ML20212A738
| ML20212A738 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/10/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212A726 | List: |
| References | |
| NUDOCS 9909170121 | |
| Download: ML20212A738 (2) | |
Text
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t UNITED STATE 3 j
j NUCLEAR REGULATORY COMMISSION C
WASHINGTON. D.C. 20555-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION J
RELATED TO AMENDMENT NO. 174 TO FACILITY OPERATING LICENSF NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By letter dated May 17,1999, Northeast Nuclear Energy Company proposed a license amendment to change the technical specifications (TS) for Millstone Nuclear Power Station, Unit No. 3 (MP3). The proposed change revises TS 4.4.6.2.2, regarding leak testing of reactor coolant system pressure isolation valves (PlVs). This revision replaces the surveillance interva!
and frequency of leakage rate testing as outlined in the American Society of Mechanical Engineers (ASME) Code,Section XI, Paragraph IWV-3427(b), with the requirements specified in TS 4.0.5, " Operations and Surveillance Requirements."
2.0 EVALUATION The existing TS 4.4.6.2.2 states:
"Each Reactor Coolant System. Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limits:"
The existing TS 4.4.6.2.2.e. states:
"As outlined in the ASME Code,Section XI, Paragraph IWV-3427(b)."
The existing TS 4.0.5.a states:
" Inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a."
The proposed TS change would replace TS 4.4.6.2.2.e. with the following:
'J "When tested pursuant to Specification 4.0.5."
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Pursuant to 10 CFR 50.55a(f)(4)(ii), inservice Test (IST) programs are required to be updated every 10 years to the edition of ASME Code incorporated by reference in 10 CFR 50.55a(b),12 months prior to the start of the next 120-month interval. The MP3 IST program second 10-year interval began in February 1998, and the applicable IST requirements are contained in the 1989 Edition of the ASME Code,Section XI. The existing TS 4.4.6.2.2.e. regarding the leak testing provisions for PlVs was prepared to reflect the requirements of the 1983 Edition of ASME Code for the first 10-year IST interval. The provisions require trending for 6-inch and larger valves, and increased testing frequency based upon increasing leakage trends. However, this leak testing requirement was elirninated from the 1989 Edition of the ASME Code. The 1989 Edition j
of ASME Code,Section XI, requires leak testing of PlVs be performed in accordance with i
Section 4.2.2.3 of Part 10 of the ANSI /ASME Operation and Maintenance Standards (OM-10).
Furthermore, the existing TS 4.0.5 and TS 4.4.6.2.2.e are inconsistent, because TS 4.0.5 requires the current effective IST requirements be implemented, while TS 4.4.6.2.2.e., if not revised, carries over the obsolete requirements of an older edition of the ASME Code. As such, a change to the TS is necessary and appropriate to resolve these conflicting requirements. The proposed TS change reflects the current test requirements and also resolves the inconsistency between TS 4.0.5 and TS 4.4.6.2.2.e. Therefore, the staff finds the proposed TS change to be acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Connecticut 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 (64 FR 38033). Accordingly, the amendment meets the l
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 l
connection with the issuance of the amendment.
5.0 CONCLUSION
Based on the above discussion, the staff finds that the proposed TS change is acceptable because the change complies with the current IST test requirements and resolves the inconsistency between existing TS 4.0.5 and TS 4.4.6.2.2.e. requirements.
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: Y. S. Huang Date: September 10, 1999