ML17264A504
| ML17264A504 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/23/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264A503 | List: |
| References | |
| NUDOCS 9605290079 | |
| Download: ML17264A504 (5) | |
Text
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0p*p4 UN)TED STATES NUCl EAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 S
VALUA ION BY THE OFFICE OF NUCLEAR REACTOR REGULATION N
N NO.
64 TO FACILITY OP RATING LICENSE NO.
DPR-18 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
~INT 0000TINN By letter dated February 9,
- 1996, as supplemented March
.15,
- 1996, and April 22, 1996, the Rochester Gas and Electric Corporation (the licensee) submitted a request for changes to the R.
E. Ginna Nuclear Power Plant Technical Specifications (TS).
The requested changes would revise the Administrative Controls Section 5.6.6 of the Ginna TS to incorporate a
reference to the methodology for determining pressure/temperature (P/T) and low-temperature overpressure protection (LTOP) limits.
The Narch 15,
- 1996, and April 22, 1996, letters provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
- 2. 0 EVALUATION The proposed amendment follows the guidance given in Generic Letter 96-03 for relocating LTOP and reactor coolant system (RCS)
P/T limits to the RCS Pressure and Temperature Limits Report (PTLR).
However, the licensee has not generated plant-specific P/T and LTOP limits using the NRC-approved WCAP-14040 methodology.
- Rather, the licensee has revised the PTLR curves, setpoints, values and parameters using portions of WCAP-14040, updated
- data, and estimated values for the neutron fluence.
The staff has reviewed the PTLR and supporting submittals submitted by the licensee and by letter dated Hay 23,
- 1996, have found the report acceptable for referencing in the administrative controls section of the TS and, therefore, have found the proposed TS change acceptable.
This acceptance is only for operation up to the end of the year 1996 after which the operation will be subject to staff approval of Revision 1
of the PTLR.
The staff acceptance of the PTLR applied only to the format of the report with the stipulation that the methodology in WCAP-14040 along with the licensee provided supplements would be used to calculate future change to the P/T and LTOP system limits.
Revision 1 of the PTLR would be submitted to the staff for review and approval to ensure that the new P/T and LTOP system limits are acceptable based on approved methodology.
9SO5aeo079 960523 PDR ADGGK 05000244 P
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3.0
~ETAT CG EU T TIO In accordance.-with the Commission's regulations, the New York State official was notified'f the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSID RATION 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.
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 (61 FR 7557).
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 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:
G. Vissing Date:
May 23, 1996
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or. Robert C. Recredy ~
liny 23, 199$
'dice President, Nuclear Operations Rochester Gas and El ectri c Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
ISSUANCE OF AMENDMENT NO. 6/I TO FACILITY OPERATING LICENSE NO.
DPR-18, R.
E.
GINNA NUCLEAR POWER PLANT (TAC NO. H94770)
I
Dear Dr. Hecredy:
The Commission has issued the enclosed Amendment No. 64 to Facility Operating License No.
DPR-18 for the R.
E. Ginna Nuclear Power Plant.
This amendment is in response to your application dated February 9,
- 1996, as supplemented March 15,
- 1996, and April 22, 1996.
This amendment revises the Administrative Controls Section 5.6.6 of the Ginna Technical Specifications (TS) to incorporate a reference to the methodology for determining pressure/temperature (P/T) and low-temperature overpressure protection (LTOP) limits.
This amendment is only for operation up to the end of the year 1996 after which the operation will be subject to staff approval of Revision 1 of the Pressure Temperature Limits Report (PTLR). It should be noted that the issuance of this amendment is with the stipulation that methodology of WCAP-14040 along with licensee provided supplements should be used to calculate future changes to the P/T and LTOP limits.
Revision 1 of the PTLR should be submitted to the staff as a license amendment for review and approval to ensure that new P/T and LTOP system limits are acceptable based on approved methodology.
In order to provide the staff sufficient time to review your submittal, we will need to have your complete submittal at least 90 days prior to the time that you need the amendment.
A copy of the related Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's biweekly Federal Re<eister notice.
Sincerely, ORIGINAL SIGI'KD BY:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
l.
Amendment No. 6/I to License No.
DPR-18 2.
Safety Evaluation cc w/encls:
See next page DISTRIBUTION:
See next page DOCUMENT NAME:
G:(GINNA)H94770.AMD To receive a copy of this document, indicate in the box:
"C" Copy without attachment enclosure "E" = Co with attachment enclosure "N" = No co OFFICE LA:PDI-E PH:PDI-1 D:PDI-1 14 OGC HAHE SLIIII GVissing/rsI JHitcheII DATE 05/~/96 05/Si /96 05/ '96 Official Record Copy 05/
/96 05/
/96
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