ML20212M543
| ML20212M543 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/03/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212M530 | List: |
| References | |
| NUDOCS 8703120065 | |
| Download: ML20212M543 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. gg TO FACILITY OPEP.ATING LICENSE NO. DPR-35 BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated February 77, 1986Property "Letter" (as page type) with input value "05000000/LER-1975-004, :on 750112 & 13,analysis of Reactor Bldg Vent Process Radiation Monitoring Sys Revealed Release of Radioactive Effluents Exceeding Tech Spec Limit by 55%. Caused by High Iodine Activity in Reactor Coolant"February 77, 1986" contains a sequence that could not be interpreted against an available match matrix for date components." contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., as corrected October 20, 1986, the Boston Edison Company (licensee) requested a revision to the Pilgrim Technical Specification Tables 4.1.1, 4.1.2, 4.2.A and 4.2.B associated with s
the addition of an analog trip system. This charge incorporates new 3
minimum calibration and test frequencies for instrument channels. The l
analog trip system was presented earlier to the NRC staff for review in General Electric topical reports NE00-21617 and NEDO-21617-A. The staff l
reviewed and found the analog transmitter / trip unit system (NEDO-21617-A) acceptable in its letter to General Electric dated June 27, 1978. The topical report provides a description of General Electric's proposed equipment to be utilized for certain engineering safeguard sensor trip inputs including inputs for the reactor protection system, emergency core cooling system and nuclear steam supply shut off systems. The proposed equipment replaces pressure, level or temperature switches with analog transmitter / trip unit combinations. This equipment then provides the equipment logic trip inputs of the switches.
2.0- EVALUATION i
The Analog Transmitter / Trip Unit System (ATTUS), as stated above, is a replacement for the mechanical tyoe sensor switches at the sensor level only. The ATTUS provides the input for the plant process parameters to the system logics for the reactor protection system, the primary containment isolation system and the core standby cooling system. Since the dual channel design (with two trip systems) of the reactor trip system is not being altered, the safe and reliable operation of the trip system is not compromised. The proposed technical specification changes would relax surveillance requirements for the analog transmitter without reducing system availability, accuracy and reliability below levels which existed before the analog trip system modification. The changes proposed would revise _ test and calibration frequencies by requiring analog transmitter l
calibration once per cycle during refueling outages. Calibration of analog trip units would be performed concurrent with functional testing. With this change, a daily instrument check would also be required which will provide a degree of confidence of system operability that was not feasible with the mechanical switches and sensors.
In addition, the licensee would provide a gross failure alam with the analog trip system which annunciates sensor failure.
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, We have reviewed the proposed Technical Specification changes which reflect the addition of an analog transmitter / trip unit system, and find that they would permit operation of the Pilgrim station in a manner that is consistent with our requirements on previous applications. These changes are, therefore, acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
-This amendment involves a change 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 amend-ment 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this 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 nor environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner, and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor:
N. Trehan Dated:
March 3, 1987 I