ML18095A459
| ML18095A459 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/04/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18095A460 | List: |
| References | |
| NLR-N90052, NUDOCS 9009110153 | |
| Download: ML18095A459 (8) | |
Text
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Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations SEP-o 4 19QJ NLR-N90052 LCR 89-05 United states Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2, respectively.
In accordance with 10CFR50.91 (b) (1) requirements, a copy of this request has been sent to the State of New Jersey.
The proposed amendment modifies Technical Specification Section 2.2, Table 2-2.1 and Section 3/4.3.2, Table 3.3-4.
The change incorporates new trip setpoints for steam generator water level low-low and steam line pressure low.
Both trip setpoint changes would increase the margin between the RPS setpoint and the safety limit. includes a description, reason, justification and significant hazards analysis for the proposed change. contains the Technical Specification pages revised with pen and ink changes.
We request that the implementation date be established at 60 days following issuance of the approved License Amendment.
Document Control Desk NLR-N90052 SEP o 4 1990*
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely,
~~
Attachments c
Mr J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering, CN 415 Trenton, NJ 08625
REF:
NLR-N90052 STATE OF NEW JERSEY
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SS.
COUNTY OF SALEM
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- s. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated September 4, 1990
, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
7 Subscribed and Sworn to before me this
- _f/.j{
day of ~/erA../w, 1990
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Notary Public of New Jersey VANITA M. MARSHALL NOTARY.PUilLIC OF NEW JERSEY My Commission expires on ~~M_y_Com_.~m-g_*_lln~kp~k-*&~M_ay~G,_1_99~3~~
NLR-N90052 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNIT NOS. 1 AND 2 LCR 89-05 STEAM GENERATOR LEVEL LOW LOW TRIP AND STEAM LINE PRESSURE LOW TRIP SETPOINTS I.
Description of Change Design change packages lSC-2241 and 2SC-2241 revised the Reactor Protection System (RPS) setpoints for steam generator level low-low and for steam line pressure low.
The Steam Generator level low-low trip setpoint was changed from 8.5% to 16% and the allowable value was changed from 7.5% to 14.8%.
The steam line pressure low trip setpoint was changed from 500 psig to 600 psig, and the allowable value was changed from 480 psig to 579 psig.
These changes are required to provide adequate margin in the subject instrument loops to account for transmitter inaccuracy due to the one hour Post-LOCA environmental effects, a criterion imposed by Section 3(4) of NUREG-0588, Rev. 1.
II.
Reason for the Change The inadequacy of the existing margins for the subject instrument loops was discovered during a review of all RPS instrument loops by Westinghouse.
This effort was initiated by Public Service Electric and Gas Company (PSE&G) to ensure the existing setpoints for both Salem units were conservative in light of a recent revision to the Westinghouse methodology for setpoint calculations. Justification for continued operation with the existing setpoints was provided by Westinghouse and approved by PSE&G via engineering evaluations S-C-RPC-CEE-0309 and S-C-RPC-CEE-0310.
III. Justification for the Change Operation of the facility in accordance with the new trip setpoints for steam generator level low-low and steam line pressure low increases the margin between* the RPS trip setpoint and its associated safety limit.
This would decrease the consequences of any accident related to those protection functions.
This change to the instrument loops is a calibration change and does not alter the Reactor Protection System (RPS) in any fashion that would decrease the reliability of the RPS.
The change in the steam generator level low-low setpoint will present a small decrease in the operating margin of the plant.
However, this setpoint has previously been set at 18% and licensed in Technical Specifications.
The methodology employed by Westinghouse has been approved by the NRC and the two calculations involved have been independently verified by PSE&G.
The proposed amendment revises the setpoints of the steam generator low-low level loop and the steam line pressure low loop in the conservative direction.
The only effect on plant operation, performance, or transient response will be to initiate a protective action earlier in an event.
IV.
Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not:
- 1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
The proposed changes to to the trip setpoints for steam generator level low-low and to steam line pressure low increase the margin between the RPS trip setpoint and its associated safety limit.
Because these changes would initiate protective actions associated with these functions earlier, the consequences of an accident previously analyzed would not be increased.
The change to the RPS is only a calibration change and does not alter the RPS is any fashion.
This would not change the reliability of the RPS and therefore, would not increase the possibility of a previously analyzed accident.
- 2.
Create the possibility of a new or different kind of accident.
The proposed changes are calibration changes.
The only effect on plant operation, performance or transient response is to initiate a protective action earlier than previously.
Therefore, there can be no impact on plant response to the point where a different accident is created.
- 3.
Involve a significant reduction in a margin of safety.
The proposed changes are conservative.
They increase the margin between the RPS trip setpoint and the safety limit.
Therefore, there is no reduction in any margin of safety.
- v.
Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.
ATTACHMENT 2
l Salem Unit 1