ML17262A791

Proposed Tech Specs Revising 6.9.1.2 & 6.9.2.5

ML17262A791
Person / Time
Site:	Ginna
Issue date:	03/20/1992
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A789	List: ML17262A788 ML17262A790 ML17262A791
References
NUDOCS 9204010294
Download: ML17262A791 (5)

Text

ATTACHMENT A Revise the Technical Specification pages as follows:

Remove Insert 6.9-2 6.9-2 6.9-7 6.9-7 PDR ADOCK 05000P44 P PDR

Startup reports shall be submitted within (1) 90 days following completion of the startup zest program, or (2) 90 days following resumption of 'commercial power opera-tion, whichever is earliest. If the Startup Report does not cover both events (i.e., completion of startup test program, and. resumption of commercial power operation),

supplementary reports shall be submitted at least every three months until both events have been completed.

Monthl 0 eratin Re ort. Routine reports of operating statistics and shutdown experience shall be submitted in accordance with 10 CFR 50.4 by the fifteenth of each month following the calendar month covered by the report.

The monthly report shall include a narrative summary of operating experience describing the operation of the facility,,including. major safety related maintenance for the monthly period, except that safety related mainte-nance performed during the refueling outage may be reported in the monthly report for the month following the end of the outage rather than each month during the outage.

Annual Radiolo ical Environmental 0 eratin Re ort A radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9-2 Proposed

results of analyses while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should, include the date and time of sampling and. the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and. one other radioiodine isotope concentration as a function of ti'me for the duration when the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

6.9.2.4 Reactor Overpressure Protection System Operation Xn the event either the PORVs or the RCS vent(s) are used to mitigate a- RCS pressure transient, a Special Report shall be prepared and submitted to the Commission within thirty days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent(s) on the transient and any other corrective action necessary to prevent recurrence.

6.9..2.5 Special reports shall be submitted. in accordance with 10 CFR 50.4 within the time period. specified for each report.

Amendment No. 6.9-7 Proposed

Attachment B The proposed change in the Ginna Technical Specifications does not, involve a significant hazards consideration. The basis for this determination is as follows:

~ There is no significant increase in the probability or conse-quences of, an accident, previously evaluated because no change is being made to any accident initiators or mitigation features or assumptions. This change is administrative in that it establishes an orderly appearance of an authorized change.

simply

~ The possibility of a new or different kind of accident from any accident previously evaluated is not created.. Xn matters related to nuclear safety, all accidents are bounded by previous analyses. The proposed changes do not add or modify any equipment or system design nor do they involve any changes in the operation of any plant system. The absence of a hardware change means that the accident initiators rema'in unaffected., so no unique accident probability is created.

~ The proposed amendment does not involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification because the proposed change is administrative in nature and. only establishes an orderly appearance of an autho-rized change.

Conclusion On the basis of the above, RG&E has determined that the Amendment does not involve a significant hazards consideration.

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