ML20245L240

Application for Amends to Licenses DPR-61 & NPF-49, Clarifying Tech Specs Re Steam Generator Tube Insp Criteria. Change Would Add Cold Leg Side as Alternate Point of Entry

ML20245L240
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	06/29/1989
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245L245	List: B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes ML20245L240
References
B13221, NUDOCS 8907050418
Download: ML20245L240 (5)

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, UMN General Offices

• Selden Street, Berlin, Connecticut I w srs vs a e F.O. BOX 270

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HARTFORD, CONNECTICUT 06141-0270 k k J 7.s $$7i ,$'.~', (203) 665-5000 June 29, 1989 Docket Nos. 50-213 50-423 B13221  !

Re: 10CFR50.90 i U.S. Nuclear Regulatory Commission Attention: Document Control Desk ,

Washington, DC 20555 Gentlemen:

Haddam Neck Plant Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications  ;

Steam Generator Tube Insoection Acceptance Criteria l Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPC0) and Northeast Nuclear Energy Company (NNECO) hereby propose to amend operating licenses, DPR-61 and NPF-49 by incorporating the changes identified in Attachments I and II into the Technical Specifications of the Haddam Neck Plant and Millstone Unit No. 3, respectively.

The proposed change would clarify the intent of Technical Specification Section 4.10.1.D.1.h for the Haddam Neck Plant and 4.4.5.4.a.8 for Millstone Unit No. 3 regarding the extent and origination point of steam generator tube examinations. The existing technical specification calls for examination of steam generator tubing originating from the hot leg side. The proposed change would add the cold leg side as an alternate point of entry.

The proposed chag e will allow steam generator tube inspections performed from either the hot leg side or the cold leg side to the tube end on the opposite side to be considered valid tube inspections. The proposed change will also optimize the inspection pattern to minimize inspection time and personnel radiation exposure.

l The intent of Regulatory Guide 1.83 (as it applies to this proposed change) is i to ensure that the hot leg and U-bend segments of the tube will be inspected.

I lhe proposed change will meet this intent. Inspection of the hot leg and U-bend tube segments can be accomplished from either the hot leg side or cold leg side. From the cold leg, the probe must be inserted through the tube to the hot leg tube end to accomplish this coverage. From the hot leg side, the probe must be inserted to at least the highest cold leg support. Therefore, an inspection from either the hot leg side or cold leg side to the tube end on the opposite leg will provide the coverage specified by Regulatory Guide 1.83.

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1 s . l U.S. Nuclear Regulatory Commission l B13221/Page 2 l June 29, 1989 i 4

The choice of entry side has no adverse effect on the inspection capability or i result. Eddy current probe response to imperfections is not dependent on the entry side selected. Therefore, inspections performed from the hot leg side are equivalent to inspections performed from the cold leg side.

CYAPC0 and NNEC0 have reviewed the proposed change in accordance with the requirements of 10CFR50.92 and have determined it does not involve a signif-icant hazards consideration. Specifically, the proposed change does not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change will allow an alternate method for meeting the intent of Regulatory Guide 1.83 that a tube inspection include the hot leg and U-bend segments. The  !

change will allow tube inspections to be performed by inserting the probe into either the hot leg or cold leg side of the steam genera-tor. The requirement that the tube be inspected from the hot leg side completely around the U-bend to the top support of the cold leg i is not changed, and the inspections will continue to meet the intent {

of Regulatory Guide 1.83. Therefore, there can be no impact on the i consequences of any accident and since the ability to detect steam generator tube degradation is not affected, there is no increase in probability of a steam generator tube rupture.

2. Create the possibility of a new or different kind of accident from any 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. Thus, a different I type of accident is not possible.

3. Involve a significant reduction in any margin of safety. As dis- ,

cussed above, the change has no impact on the consequence's of any accident previously analyzed. Furthermore, since no changes are proposed to any acceptance criteria related to tube defects, there  ;

is no impact on the integrity of the reactor coolant pressure  !

boundary. j Moreover, the Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (51FR7751, March 6,  ;

1986) that are considered not likely to involve a significant hazards consid- (

eration. While the change proposed herein is not enveloped by a specific l example, CYAPC0 and NNEC0 have determined that the proposed change doos not '

involve a significant hazards consideration, in that the proposed change clarifies the technical specification of a valid examination technique. i Based upon the information contained in this submittal and the environmental assessment for the Haddam Neck Plant and Millstone Unit No. 3, there are no significant radiological or nonradiological impacts associated with the proposed action, the proposed license amendment will not have a significant effect on the quality of the human environment.

U.S. Nuclear Regulatory Commission B13221/Page 3 June 29, 1989 i

The Haddam Neck Plant and Millstone Unit No. 3 Nuclear Review Boards have reviewed and approved the attached proposed revision and have concurred with the above determinations.

It should be noteJ that a similar license amendment was granted by the NRC on January 3, 1989 for Millstone Unit No. 2.

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

Issuance of the license amendment is requested at your earliest convenience for Millstone Unit No. 3, at which time it can become effective immediately.

Issuance of the license amendment for the Haddam Neck Plant is requested by September 1, 1989, at which time it can become effective immediately. If this proposed change is issued prior to the start of the next refueling outage at the Haddam Neck Plant (currently scheduled for September 3, 1989), it would aid the steam generator tube inspection and repair effort planned during the refueling outage.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY l

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E. J. Np6czka y' Senior Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant D. H. Jaffe, 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 J Hartford, Connecticut 06116 i

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U.S. Nuclear Regulatory Commission B13221/Page 4 l June 29, 1989 STATE OF CONNECTICUT)

) ss. Berlin COUNTY OF HARTFORD )

1 Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company and Connecticut Yankee Atomic Power Company, Licensees herein, that he is author-ized to execute and file the foregoing information in +he name and on behalf of the Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.

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N6taryPuby ,

MyCommission Expkes March 31,199 i

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Docket Nos. 50-213 B13221

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Attachment I Haddam Neck Plant Proposed Revision to Technical Specifications i

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