ML20042E711
| ML20042E711 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/25/1990 |
| From: | Chrzanowski R COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20042E712 | List: |
| References | |
| 0912T, 912T, NUDOCS 9005010224 | |
| Download: ML20042E711 (3) | |
Text
} 1400 Opus Place Commonwealth Edison g-
.(
) Downers Grove, Illinois 60515 k/
April 25, 1990 l
l i
Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn. Document Control Desk
Subject:
Zion Station Units 1 and 2 Application for Amendment to Facility Operating License DPR-39 and DPR-48 NEC_ Docket Nas. 50-225_and_10-30A
Reference:
March 23, 1990, letter from R.A. Chrzanowski to T.E. Murley
Dear Dr. Murley:
Commonwealth Edison proposes to amend Appendix A, Technical Specifications for Facility Operating Licenses DPR-39 and DPR-48 for the Zion Station, pursuant to 10 CFR 50.90.
The proposed amendment corrects inconsistencies in the Reactor Vessel Toughness Tables.
The referenced letter notified the NRC and provided a detailed description and resolution of the inconsistencies found in the Babcock 0 Wilcox reactor vessel drawings for Zion Station Units 1 and 2.
T1.e corrections for the inconsistencies are administrative in i.ature and as such current operational limits remain unchanged.
l l contains a summary of the proposed changes. Attachment l
2 contains marked up Technical Specification pages and a copy of the retyped Technical Specification pages.
The proposed changes have been reviewed and approved by both onsite and offsite review in accordance with 10 CFR 50.92(c).
Commonwealth Edison has determined that no significant hazards consideration exists and has performed an Environmental Assessment.
Documentation of these reviews is l
contained in Attachments 3 and 4 respectively.
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,-T.E,*Murley '
April 25, 1990 2
Commonwealth Edison is notifying-the State of Illinois of this i
application for amendment by transmitting a copy of this letter and its 3
attachments to the designated state official.
Please direct any questions regarding this matter to this office, f
i Very truly yours, p
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R. A; hrzanowskt Nuclear Licen ing Administrator
(
Attachments:
- 1) Summary of Proposed Changes i
- 2) Marked up' Technical Sepcification Pages and Typed Techical Sepcification Pages
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- 3) Evaluation of Significant_Ilazards Consideration-
- 4) Environmental Assessment cca C. Patel - NRR I
Resident Inspector - Zion Region III Office i
j Office of Nuclear Facility Safety - IDNS f
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i 0912T:2
ATTACHMENT 1 a
SUMMARY
OF PROPOSED CHANGES This proposed change is being submitted in accordance with the letter dated March 23, 1990 from R.A Chrzanowski to T.E. Murley, regarding administrative inconsistencies in the Reactor Vessel Toughness Tables. These inconsistencies consist of the omission of three weld materials from the Unit I and 2 Reactor Vessel Toughness Tables and the interchange of the lower and intermediate shell materials in the Unit 2 data table. These changes are considered to be administrative in nature and alter no current operating limitations or additional Specifications. The appropriate limitat.4ons, such as Heatup/Cooldown Curves and Pressurized Thermal Shock calculations, are based on the most limiting weld which has been properly accounted for in all required calculations.
This proposed change is being made to correct reference to materials only.
The discrepancies addressed by this proposed change were discovered during a drawing review to support a neutron flux reduction study for Zion Station.
The discrepancies have been resolved between Commonwealth Edison, Babcock &
Wilcox, and Westinghouse as addressed in the March 23, 1990 letter from R. A. Chrzanowski to T. E. Murley.
Following is a detailed description and justification of the changes made to Tables 3.3.2-1 and 3.3.2-2:
A line item has been added to Table 3.3.2-1 adding weld materials WF154 and SA1769 not previously addrested. The materials are located in the Nozzle to Intermediate Shell Girth Weld Seam.
Items (e) and (f) have been added to address the weld material heat lot and flux composition for these materials.
The changes are being made due to the omission of these items from the present table.
A line item has been added to Table 3.3.2-2 adding weld material WF200 not previously addressed. This material is located in the Nozzle to Intermediate Shell Girth Weld Seam.
Item (c) has been added to address the weld material heat lot and flux composition for this material. The change is being made due to the omission of this item from the present table.
In addition, the Intermediate and Lower Shells have been changed due to a transposition error. During construction of the Reactor Vessels, the Lower and Intermediate Shells were interchanged.- This interchange of shells has resulted in Table 3.3.2-2 referencing the wrong materials for these shells. The change will correct this situation, sn that the shells will reference the correct materials.
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0912T 3
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