ML17157A849

Forwards Staff Comments,Requesting Addl Info Re Licensee 910418 Request for Change to TS of RSC pressure-temp Limits for Facility

ML17157A849
Person / Time
Site:	Susquehanna
Issue date:	09/10/1991
From:	Raleigh J Office of Nuclear Reactor Regulation
To:	Keiser H PENNSYLVANIA POWER & LIGHT CO.
References
TAC-80224, TAC-80225, NUDOCS 9109180126
Download: ML17157A849 (6)

Text

Docket Nos.

50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Al1 entown, Pennsy 1 vani a 18101

Dear Mr. Keiser:

September 10, 1991 DISTRIBUTION:

-NRC

& Local PDRs PDI-2 Reading SVarga JCalvo WButler MO'Brien(2)

JRaleigh OGC EJordan 3701 ADRS(10 Rg lough, RGN-I

JWhite, RGN-I

CYCheng, 7D-4

SSheng, 7D-4

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED CHANGES TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO THE REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE (P-T) LIMITS (TAC NOS. 80224 AND 80225)

The staff has reviewed the request that was made by Pennsylvania Power and Light Company (PPIIL or the licensee) of April 18, 1991 to change the technical specifications of the reactor coolant system P-T limits.for the Susquehanna Steam Electric Station (SSES), Unit Nos.

1 and 2.

Based on this review, we have concluded that further information is required.

As a result of the review, the staff has developed comments which form the basis of this request for additional information.

These comments are provided in the enclosure.

If there are any questions regarding this letter please contact me on (301) 492-1447.

This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget Review under P.L.96-511.

S in cere ly,

/S/

James J. Raleigh, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Staff Comments cc w/enclosure:

See next page I:c NAME

M

DI-2/P

JRAI IEG

P~2 lc

WBUTLER DATE V91

'//11/91 BF ETR REEDRD DDPV Document Name:

RFI SU PT LIMITS o/9 9109180126 910910 PDR POR ADOC)C O>OOOO~7 QFo

II I

n t

4

gp,S Racy Wp C

0 C

00

~O

+***+

Docket )los.

50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 10, 1991 Hr. Harold M. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

SUBJECT:

REQUEST'OR ADDITIONAL INFORMATION ON THE PROPOSED CHANGES TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO THE REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE (P-T) LIMITS (TAC NOS. 80224 AND 80225)

The staff has reviewed the request that was made by Pennsylvania Power and Light Company (PPKL or the licensee) of April 18, 1991 to change the technical specifications of the reactor coolant system P-T limits for the Susquehanna Steam Electric Station (SSES),

Unit Nos.

1 and 2.

Based on this review, we have concluded that further information is required.

As a result of the review, the staff has developed comments which form the basis of this request for additional information.

These comments are provided in the enclosure.

If there are any questions regarding this letter please contact me on (301) 492-1447.

This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Nanagement and Budget Review under P.L.96-511.

Sincerely,

Enclosure:

Staff Comments cc w/enclosure:

See next page James J. Raleigh, Project IIanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Mr. Harold W. Kei ser Pennsylvania Power

& Light Company Susquehanna Steam Electric Station Units 1

& 2 CC:

Jay Si lberg, 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 Al1entown, Pennsylvania 18101 Mr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power

& 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. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.

Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Mr. S.

B. Ungerer Joint Generation Projects Department Atlantic Electric P.O.

Box 1500 1199 Black Horse Pike Pleasantvi lie, New Jersey 08232 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwi ck, Pennsylvania 18603 Mr. Robert G. Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsy 1vani a 18101

4

~

~

~

~

I

~

~

~

~

ENCLOSURE Staff Comments regarding proposed revisions to the Susquehanna Steam Electric Station Technical Specification Requireme'nts related to the reactor coolant system pressure Temperature (P-T) limits (Docket Nos.

50-387 and 50-388)

The staff has completed the preliminary review of the proposed changes and requests the following additional information regarding the calculation of non-beltline P-T limit curves presented in document SASR 89-40.

Calculatio o

rimar membrane and bendin stresses due to ressure and i in load

1. Equation (4-3) in SASR 89-40 suggests that the stress intensity factor K, for the feedwater nozzle under the "heatup/cooldown" condition is calculated through the determination of M

value, which implies the use of Fig. G-2214-1 in Appendix G of ASME Code,Section III in the calculating procedure.

However, equation (4-

1) in the same report suggests another way to calculate K, due to pressure and piping loads under the "pressure test" condition.

Justify the use of different equations for the same mechanics problem.

2.

For an assumed

pressure, say 500 psi (or convenience),

supply the numerical values parameters, M,,

, 4>, <-, and a,~ appeared in identify the documents these numbers are cited any value of your of the following equation (4-3) and from.