ML20235G765
| ML20235G765 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/23/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235G755 | List: |
| References | |
| NUDOCS 8709300203 | |
| Download: ML20235G765 (3) | |
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION 3.
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' - ' ' l W ASHINGTON. D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENOMENT NO. 11 T0' FACILITY OPERATING LICENSE NO. NPF-47 GULF STATES UTILITIES COMPANY RIVER BEND STATION, UNIT 1 l
DOCKET NO. 50-458
1.0 INTRODUCTION
By letter dated September 12, 1986, Gulf States Utilities Company (GSU)
(the licensee) requested an amendment to Facility Operating License No.
NPF-47 for the River Bend Station, 'Jnit 1.
The proposed amendment would change the trip setpoints, allowable values and footnotes for the Main Steam Line Flow-High and the Reactor Core Isolation Cooling (RCIC) Steam Line Flow-High. The proposed revision would also change a footnote for the Residual Heat Removal (RHR)/RCIC Steam Line Flow-High.
2.0 EVALUATION River Bend Unit 1 Technical Specification 3.3.2, Isolation Actuation Instrumentation, Table 3.3.2-2, Isolation Actuation Instrumentation Setpoint, Item 2.d, Main Steam Line Flow-High presently identifies a trip setpoint of < 173 psid with an allowable value of < 178 psid and includes a footnote which states that this is a.prelimiiiary setpoint subject to confirmation or revision based on startup test data. The proposed changes would establish the following setpoints based on the results of the completed startup testing:
2.d.
Main Steam Line Flow-High Trip Setpoint Allowable Value 1.
Line A
< 146 psid
< 151 psid 2.
Line B 7 156 psid i 161 psid 3.
Line C 7 153 psid 7 158 psid 4.
Line D 5164psid
{169psid The change also deletes the footnote since the required testing has been completed.
All of these setpoints are within the design basis specification and are conservative with respect to the assumptions of the accident analysis to ensure the isolation of the Main Steam Line System in the event of a break in that system.
The use of four setpoints instead of one allows for operational flexibility while still maintaining the leak detection limit at 140% of rated flow for all four legs.
9709300203 870923 PDR ADOCK 05000458 P
q The proposed change does not involve a physical change to the plant and is within the bounds of the design basis and the assumptions of the accident analysis.
The proposed change does not include a significant reduction in safety margin because these setpoint revisions are more
.' conservative and reflect actual plant test data on Main Steam Line Flow. The staff finds the changes to Technical Specification Table 1
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3.3.2-2 Item'2.d. to be acceptable.
i Technical Specification 3.3.2, Isolation Actuation Instrumentation,
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Table 3.3.2-2, Isolation Actuation Instrumentation Setpoint, Item 5.a, t
RCIC Steam Line Flow-High, presently identifies a trip setpoint of
< 222" H 0 with an allowable valve of < 230.5" H O and includes a 2
2 Tootnote which states that this is a preliminary setpoint subject to confirmation or revision bass.d on startup test data.
The proposed changes would establish the trip setpoint at < 127" H.30 with an allowable value of < 135.5" H 0 and delete the footnote about preliminary status.
2 The proposed change does r.ot include a physical change to the plant and is within the bounds of the design basis and the assumptions of the accident analysis.
The proposed change does not include a significant reduction in safety margin because this setpoint revision is more conservative and reflects actual plant test data on RCIC flow.
The staff finds the changes to Technical Specification Table 3.3.2-2 Item 5.a to be acceptable.
4 Technical Specification 3.3.2, Isolation Actuation Instrumentation, Table 3.3.2-2, Isolation Actuation Instrumentation Setpoint, Item 5.1, RHR/RCIC Steam Line Flow-High, includes a footnote which states that the setpoint listed is an initial setpoint with the final setpoint to be determined during startup testing.
The proposed change would revise the footnote to state that the final setpoint will be determined during testing prfor 4
to operation in the steam condensing mode following the Nuclear Regulatory Commission's approval to operate in that mode.
The requirement to submit I
any setpoint changes to the NRC within 90 days after testing would remain.
Since operation in the steam condensing mode is necessary to establish setpoint and there is a preexisting License Condition (Reference License Condition 5.a to NPF-47) which requires NRC approval to operate in that j
mode, this change is administrative only with no impact on safe operation of the plant and is, therefore, acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the i
i installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no signi-l I
ficant change in the types, of any effluents that may be released offsite, 1
and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a I
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' proposed finding that 'this' amendment involves no significant hazards consideration and there has been no public comment on such finding.
4 Accordingly, this 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 nor environmental assessment need be pnepared in connection with the issuance of this amendment.
40 CONCLUSION The staff 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, and (2) 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.
The staff therefore concludes that the proposed changes are acceptable, and they are hereby incorporated into the River Bend Unit 1 Technical Specifications.
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Principal Contributors:
J. Stewart Dated: Septemb~er 23, 1987 l
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