ML20081L995
| ML20081L995 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/01/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081L989 | List: |
| References | |
| NUDOCS 9107080266 | |
| Download: ML20081L995 (3) | |
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WASHINoTON, D.C. 20556 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.102 TO FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT N0. 1 DOCv,ET N0. 50-395
1.0 INTRODUCTION
By letter dated October 26, 1990, as supplemented April 15, 1991, South Carolina Electric & Gas Company (the licensee), submitted a request for changes to the Virgil C. Summer Nuclear Station, Unit No. 1 (Summer Station), Technical Specifications (TS). The April 15, 1991, supplement provided minor corrections and did not affect the staff's finding of no significant hazards considerations.
5 2.0 EVALUATION TS 3/4.8.4.2 addresses thermal overload and bypass devices for motor-operated valves (MOVs). The MOVs of concern are listed in a table designated Table 3.8-2.
The surveillance tests associated with this TS ensure the operability of the thermal overload and bypass devices. The proposed amendment would make the following changes to the TS.
1.
The removal of two valves from Table 3.8-2.
2.
The addition of twelve valves to Table 3.8-2.
3.
The rearranging of Table 3.8-2 into alphanumeric order.
4.
The updating of twelve valve dcsignations and functions.
5.
The addition of surveillance tests for valves whose overloads-are not bypassed.
6.
The deletion of surveillance requirements for circuitry not used at Summer Station.
These proposed changes shall be evaluated in order.
9107080266 9107o1 hDR ADOCK 05000393 PDR
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. During Refueling Outage No. 2, the boron injection tank was removed. This hardware change was controlled under the Summer Station's modification program.
Along with the boron injection tank valves XVG-8803A-SI and XVG-8803B-SI, the boron injection tank inlet isolation valves, were' removed. These valves are currently in Table 3.8-2; however, as they are no longer a part of the plant, their deletion from the TS is considered acceptable.
The addition of twelve valves to Table 3.8-2 will ensure that surv'illance tests verifying their operability will be performed. Of these twelve valves, four (XVG-7501, 2, 3, and 4-AC,-the AC supply and return-header isolation valves) are needed for containment isolation and should have been included initially. Prev.iously these four valves were tested for correct operation under plant procedures.
The other eight valves-(XVB-3126 A&B-SW, XVB-A&C-SW,-
and XVG-6516,17,18, and 19-VU) are added since they are considered auxiliary support devices and are subject to the recommendations of Regulatory Guide 1.106. These eight valves must open and close depending on the operation of the equipment with which they are associated. The addition of these twelve valves will enhance ' safety by providing additional assurance that the valves will operate properly under accident conditions; therefore,_the1 proposed change is considered acceptable.
The rearrangement of Table 3.8-2 into alphanumeric order.is a purely administra-tive change.
It is done to make the table easier to use-and has no impact on plant safety;-therefore, this change.is considered acceptable.
The updating of the valve designations is also a purely-administrative change.
It is done to. achieve consistency with-the designations found-on the plant computer and has no impact on plant safety; therefore, this change is.
-considered acceptable.
The combination of surveillance requ'irements 4.8.4.2.b.1 and 4.8.4.2.b.2 adds a.
requirement to test 38 MOVs whose overloads are not bypassed. This additional surveillance requirement.is conservative, and will add _ assurance that these valves will operate properly under: accident conditions;- therefore,. this change -
is considered acceptable.
The deletion-of surveillance requirements 4.8.4.2.a.1 removes the requirement for surveillance-testing ~of MOVs-whose overloads'are continuously. bypassed.
-Since there are no such MOVs;at Summer Station, this change has.no--impact on plant safety and is considered acceptable.-
3.0 STATE CONSULTATION
In accordance with the Commission's~ regulations, the South Carolina State official was-. notified of the proposed issuance of the amendment.
The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located wa;nin the restricted area as defined in 10 CFR Part 20 and changes the surveillance requirements. The NRC staff has determined that the amendment involves 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 radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (56 FR 896).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has 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, (2) such s
activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
G. Wunder Date:
July 1,1991
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