ML19256A946
| ML19256A946 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/20/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256A929 | List: |
| References | |
| NUDOCS 7901170188 | |
| Download: ML19256A946 (2) | |
Text
i 7590-01 l
UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-333 POWER AUTHORITY OF THE STATE OF NEW YORK NOTICE OF ISSUAMCE OF AMENDMENT TO FACILITY OPERAT mG LICENSE The U. S. Nuclear Regulatory Commission (the Comission) has issued Amendment No. 44 to Facility Operating License No. DPR-59, issued to Power Authority of the State of New York, which revised Technical Specifications for operation of the James A. FitzPatrick Nuclear Power Plant (the facility) located in Oswego County, New York. The amendment
{
is effective as of its date of issuance.
[
The amendment revises the Technical Specifications on an interim
- asis to allow plant operation with higher than allowable leakage of the outboard Main Steam Isolation Valve for a main steam line.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and I
the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Comission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant.
to 10 CFR Section 51.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
7901170183
7590-01 For further details with respect to this action, see (1) the application'for amendment dated December 12,1978,(2) Amendment No. 44 to License No. OPR-59, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N. W.,
Washington, D. C. and at the Oswego County Office Building 46 E. Bridge Street, Oswego, New York 13126. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Director, Division of Operating Reactors.
I
~
Dated at Bethesda, Maryland, this 20th day of December 1978.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas A.
polito Chief Operating Reactors Branch #3 Division of Operating Reactors
TABLE 1 ASSUMPTIONS USED IN ESTIMATING DOSE CONSEQUENCES FROM MSIV LEAKAGE, POST-LOCA AT FITZPATRICK Power Level 2560 MWT Operating Time 3 years Fraction of Core Inventory Released to Containment:
Iodines 25%
Noble Gases 100%
Iodine Distribution:
Elemental 91%
Particulate 4%
Organic 5%
3 Drywell Free Volume 150,000 ft 3
x/Q Values *, sec/m Stack Release EAB LPZ 0-2 Hours 5.1 x 10-5 2.6 x 10-5 2.6 x 10-5 2-4 Hours 6.2 x 10-6 4-8 Hours 4.4 x 10-6 8-24 Hours 1.7 x 10-6 24 - 96 Hours 5.5 x 10-7 96 - 720 Hours Ground Level Release 0 - 10 minutes 1.3 x 10-4 1.5 x 10-5 Standby Gas Treatment System Charcoal Filter Efficiencies for Iodine **-
Elemental 90%
Particulate 90%
Organic 70%
Time to Actuate the LCS 10 minutes
- From " Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant," USAEC, November 20, 1972, pp. 2 - 13 through 2 - 17.
- Ibid., p. 10 - 3.
. Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be con-ducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: December 20, 1978 at 25 psig. The licensee will be required to confom to the current Technical Specifications before returning to power following the next scheduled refueling outage. We believe that operation in this manner for a short time period will not significantly increase the risk to the public.
For purposes of evaluating this Technical Specification change only, we have estimated the dose consequences of a LOCA with the LCS functioning using the assumptions in Table 1 and the containment leakage dose contri-bution from our 1972 SER. We have assumed the leakage across the valves is not collected and filtered by the LCS until after its actuation ten minutes into the accident. For main steam lines which have both valves closed, the pressure between the valves is expected to preclude any out-leakage across those outboard MSIVs prior to actuation of the LCS. Leakage across the one outboard MSIV leaking at 300 SCfD was assumed to start at the time of the accident due to a postulated single active failure of the inboard MSIV to close. Once the LCS is actuated, however, this leakage is also assumed treated by the charcoal filters and vented thrcugh the plant stack. These assumptions do not give credit for any delay of the first ten minutes of leakage down the main steam piping. The difference between this valve leaking at 300 SCFD for ten minutes and leaking at 276 SCFD for ten minutes is estimated to be two rem to the thyroid at the exclusion area boundary (EAB) and less than one rem to the thyroid at the low population zone (LPZ) boundary. The whole body dose will be increased by less than 0.1 rem at both the EAB and at the LPZ. The tutal valve leakage following actuation of the LCS will contribute the same dose as at current Technical Specification limits. We have estimated the total dose consequences of the LOCA, including containment leakage, to be 108 rem to the thyroid and 5 rem to the whole body at the EAB and 170 rem to the thyroid and 5 rem to the whole body at the LPI. These are within the guidelines of 10 CFR Part 100.
We, therefore, conclude that modifying the Technical Specifications to permit one valve to exceed the current 276 SCFD limit by 24 SCFD and maintaining the total leakage at 1104 SCFD will not significantly change the estimated consequences of a postulated loss-of-coolant accident at FitzPatrick. Assumptions used in this evaluation are p esented in Table 1.
We have detemined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this dett:mination, we have further concluded that the amendment involves an action which is insignifi-cant from the standpoint of environmental impact and, pursuant to 10 CFR
!i51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.