ML20154B857
| ML20154B857 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/02/1988 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20154B860 | List: |
| References | |
| B12985, NUDOCS 8809140165 | |
| Download: ML20154B857 (3) | |
Text
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NORTHEAST UTILITIES cenem Omce. seiaen sireet. Bernn. Connecticui HARTFORD CONNECTICUT 06141-0270
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L t T; (2o3) ses-sooo September 2, 1988 Docket No. 50-423 B12985 Re:
10CFR50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Containment Isolation Valves Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License No. NPF-49 by incorporating the changes identified in Attachment 1 into the plant Technical Specifications for Hillstone Unit No. 3.
Discussion The proposed changes to the Hillstone Unit No. 3 Technical Specifications consist of deleting Table 3.6-2 which lists containment isolation valves and replacing it with a reference to the Hillstone Unit No. 3 FSAR Table 6.2-65 in the Technical Specifications bases (3/4.6.3).
The FSAR Table 6.2-65 contains a complete listing of all containment penetration valves and far more informa-tion than contained in the existing Technical Specifications.
Thus, to include this information in the Technical Spec 1fications is redundant.
The proposed changes to Technical Specification Section 3/4.6.1 and 3/4.6.3 delete references to Table 3.6-2 as it will no longer be a part of the Techni-cal Specifications.
In addition, a note on opening of certain manual valves during the plant operations under administrative control has been taken from Table 3.6-2 and adequately included in the Technical Specifications (Defini-tion 1.7, Containment Integrity and Section 4.6.1.1.a).
The addition or deletion of any containment isolation valve shall be made in accordance with 100FR50.59 and approved by the Plant Operation Review Committee.
Deletion of the tabular listing from the Technical Specifications contributes to the ongoing efforts to upgrade the Hillstone Unit No. 3 Technical Specifi-cations into a more usabin and less cumbersome document without compromising the ability to control changes made to the contents of the table.
- Moreover, deletion of the table is consistent with the recommendations of NUREG-1024 as a short-term improvement item and the efforts by the Westinghouse Owners Group (WOG) and NUHARC Technical Specification upgrade initiatives to make the Technical Specifications a more clear and concise document.
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U.S. Nuclear Regulatory Commis: ion B12985/Page 2 September 2, 1988 The proposed changes do not delete the requirement for containment isolation valve operability from the Technical Specifications.
The action statements and surveillance requirements will remain in the Technical Specifications.
Therefore, the proposed changes do not reduce the effectiveness of the Techni-cal Specification requirements.
The proposed changes can in no way adversely affect nuclear safety.
Sianificant Hazards Consideration In accordance with 10CFR50.92, NNEC0 has reviewed the proposed changes and concluded that they do not involve a significant hazards consideration.
The basis of the conclusion is that the three criteria of 10CFR50.92(c) are 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 removal of Table 3.6-2 from the Technical Specifications and replacing it with a reference to the Millstone Unit No. 3 FSAR Table 6.2-65 in the Technical Specification b:ses does not reduce the effectiveness of the Technical Specifications.
Also, there are no changes proposed to the Limiting Conditions for Operation (LC0) or to surveillance requirements.
Therefore, there is no impact on the design basis accidents.
2.
Create the possibility of a new or different kind of accident from I
previously analyzed.
Since there are no changes in the way the plant is operated, the potential for an unanalyzed accident is not created.
No new failure modes are introduced. The proposed changes have no effect on plant operation.
3.
Involve a significant reduction in a margin of safety.
Since the proposed changes do not affect the consequences of any accident previous-ly analyzed, there is no 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, FR7751)
I of amendments that are considered not likely to involve a significant hazards consideration.
Although the proposed changes are not enveloped by a specific example, the proposed changes would not involve a significant increase in the l
probability or consequences of an accident previously analyzed.
As stated earlier, the proposed changes are being made to coincide with the efforts by the WOG and NUMARC activities to upgrade the Technical Specifications to a more clear and concise document.
The Hillstone Unit No. 3 FSAR Table 6.2-65 contains a complete listing of all containment penetration valves and far more l
information than contained in the existing Technical Specifications.
The proposed changes do not reduce the effectiveness of Technical Specification l
requirements as they do not delete the requirement for containment isolation valve operability from the Technical Specifications.
In addition, the action statements and surveillance requirements will remain in the Technical
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U.S. Nuclear Regulatory Commission B12985/Page 3 September 2, 1988 Specifications.
The addition or deletion of any containment isolation valve shall be made in accordance with 10CFR50.59 and approved by the Plant Opera-tion Review Committee.
Based upon the information contained in this submittal and the environmental assessment for Millstone Unit No. 3, there are no significant radiological or nonradiological impacts associated with the proposed action, and the proposed license amendment will not have a significant effect on the quality of the human environment.
The Millstone Unit No. 3 Nuclear Review Board has reviewed and approved the proposed change and has concurred with the above determinations.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this prc)) sed amendment.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY M
E. Kjefoi:zka
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Seniof Vice President cc:
Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection Hartford, CT 06116 W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit Nos. 2 and 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 STATE OF CONNECTICUT) ss. Berlin COUNTY OF HARTFORD Then personally appeared t'efore 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 knowledge and belief.
NN %.SMCLn Nota'ry Public