ML20246H540
| ML20246H540 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/11/1989 |
| From: | Hock D PUBLIC SERVICE CO. OF COLORADO |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| P-89180, NUDOCS 8905160127 | |
| Download: ML20246H540 (8) | |
Text
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Public Service *
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Company of Colorado 1
P.O. Box 840 oenver, Co 80201 0840 D.D. HOCK andbNeIE ec e Officer 1
l May 11, 1989
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Fort St. Vrain Unit No. 1 f
P-89180 i
Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Docket No. 50-267
Subject:
Fort St. Vrain Executive Meeting
Dear Dr. Murley:
Several new members of the Public Service Company of Colorado's
.(PSC's) nuclear management team met with members of NRR
' management on May 11, 1989.. We are sorry that last minute scheduling conflicts prevented you from joining us at the meeting. We hope to schedule another meeting with you soon where PSC management can introduce ourselves and discuss our future plans for Fort St. Vrain.
Due to ' the timing involved with several of the key topics PSC wished to discuss, PSC decided it was best to proceed with the May lith meeting. A copy of the meeting handout is attached for information. A few of the key meeting topics are briefly summarized below.
Based on preliminary assessments perfnrmed in 1988, PSC planneo to obtain various NRC reviews and approvals for defueling activities at Fort St. Vrain. PSC had planned to submit by May 31, 1989, the PSC defueling plan, associated safety analysis report, and defueling Technical Specification changes for NRC approval.
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PDR ADOCK 05000267 3
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g PSC's defueling plans and analyses have now progressed to the point that we are confident that the changes and modifications for. defueling do not involve any unreviewed safety questions.
Also, PSC considers that the Fort St. Vrain defueling can be safely accomplished under the requirements of the existing Technical Specifications.
Therefore, PSC believes that the defueling operation can be accomplished'under the provisions of
- 10. CFR 50.59, and PSC no longer plans to submit the aforementioned defueling plan, associated safety analysis report, or Technical Specification Changes for NRC approval prior to defueling.
These' matters were di'icussed with NRR management at the May lith meeting, and we will continue to keep the NRC apprised of our Fort St. Vrain defueling plans and activities.
Again, we a're sorry we were not able to meet with you on May lith, and hope to have the opportunity of introducing ourselves to you in the near future.
Sincerely yours, k
Delwin D. Hock
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Chairman, President and CEO DDH:emm Attachment cc: Document Control Desk,ERC 1
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NRC - PSC EXECUTIVE MEETING MAY 11, 1989 l
l PARTICIPANTS:
. g James G. Partlow, Associate Director for Projects, NRR Gary Holahan, Acting Director, DRSP Les Rubenstein, Assistant Director, Region IV Fred Hebdon, Director, Project Directorate IV (as of 5/15/89)
Pete Erickson, Dec. commissioning Project Manager Kenneth Heitner, FSV Project Manager EEC1 Delwin D. Hock, Chairman, President and CEO Clegg Crawford, Vice President, Nuclear Operations James R. McCotter, Sr. Vice President, General Counsel Charles H. Fuller, Manager, Nuclear Production and Station Manager H. Lawrence Brey, Manager, Nuclear Licensing and Resource Management Richard Vollmer, Sr. Vice President, TENERA Corporation.
AGENDA
- 1. INTRODUCTIONS Del Hock Jim Partlow
- 2. PURPOSE AND OBJECTIVES Del Hock
- 3. PSC PRESENTATION Del Hock
- Operating Plans
- Defueling Plans
- Fuel Disposal Plans
- Decommissioning Plans p-
- 4. DISCUSSION
- 5. CONCLUDING REMARKS L
4.
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i FORT ST. VRAIN I
OPERATING PLANS f
- CURRENT PLANT STATUS l
- OPTIMIZE GENERATION UNTIL FINAL SHUTDOWN z
- POSSIBLE CYCLE 4 P.?4ER LEVEL C0ASTDOWN PERIOD-
- Existing Technical Specifications Are Met
- Unreviewed Safety Questions Not Involved
- FINAL SHUTDOWN DATE:
6 30-90'
' EARLIEST START DATE FOR DEFUELING:
11-01-89
- SCHEDULED DEFUELING DURATION OF 20 TO 30 MONTHS
- TO AVOID ANY' SAFETY IMPACT, PSC PLANS TO COMPLETE DEFUELING BEFORE INITIATING ON-SITE CONVERSION WORK L
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c FORT ST. VRAIN:
DEFUELING PLANS PERFORM DEFUE!.ING SIMILAR TO REFUELING
- Defuel by Region
- Use Boronated Graphite " Dummy" Blocks ANALYSIS TO DATE INDICATES NO TECHNICAL SPECIFICATION CHANGES REQUIRED AND.N0 UNREVIEWED SAFETY QUESTION EXISTS DEFUELING WOULD PROCEED UNDER AUTHORITY PROVIDED IN 10 CFR 50.59 i
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FORT.ST. VRAIN-DEFUELING PLANS
- USE EXISTING TECHNICAL SPECIFICATIONS FOR DEFUELING BASED ON THE FOLLOWING REASONS:
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- Existing technical specifications.contain essential requirements for refueling /defueling.
- PSC has a proven safety. record under~ shutdown conditions with existing Technical Specifications.
- Plant personnel are trained in and proficient with existing technical. specifications.
- Unnecessary human factors perturbations are avoided.
- Overall safety is enhanced by focusing on essential defueling activities.
--NRC and PSC resources can be allocated to activities essential for a safe defueling.
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FORT ST. VRAIN FUEL DISPOSAL PLANS
- SEGMENTS 1 - 8
- DOE Idaho Storage Facility SEGMENT 9 OPTIONS
- FSV Reactor Building fuel Storage
- Ship to DOE Storage Facility
- ISFSI on FSV site SEGMENT 10 (UNIRRADIATED)
Sold to Nuclear Fuel Services, Erwin, TN
. Stored at FSV up to 1992 i
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V, FORT ST. VRAIN DECOMMISSIONING PLANS COMPONENT REMOVAL PHASE
- Control Rod Drive Assemblies
- Helium Circulators DECOMMISSIONING OPTIONS BEING CONSIDERED T
- SAFSTOR Followed By Dismantlement.
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- Early Dismantlement 1
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