ML20247C273
| ML20247C273 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/10/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20247C150 | List: |
| References | |
| NUDOCS 8905240386 | |
| Download: ML20247C273 (7) | |
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LION NUCLEAR POWER STATIOl{
ERREQSED MIEHDMENT TQ IE.CIEllCAL SPEClflCAILQUE SECTIONJ 3.1 and 4.1 SIGNIFICANT HAZAEDS REVIEW l
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EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION i
Commonwealth Edison has evaluated this proposed amendment and has determined that it involves no significant hazards considerations.
According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards considerations if operation of the facility, in accordance with the proposed snendment, would not 1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)
Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)
Involve a algnificant reduction in a margin of safety.
The proposed amendment involves revisions to the operability and surveillance requirements given in Technical specification Tables 3.1-1 and 4.1-1 for Zion Station. The changes clarify the operability requirements for Automatic Reactor Trip Logic and the Reactor Trip Breakers. The changes to Table 4.1-1 clarify the surveillance requirements for the Manual Reactor Trip function to require independent verification of the operability of the Undervoltage'and Shunt Trip circuits and the operability of the Bypass Breaker circuit; the Monthly Channel Functional Test for the Automatic Reactor Trip Logic has been clarified to require testing each train on alternate months (at a 62 day interval). Monthly and Refueling Surveillance Requirements have been defined for Reactor Trip Breakers and Bypass Breakers.
All of the proposed changes have been worded in accordance with the guidelines of NRC Generic Letter 85-09, and are consistent with Technical Specifications in effect for other Pressurized Water Reactors of similar vintage. The clarification notes for the Automatic Reactor Trip Logic Surveillance and the use of the alternate month testing interval are similar to the Specifications currently in effect at the Ginna plant.
1)
Th.e proppsgighangas_da_not involve a_significant increase to tite probability or. conge_quengga_0Lan_acsidenLpleYinnsly evaluntadt The addition of the requirement for automatic actuation of the shunt trip device provides an alternate method to open the reactor trip breakers.
Therefore, when a reactor trip signal is generated there are diverse mechanisms to provide a reactor breaker trip which should minimize the possibility of an Anticipated Transient Without Scram (ATWS). The proposed changes revise the surveillance to require independent testing of the undervoltage and shunt trip devices for the manual reactor trip and the reactor trip breakers. These surveillance ensure reactor trip breaker operability when required and thus do not involve a significant increese to the probability or consequences of an accident that was previously evaluated.
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- 2) Ihe_pIspaned chang.es do not create the possibility oL a new or different kind oLJacident from any previously evaluated.
The proposed changes do not change the manner in which the reactor protection system provides plant protection. The addition of the shunt trip attachment provides an alternate method to open the breakers when a reactor trip signal is generated. Therefore, if one trip mechanism falls, the other trip mechanism is available, which increases the reliability of the reactor protection system and decreases the possibility of an ATWS event and therefore does not create the possibility of a new or different kind of accident that was previously evaluated.
- 3) The._ptsppagd changes do not involve a significant reductiqa_in_a margin of safety.
The proposed changes are expected to increase the overall margin of safety because they provide an alternate method to trip the reactor trip breakers, thereby limiting the potential for an ATWS event. The proposed surveillance changes are designed to verify operability of the reactor trip and bypass breakers and therefore do not involve a significant reduction in the margin of safety.
Therefore, based upon the above evaluation, Commonwealth Edison concludes that the proposed changes to the Technical specifications do not involve a significant hazards consideration.
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