ML20248F151
| ML20248F151 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/28/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248F150 | List: |
| References | |
| NUDOCS 9806040122 | |
| Download: ML20248F151 (3) | |
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UNITED STATES s
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.118 TO FACILITY OPERATING LICENSE NO. NPF-43 DETROIT EDISON COMPANY FERMI 2 DOCKET NO. 50-341
1.0 INTRODUCTION
By letter dated January 28,1998 (NRC-98-0006), as supplemented on March 10,1998 (NRC-98-0036), the Detroit Edison Company (DECO or the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. NPF-43 for Fermi 2. The proposed amendment would revise TS surveillance requirement 4.4.3.2.2.a for the leak rate test of the pressure isolation valves (PlVs), extending it from the current 18-month interval to a 24-month interval. This change is consistent with the requirements of the applicable version of the American Society of Mechanical Engineers (ASME) Code,Section XI.
The March 10,1998, supplement requested a change in the implementation period.. This information was within the scope of the original Federa/ Register notice and did not change the staff's initial proposed no significant hazards considerations determination.
Current TS Section 4.4.3.2.2 ctates "Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit: a. At least once per 18 months." This section would be revised by extending the surveillance frequency (shown underlined) from, "At least once per16 months" to "At least once per 24 months." As described above, this is a change only to the surveillance frequency. It does not cause a change to any surveillance requirement nor does it change the way in which the surveillance is performed. Furthermore, the proposed change does not involve any physical changes to plant systems or components.
PlVs perform an isolation function between the high pressure and low pressure portions of systems connected to the reactor coolant system (RCS). There are several safety systems connected to the reactor coolant pressure boundary that have design pressures below the rated reactor system pressure. The low pressure portions of these systems are protected from overpressurization by the PlVs placed in series to form the interface between the high pressure and low pressure portions of these systems. The low pressure portions of these systems are also equipped with relief valves and alarms in the control room that alert the operator of PlV leakage. Leak tight integrity of the PlVs should be maintained at acceptable values to prevent overpressurization of the low pressure portions of systems connected to the RCS.
9806040122 980528 PDR ADOCK 05000341 P
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2.0 EVALUATION Fermi 2 TS Section 4.0.5 specifies that inservice testing (IST) of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with ASME Code Section XI as required by 10 CFR 50.55a. The current IST program for Fermi 2 nuclear plant was developed to the requirements of the 1980 Edition of the ASME Code,Section XI, up to and including the Winter 1980 Addenda. Paragraph IWV-3422 of this ASME Code Section XI requires that a seat leakage test be conducted at least once every 2 years. However, an earlier version of -
Section XI required these tests to be conducted at the same frequency as scheduled refueling outages, but not less than once every 2 years. The PlV leak tests are normally performed during extended plant shutdown conditions, and the 18-month refueling outage interval for Fermi 2 plant was therefore specified in TS Section 4.4.3.2.2.a. Due to unexpected shutdowns and extended outages, certain refueling intervals might extend beyond 18 months. In such cases, performance of the 18-month PlV leak tests would require a plant shutdown. If the leak i
tight integrity of the PlVs has been maintained at an acceptable level and has not exhibited increasing seat leakage from previous tests, shutting down the plant to perform valve leak tests would be a hardship to the licensee without compensating increase in the level of quality and safety.
Extending the test frequency from every 18 months to every 24 months would still meet the ASME Code Section XI requirements, and thus, would provide an adequate level of verification of the leak tight integrity for the affected PlVs. Furthermore, the 24-month testing frequency is consistent with the guidance provided in Table 3.2 of NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants," which recommends that leak tests for PlVs (Category "A" and "A/C" valves) be performed at a frequency of once every 2 years. Accordingly, the staff finds the proposed TS changes to be acceptable.
Based on the above evaluation, the staff concludes that the proposed TS change meets the requirements of ASME Code,Section XI, and is consistent with the guidance delineated in Table 3.2 of NUREG-1482. Performing leak tests in accordance with the requirements of ASME Code,Section XI, provides assurance of operational readiness for the PlVs and is, therefore, acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Michigan State official was notiGed of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a surveillance requirement. The 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 (63 FR 9598). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR
s 3-51.22(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: John Huang Date:
May 28, 1998
x,-
s DATED:
May 28, 1998 AMENDMENT NO.118 TO FACILITY OPERATING LICENSE NO. NPF FERMI 2 Docket File (50-341).
PUBLIC E. Adensam (EGA1)
C. Jamerson A. Kugler OGC G. Hill, IRM (2)
W. Beckner J. Huang, EMEB ACRS-B. Burgess, Rill SEDB (TLH3) 1