ML20079P666
| ML20079P666 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/29/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P663 | List: |
| References | |
| NUDOCS 9111130134 | |
| Download: ML20079P666 (3) | |
Text
_ _ _ - _ _ _ _ _ _ _ _ - _ - _ _
/p mh UNITED STATES g
y
. <, q' i NUCLEAR REGULATORY COMMISSION jg WASHINGTON. D. C 20$55 QsAf SAFETY EVALUAT10fl CY THE OFFICE OF NUCLEAk REACTOR REGUL ATION PELATE0 TO AMEN 0 MENT NO. 126TO FACILITY OPERATING LICENSE HPF-9 Afl0 AMENOMENT NO.108 TO FACILITY OPERATING LICENSE NPF-17 OttKE p0WER COMPANY MCGUIRE NtlCLEAR STATION, llNITS 1 ANO 2 00CKET f05, 50-369 ANO 50-370 1.0 illTRODllCT10f; By letter dated August 8,1991, as supplemented October 2,1991, the Duke Power Company (licensee) submitted a request for changes to the McGuire Nuclear Station, Units 1 and 2. Technical Specifications (TS). The requested changes would revise the visual inspection requirements for snubbers in TS 4.7.8 in response to the guidance provided in the NRC's Generic letter 90-09, "Alterna-tive Requirements for Snubber Visual Inspection Intervals and Corrective Actions."
The October 2,1991 letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 EVAltlAT10f4 The present snubber visual examination schedule in the TSs is based on the number of inoperabit snubbers identified in the previous visual ex3mination. The schedule is determined only by the absolute number of the inoperable snubbers discovered during the previous visual examination and does not depend on the size of the snubber population.
Therefore, licensees with a brge snubber population find the schedule excessively restrictive.
Generic letter 90-09 provides an acceptable alternative visual examination schedule permitting licensees to perforn visual examinations and corrective actions during refueling outagts without disturbing the confidence level provided by the existing surveillance requirements. The basic examination interval is the normal fuel cycle up to 24 months. This interval may be extended to as long as twice the fuel cycle er reduced to as small as two-thirds of the fuel cycle depending on the number of unacceptable snubbers found during the risual examinttion. The examination interval may vary by 125 percent to co:ncide with the actual outage.
If one or more snubbers are found inoperable during a visual examination, the Limiting Conditions for Operation (LCO) in the present TSs require the licensee to restore or replace the inoperable snubber (s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or ci2clare the attached system inoperable and follow the appropriate action statement for that system.
This LCO will remain in the TSs. However, the permissible number of inoperable snubber (s) and the subsequent visual examination interval will now be determined in accordance with the new visual Q1130134931op9 ADOCK 05000369 p
PDR j
i
I i
4 2
examination schecule (proposed TS Table 4.7-2).
As noted in the guidance of Generic Letter 90-09 for this 11rit item TS improvement, certain cortective actions taay huve to be performed dependir.g on the number of inoperable snubbers found. All tequirenents for corrective actions and evaluations associated with the use of the visual exeminetton schedule, and those stated in Fcotnotes 1 through 7 (Table 1 of Generic Letter 90-09)-are proposed to be incluced in the TSs.
The licensee has proposed changes to TS 3/4.7.8 that are consistent with the guidance proviced in Generic Letter 90-09 for the re;1acenent of the snubber visu6l exorninetion schedule with Table 1 (incluoing rootrctes 1 through 7) of Generic Letter 90-09.
The NRC staf f h65 reviewed the propostd acendnents ano finds that the proposed char.ges to trie 155 f cr PcCuire 1 and 2 are acceptable.
3.0 $1ATL CONSULTATION In accordance with the Commissicr's rer11atict the North Carolir.t State
- 1 official was r.otified of the prcposed issuance.s,f the -anendnents.
o The State official had no comnents.
4.0 ENVIR0hP. ENTAL CONSJDERATION,,
lhe amendnents ch6t ge requirenents with respect to installation or use of a facility component located within the restricted nrea as defined in 10 CFR Part 20 and change surveilltr ce requirements.
The NRC staff h6s dttermined that the dmendnents involve no Significant increase in the amounts, anC r.o significant change in the types, of any ef fluents that ni6y be released off site, and that there is no significant increase in individual or cunul6tive occupatier.61 radiation exposure. The Conaissitn has.previously issued a proposed finding l
that the amendrents involve no significant hazards ccnsiderationAccordingly,ndthereha a
been nu public ccn.nent on such finding (56 FR 43807).
the anenduents i
tret the eligibility criteria-for c6tegorical exclusion set-forth in 10 CFk 51.??(c)(9).
Fursuent to 10 CTR 51.22(b) no environnet.tal impact statenent or environmental 6ssessnent neto be prepared in cor.riection with the issuance of the ouendments.
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 optratictcin the proposed manner, (2) such activities will be conducted in compliarct with the Conmission's regulations.
and (3) the issuance of the arrrdments will not be iniinical. to the common defense and sscut ity or to the health and sof ety of tht-public.
i l
Principal Contributor:
H. Shaw, ENEB-Date:
October 29. 1991 l
,..