ML20070D274
| ML20070D274 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070D267 | List: |
| References | |
| NUDOCS 9407070311 | |
| Download: ML20070D274 (3) | |
Text
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%e y?g y-UNITED STATES 4
S NUCLEAR REGULATORY COMMISSION E
f WASHINGTON, D.C. 20566-0001
%,..... p SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGVLATION RELATED TO AMENDMENT N0.186 TO FACILITY RER_ATING LICENSE NO. DPR-50 METROPOLITAN EDIS0N CQifFT JERSEY CENTRAL POWER & LIGH1 COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NVCLEAR CORPORATIO_t]
THREE MILE ISLAND NUCLEAR STATION. UNIT N0. 1 DOCKET N0. 50-289
1.0 INTRODUCTION
By letter dated June 12, 1991, the GPU Nuclear Corporation (GPUN or the licensee) submitted a request for changes to the Three Mile Island Nuclear Station, Unit No.1 (TMI-1) Technical Specifications (TS).
The requested changes would clarify the pressurizer power-operated relief valve (PORV) setpoint ranges and would provide action requirements to be satisfied when the setpoint ranges are not met.
2.0 EVALVATION The function of the PORV is to prevent overpressurization of the reactor coolant system (RCS) during normal power operation as well as to provide low temperature overpressure protection (LTOP) when RCS temperature is below 275'F.
The LTOP function is a safety function whereas the overpressure safety function when RCS temperature is above 332*F is provided by the two Code safety relief valves on the pressurizer.
No credit is taken for the PORV or PORV block valve in the plant safety analysis.
The proposed TS requires certain plant conditions to be met in order to isolate the PORV at temperatures below 332*F.
The motor-operated PORV block valve is located between the pressurizer and the PORV and can be used to isolate the PORV in the event of PORV seat leakage or failure of the PORV to reseat following actuation.
There are tolerance bands in the TMI-l TS for both temperature and pressure with respect to the PORV setpoints.
The tolerance band for temperature is 275'Fil2*F (263*F to 287'F). The tolerance band for the pressure setpoint is the nominal value 125 psig.
The nominal value with RCS temperature above 287'F is 2450 psig (range of 2425 psig to 2475 psig).
The nominal value with RCS temperature below 263'F is 485 psig (range of 460 psig to 510 psig).
9407070311 940630 PDR ADOCK 05000289 P
i 2-The proposed amendment clarifies the setpoint requirements and tolerance bands to make them more understandable to the plant operators.
The specific changes are discussed below:
3.1.12.1 Clarifies that the PORV shall not be taken out of service or isolated from the system when RCS temperatures are below 332*F unless one of three specified conditions is in effect.
s Brerks down into separate conditions the requirement to rack out high pressure injection pump breakers and closing valves MU-V16A/B/C/D and MU-V217.
Adds a requirement to open the breakers to MU-V16A/B/C/D when the valves are required to be closed, f
3.1.12.2 More clearly status acceptable range for PORV pressure setting stating a minimum for RCS temperature above 275'F (il2*F) and a maximum for RCS temperatures below 275'F (il2*F).
States actions to be taken when PORV pressure setpoints do not meet the required range (formerly stated in 3.1.12.4.a).
3.1.12.3 Adds a requirement that the breakers for MU-V16A/B/C/D be opened whenever the valves are required to be shut (with RCS temperature s332*F and the reactor vessel head installed).
3.1.12.4 Relocates action requirements for an inoperable PORV to Section 3.1.12.3.
The " Bases" section for TS 3.1.12 would also be revised to clarify the bases i
for the setpoints and operability requirements.
l In addition to clarifying the TS to make them more understandable (i.e.,
administrative and editorial changes), the licensee stated that the minor reorganization of PORV requirements from 3.1.12.4 to 3.1.12.2 is justified because the PORV is used neither as the primary means of mitigating a design-basis stean generator tube rupture accident nor for RCS pressure control during plant cooldown.
The staff has reviewed these changes and agrees with the licensee's determination.
The changes are, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATIQB The amendment chances requirements with respect to installation or use of a facility component located within the restricted area as defined in
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The NRC staff has determined that the amendment involves no significant increase in the amounts or types of 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 31435).
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 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 pubilc.
Principal Contributor:
R. Hernan Date: June 30, 1994
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