ML20149J777
| ML20149J777 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/17/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149J762 | List: |
| References | |
| NUDOCS 8802230214 | |
| Download: ML20149J777 (2) | |
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UNITEnhTATES NUCLEAR REGULATORY COMMISSION c
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WASHINGTON, D. C, 20555
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\\1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
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RELATED TO AMENDMENT NO..% 10 FACILITY OPERATING LT ENSE,N0 MPF-30,
j UNION ELECTRIC COMPANY
+T CALLAWAY PLANT, UNIT I DOCKET NO. TfN 50-483
1.0 INTRODUCTION
By brter date:i Sept' ember 10, 1987, Unir Factric Company submitted a yequest for changes to the. Tecndiaal Specificati, c Table 4.3-1 surveillance re'qufrea s ments and b igclude (tQ addition of runctional testing requirements for ti.b\\.k, reactor trip bypass Dieakers prior to placing them in service during monthly reactor trWbreaker testirq and during refueling outages.
2.0 DISCUSSION On April 3,1987, the stafrissued Amendment No.19 to Operating License No. NPF-30. The amendmdnt changed the Tectoi the reactor trip breake"s te equire 48-hour. cal Specifications regarding restoration in the event of loss of one,00 the divgsesreac tor trip featurd (undervoltage or shunt trip attacheer.t), indepWent verification of the operability of the under-voltage and shunt trip ar,achsents, and independent testing.pf,6utage.,
j tte control roo.n manual reactor trif switch contacts dur fog each refueling l
Amendment No.19 reflected the licensee's response to a }ortion of those l
changes specified in Generic Letter 85-09. However, the licensee did not
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l propose a Technical Specifit3 tion change to incorporate functional testing N l
of bypass breakers prior to placing them in operation. The staff found the i licensee's position with regard to bypan breakers unacceptable and requested the licensee to propose changes to the Callaway Technical Specifications to provide for bypass breaker testig c6nsistent wititthe staff position stated in Generic Letter 85-09.
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g On September 10, 1987, the ifcensee requested changes, to ta Callamy'iechnical Specifications to include the addition 6f funct,!olal t.estfr@rsquirenents fort the reactor trip bypass breaken. The licensee' also stated tnat 'the September 10, 1987 appifcation supersaded their orfgicd: position An 1ypass breaker testing.
1 3.0 EVALUATION
\\t The licensee has proposed the following changes with resp'tict to reactor trip bypass breaker testing.
Prior to the monthly reactor trip breaker tests, the
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bypass breaker for that train will be racked to the test position, operability will be verifled by a local manual shunt trip, and then the breaker will be racked into the operate position and closed to pemit testing of its associated reactor trip breaker.
Since the operation of the undervoltage 8802230214 800217 PDR ADOCK OSO 3
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trip attachments for the bypass breakers is controlled by the opposite train of the reactor protection system, it is proposed that this feature be tested during refueling outages only.
In Generic Letter 85-09 the staff concluded that the above methods for testing l
bypass breakers are acceptable.
The basis for this conclusion included the fact that a readily available means does not exist to permit online testing of the automatic undervoltage trip feature of the bypass breakers and that confinnation of the cperability of the shunt trip attachment prior to placing the bypass breaker in service provides additional assurance that the bypass breaker could be tripped via a manual reactor trip. Since each bypass breaker is exercised prior to use through actuation via the shunt trip which has a margin of operating force sufficient to overcome any resistance to actuation caused by accumulated dit t, corrosion or lubricant aging, this provides greater assurance that the bypass breaker will trip in response to a valid automatic trip signal. Also, because this bypass breaker trip prior to use tests the shunt trip which accomplishes the manual trip function, it provides greater assurance that the bypass breaker can be tripped manually by the operator when required.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and/or a change to the surveillance require-ment. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of at.y effluents that may be released offsite, and that there is no significant
- increase in individual or cumulative occupational radiation exposure. The Coninission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coninent on such finding. Accordingly, this amendment meets the eli criteria for categorical exclusicn set forth in 10 CFR 651.22(c)(9)gibility Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of this amendment.
y 5.0 QNCLUSION The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner; and (2) public such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
l 6.0 -ACKNOWLEDGEMENT l
Principal Contributor:
T. Alexion, PDIII-3 Dated: Febmary 17, 1988 y
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