ML20095K001

Application for Amend to License NPF-49,changing TS to Remove License Conditions 2.C(5) Re Inservice Insp Program & 2.C(10) Re Initial Test Program

ML20095K001
Person / Time
Site:	Millstone
Issue date:	04/28/1992
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20095K005	List: B14078, Proposed TS Deleting License Conditions 2.C(5) Re Inservice Insp Program & 2.C(10) Re Initial Test Program ML20095K001
References
B14078, NUDOCS 9205040260
Download: ML20095K001 (5)

Text

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HARTFORD. CONNECTICUT 061414270 k ' J N,*[. [,3CI;2, (203) 665-$000 April 28, 1992 Rocket No. 50-421 D14078 Re: 10CFR50.90 7

U.S. Nucle u Regult. tory Commission Attention: Document Control Desk Washington, DC 20555 6entlemn:

f- Millstone Nuclear Power Stat.an, Unit No. 3 Deletion of License Conditions from the Operatina License The NRC imposed 14 license conditions in the Hillstone Unit No. 3 full power license issued January 31, 1986. Fince then, Northeast Nuclear Energy Company (NNECO) has satis In a letter dated December 18, .1989,gdthe most NRCofissued the license conditions.

a license amendment to the Millstone Unit No. 3 Operating License by deleting the following license conditions:

1. 2.C(3) - Containment Average Temp.

2. 2.C(4) - N 1 Loop Operation .

3. 2.C(6) -

Instrumentation for Monitoring Post-Accident Conditions 4, 2.c(8) - Moisture in Air Start System

5. 2.C(9) -

Operating Staff Experience Requirements

6. 2.C(11) -

Revised Small Break LOCA

7. 2.C(12) -

SPDS-

8. 2.C(13) -

Detailod CRDR In-addition, NNEC0 sctisfied two additional license conditions and therefore, their existence is no longer necessary in the Operating License. Therefore, aursuant to 10CFR50.90, NNECO hereby proposes to amend its facility Operating

_icense, NPF-49, by removing these two license conditions from the Operating License. Specifically, the license conditions to be deleted are as follows:-

(1) D. H. Jaffe letter to E. J. Mroczka, " Millstone Unit 3--Issuance of Amendment (TAC No. 74555)," dated December 18, 1989.

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U.S. Nuclear Regulatory Commission B14070/Page 2 i April 28, 1992  ;

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1. 2.C(S) - Inservice Inspection Progsam 2, 2.C(10) - Initial Test Program NNECO will also request to delete License Condition 2.C(14), Salem ATWS Events Generic Letter 83-28, at a later date when the NRC Staff review has been completed for this license condition. License Conditions 2.C(7), Fire  :

Protection, 2.C(1), Maximum Power Level and 2.C(2), Technical Specifications .

will not be deleted and are expected to remain for the duration of the Operating License. The above remaining license conditions are renumbered to

, rcflect the deleted license conditions. This change does not reduce the effectiveness of the Operating License.

Discussion

.l. License condition 2.C(5)--Inservice Inspection Proaram License Condition 2.C(5) in the Millstone Unit No. 3 Operating License requires' that " Prior to May 25,1986, NNEC0 shall submit the inservice -

inspection program which conforms to the ASME Code in effect on November 25, 1984 inaccordancewith50.55(a)(q)f4),forNRCStaffreview and approval." By letter dated May 22, 1986, .NNECO submitted to the NRC the Millstone Unit No. 3- Inservice Inspection Program Plan. The

' Program Plan was submitted for review and evaluation of its compliance with- the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, regulations, and In a letter dattd February 8, 1991,gnt the Technical Specifications.

Staff concluded that License Condition 2.C(5) had been met; therefore, removal of License Condition 2.C(5) is appropriate and safe.

2- License Condit bn 2.C(101--Initial Test Proar:9 License Condition 2.C(lJ) in the Millstone Unit No. 3 Operating License requires that "Any. changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of-10CFR50.59-shall be reported in .ccordance with 50.59(b) within-one month

.of . such change." -NNECO made a series of submittals in accordance with L

r L (2) J. F. Opeka letter to U.S. Nuclear Regulatory Commission, "First Ten-Year

! Program Plan," dated _ May 22, 1986.

