ML19332E077
| ML19332E077 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/28/1989 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19332E078 | List: |
| References | |
| B13350, NUDOCS 8912060211 | |
| Download: ML19332E077 (3) | |
Text
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General Offices
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(203) 665-5000 j
November 28, 1989 Docket No. 50-245 B13350
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Re:
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
r Millstone Nuclear Power Station, Unit No.1 Proposed Revision to Technical Specifications Condensate Demineralizer Resin Pursuant to 10CFR50.90, Northeast Nuclear Energy Company- (NNECO) hereby proposes to amend its Operating License, No. DPR-21, by incorporating the changes: identified in Attachment 1 into the Technical Specifications of Millstone Unit No.1.
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The' criteria. of the resin monitoring c.nd resin replacement program have been established to protect the: reactor from a high chloride 41evel, should a sea-water: leak occur in the main condenser.. The proposed changes will reduce the
- allowable minimum condensate demineralizer capacity from 30 to 5 pounds in Section 3.6.J.1 and in Bases Section 3.6.J.
Changing _ the allowable minimum capacity of the condensate demineralizers from 30~ to 5 pounds as chloride ion, L
prior' to replacement of a-resin charge, increases' the usage of each bed by approximately 14 percent, while still assuring that time is available for an a
orderly plant shutdown before the quality of the reactor water is degraded.
Procedures require a controlled plant shutdown at 2 5 umho conductivity in the condensate pump. discharge and a scram at 215 umho.
With 5 pounds resin I
capacity, a leak resulting in 5 umho conductivity will not deplete the resin for a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; a. leak resulting in 15 umbo conductivity will not deplete the resin for_ approximately ~ 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. These times are considered to be sufficient for carrying out the actions required by procedures.
In the event that leakage increases to a value that results in resin depletion, plant 4
. procedures require a reactor scram and isolation of feedwater to the reactor vessel if the conductivity measured downstream of the demineralizers is 2 0.5 umho.
This action serves as a backup in the event of demineralizer failure. Also, the requirements relating to regenerated resin will be deleted in Sections 3.6.J.1, 3.6.J.2, 4.6.J.2, and 4.6.J.3 and in Bases Section 3.6.J p
because Millstone Unit No. I no longer regenerates resin.
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8912060211 891128 PDR ADOCK 05000245 P
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U.S. Nuclear Regulatory Commission B13350/Page 2 November 28, 1989 NNECO has reviewed the proposed changes in accordance with 10CFR50.92 and has concluded that they do not involve a significant hazards consideration in that the changes do not.
I 1.
Involve a significant increase in the probability or consequences of any accident previously evaluated.
Changing the minimum resin capacity of the condensate demineralizers from 30 to 5 pounds as chloride ion does not compromise the quality of the reactor water because Plant Operating Procedures are in place which provide for increased monitorir.g, plant shutdown, and scram as conductivity levels rise and limits are exceeded.
Procedures require a controlled plant shutdown at 15 umho conductivity in the condensate pump discharge and a scram at 215 umho.
The proce-dures, which are not being changed, along with a 5-pound minimum capacity will continue to ensure enough time is available for a controlled plant shutdown before the quality of reactor water is degraded to a point where damaging effects on core internals and fuel would occur.
Therefore there is no adverse effect to the consequences of the design basis accidents.
Removal of the regeneration requirements has no impact on any conduc-tivity transient since Millstone Unit No. I no longer regenerates resin, but rather replaces spent resin with new resin.
2.
Create the possibility of a new or different kind of accident.
There-is no change in plant design or operating procedures proposed by the subject changes..The modification of Technical Specification requirements does not change the probability of any conductivity transient.
Additionally, there are no new failure modes introduced by the change.
Therefore, there can be no impact on plant response to the point where a different accident is created.
3.
Involve a significant reduction in the margin of safety.
The changes have no adverse impact on the consequences of an accident or on any of the protective boundaries.
Therefore, there is no reduction in any i
margin of safety.
The Commission has provided guidance concerning the application of standards l
in 10CFR50.92 by providing certain examples (March 6, 1986, 51FR7751).
The I
changes proposed herein most closely resemble Example (vi), a change which either may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria.
The proposed Technical Specification change request changes the minimum resin value from 30 to 5 pounds as chloride ions, prior to replacement of a conden-sate demineralizing resin charge and removes requirements related to regenera-tion of resin, since resin is no longer regenerated at Millstone Unit No.1.
This criteria will continue to provide a sufficient buffer for an orderly plant shutdown should a seawater leak occur in the main condenser.
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U.S. Nuclear Regulatoby Commission B13350/Page 3 November 28, 1989' The Millstone Unit-No.1 Nuclear Review Board-has reviewed and approved the attached proposed revisions and has concurred with the above determinations.
The changes are not required to support continued plant operation and can be effective 30 days upon issuance.
No specific schedule for approval and
- issuance is requested.
In accordance with ICCFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
'l E. J. p czka
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Senior Vice President Attachment cc: Mr. Kevin McCarthy, Director Radiation Control Unit j
Department of Environmental Protection Hartford, CT 06116 W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 STATE OF CONNECTICUT) l
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me, E. J. Mroczka, who being duly sworn, did i
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
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his knowledge and belief.
hMeer l
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- Nptary Pub My Comm!stic, apires March 31,1993 l
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