ML20056D451
| ML20056D451 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/23/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D449 | List: |
| References | |
| NUDOCS 9308160231 | |
| Download: ML20056D451 (3) | |
Text
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a SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 193 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT d
t DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated December 18, 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 (TS). The requested 1
changes would revise TS 4.3.B.1 and as'sociated Bases to require verification.
of control rod coupling integrity each time a control rod is withdrawn to the j
z
" full out" position ar.d' prior to declaring a control rod operable after work-on a control rod or the control rod drive system that could affect coupling.
The proposed changes would make the James A. FitzPartrick TS consistent with 4
the guidance provided by the NRC's revised Standard Technical Specifications for General Electric plants (NUREG-1433).
1 2.0 EVALUATION TS 4.3.B.1 currently requires confirmation of control rod coupling integrity during the initial withdrawal following ~a refueling outage or after control-rod or control rod drive (CRD) maintenance. This confirmation is accomplished-by verifying that the CRD does.not go to the' overtravel position when the control rod is fully withdrawn.
TS 4.3.B.1 also currently requires verification of discernible response on the nuclear instrumentation during initial control rod withdrawal after each refueling outage or_ after maintenance on the control rods or CRDs.
The proposed change to TS 4.3.B.1 would require confirmation of control rod coupling integrity each time a control rod is withdrawn to the " full out" position and prior to declaring a control rod operable after work on a control-rod or the CRD system that could affect coupling; Confirmation of coupling is to be accomplished by demonstrating that each control rod drive does not go to-y the overtravel position when a control rod'is fully withdrawn. The proposed change provides additional assurance of control rod to CRD coupling through-the additional surveillance testing each time a control rod is fully withdrawn. This additional surveillance is consistent with the guidance provided in the NRC's revised Standard Technical Specifications for General-Electric plants (NUREG-1433) and is t!erefore acceptable.
9308160231 930723 E PDR ADDCK 05000333
'P PDR
. The requirement to verify discernible response on the nuclear instrumentation during control rod withdrawal does not demonstrate control rod coupling integrity but does demonstrate control rod movement and that the control rods are not stuck. However, TS 4.3.A.2.a. provides adequate demonstration of control rod movement and that the control rods are not stuck on a weekly basis and therefore, deletion of the requirement for discernible response on the nuclear instrumentation from TS 4.3.B.1 is also acceptable.
Therefore, we find the proposed technical specification changes acceptable.
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 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 (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:
Donald S. Brinkman Date: Mv n,1043
4 July 23, 1993 Docket No. 50-333 Mr. Ralph E. Beedle Executive Vice President - Nuclear Generation 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 NUCLU R POWER PLANT (TAC NO. M85832)
The Commission has issued,the enclosed Amendment No.193 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TS) in response to your application transmitted by letter dated December 18, 1992.
The amendment revises TS 4.3.B.1 and associated Bases to require verification of control rod coupling integrity each time a control rod is withdrawn to the
" full out" position and prior to declaring a control rod operable after work on a control rod or the control rod drive system that could affect coupling.
These changes make the James A. FitzPartrick TS consistent with the guidance provided by the NRC's revised Standard Technical Specifications for General Electric plants (NUREG-1433).
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 I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.143 to DPR-59 2.
Safety Evaluation cc w/ enclosures:
See next page
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