ML20091F357
| ML20091F357 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/13/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091F355 | List: |
| References | |
| NUDOCS 9204210348 | |
| Download: ML20091F357 (3) | |
Text
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UNITED STATES
'Q/i NUCLEAR REGULATORY COMMISSION h
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SAFETY EyfEIATION BY THE Off!CE Of NUCLEARRK10R RLW1AllQ!f RELATED TO AMEtiDMENT NO.I m TO FAClllTY OPERAllNG LICMSL!(0. DDR-59 POWER AUTHOR 11Y Of THE_ STATE Of NEW Y0E JAMES A. Fil2 PATRICK N E LEAR POWER PLANT D_Q Z L L E. 1 0-1 31 1.0 INTRODUCllDlf By letter dated November 15, 1991, as supplemented March 11, 1992, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. FitzPatri:k Nuclear Power Plant, Technical Specifications (TS).
The requested changes would reviso the schedule for visual inspection of snubbers in T.S. 4.6.1 in response to the guidance provided in the NRC's Generic letter (GL) 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Action."
The March 11, 1992, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 [yAlpM10N Technical Specifications (TS) impose surveillance requirements for visual inspection and functional testing of all safety-related snubbers. A visual inspectiun is the observation of the condition of installed snubbers to identify those that are damaged, degraded, or inoperable as caused by physical means, leakage, corrosion, or environmental exposure.
To verify that a snubber can operate within specific performance limits, the licensee performs functional testing that typically involves removing the snubber and testing it on a specially-designed test stand.
Functional testing provides a 95 percent confidence level that 90 percent to 100 percent of the snubbers operate within the specified acceptance limits.
The performance of visual examinations is a separate process that complements the functional testing program and provides additional confidence in snubber operability.
The TS specifies a schedule for snubber visual inspections that is based on the number of inoperable snubbers found during the previous visual inspection.
The schedules for visual inspections and for the functional testing assume that refueling intervals will not exceed 18 months.
Because the current schedule for snubber visual inspections is based only on the number of inoperable snubbers found during the previous visual inspection, irrespective of the size of the snubber population, licensees having a large number of snubbers find that the visual inspection schedule is excessively restrictive.
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~2-Some licensees have spent a significant amount of resources and have subjected plant personnel to unnecessary radiological exposure to comply with the visual examination requirements.
To alleviate this situation, in Generic letter (GL) 90-09 the staff developed an alternate schedule for visual inspections that maintains the same confidence level as the existing schedule and generally will allow the licensee to perform visual inspections and corrective actions during plant outages.
Because this line-item TS improvement will reduce future occupational radiation exposure and is highly cost effective, the alternative inspection schedule is consistent with the Comission's Policy Statement on TS improvements.
The alternative inspection schedule is based on the number of unacceptable snubbers found during the previous inspection in proportion to the sizes of the snubber populations or categories.
A snubber is considered unacceptable if it fails the acceptance criteria of the visual inspection.
The alternative inspection interval is based on a fuel cycle of up to 24 months and may be as long as 2 fuel cycles, or 48 months for plants with other fuel cycles, depending on the number of unacceptabic snubbers found during the previous visual inspection.
The inspection interval may vary by 125 percent to coincide with the actual outage.
In its letter dated November 15, 1991, as supplemented March 11, 1992, the licensee proposed changes to TS 4.6.1 for the snubber visual examination schedule.
Since the alternative inspection schedule proposed by the licensee is consistent with the guidance provided in GL 90-09, the staff finds the proposed changes acceptable.
3O SJATLMSULTAT10N 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 DiMQMMIALCONSIDERATION 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.
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 anandment involves no significant hazards consideration, and there has been no public ccmment on such finding (56 FR 66928).
Accordingly, the amendment
meets the eligibility criteria for categorical exclusion set forth in 10 CfR51.22(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
.QNCLUSION The Comission 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 Comission'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:
J. Rajan Date: April 13,1992
April 13, 1992 Docket No. 50-333 DISTRIBVT104:
See attached theet Mr. Ralph E. Beedle_
Executive Vice President - Nuclear Generation Power Authority of the Statn of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
ISSUANCE OF AMENDMENT f0R JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M82183)
The Commission has issued the enclosed Amendment No.180 to facility Operating License No. OPR-59 for the James A. FitzPatrick Nuclear Power Plant.
The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated November 15, 1991 as supplemented by letter dated March 11, 1992.
The amendment revises the Technical Specification (TS) surveillance requirements regarding visual inspection of snubbers.
These revisions are consistent with the guidance provided in Generic Letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions."
A copy of the related Safety Evaluation is enclosed. A Notice of issuance will be included in the Commission's next regular biweekly Federal B E!J1Er notice.
Sincerely, Original Signed Ily Brian C. McCabe, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.180 to OPR-59 2.
Safety Evaluation cc w/ enclosures:
See next page l
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