B13472, Application for Amend to License DPR-65,adding Tech Specs Re UHS for Reactor & Containment Cooling Sys
| ML20012E660 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/21/1990 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20012E661 | List: |
| References | |
| B13472, NUDOCS 9004060069 | |
| Download: ML20012E660 (3) | |
Text
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March 21. 1990 Docket No. 50 311 B13472 Re:
10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
p Millstone Nuclear Power Station, Unit h 2 Proposed Revision to Technical Specifications Ultimate Heat Sink y
Pursuant to 10CFR50.90, Northeast Nuclear Energy! Company (NNECO) proposes amend its Operating License. DPR 65, by incorpor# ting the ;ttached change into the Technical Specifications of Millstone Unit No. 2.
Backaround In a letter dated January 29,1990,(I) NNECO informed the NRC Staff of its plans to submit, by the end of April 1990, a license amendment request which would add a new Technical Specification on ultimate heat sink in order to obviate the reliance on a justification for continued operation for hot weather conditions.
The change proposed herein adds a new specification on ultimate heat sink for reactor and containment cooling systems at Millstone Unit No. 2.
In Sec-tion 3.7.11 of the Millstone Unit No. 2 Technical Specifications, the change requires an average water temperature of 5 75'T at the Unit No. 2 intake structure except w1en the reactor is in cold shutdown or refueling condition.
A surveillance requirement for the ultimate heat sink is accordingly provided in Section 4.7.11.
Reactor and containment cooling systems are provided to assurr adequate cooling capability for heat removal in the event of a loss of-coolant accident (LOCA) or isolation from the normal reactor heat sink.
The proposed change imposes additional requirements and is more restrictive in both operational (1)
E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, "Haddam Neck Plant, Millstone Nuclear Power Station, Unit Nos. I and 2 Ultimate Heat Sink," dated January 29, 1990.
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I U.S. Nuclear Regulatory Commission 813472/Page 2 March 21, 1990 and surveillance requirements than the current Technical Specifications and more in line with the Staff approved Standard Technical Specifications.
Sionificant Hazards Consideration in accordance with 10CFR50.92, NNECO has reviewed the above-described proposed change and has concluded that it does not involve a significant hazards consideration.
The proposed change does not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The change reflects the assumption made for ultimate heat sink in the design basis analysis and is more stringent than the existing Technical Specifications.
There are no design basis accidents adversely affected by the proposed change, and the change cannot result in the initiation of any event.
The additional shutdown requirement will maintain the plant within the 75'r design basis service water temperature.
2.
Create the possibility of a new or different kind of accident from those previously analyzed.
The proposed change has no effect on plant operation within the design basis, no new failure modes are introduced, and no hardware modifications are included in this change.
3.
Involve a significant reduction in the margin of safety.
The change does not have any adverse impact on the protective boundaries.
The change has no effect on the consequences of any accident and there is no reduction in the margin of safety.
The Commission has provided guidance concerning the application of standards in 10CFR50.92 by giving certain examples (March 6, 1986, 51FR7751) of amend-ments that are considered noi likely to involve significant hazards considera-tions.
The change proposed herein most closely resembles Example (ii), a change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications; e.g.,
a more stringent surveillance requirement.
In the current Technical Specifications there is no specification covering the ultimate heat sink.
The change requires the plant to be in cold shutdown or refuel condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the ultimate heat sink is unavailable.
It also requires verification of the average water temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
When the average water temperature exceeds 70'f, verification that the temperature is within the limit is required every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The design basis assumed a maximum service water /
emergency service water temperature of 75'f, and the change simply reflects the assumption made for the design basis analyses.
As such, there is no adverse impact on the design basis accident due to the changes.
Since the i
current Technical Specifications have no requirements covering ultimate heat i
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U.S. Nuclear Regulatory Commission B13472/Page 3 March 21, 1990 sink, the proposed changes are more restrictive in both operational and surveillance requirements.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the changes proposed herein and has concurred with the above determinations.
This change is not required to support continued plant operation and can be effective 30 days upon issuance.
No specific schedule for issuance is requested.
In accordance with 10CFR50.91(b), NNECO is providing the State of Connecticut with a copy of this proposed amendment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY f h Y M v.A A E. J. T oczka Senio/ Vice President ec: Mr. Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection Hartford, CT 06116 W. T. Russell, Region 1 Administrator G. 5. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are true and correct to the best of his vnowledge and belief.
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