ML20202H738

Forwards Request for Addl Info Re 981109 Submittal Requesting leak-before-break Approval for Millstone Nuclear Power Station,Unit 2

ML20202H738
Person / Time
Site:	Millstone
Issue date:	01/28/1999
From:	Stephen Dembek NRC (Affiliation Not Assigned)
To:	Bowling M NORTHEAST NUCLEAR ENERGY CO.
References
TAC-MA4126, NUDOCS 9902080213
Download: ML20202H738 (6)

Text

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January 28, 1999 1 '. Mr. Mirtin L. Bowling, Jr.

' R:cov:ry Officer - Technical S:rvices Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus

Director- Regulatory Affairs .

P.O. Box 128 Waterford, CT 06385 1

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SUBMITTAi.

REQUESTING LEAK-BEFORE-BREAK APPROVAL- MILLSTONE NUCLEAR POWER STATION, UNIT NO.' 2 (TAC NO. MA4126) .

Dear Mr. Bowling:

By letter dated November 9,1998, Northeast Nuclear Energy Company submitted a request for leak-before-break approval for the Millstone Unit 2 surge line. This approval was requested in response to Licensee Event Report 98-005-01 and was submitted to address concerns

- about the dynamic effects of pipe rupture in accordance with the provisions of General Design Criteria 4 of Title 10 of thw Code of Federal Regulations Part 50, Appendix A. In order to

, complete the staff's review of this issue, additionalinformation, as specified in the enclosure, is required.

In a January 19,1999, phone call, Mr. Ravi Joshi of your staff agreed to provide this information by February 1,1999. Should a situation occur that would prevent you from meeting this due date, please contact me at 301-415-1455.

Sincerely, Stephen embek, Project Manager Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

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1 y j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 400*

%,.....[ January 28,-1999 Mr. Martin L Bowling, Jr.

Recovery Officer - Technical Services -

, Northeast Nuclear Energy Company.

' c/o Ms. Patricia A. Loftus Director- Regulatory Affairs P.O. Box 128 -

, Waterford, CT 06385

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SUBMITTAL REQUESTING LEAK-BEFORE-BREAK APPROVAL- MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO. MA4126)

Dear Mr. Bowling:

By letter dated November 9,1998, Northeast Nuclear Energy Company submitted a request

' for leak-before-break approval for the Millstone Unit 2 surge line. This approval was requested in response to Licensee Event Report 98-005-01 and was submitted to address concems about the dynamic effects of pipe rupture in accordance with the provisions of General Design Criteria 4 of Title 10 of the Code of Federal Regulations Part 50, Appendix A. In order to complete the staff's review of this issue, additionalinformation, as specified in the enclosure, is required, in a January 19,1999, phone call, Mr. Ravi Joshi of your staff agreed to provide this information by February 1,1999. Should a situation occur that would prevent you from meeting this due date, please contact me at 301-415-1455.

Sincerely, Stephen Dembek, Project Manager Project Directorate 1-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

As stated cc w/ encl: See next page

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I * ' Millst:n2 Nucinr Pow;r Str. tion

/* ' Unit 2.

a ec:

Lillian M. Cuoco, Esquire Mr. F. C. Rothen Senior Nuclear Counsel Vice President - Nuclear Work Services ,

Northeast Utilities Service Company Northeast Utilities Service Company l P. O. Box 270 P. O. Box 128 -;

Hartford, CT 06141-0270 Waterford, CT 06385 1 2

Mr. John Buckingham Emest C. Hadley, Esquire

, Department of Public Utility Control 1040 B Main Street Electric Unit P.O. Box 549 10 Liberty Square ' West Wareham, MA 02576 I New Britain, CT 06051 l Mr. Raymond P. Necci Edward L. Wilds, Jr., Ph.D. Vice President - Nuclear Oversight .

Director, Division of Radiation and Regulatory Affairs g Department of Environmental Protection Northeast Utilities Service Company- l 79 Elm Street P. O. Box 128 l Hartford, CT 06106-5127 - Waterford, CT 06385 -  !

Regional Administrator, Region i Mr. John Carlin ,

U.S. Nuclear Regulatory Commission Vice President - Human Services l 475 Allendale Road Northeast Utilities Service Company King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmen Town of Waterford Mr. Allan Johanson, Assistant Director  !

15 Rope Ferry Road Office of Policy and Management Waterford, CT 06385 Policy Development and Planning i

, Division Mr. Wayne D. Lanning, Director 450 Capitol Avenue - MS# 52ERN Millstone Inspections P. O. Box 341441 l Office of the Regional Administrator Hartford, CT 06134-1441 475 Allendale Road King of Prussia, PA 19406-1415 Mr. M. H. Brothers i Vice President - Millstone Operations  !

Charles Brinkman, Manager Northeast Nuclear Energy Company

- Washington Nuclear Operations P.O. Box 128 ABB Combustion Engineering Waterford, CT 06385 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852 Mr. J. A. Price l Director - Unit 2  !