L (3) J, F. Stolz. letter to E. J. Mroczka, "First Ten-Year Program Plan and In .rvice Inspection Relief Request, Millstone Unit 3 (TAC No. 60385),"

dated February 8, 1991.

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U.S. Nuclear Regulatory Commission B14078/Page 3 April 28, 1992 License Condition 2.Cg10). In a letter dated May 10, 1989.54) W HE concluded that the changes to the Initial Te.,L Program are acceptable and License inndition 2.C(10) had been met; therefore, removal of License Condition F.C(10) is appropriate and safe.

Sionificant Hazards Consideration In accordance with 10CFR50.92, NNECO has reviewed the proposed license )

aniendment and concluded it does not involve a significant hazards  ;

consideration. The basis for this conclusion is that the three criteria of l 10CFR50.92(c) are not compromised. The proposed amendment does not involve a significant hazards consideration because it would not:

1. Involve a significant increase in the probability or consequences of an accident previously analyzed. Individual license conditions discussed above were one-time commitments that have been met. Their existence is no longer warranted; tbtrefore, removal of license conditions is appropriate and safe. As a result of the proposed amendment, there are no physical changes to the facility and all operating procedures,

-limiting conditions for operation (LCO), limiting safety system settings, and safety limits specified in the Technical Specifications will remain unchanged.

2. Create the possibility of a new or different kind of accident from any previously evaluated. Since _there are no changes in the way the plant is operated, the potentirl for an unanalyzed accident is not created. No new failure modes are introduced.

3. Involve a significant reduction in a margin of safety. Plant safety margins are established through LCOs limiting safety system settings, and safety limits specified in the Technical Specifications. As a result-of the proposed amendment, there will be no changes to either- the physical design of the plant or to any of these settings and limits; therefore, there will be no changes to any of the margins of safety.

Moreover, the Commission has provided guidance concerning the application of standards set forth- in 10CFR50.92 by providing certain examples (March 6, 1986, SIFR7751) of amendments that are considered not likely to involve a significant hazards censideration; however, the proposed amendment is not -

enveloped by a specific example. - The indivic'ual license condition discussed above were one-time commitments which have been met. As such, removal of these license conditions from the Millstone Unit No. 3 Operating License is appropriate and safe._ As noted above, this action does not involve a (4) D. H. Jaffe letter to E. J. Mroczka, " Millstone Unit 3 Initial Test Program (TAC No. 60380)," dated May 10, 1989.

e U.S. Nuclear Regulatory Commission B14078/Page 4 April 28, 1992 significant increase in the probality or consequences of an accident previously analyzed.

NNECO has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed change meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an environmental impact statement.

The Millstone Unit No. 3 Nuclear Review Board has reviewed and approved the proposed change and has concurred with the above determination.

The /atype of the proposed change to the 0)erating Licen3e in Attachment I reflects the currently issued version of tie Operating License. Operating License changes issued subsequent to this submittal or pending Operating License changes are not reflected in the enclosed retype. The enclosed retype should be cher.ked for continuity with the Operating License prior to issuance.

Revision bars are provided in the right hand margin to indicate a revision to the text. No revision bars are utilized when the page is changed solely to accommodate the shifting of text due to additions or deletions.

In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a cooy of this proposed amendment.

Regarding our proposed schedule for this amendment, we request issuance at your earliest convenience with the amendment effective as of the date of issuance to be implemented within 30 days of issuance.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY hbbb J. F..Op6kaJ u Executive Vice President l

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4 U.S. Nuclear Regulatory Commission B14078/Page 5 April 28, 1992 cc: T. T. Martin, Region I Administrator V. L. Rooney, 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, CT 06116 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me, J. F. Opeka, who being duly sworn, did state that he is Executive 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 Licensae herein, and that the statements cr:dained in said information are true and correct to the best of his knowledge and belief, u J

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