ML20245L388
| ML20245L388 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/16/1989 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20245L393 | List: |
| References | |
| P-89287, NUDOCS 8908220105 | |
| Download: ML20245L388 (2) | |
Text
g h Public Service
- M"'O*Lo,.o.
P.O. Box 840 Denver CO 80201- 0840 l
August 16, 1989 A. clegg crawford Fort St. Vrain vie, p,,sioen Unit No. I Nuclear opmatims P-89287 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 Attn: Mr. Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Docket No. 50-267
SUBJECT:
Fort St. Vrain Defueling SAR
REFERENCE:
NRC Letter, Heitner to Williams, dated August 8, 1989 (G-89261)
Dear Mr. Weiss:
Public Service Company of Colorado (PSC) is concluding its development of an effective program to proceed with the defueling of the Fort St. Vrain (FSV) Nuclear Generating Station. An NRC/PSC meeting was held on July 18, 1989 to discuss the defueling methodology as well as specific issues of NRC concern.
As discussed in the July 18th meeting, PSC is hereby submitting for your information the Safety Analysis Report (SAR) for defueling of the FSV reactor.
PSC has concluded that no unreviewed safety questions exist which would preclude PSC from proceeding with the defueling process.
This SAR has been reviewed and approved by both the onsite and offsite safety review committees.
The NRC should take particular notice that the base case reactivity calculations performed in support of the Defueling SAR utilized the assumption that the reactor core had experienced 154.5 EFPD of burnup in Cycle 4.
At the present time the Cycle 4 core has experienced over 225 EFPD of burnup. Each 50 EFPD of plant operation reduces core positive reactivity by approximately 0.5 percent, and therefore, every succeeding day of operation introduces additional conservatism for the actual defueling as compared to the base case analyzed in the SAR.
For example, as explained in Section 3.4 of the Defueling SAR, at the present time only one specific control rod drive would need to be disconnected from its poser source to prevent any possibility that a wrong rod withdrawal during defueling could lead to an inadvertent criticality.
In the 154.5 EFPD case, three specific control rod drives had to be disconnected.
3908220105 890816 k
fDR ADOCK 05000267 9,
eDe
s 4:
F P-89287-F 2
.Page 2.
r L
August 16, 1989 m
o PSC's position. relative to the need for additional-Technical Specifications and. modifications to the existing Technical Specifications was discussed in significant detail during the July 18th meeting.- PSC has completed an assessment of whether Technical Specification changes are required relative to. LWR core off-loading.
Based on this assessment, core off-loading activities do' not appear-to' be ' described in LWR Technical Specifications, and LWR core off-
-loading can proceed without - Technical specification revision. The existing FSV Technical Specifications cover the broader spectrum of fuel handling activities with the same basic requirements as LWR Technical Specifications.
In addition, the attached.Defueling SAR i
evaluates core off-loading safety and accident conditions in as much I
or more detail than several representative LWR FSARs.
In conclusion, PSC believes that this assessment supports PSC's position that the existing FSV = Technical Specifications contain adequate controls to
- assure a safe defueling.
~In_ the referenced letter, the NRC requested that PSC submit proposed amendments to the existing Technical Specifications which govern reactivity control, spent fuel handling and spent fuel storage by September 6.11989. PSC is in the process of preparing the changes to
. upgrade these' Technical Specifications in accordance.with the NRC request. PSC remains ready to work with the NRC to resolve any outstanding issues or concerns that may exist related to defueling.
Should you have any questions on this matter, please contact Mr. M.
' H. Holmes at (303) 480-6960.
Very truly yours, A. Clegg Crawford Vice President, Nuclear Operations ACC/JCS:drg Attachment cc: Regional Administrator, Region IV Attn: Mr. T. F. Westerman, Chief Projects Section B Mr. R. E. Farrell Senior Resident Inspector fort St. Vrain Robert M. Quillen Director Radiation Control Division Colorado Department of Health 4210 East lith Avenue Denver Colorado 80220 l
_____________________________.__ _ _______ __________ _ _ _ _____ _ _ _ J