ML20097G733
| ML20097G733 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/16/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20097G728 | List: |
| References | |
| NUDOCS 9206170262 | |
| Download: ML20097G733 (3) | |
Text
. _ _ _. _ _. _ _ _. _..
._.__.___m
/gwa s%
1 n
UNITED STATES
{
.,i NUCLEAR REGULATORY COMMISSION o
.t WASHINoToN. D.c. 20M4 4....*f
'4 i
SAFETY EVALUATION BY,_THE OFFICE OF NUCLEAR REACTOR REGULATIQB RELATED TO AMENDMENT NO.160 TO FACillTY OPERATING LICENSE-NO. DPR-65
[031HEAST NUCLEAR ENERGY COMPANY. ET AL.
)
2! R IONE NUCLEAR POWER STATION. UNIT NO. 2 QQCKET NO. 50-336
1.0 INTRODUCTION
By letter dated february 3, 1992, as supplemented by letter dated April 1, 1992, the Northeast Nuclear Energy Company (the license,e). submitted a request for an amendment to the Millstone Nuclear Power Station, Unit No. 2 Ti hnical Specifications (TS).
The requested amendment would remove the snubber visual examination schedule in the existirq Technical Specifications and replace it with a refueling outage based
.sual examination schedule, Table 4.7-2 of the Generic letter 90-09 dated December 11, 1990, to all holders of operating licenses or construction permits for nuclear power reactors.
2.0 EVALUATION The snubber visual examination schedule in the existing Technica'. Specifi-cation, is based on the permissible number of ino)erable snub'aers found during the visual examination.
Because the existing snu)ber visual examination schedule is based only on the absolute number of inoperable snubbers found.
during the visual examination irrespective of.the total population of snubbers, licensees with a.large snubber population find the visual examination schedule excessively restrictive.
The purpose of the alternative vis. examination schedule is to allow the licensee to perform visual examinatLs and corrective actions during plant outages without reduction ut the confidence level provided by the existing visual examination schedule.
The new vis'lal examination schedulo specifies the permissible number of. inoperable snubbers for various snubber populations. 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 or -
reduced to as small as two' thirds of the fuel cycle depending on the number of unacceptable snubbers found during the visua1' examination.
The examination interval may vary by 125 percent:to coincide with the actual outage..
In the event'one or more snubbers are found inoperable'during a visual examination, the Limiting Conditions for Operation (LCO) in the present TS 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 declare' the attached system inoperable and 9206170262-920616 PDR ADOCK 03000336 i
P-PDR
. _.. ~. _, _ - - _, _ _.-.
, l follow the appropriate action statement for that system. This LCO will remain in the TS; however, the permissible number of inoperable snubber (s) and the subsequent visual examination interval will now be determined in accordance with the rew visual examination schedule-(Table 4.7-2 of Generic letter 90-09 dated December 11,1990). As noted in the guidance for this line item TS improvement, certain corrective actions may have to be performed depending on the number of inoperable snubbers found. All requirements, for corrective actions and evaluations associated with the use of visual examination schedule and Stated in the footnotes 1 through 6, (Table 4.7-2 of Generic Letter 90-09) shall be included in the TS.
The licensee has aroposed changes to Specifications 3.7,8 and 4.7.8 that are consistent with tie guidance provided in Generic Letter 90-09 for the replacement of the snubber visual examination schedule with Table 4.7-2 (including footnotes 1 through 6) of the Generic Letter 90-09.
On the basis of its review of this matter, the staff find 3 that the proposed changes to the TS for Millstone Unit No. 2 are acceptable.
3.0 JJAILCQ!iSULTATION in accordance with the Comission's regulations, the Connecticut State official was notified of the proposed issuance of-the amendment.
The State official had no coments.
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 effluent that may be released offsite, and that-there-is no significant increase in individual or cumulative occupa-tional radiation exposure.
The Commission has prevluusly issued a proposed finding that the amendment involves no significant hazards consideration, and ther6 has been no public coment on such finding (57 FR 18176).
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 r.eed be prepared in connection with the issuance of the amendment.
5.0- (QRCLUSION 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 endangered by operation in the proposed manner, (2). such I
activities will be conducted in compliance with the Comission's regulations, ard (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principa' Contributor:
J. Rajan Date:
June 16, '992 4
I t
h
ACCELERATEDT DISTRIBLTTION DEMONSTRATION SYSTEM
~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9206170256 DOC.DATE: 92/06/16 NOTARIZED: NO DOCKET #
FACIL: 10-744 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTI/.14 AME AUTHOR AFFILIATION JOliNSCL,A.
Project Directorate I-3 RECIP.NAME RECIPIENT ArrILIATION MECREDY,R.C.
Rochester Gas & Electric Corp.
SUBJECT:
Responds to 910424 telcon & 910506 lte re revs to QA manual App B,
" Inservice Insp Program for 1990-1999 Interval."
R Requests confirmation,within 60 days,that repairs, mods or replacements under ASME Code Section XI met.
y DISTRIBUTION CODE: DF01D COPIES RECEIVEDtLTR
/ ENCL h SIZE
[
U TITLE: Direct Flow Distribution: 50 Docket (PDFAvail) ~
g NOTES License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 f
RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL-
-D INTERNAL: NUDOCS-ABSTRACT 1
L REG FILE 01 1
D EXTERNAL: NRC PDR 1
NSIC 1
_S R
I D
- S.-
/
A D
- D NOTE TO ALL " RIDS" RECIPlENTS:
S PLEASE IIELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,-
ROOM PI 37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBtJrlON-LISTS FOR DOCUMEN'13 YOU DON'T NEED:
G TOTAL NUMBER OF COPIES REQUIRED: LTTR 4. ENCL d-
_ _ _ _ __= _ _ _ _ _
.5