ML20012C568
| ML20012C568 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/15/1990 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20012C569 | List: |
| References | |
| B13462, NUDOCS 9003220215 | |
| Download: ML20012C568 (4) | |
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r March 15, 1990 Docket No. 50-423 B13462 Re:
10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Containment Systems and Refuelina Operations' Pursuant to -10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend operating license NPF-49 by incorporating the changes identified in Attachment 1 into the Technical Specifications of Millstone Unit No. 3.
Discussion Conta'inment Systems. Sections 4.6.2.1 and 4.6.2.2 The proposed change to the Millstone Unit No. 3 Technical Specifications incorporates the word "that" after flow path to clarify the existing specifi-cation.
This addition is imnded to clarify the surveillance requirement by making it easier to read.
Ihis change is considered editorial in nature.
There is no change in the technical content of the surveillance requirement.
In ' addition, the proposed change makes the technical specifications consistent
~ with existing Technical Specification Section 4.6.2.3.
Refuelino Operations. Section 3/4.9.1 The proposed change to Section 3/4.9.1 revises the surveillance requirement for valve 3CHS-V305 to require verification that the valve is closed and locked rather than secured in' position.
Valve 3CHS-V305 is a manual valve which provides primary grade flushing water to the emergency boration line.
This valve is normally locked closed with a typical lock and chain device.
The proposed change does not alter the position of valve 3CHS-V305, it simply clarifies that removal of air or electrical power and installation of mechan-ical. stops are not necessary on a manually operated valve.
The proposed change would correct an inconsistency between 'as built' conditions and the Technical Specifications and would not change the requirements in the Technical Specifications or the safety analysis.
9003220215 900315 x
PDR ADOCK 05000423 P
PDC OS3422 REY. 4-88 >
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U.S. Nuclear Regulatory Commission B13462/Page 2 4
March 15, 1990 Sionificant Hazards Consideration i
NNECO has reviewed the proposed changes in accordance with 10CFR50.92 and has concluded that the changes do not involve a significant hazards consideration.
The basis for this conclusion is that the three criteria of 10CFR50.92(c) are i
not compromised.
The proposed changes do not involve a significant hazards consideration because the changes would not:
1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
The proposed change which atM ' the word "that" after flow path is I
intended to clarify the existing technical specification without changing the technical content of the surveillance requirement.
There are no failure modes associated with the proposed change nor are any design basis accidents impacted by the change.
The proposed change to the surveillance requirement for valve 3CHS-V305 clarifies that removal of air or electrical power and installation of mechanical stops are not necessary on a manually operated valve.
The intent of the Technical Specification remains the same by verifying that the valve is locked closed.
For these reasons, the proposed changes do not increase the probability or consequences of any event.
2.
Create the possibility of a new or different kind of accident from that previously analyzed.
The addition of the word "that" is editorial in nature and intended to provide easier reading of tha surveillance requirement.
The proposed change '
ihe surveillance requirement for valve 3CHS-V305 provides continued oaurance that the valve will remain in its required closed position.
There are no changes in the way the plant is operated or in the operation of equipment credited in the design basis accidents.
Therefore, the potential for an unanalyzed accident is not created.
3.
Involve a significant reduction in the margin of safety.
The intent of the Technical Specifications for both changes remains unchanged.
The proposed changes will not impact any protective boundary and do not affect the consequences of any accident previously analyzed.
Therefore, there is ao reduction in the margin of safety.
l Moreover, the Commission has provided guidance concerning the application of l
standards in 10CFR50.92 by providing certain examples (March 6,
- 1986,
p U.S. Nuclear Regulatory Consnission B13462/Page 3 March 15, 1990 51FR7751) of amendments that are considered not likely to involve a signifi-cant hazards consideration.
The proposed changes to Technical Specification Section 3/4.6.2, Containment Systems, are enveloped by example (1) a purely administrative change to technical specifications.
The proposed change
-incorporates the word 'that" after flow path to clarify the existing specifi-cation and allow easier reading of the surveillance requirement. Although the proposed change to Section 3/4.9.1, Refueling Operations, is not enveloped by a specific example, the change would not involve a significant increase in the probability or consequences of an accident previously analyzed. As previously stated, the proposed change to the surveillance requirement for valve 3CHS-V305 provides continued assurance that the valve will remain in its required closed position, without changing the intent of the surveillance requirement.
Based upon the information contained in this submittal and the environmental assessment for Millstone Unit No. 3, there are no radiological or nonradio-logical impacts associated with the proposed changes and the proposed license amendment will not have a significant effect on the quality of the human environment.
I The Millstone Unit No. 3 Nuclear Review Board has reviewed and approved the i
attached proposed revisians and has concurred with the above determinations.
In accordance with 10CFR50.91(b) we are providing the State of Connecticut l
with a copy of this proposed amendment.
l l
Regarding our propos?.J schedule for this amendment, we request issuance at j
your earliest convenience with the amendment effective within 30 days upon issuance.
Should the Staff have any additional questions, please contact my Staff directly.
Very truly yours, 1
HORTHEAST NUCLEAR ENERGY COMPANY FOR: E. J. Mroczka l
Senior Vice President 1
BY:d[. P. Werner
~
Vice President i
r',
t-U.S. Nuclear Regulatory Commission B13462/Page 4 March 15, 1990 I
cc:
W. T. Russell, Region I Administrator D. H. Jaffo, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me, R. P. Werner, who being duly sworn, did state that he is 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 knowledge and belief.
y eMdnk.
972 4V Notary Pplic My Ccmmbs:en Expires thrch 31,1993 l
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