ML17157C484

Forwards Request for Addl Info Re 920615 Submittal of Licensing Topical Rept on Power Uprate

ML17157C484
Person / Time
Site:	Susquehanna
Issue date:	09/21/1993
From:	Clark R Office of Nuclear Reactor Regulation
To:	Byram R PENNSYLVANIA POWER & LIGHT CO.
References
PLA-3788, TAC-M83426, TAC-M83427, NUDOCS 9309270129
Download: ML17157C484 (7)

Text

September 21.

3 Docket Nos.

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

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION, LICENSING TOPICAL REPORT ON POWER UPRATE, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (PLA-3788)

(TAC NOS.

M83426 AND M83427)

Your letter of June 15, 1992 provided a licensing topical report and other submittals supporting an increase in licensed power level with increased core flow.

You have subsequently revised and updated the report in response to our comments and questions.

We do have a supplemental request for additional information identified as the Enclosure to this letter.

This requirement affects 9 or fewer respondents and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

If you have any questions, please contact me at (301) 504-1402.

Sincerely, 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

Enclosure:

Request for Additional Information cc w/enclosure:

See next page DISTRIBUTION:

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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 21, 1993 Docket Nos. 50-387 and 50-388 Mr. Robert G.

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION, LICENSING TOPICAL REPORT ON POWER

UPRATE, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (PLA-3788)

(TAC NOS.

M83426 AND M83427)

Your letter of June 15, 1992 provided a licensing topical report and other submittals supporting an increase in licensed power level with increased core flow.

You have subsequently revised and updated the report in response to o'ur comments and questions.

We do have a supplemental request for additional information identified as the Enclosure to this letter.

This requirement affects 9 or fewer respondents and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

If you have any questions, please contact me at (301) 504-1402.

Sincerely,

Enclosure:

Request for Additional Information cc w/enclosure:

See next page R

J.

C ark, Senior Project Manager Project Dir ctorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ENCLOSURE Request for Additional Information Licensing Topical Report for Power Uprate Susquehanna Steam Electric Station, Units 1 and 2

Docket Nos.

50-387 and 50-388 (Sections

3. 1)

For the power uprate, the number of SRV valve groups is reduced from five to three to prevent an increase in the number of unnecessary SRV actuations.

Provide a discussion on how the change in number of SRV groups from five to three affect the SRV dynamic loads regarding frequency,

content, amplitude and symmetry of load boundary.

(Section 3.3.2. 1)

Tables 3-1 and 3-2 show 'that the reactor internal pressure differential (RIPD) increase from 9X to 26X for the power uprate with increased core flow (ICF), in comparison to the original analysis.

However, the topical report stated that recalculated core loads and RIPDs decrease for power uprate with ICF because of the improved current fuel designs.

Please clarify.

(Section 3.3.2. 1)

LOCA dynamic loads consist of pool swell, condensation oscillation and chugging loads.

The licensee's evaluation concluded that all original LOCA dynamic loads, except pool swell, are bounding for power uprate.

Provide a discussion on how the increase in pool swell dynamic loads for the power uprate affect the design basis analyses of the reactor internals and the reactor coolant piping.

(Section 3.3.2.2)

The licensee concluded that the reactor internals response to flow-induced vibration for the power uprate with ICF will remain within acceptable limits, based on the comparison of valid prototype vibration data and SSES test data.

Provide a detailed discussion regarding the effects of power uprate with ICF on flow-induced vibration, and how the valid prototype vibration data and SSES test data were used for the SSES power uprate conditions.

Also, provide locations of the critical low-frequency components, the maximum fluid-elastic instability ratio, and cumulative fatigue usage for the uprated conditions.

(Section 3.5. 1)

The licensee's evaluation was rather conclusory and lacked adequate technical basis.

Provide a detailed discussion regarding the evaluation of pipe supports, equipment nozzles, and in-line components for the power uprate, and summary of results in comparison to the existing design allowable.

(Section 3.5.2. 1) It appears that the licensee did not perform detailed evaluation, but rather, suggested that BOP piping systems will be acceptable by methods as stated in this section.

Provide a description and results of evaluations that were performed, regarding compliance with the code of record.

Please also discuss the SRV discharge lines evaluation, considering an increase of pool swell velocity for the power uprate condition with increased core flow.

~REFERERC:

Pennsylvania Power Ik Light Company, "Susquehanna Steam Electric Station Units 1 and 2 Licensing Topical: Report for Power Uprate with increase Core Flow,"

NE-092-001, Revision 0, June 1992.

1V Hr. Robert G.

Byram Pennsylvania Power

& Light Company Susquehanna Steam Electric Station, Units 1

& 2 CC:

Jay Silberg, Esq.-

Shaw, Pittman, Potts

& 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 Hr. J.

H. Kenny Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.

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

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

212 Locust Street P.O.

Box 1266 Harri sbur g, Pennsyl vani a 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hr. 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

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