ML20081L888
| ML20081L888 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/01/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081L883 | List: |
| References | |
| NUDOCS 9107080181 | |
| Download: ML20081L888 (3) | |
Text
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UNITED STATES N
1-i NUCLEAR REGULATORY COMMISSION
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WASHINoTON, D.C: 20066 o
%'f.....p SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
'RELATED TO AMENDMENT N0.170 T0 FACILITY OPERATING LICENSE He sPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR PO) Q PLANT 00CKET !!0. 50-333 1.0 It(TRODUCTION
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By letter dated April 15, 1991, the Power _ Authority of the State of New York (PASHY, the licent.ee)-submitted a request for chan Nuclear Power Plant,: Technical Specifications (TS)ges to the James A. FitzPatrick
.l The requested change (ISI)porates a reference to the NRC-approved FitzPatrick Inservice Inspection incor program into the Technical Specifications.
The change adds the following' statement to Section 4.6.F.3: - "An Inservice Inspection Program for-piping _ identified in the NRC Generic Letter 88-01 shall be implemented in accordance with NRC staff l positions on schedules, methods, personnel,-and sample expansion _ included in this Generic Letter, or in j
-accordance with alternate measures approved by the NRC staff."
2.0 DISCUSSION I
-NRC-Generic Letter (GL) 88-0), issued January 25, 1088,-provided guidance-in j
the; form of NRC positions regarding -Intergranular Stress Corrosion Cracking (IGSCC) problems in Boiling' Water Reactor (BWR)-piping made of austenitic.
stainless steel that is 4 inches or_ larger in nominal diameter and contains reactor coolant-at a temperature above 200 degrees Fahrenheit during. reactor:
power operation regardless of ASME code t.lassification. NRC GL 88-01 reouested licensees of operating BWRs and holders of construction permits for BWRs to provide information regarding conformance with the NRC positions. One of the-
. items which the GL requested licensees to address was a TS change to include a statement in the TS section_on Inservice Inspection that the 151 program for
- piping covered by the scope of NRC GL 88-01 will be in conformance with the NRC fpositions on schedule, methods, personnel, and sample expansion included in the GL.
3.0 E_ VALUATION The NRC. staff _previously completed _an evaluation of the licensee's ISI programs outlined in response to_GL 88-01. Ey letters dated May 4,1990 and December 6, 1990, we informed PASNY that their programs were fully acceptable and satisfied ell _of the requirenents in GL 88-01 except for the TS on ISI.
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- i. The licensee has proposed the following change to the.TSs in conformance with the guidance in GL 88-01:
Add new Surveillance Requirement 4.6.F.3 to read:
"The inservice Inspection Program ~for piping identified in the NRC Generic Letter 88-01 shall be implemented in accordance with NPC staff positions on schedules, methods, personnel, and sample expansion included in this Generic Letter, or in accordance with alternate measures approved by the NRC staff."
The above change is generally in accordance with the model TS and wording in
.GL 88-01. This change is administrative in nature because it amends the Technical Specifications by adding a statement which incorporates a reference to the existing NRC-approved FitzPatrick 151 program. The existing FitzPatrick ISI program ensures that surveillance is performed on piping susceptible to IGSCC in a manner that increases the probability of detecting any defects or flaws.
The conclusions of the FitzPatrick plant's accident analyses as documented in the FSAR or the NRC staff's SER are not altered by this change to the Technical Specifications.
Therefore, the staff has concluded that the TS change satisfies the intent and objective of GL-88-01 and is acceptable.
4.0 STATE CONSULTATION
in accordance with the Commission's regulations, the New York Stct: official was notified of the prorosed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTA,L, CONSIDER,AT1,0N S
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 radittion 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 (56FR24215). Accordingly, the amendment meets the eli forth in 10 CFR 51.22(c)(9)gibility criteria for categorical exclusion set 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.
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6.0 CONCLUSION
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 er. dangered by operati.on in the proposed manner, (P) such activities will be conducted in cornpliance with the Comission's regulations, and (3) the issuance of the amendirent will not be inimical to the comon defense end security or to the health and safety of the public.
- Principal Contributor:
B. VcCabe Date: July 1,1991 l
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