B11512, Application for Amend to License DPR-21,revising Tech Specs 3.7.A.2.a & 3.7.A.6 Re drywell-to-suppression Chamber Differential Pressure & Drywell Oxygen Concentration, Respectively,To Allow for Up to 48 H Nonmaint.Fee Paid
| ML20127M422 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/15/1985 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20127M426 | List: |
| References | |
| B11512, NUDOCS 8505230265 | |
| Download: ML20127M422 (3) | |
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en wal Hicen Selden Smt. BerHn, ConnectM NOItTIMAST E5TIIJTIES P.O. BOX 270
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l May 15,1985 L
E Docket No. 50-245 M
E B11512 4
Director of Nuclear Reactor Regulation i
L Attn:
Mr. John A. Zwolinski, Chief F
Operating Reactors Branch #5 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
b Millstone Nuclear Power Station, Unit No.1 Proposed Revision to Technical Specifications g
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Containment Systems o
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Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby b
proposes to amend its Operating License, DPR-21, by incorporating the attached j
proposed changes into the Millstone Unit No.1 Technical Specifications.
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The proposed revisions to the Technical Specifications are provided as y. The proposed changes allow periods of up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> wherein the j
drywell to suppression chamber differential pressure need not be maintained at 1 e
a psid (Technical Specification 3.7.A.2.a) and the drywell oxygen concentration g
need not be maintained at less than 4% by volume (Technical Specification
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3.7. A.6).
il These proposed revisions will allow drywell entry at power for the purpose of
_d performing leak inspections, equipment adjustments or other inspection and i
maintenance activities.
By permitting these evolutions at power, thermal 4
cycling of major plant components is reduced.
a b
NNECO has reviewed the attached proposed revisions pursuant to 10CFR50.59 3
and has determined that they do not constitute an unreviewed safety question.
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Specifically, the proposed technical specification allows the same 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period d
y for a drywell entry as is currently allowt;d for a shutdown and subsequent i
startup. Current technical specifications allow the drywell to be de-inerted for j
a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> without limitation on power level, provided a j
g plant shutdown and subsequent startup are involved. This proposed change would
-authorize de-inerting the drywell for the same 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> interval, but a plant g
shutdown would not necesssrily occur. Thus, considering that the plant transient ji p
and associated thermal cycling of equipment is lessened, the proposed change is g
bounded by that authorized by current Technical Specifications. The precise a
T conditions under which a drywell entry would occur would be governed largely by h0
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personnel access factors including the purpose and duration of the entry, exact location within the drywell, drywell temperature, and ALARA considerations.
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p The margins of safety as defined in the technical specification bases are 3
8505230265 850515 0\\
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,_. maintained, the probability of occurrence or the consequences of a previously
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analyzed accident have not been increased, and the possibility for a new type of
- accident not previously evaluated has not been created. Therefore, this proposed -
change does not constitute an unreviewed safety. question as defined in
- 10CFR50.59.
NNECO has reviewed the attached proposed license amendment pursuant to the requirements of 10CFR50.91(a) and has determined that the changes involve no significant hazards consideration. The basis for this conclusion is that none of the criteria delineated in 10CFR50.92 have been compromised, a conclusion supported by the unreviewed safety question determination discussed previously.
That. is, the proposed changes do not involve a significant increase in the probability or consequences _of an accident previously evaluated; create the possibility of a new or different kind of accident from any accident previously
-- evaluated; or involve a significant reduction in a margin of safety. A comparison of the contents of this amendnient request with the list of examples of
~ amendments in 48FR14870 likely to involve no significant hazards considerations reveals that none of the examples precisely envelopes this proposal. Portions of example (vi) are applicable, in that the results of the proposed changes are clearly.within all acceptance criteria. This conclusion flows from the fact that the proposed change is bounded by what is already authorized-by current Technical Specifications.
The Millstone Unit No.1 Nuclear Review Board has reviewed and approved the attached proposed revision and has concurred with the above determinations.
. Please note that a-situation could arise requiring drywell entry to prevent a shutdown while the requested Technical Specification changes are undergoing
. Staff review. Therefore, we request, in accordance with 10CFR50.91, that the Staff review these proposed changes without delay and, if necessary,' proceed
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with an individual. Federal Register notice-(possibly with a shortened public
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comment period) to expedite the amendment process.
Should it become necessary to process the proposed change on the basis of exigent or emergency circumstances, we will promptly advise the Staff. We will keep the NRC Project Manager verbally informed regarding our need for this amendment.
In accordance with 10CFR50.91(b), NNECO ia providing the State of Connecticut a copy of this proposed amendment.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.00.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
- h bb J. L D>eka O
Senior Vice President ir
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., - cc:
Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, CT. 06116 STATE'OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD
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Then personally appeared before me J. F. Opeka, who being duly sworn, did state
- that he is Senior Vice President of Northeast Nuclear Energy Company, the 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, haw:
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-Notary Pu
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