ML20082L860
| ML20082L860 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/17/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082L858 | List: |
| References | |
| NUDOCS 9504210337 | |
| Download: ML20082L860 (3) | |
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- * *8%g stA It UNITED STATES y-NUCLEAR REGULATORY COMMISSION
\\.....lf WASHINGTON, D.C. 20066-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 165 AND 146 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
i By letter dated September 20, 1994, Public Service Electric & Gas Company (PSE&G or the licensee) requested changes to the auxiliary feedwater (AFW) system technical specification (TS) for Salem, Units 1 and 2.
Specifically, the proposed changes would revise TS surveillance requirement 4.7.1.2.b.2 to '
reduce the secondary side steam pressure required for testing the steam turbine-driven AFW pump and to clarify the time required to perform the turbine-driven AFW pump surveillance test when entering Mode 3.
i The proposed reduction in required steam test pressure is necessary to coincide with the licensee's fuel upgrade and margin recovery project which includes analyses for reduced Tavg (average reactor coolant system temperature) and increased steam generator tube plugging. The new operating 1
parameters reduce the normal operating secondary side steam pressure.
However, the zero load secondary side steam pressure is not affected by the new operating parameters. The proposed change to clarify the time for performing the surveillance test after entry into Mode 3 is necessary to assure that the test is performed in a timely manner upon entering Mode 3.
Prior to entry into Mode 3, sufficient steam pressure does not exist to perform the required test and, therefore, the current TS includes an exemption to allow entry into Mode 3 without having performed the required turbine-driven pump test.
2.0 EVALUATION The 92-day surveillance requirement for the turbine-driven AFW pump in the current AFW system TS specifies that the steam supply pressure during testing should be greater than 750 psig (pounds per square inch gauge). The proposed change would reduce this minimum test pressure to 680 psig and clarify that 9504210337 950417 DR ADOCK 05000272 PDR
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the steam " supply" pressure is steam " generator" pressure.
The minimum
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required discharge pressure developed during the test as specified in the existing surveillance requirement is 1500 psig and will remain unaffected by i
the proposed change.
Because the minimum required steam generator test I
pressure has.been reduced by the proposed change while the minimum developed i
discharge pressure remains the same, the staff concludes that the proposed change is conservative in nature and, therefore, acceptable.
The staff also notes that under zero steam load conditions (conditions under which the AFW system will normally operate in an emergency) the minimum steam generator pressure available would still be greater than 750 psig.
The current 92-day surveillance requirement.also contains a statement (exception) that the provisions of SpecUication 4.0.4 (mode change restriction) are not applicable.
This exception is required to allow entry into Mode 3 prior to testing the turbine-driven AFW pump because there is i
insufficient steam generator pressure to perform the test prior to entering Mode 3.
However, the plant may be in Mode 3 and still not meet the necessary plant conditions for the test to be performed. The current specification is not clear in this regard and could be interpreted to require the turbine-driven AFW pump to be declared inoperable immediately after entry into Mode 3.
The proposed change would specify that the surveillance must be performed J
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after secondary side steam generator pressure is greater than 680 psig. The proposed clarification is acceptable because it retains the j
necessary operating flexibility by not requiring an unnecessary entry into an action statement (in Mode 3 with the test not yet performed) and at the same time ensures that the test will be performed in a timely manner (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) after the plant conditions. required for the test are satisfied. The proposed
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24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is also consistent with the time allowed in NUREG-1431,
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" Standard Technical Specifications - Westinghouse Plants".
Based on its evaluation, the staff concludes that the proposed change to i
reduce the minimum required steam generator pressure during performance of the 92-day surveillance test of the turbine-driven AFW pump is necessary to be consistent with the licensee's fuel upgrade and. margin recovery program and is acceptable because it is conservative in nature (retains the same minimum discharge pressure requirement) and still demonstrates the pump's capability to perfone its design safety function. The staff further concludes that the proposed change to allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the test after entry into Mode 3 is acceptable because it clarifies the surveillance requirement and ensures that the test will be performed in a timely fashion after suitable plant conditions are reached.
The staff, therefore, concludes that the proposed j
changes to TS surveillance requirement 4.7.1.2.b.2 are acceptable and should r
be approved.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendments. The State official had no comments.
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I 4 4.0 ENVIR0fBtENTAL CONSIDERATION The amendments change surveillance requirements. The NRC staff has determined j
that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released i
offsite, and that there is no significant increase in individual or cumulative occupational radfation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards j
consideration, and there has been no public comment on such finding (59 FR 55889). Accordingly, the amendments meet 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 amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, j
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 amendments will not be inimical to the comunon 3
defense and security or to the health and safety of the public.
I Principal Contributor:
W. LeFave Date: April 17, 1995
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