ML20058L940
| ML20058L940 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/09/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L932 | List: |
| References | |
| NUDOCS 9312200076 | |
| Download: ML20058L940 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055& 0001 6
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 200 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YOFX JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333
1.0 INTRODUCTION
By letter dated September 25, 1992, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A.
FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would delete the surveillance requirements for the iodine analyzer portion of the drywell Continuous Atmosphere Monitoring (CAM) system from TS Table 4.6-2, " Minimum Test and Calibration Frequency for Drywell Continuous Atmosphere Radioactivity Monitoring System," and make accompanying changes to TS Bases Section 3.6/4.6.0.
The drywell CAM system is part of the reactor coolant system leakage detection system and incorporates a three-channel combination monitor for counting gross particulate, iodine, and noble gas activities in the drywell atmosphere. The CAM system takes a continuous flow sample and passes it through a shielded assembly containing the detector unit before discharging back into the drywell. Measurements are taken and analyzed to determine if there is abnormal reactor coolant leakage into the drywell.
2.0 EVALUATION Regulatory Guide 1.45 (RG 1.45), " Reactor Coolant Boundary Leakage Detection Systems," recommends that at least three separate reactor coolant pressure boundary leakage detection methods be employed. Two of these methods should be (1) sump level and flow monitoring and (2) airborne radioactivity monitoring The third method may be either the monitoring of condensate flow rate from air coolers, or the monitoring of airborne gaseous radioactivity.
Technical Specification 3/4.6.D, " Coolant Leakage," identifies the plant-specific methods required for detection of reactor coolant leakage. Technical Specification 3/4.6.D requires that the primary containment sump monitoring system and the gaseous and particulate portions of the drywell CAM system be operable during reactor power operation, consistent with RG 1.45.
Technical Specification Table 4.6-2, " Minimum Test and Calibration Frequency for Drywell Continuous Atmosphere Radioactivity Monitoring System," currently specifies calibration and sensor check requirements for the air particulate, gaseous activity, and iodine analyzer portions of the drywell CAM system.
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However, as previously discussed, the TSs do not require the iodine portion of the CAM to be operable, consistent with RG 1.45.
The licensee has, therefore, l
proposed to delete the iodine analyzer surveillance requirements from TS Table 4.6-2, and to make accompanying changes to the TS Bases. The requested changes to the TSs would simplify equipment maintenance by not requiring testing, calibration, and repairing of the iodine portion of the CAM system.
In addition, future replacement or upgrading of the CAM system would not require the inclusion of an iodine data channel.
The NRC staff has determined that the proposed changes to TS Table 4.6-2 and i
Bases Section 3.6/4.6.D are consistent with the guidance provided in RG 1.45 and the requirements of TS 3/4.6.D for reactor coolant system leakage detection systems. The staff has, therefore, concluded that the proposed TS changes are acceptable, in addition, the staff has no objections to the proposed Bases changes.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATigi 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 p oposed finding that the amendment involves no significant hazards l
consideration, and there has been no public comment on such finding (58 FR 16229). 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:
M. Griggs Date:
December 9, 1993 P
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l December 9, 1993 Docket No.60-333 Mr. Ralph E. Beedle Executive Vice President - Nuclear Generation I
Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT-i (TAC NO. M84622)
The Commission has issued the enclosed Amendment No. 200 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 25, 1992.
The amendment revises TS Table 4.6-2 to delete the surveillance requirements for the iodine analyzer portion of the drywell Continuous Atmosphere Monitoring system.
The amendment also makes accompanying changes to TS Bases Section 3.6/4.6.D.
These changes are consistent with the guidance in Regulatory Guide 1.45, " Reactor Coolant Boundary Leakage Detection Systems."
A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, Original signed by:
John E. Menning, Project Manager Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 20010 DPR-59 2.
Safety Evaluation cc w/ enclosures:
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