ML20080T727
| ML20080T727 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/08/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080T720 | List: |
| References | |
| NUDOCS 9503140086 | |
| Download: ML20080T727 (2) | |
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- i UNITED STATES
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NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 20555 4091 4,..... p
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. DPR-35 BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated November 22, 1994, the Boston Edison Company (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station Technical Specifications (TSs). This amendment would revise the mode conditions under which the Scram Discharge Instrument Volume (SDIV) - Scram Trip Bypass in Table 3.2.C.1 is required to be operable and changes the associated functional test frequency from quarterly to once per operating cycle in Table 4.2.C.
2.0 EVALUATION The SDIV-Scram Trip Bypass Switch is a manual keylock switch located in the control room which permits the operator to oypass the scram discharge volume high level scram trip if the mode switch is in SHUTDOWN or REFUEL. This bypass allows the operator to reset the reactor protection system so that the system is restored to operation while the operator drains the scram discharge volume.
In addition to allowing the scram relays to reset, actuating the bypass initiates a control rod withdrawal block.
Resetting the trip actuators opens the scram discharge volume vent and drain valves. An annunciator in the control room indicates the bypass condition.
The proposed change removes the requirement of Table 3.2.C.1 " Instrumentation that Initiates Control Rod Blocks" to have the " Scram Discharge Instrument Volume - Scram Trip Bypassed" operable in the Run and Startup modes.
Operability for this instrumentation is applicable only in the Shutdown and Refuel modes. Also, the quarterly functional surveillances of Table 4.2.C are being revised to once/ cycle to coincide with the period of time the instrumentation is required to be operable.
i The proposed change to Table, 2 S.c.1, and the associated change to Table 4.2.C, removes incorrect rea, Rr m,les listed for the SDIV - Scram Trip Bypass l
function. The Pilgrim control rod bhk logic for the SDIV Bypass is not
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operable nor is it required by design when in the Run and Startup modes. The control logic and the final safety analysis report (FSAR) (section 7.2.3.10) specifies SDIV - Scram Trip Bypass operability only in the Refuel and Shutdown modes.
9503140086 950300 PDR ADOCK 05000293 P
l This change will not result in any physical modification or operation of the control rod block system.
The change conforms the TSs to the actual design of the SDIV Scram Trip Bypass as described.in the FSAR. Changing the functional j
-surveillance frequency from quarterly to once per operating cycle also--
conforms the TSs to the applicable mode for the function.
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The change'is classified as an administrative change because it corrects an i
administrative requirement that does not reflect-the logic design.
It improves safety by removing the need to. install jumpers during reactor operations to perform unnecessary and potentially. risky functional-surveillances.-
i The NRC staff finds'the amendment acceptable. This. change is administrative j
in nature. The change wil1~ not result in the physical modification or j
operation of the control rod block system. The change conforms the TSs to the actual design of the SDIV Scram Trip Bypass as described in the FSAR.
3.0 STATE CONSULTATION
In accordance with ~ the' Commission's regulations, the Massachusetts State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any 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 (60 FR 3671). 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 public.
Principal Contributor:
K. R. Cotton Date: March 8, 1995