ML20206L754
| ML20206L754 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/06/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206L752 | List: |
| References | |
| NUDOCS 8608200261 | |
| Download: ML20206L754 (2) | |
Text
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'o UNITED STATES g
g NUCLEAR REGULATORY COMMISSION 3
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WASMNGTON, D. C. 20555
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SAFETY EVALUATION PY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. DPR-35 BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
Ry letter dated April 12, 1985, the Boston Edison Company (the licenseel requested a revision of Table 4.2.F of the Pilgrim Station Technical Specifications. The revision would change the calibration frequency for the reactor water level, reactor pressure, and drywell pressure surveillance instrument channels from once every 6 months to once each refueling outaoe.
The change in calibration frequency was proposed to reduce the number of calibrations performed and to eliminate the on-line valving of these instruments that is often required for 6-month calibrations. Thus, the risk of inadvertent actuation of safety systems would also be reduced.
2.0 EVALUATION The licensee considers the proposed decrease in calibration frequency to be warranted because of the improved accuracy and stability provided by Rosemount analog transmitters which were installed for these instrument channels during the last refueling outage. The new transmitters replaced mechanically-operated transmitters which had become obsolete. Mechanical force transfer and problems associated with shock and vibration are eliminated in the Rosemount transmitters by direct electronic sensing with a sealed capacitance sensing element.
Similar analog transmitters were included in the Analog Transmitter / Trip Unit System (ATTUS) which was presented by the General Electric Company to the NRC staff for licensing review in topical report NEDO-21617-A.
ATTUS provides the input for plant process parameters to the system logics for the reactor protection system, the primary containment isolation system, and the core standby cooling system. The staff reviewed the ATTUS and found it acceptable, as stated in its letter to General Electric dated June 27, 1978. That finding included Technical Specification changes proposed in NEDO-21617-A which would revise the test and calibration frequencies by requiring analog transmitter calibrations to be performed once per cycle during refueling outages.
Together with such a change, a daily instrument check is required to provide assurance that the instrumentation is operable.
8608200261 860906 PDR ADOCK 05000293 P
. The proposed amendment would apply the ATTUS calibration frequency (i.e.,
each refueling outage) to the reactor water level, reactor pressure, and drywell pressure surveillance instrumentation. An instrument check during each shift is already required for these channels. Thus, we find that the proposed Technical Specification changes, in con.iunction with the recent installation of analog transmitters for these channels, are consistent with our requirements for ATTUS. The Technical Specification changes are, therefore, acceptable.
3.0 ENVIRONMFNTAL CONSIDERATION This amendnent involves only a change in a surveillance requirement. The 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 Commis-sion has previously issued a proposed finding that this amendnent involves no sionificant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibil.ity criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.?2(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:
(1) there is reasonable assurance that the health and safety of the public will not be endancered by operation in the proposed manner, and (P) 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: Paul H. Leech Dated:
August 6,1986 O
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