ML20247C145
| ML20247C145 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/10/1989 |
| From: | Trzyna G COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20247C150 | List: |
| References | |
| NUDOCS 8905240355 | |
| Download: ML20247C145 (4) | |
Text
-..
] C*mm:nw:dth Edison
.X ; : 72 West Adams Street, Chicago, Illinois
. Address Reply toTWOffice BoTf6T V
Chicago, Illinois 60690 - 0767 L
l May 10, 1989 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington,'DC 20555
Subject:
' i.on Nuclear Power Station, Units 1 and 2 acense Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304 Proposed Amendment to Technical Specifications Sections 3.1 and 4.1.
" Reactor Protection System" References April 17, 1989 letter from G.E. Trzyna to US NRC Centlement The original request for a proposed amendment to Sections 3.1 and 4.1 of the Technical Specifications for Zion Station was submitted on April 17, 1989.
Subsequent to the original submittal, additional discussions between Commonwealth Edison and NRC personnel have indicated that some minor clarifications to the original submittal would be required. The purpose cf this letter is to provide the appropriate revisions to the proposed amendment.
A summary of the changes is provided belows
- 1) Table 3.1-1.
page_10_and 31. T.nhle Heading,_Io.lumn_5 This change removed the (+) footnote from the heading of Column 5 and applied it to the individual line items as appropriate. This change was necessary because the (+)
footnote would not apply to Line Item 22',
an addition to the Table.
- 2) Igble 3.1-1, page 31 Line 17 This change clarified the wording of the "Setpoint" to make it consistent with Standardized Tech Specs.
- 3) Inbje 3.1-1, page 31 Line 16.
This change clarified the wording of the "Setpoint" to make it consistent with Standardized Tech Specs.
- 4) Inb1r l.1-1. paga ll d ine 21 This change distinguished the Automatic Reactor Trip Logic and the R actor Trip Breakers as two separate line items.
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' i-L Also, the (R) footnote has been changed to read, "During Modes 3,4 or 5 and with the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal, the following applies: With the number of OPERABLE channels one less than the minimum OPERABLE channels requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor Breakers within the next hour."
These words are consistent with the requirements of Generic Letter 85-09.
- 5) Iphie 3.1-1. PAgg 3 J Eg_22 This change incorporates " Reactor Trip Breakers" as a separate line item in the table.
Also, a new (1#) footnote has been added to read, "During Modes 1 or 2,' with one of.the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperabit and maintain or proceed.to Hot showdown within four hours if the unacceptable condition arises during power operation. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance and testing to restore the breaker to OPERABLE status. The words are consistent with the requirements of Generic Letter 85-09.
- 6) IAble 3.1-1. page_12 This change addresses the (+++)
footnote to change the allowable outage time from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This time period was discussed with NRC personnel, and is consistent with other facilities that have similar vintage reactor protection circuitry.
- 7) Table 3.1-1. s ge 32 This change added (landl#) footnotes to the table.
- 8) Ip121R_id-lLpage_15dna_1 This change provides a clarification of the last sentence of the Remarks column to indicate that the appropriate test shall apply to the Reactor Trip Bypass Breakers. contains the revised pages of the Technical Specifications. contains a significant hazardu review which demonstrates that the proposed changes are of minor significance, and are consistent with the guidance of Generic Letter 85-09, and consequently warrant consideration as no significant hazards.
Some of the changes contained in this amendment will require Zion Station to perform routine surveillance on a refueling frequency to components of reactor protection circuitry that were not previously required to be tested. The item of specific concern is the refueling surveillance associated with item 23 of Table 4.1-1.
In order to accomplish the new test requirements, procedure revisions will be required.
Commonwealth Edison will attempt to expedite these revisions, however, these procedures may not be available for use during the Fall, 1989 Unit 3 refueling outage. Therefore, Commonwealth Edison requests that consideration be given to delay the requirement for testing until the first refueling outage for each unit after January 1, 1990.
L i
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As provided by 10CFR 50.91, the State of Illinois is being notified of this amendment request by transmittal of this letter and attachments.
(
Please direct any questions that you may have to this office.
Ver truly yours, k)A.
d p
G.E. Trzyna Nuclear Licensing Administrator 0115T22-24 cca Chandu Patel - NRR NRC Resident Inspector - Zion M.C. Parker - IDNS
j s
i ATTACiniENI_1 l
21DILNHCLEAR POWER STATION EEDEQEED_AMENDMERI_TD IICENICAL SPECIFICATIONS SECTIONS 3.1 AND 4.1 EAGRISLMODif1ED 30 31 32 35 EAGEISl_ADDED NONE FAGELSLDELEIED NONE
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