3 to reflect PSCo's organizational change involving change in the title of the Facility Support Manager to the Radiation Protection Manager.
Updated the description of the Westinghouse Team radiation protection organization to account for organizational changes of the Scientific Ecology Group (SEG) that occurred in 1995.
i section 4 i
j The NRC approved the FSV Final Survey Plan for Site Release (FSP),
as modified by PSCo responses to NRC requests for additional information (RAI), in a letter dated January 26, 1995.
In a letter dated May 25,
- 1995, PSCo submitted the updated
- FSP, which x
incorporated these RAI responses into the FSP.
This approved FSP supersedes the final radiation survey plan that was included in Section 4 of the DP, but never approved by the NRC.
Rather than incorporate the entire approved FSP in the DP, it was decided to reference the approved FSP in Section 4 of the DP.
DP Section 4 was thus revised to delete the outdated final radiation survey plan, and reference the approved FSP.
In addition, the criteria by which PSCo is permitted to implement certain changes to the FSP without prior NRC approval have been included in Section 4.
i Section a Revised Section 8 to reflect the change in title of PSCo's Facility Support Manager to the Radiation Protection Manager.
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INSTRUCTIONS FOR INSERTING REVISION 3 PAGES IN THE FORT ST. VRAIN DECOMMISSIONING PLAN NOTE:
DO NOT REMOVE ANY TABLES OR FIGURES UNLESS SPECIFICALLY DIRECTED IN THESE INSTRUCTIONS.
MOST PAGES AFFECTED BY REVISION 3 ARE TEXT PAGES. VERY FEW TABLES OR FIGURES HAVE BEEN REVISED.
List of Effective Paces (LOEPs)
Remove the Rev. 2 LOEPs, pages A and B,
and insert the Rev. 3 LOEPs, pages A, B and C.
Tables of Contents in Front of DP Remove the Rev. 2 Table of Contents, pages i through vi, and replace with the Rev. 3 Table of Contents, pages'i through vi.
Do not remove the Rev. 2 List of Tables.
Remove the Rev. 2 List of Figures, pages ix through xi, and replace with the Rev. 3 List of Figures, pages ix through xi.
Do not remove the Rev. 2 Commonly Used Acronyms and Commonly Referenced Isotopes and Elements (pages xiii-xvii).
]
Section 2 Remove Rev. 2 pages 2.2-1 through 2.2-26, and replace with Rev. 3 pages 2.2-1 through 2.2-27.
Remove Rev. 2 pages 2.3-1 through 2.3-60, and replace with Rev. 3 pages 2.3-1 through 2.3-65.
Remove Rev.1 Figures 2.3-3 and 2.3-4 (same page), and replace with Rev. 1 Figure 2.3-3 and Rev. 3 Figure 2.3-4.
1 Remove Rev. 1 Figures 2.3-21 and 2.3-22 (same page), and replace with Rev. 1 Figure 2.3-21 and Rev. 3 Figure 2.3-22.
Remove Rev. 2 pages 2.4-1 through 2.4-5, and replace with Rev. 3 pages 2.4-1 through 2.4-5.
Remove Rev. 2 Figure 2.4-1, and replace with Rev. 3 Figure 2.4-1.
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e Section 3 Remove Rev. 2 pages 3.2-1 through 3.2-87, and replace with Rev. 3 pages 3.2-1 through 3.2-89.
Remove Rev. 2 Figure 3.2-1 and Rev.1 Figure 3.2-2 (same page), and replace with Rev. 3 Figures 3.2-1 and 3.2-2.
Remove Rev. 2 pages 3.3-1 through 3.3-18, and replace with Rev. 3 pages 3.3-1 through 3.3-19.
Section 4 Remove Rev. 2 pages 4-1 through 4-12, and replace with Rev. 3 pages 4-1 through 4-4.
Section 8 Remove Rev. 2 pages 8-1 through 8-3, and replace with Rev. 3 pages 8-1 through 8-3.
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