ML20070K274
| ML20070K274 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/11/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K271 | List: |
| References | |
| NUDOCS 9103180376 | |
| Download: ML20070K274 (3) | |
Text
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UNITED STATES y
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g NUCLEAR REGULATORY COMMISSION 3
W ASHING TON, D. C. 20655
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 121 AND 101 TO FACILITY OPERATING 4
LICENSE NOS. DPR-70 AND DPR-75 J
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET N05. 50-272 AND 50-311 l
1.0 INTRODUCTION
By letter dated September 4, 1990 and supplemented by letter dated January 29, 1991, the licensee requested an amendment to the Facility _
l Operating Licenses for the Salem Nuclear Generating Station, Units No. 1 and 2.
The January 29, 1991 supplemental letter provided a new marked up page for the Salem Unit 2 Technical Specifications that included all previous revisions. This supplement did not increase the scope of the original amendment request and did not affect the staff's original no significant hazards determination.
The requested amendment would revise l
the Reactor Protection System (RPS) setpoints for Steam Generator Level Low-Low and for Steam Line Pressure Low.
I To support these Technical Specification changes, the licensee submitted j
the following:
I 1.
Description and Justification of changes.
2.
Revised Technical Specification pages 3.
Justification for Salem Past and Continued Operation (Westinghouse Report S-C-RPC-CEE-0309-1) 2.0 DISCUSSION & EVALUATION In-November 1981, the Salem Technical Specification specified that the Steam Generator Level Low - Low Trip setpoint for the Reactor Protection System and Engineering Safety Features Actuation System was 18% of span, with an allowable value of_17% of span.
In May 1983, with the addition of reference leg insalation and transmitter changes, the Technical Specification was amended to change.the Steam Generator-Level Low - Low Trip. That amendment incorporated the setpoint value of 8.5% of span for-trip with an allowable value of 7.5% of span.
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. The recent development of setpoint methodology by Westinghouse has identified additional uncertainties in the instrument loop.
Replacement of components and changes to the setpoint methodology necessitated the increase from the previous trip setpoint to 14% span as calculated by Westinghouse.
The allowable value also changed to 12.8% span. The largest single contribution to the channel statistical accuracy (CSA) is due to environmental allowance. Without an adverse environment CSA is only 3.7% span. _The additional increase from 14% span to 16% span is-due to a reference leg heat up error of 2%.
1 The steam line pressure low trip is also changed due to the additinnal uncertainties in the instrument loop.
The proposed changes revise Technical Specification Section 2.2, Table 2.2-1 and Section 3/4.3.2, Table 3.3-4 The changes are as follows:
A. Steam Generator Level Low-Low setpoint Previous New Setpoint 8.5% span 16% span Allowable Value 7.5% span 14.8% span B.
Steam Generator pressure - low setpoint Previous New Setpoint 500 psig 600 psig Allowable Value 480 psig 579 psig The staff has evaluated and reviewed the licensee's request and found these changes are in a more conservative direction and more accurately 3
reflect instrument uncertainties.
Implementation of the proposed change does not involve modification of any existing equipment system or components.
Based on our review of the licensee's submittal, the staff concludes that this Technical Specification change more accurately includes uncertainties in the setpoints for steam generator low-low level and low pressure will have a favorable impact upon the safety of the plant, and is therefore acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
Th(
amendments involve a chango 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.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released l
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F offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Comission has previously issued a proposed finding that the amendments involve no such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to l
l 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in cunnection with the issuance of the amendmer.ts.
4.0 C0HCLUS10N The Comission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (55 TR 53075) on December 26, 1990 and consulted with the State of New 7ersey.
No public coments were received and the State of New Jersey did not have any coments.
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurarce that the health and safety of the p(2) such activities will be conducted in compliance with theublic will n and Comission's regulations and the issuance of the amendments will not he inimical to the common defense and security nor to the health and safety of the public.
Dated: March 11, 1991 Principal Contributor:
D. Nguyen I
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