Senior Resident inspector Northeast Nuclear Energy Company )

Millstone Nuclear Power Station P.O. Box 128 I clo U.S. Nuclear Regulatory Commission Waterford, CT 06385 P.O. Box 513 Niantic, CT '06357

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' Millstone Nucle:r Power St tion Unit 2 k

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i Mr. Leon J. Olivier Chief Nucler Officer- f.lillstone Northeast Nuclear Energy Company  ;

- P.O. Box 128 i

Waterford, CT 06385 L Citizens Regulatory Commission -

i

; ATTN

. Ms. Susan Perry Luxton '

, 180 Great Neck Road ,

Waterford, CT 06385 -

Deborah Katz, President Citizens Awareness Network y .

. P. O. Bex 83 j Shelburne Falls, MA 03170 l

Ms. Terry Concannon -

Co-Chair

)- Nuclear Energy Advisory Council .  :

1 Room 4100 l Legislative Office Building

, Capitol Avenue Hartford, CT 06106

Mr. Evan W. Woollacott i Co-Chair )

., Nuclear Energy Advisory Council l

. 128 Terry's Plain Road Simsbury, CT 06070 -

% l I ~ Little Harbor Consultants, Inc.

- Millstone -ITPOP Project Office

P.' O. Box 0630 Niantic, CT 06357-0630 Mr. Daniel L. Curry Project Director Parsons Power Group Inc.

2675 Morgantown Road Reading, PA 19607 Attorney Nicholas J. Scobbo, Jr.

Ferriter, Scobbo, Caruso, Rodophele, PC 1 Beacon Street,11th Floor Boston, MA 02108 7

k REQUEST FOR ADDITIONAL INFORMATION MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336 1

The staff has completed an initial review of the information provided in the Northeast Nuclear

Energy Company's (NNECO's) November 9,1998, letter requesting approval of leak-before-

. break (LBB) status for the Millstone Unit 2 surge line. The following questions are based on the report from Structural Integrity (SI) Associates, Inc. (SIR-98-096), an enclosure to the November 9,1998, letter.

Question #1 - Material Specifications Page 4-1, Section 4.2 - kis implied that all sections of piping in the surge line are centrifugally case CF8M stainless steel. Confirm that this is true for the surge line elbows and provide documentation which supports this conclusion.

Question #2 - Loading Analysis The guidance that has been developed on Leak-Before Break by the NRC staff in NUREG-1061, Volume 3 and in Draft Standard Review Plan Section 3.6.3.

(DSRP 3.6.3) indicates that several sources of loading should be considered when evaluating leakage flaw and critical flaw sizes. These sources include intemal pressure, piping deadweight, thermal expansion, the safe shutdown earthquake (SSE), and seismic anchor motion. The intent of these loading analyses was to examine the loads which would cause a luakage flaw to open under normal operation (NOP) conditions and to examine the loads which could cause the critical flaw to fail under the assumed bounding case of (NOP+SSE).

When the guidance in NUREG-1061, Volume 3 and DSRP 3.6.3. was developed, application of LBB to pressurized water reactor (PWR) surge lines was not explicitly considered and the occurrence of thermal stratification in surge lines was not widely known. However, in reviewing other submittals to apply LBB to PWR surge lines, the NRC staff's position das been that like thermal expansion loads, loads due to thermal stratification must be considered.

Provide the following analyses to supplement your November 9,1998 submittal:

(1) Evaluate the impact of including the thermal stratification loads at normal operation (100 percent power) when determining the leakage flaw sizes (or explain why the assumptions made in your November 9 assessment l lead to a bounding ana!ysis). Provide the lo9ds (forces and moments) which were included in determining the leakage flaw sizes. If some of l

Enclosure 1

e the loading components (e.g. the deadweight loads) have not changed, simply reference the information previously submitted, but provide a summation of all loads which were included in this analysis.

(2) Evaluate the critical flaw sizes (considering both the criteria for a margin of 2 between the critical and leakage flaw sizes ansn the criteria based on a margin of (2 on the loads) when startup and cooldown thermal stratification loads are considered. This evaluation should consider the largest temperature differences which could develop between the reactor coolant system hot leg and the pressurizer based on a review station l l

startup and cooldown operating procedures.

)

However. because of the extremelv low crobability of havino an SSE concurrent with startuo or cooldown transients. it is not necessary to include the SSE loads in this analysis, i

As with question (1) above, provide the loads which were included in the l critica'i flaw size analysis and a summation of these loads. Also indicato I any other factors which were included in the analysis. For example, I when the time history of the startup or cooldown transient is evaluated, i consideration of the actual system temperature (and the resulting material temperature) at the time when the largest temperature difference occurs may be used to evaluate the materials' tensile and fracture properties. Altematively,if an analysis is proposed to bound the conditions which actually occur at any time in the startup or cooldown transient, explain why the assumptions made provide a bounding analysis.

Based on the NRC staff's independent evaluation of the material provided in the November 9,1998, submittal and the telephone conference between the NRC, NNECO, and SI Associates, Inc. on December 21,1998, the staff expects that the limiting LBB analysis location for the Millstone Unit 2 surge line will be at node 2,16, or 13. Your response to this question should, at a minimum, address these lccations, unless you identify another location which is more limiting in the course of your evaluation.

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