ML20246L979
| ML20246L979 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/09/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246L976 | List: |
| References | |
| GL-83-28, GL-85-09, GL-85-9, NUDOCS 8905190006 | |
| Download: ML20246L979 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 63 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 57 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMPANY, ET AL.
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET N05. 50-413 AND 50-414 1.0 INTR 00VCTION By Item 4.3 of Generic Letter (GL) 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events," the Commission established the requirement for the automatic actuation of the shunt trip attachment on reactor trip breakers'for nuclear plants utilizing Westinghouse nuclear steam supply systems. GL 83-28 also established that licensees were to submit needed Technical Specification (TS) change requests after staff approval of the modified design.
In its evaluation of the Westinghouse generic design
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modifications, the Commission concluded that TS changes should be proposed by licensees to explicitly require independent testing of the undervoltage and shunt trip attachments during power operation, testing of bypass breakers prior to use, and independent testing of the control room manual switch contacts and wiring during each refueling outage. Accordingly, the Commission issued GL 85-09, " Technical Specifications for Generic Letter 83-28, Item 4.3" to identify the appropriate changes to this end, to provide a model TS to.use as guidance, and to request that licensees propose TS changes using this guidance.
By letter dated June 19, 1987, and supplemented March 10, 1989, Duke Power Company, et al., (the licensee) proposed changes to the Catawba Units 1 and 2 TSs in accordance with GL 85-09.
2.0 EVALUATION The licensee's proposed changes consist of:
(a) Adding a new Action Statement 12 to Item 19 "Recctor Trip Breakers" of TS Table 3.3-1.
This new Action requires that:
With one or 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 inoperable and apply ACTION 9.
The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status. With the breaker bypassed, apply Action 9.
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- (b) Adding a new Item 21 " Reactor Trip Bypass Breakers" and its associated Action Statement 13 to TS Table 3.3-1.
This new Action requires that:
With any reactor trip bypass breaker inoperable, restore the bypass breaker to OPERAELE status prior to placing it in service.
(c) Adding a new Table Notation 14 to Item 1 " Manual Reactor Trip" of TS Table 4.3-1.
This new Notation states that:
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
(d) Adding Item 21 " Reactor Trip Bypass Breakers" and its associated Table Notations 7,15, and 16, and modify Table Notation 11 of TS Table 4.3-1.
Notations 7,15, and 16, respectively, state that:
Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
A local manual shunt trip on the bypass breakers shall be performed prior to placing breaker in service.
The automatic undervoltage trip capability shall be verified OPERABLE.
The modified notation 11 states that:
The TRIP ACTUATING DEVICE OPERATIONAL TEST shal: include independent verification of the OPERABILITY of the undervoltage and shunt trips.
Additionally, TS Bases 3/4.3.1 and 3/4.3.2 were supplemented to indicate that the TSs for the Reactor Trip Breakers and the Reactor Trip Bypass Breakers us based upon GL 65-09.
We have reviewed the above TS changes proposed by the licensee and find them to be consistent with those of GL 85-09. Therefore, we conclude that these changes enhance plant reliability and safety, and that they are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational exposure. The NRC staff has made a determination that the amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for
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- categorical exclusion ::et forth in CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact s
' ment or environmental assessment need be prepared in connection with the ist nce of these amendments.
4.0 CONCLUSION
The Comitsion made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (54 FR 13763) on April 5, 1989. The Comission consulted with the sta.te of South Carolina.
No public coments were received, and the state of South Carolina did not have any coments.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of these amendments will not be inimical to the common defense and security or to the health and safr4ty of the public.
Principal Contributors:
K. Jabbour, PDII-3/DRP-I/II Dated: May 9, 1989 l
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