ML17157C418

Forwards Request for Addl Info to Conclude Review of Licensee 920708 Response to NRC GL 92-01, Rv Structural Integrity

ML17157C418
Person / Time
Site:	Susquehanna
Issue date:	07/14/1993
From:	Clark R Office of Nuclear Reactor Regulation
To:	Byram R PENNSYLVANIA POWER & LIGHT CO.
References
GL-92-01, GL-92-1, TAC-M83518, TAC-M83519, NUDOCS 9308030365
Download: ML17157C418 (6)

Text

July 14, 1993 Docket Nos.

50-387 and 50-388 Hr. Robert G.

Byram Senior Vice President Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 ISTfQBlKIO

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SUBJECT:

GENERIC LETTER 92-01, REVISION 1 (PLA-3804),

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, (TAC NOS.

M83518 AND H83419)

Your letter of July 8,

1992, provided your response to NRC Generic Letter 92-01, "Reactor Vessel Structural Integrity."

To complete our review, we are requesting clarification on several items as enumerated in the enclosed request for additional information.

This request is specific to the Susquehanna reactor vessels.

The request affects fewer than 10 respondents and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.

Sincerely,

Enclosure:

Request for Additional Information cc w/enclosure:

See next a

e Original signed by Richard J. Clark Richard J. Clark, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation OFC PDI-2 PDI-2 D

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+~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 July 14, 1993 Docket Nos.

50-387 and 50-388 Hr. Robert G.

Byr am Senior Vice President - Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

SUBJECT:

GENERIC LETTER 92-01, REVISION 1 (PLA-3804),

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, (TAC NOS.

H83518 AND H83419)

Your letter of July 8, 1992, provided your response to NRC Generic Letter 92-01, "Reactor Vessel Structural Integrity."

To complete our review, we are requesting clarification on several items as enumerated in the'nclosed request for additional information.

This request is specific to the Susquehanna reactor vessels.

The request affects fewer than 10 respondents and, therefore, is not subject to the Office of Hanagement and Budget review under P.L.96-511.

Sincerely,

Enclosure:

Request for Additional Information ark, Senior Project Hanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosure:

See next page

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION RELATING TO GENERIC LETTER 92-01 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 DOCKET NOS.

50-387 AND 50-388 Sus uehanna Unit 1

uestion 2a in GL 92-01 The response to Generic Letter (GL) 92-01 indicates that the end-of-life (EOL) upper-shelf energy (USE) for the limiting beltline material is 70.8 ft-lb.

From a previous submittal (dated May 20, 1981) that provided material data for NRC review of Safety Evaluation Report (SER) issues 21, 22, 23, and 24, measured values of USE were absent for all beltline materials and the EOL USE of 70.8 ft-lb was reported based on an initial USE of 81 ft-lb derived from plate USE data associated with other plants.

A topical report, NED0-32205, titled "BWR Owners'roup Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by General Electric (GE) Corporation on April 30, 1993.

You must either confirm that this topical report will be used as the licensing bases or provide a plant-specific approach to demonstrate that all beltline materials that do not have measured USE will meet the requirements of Appendix G, 10 CFR Part 50.

uestion 2b in GL 92-01 The response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial RTw~ determination.

An alternative method develo'ped by GE was used in deriving the initial RTwe for these materials.

In the GE method, the establishment of the slope for the transition zone of the Charpy curve is crucial in deriving the initial RT~~

from incomplete test data.

Provide all plate and weld Charpy test curves compiled by GE for establishing the 2'F per ft-lb slope for the transition zone of the Charpy curve.

All test data must be from materials equivalent to (i.e.

same vendor, fabrication time frame, fabrication process, material specification, etc.) the beltline materials of this reactor vessel.

Sus uehanna Unit 2 uestion 2a in GL 92-01 The response to GL 92-01 indicates that the EOL USE for the limiting beltline material is 53.7 ft-lb.

From a previous submittal (dated October 3, 1983) that provided material data for NRC review of SER issue number

112, measured USE values were absent for all beltline materials and the EOL USE of 53.7 ft-lb was based on an initial USE of 61 ft-lb derived from three of the six beltline plates.

In

addition, that report also indicated that the initial USE for welds is greater than 75 ft-lb based on cited USE values from three plants.

A topical report, NED0-32205, titled "BWR Owners'roup Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by GE on April 30, 1993.

The licensee must either confirm that this topical report will be used a

s its licensing bases or provide its plant-specific approach to demonstrate that all beltline materials that do not have measured USE will meet requirements of Appendix G,

10 CFR Part 50.

uestion 2b in GL 92-01 The test data requested above for Unit 1 is also requested for the Unit 2 reactor vessel.

Mr. Robert G.

Byram Pennsylvania Power 5 Light Company Susquehanna Steam Electric Station, Units 1 5 2 CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts

5. Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.

Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Vice President-Nuclear Operations Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101