ML18102A707

Forwards Radial Peaking Factor Limit Rept for Tenth Cycle of Operation Which Includes Limits for Rated Thermal Power for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes

ML18102A707
Person / Time
Site:	Salem
Issue date:	12/23/1996
From:	Eric Simpson Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N96400, NUDOCS 9701020226
Download: ML18102A707 (5)

Text

Public Service Electric and Gas

' Company E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - Nuclear Engineering DEC 2 3 1996 LR-N96400 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SALEM GENERATING STATION UNIT NO. 2 CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 Gentlemen; In accordance with Salem Generating Station (SGS) Unit 2 Technical Specification 6.9.1.9, Public Service Electric and Gas Company (PSE&G) hereby submits the Radial Peaking Factor Limit Report for the tenth cycle of operation (Attachment 1 ). This report includes the radial peaking factor limits for rated thermal power for all core planes containing Bank "D" control rods and all unrodded core planes. It also includes the plot and limit envelope of predicted heat flux hot channel factor multiplied by relative power, vs. axial core height.

Should you have any questions regarding this report, please contact us.

Attachment ( 1 )

9701020226 961223 PDR ADOCK 05000311 p

PDR IJ>t. Printed on

~

Recycled Paper

Document Control Desk LR-N96400 2

C:

Mr. H. Miller, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 DEC 2 3 1996

Document Control Desk LR-N96400 3

DWD/

BC Senior Vice President - Nuclear Operations (X04)

Senior Vice President - Nuclear Engineering (N19)

General Manager - Salem Operations (SOS)

Director - QA/NSR (X01)

Manager - Business & Co-Owners Affairs (N18)

Onsite Safety Review Engineer - Salem (S12)

General Solicitor, E. Selover, Jr. (Newark, SG)

Perry Robinson, Esq.

Records Management (N21)

Microfilm Copy File Nos. 1.2.1 M. Mannion (N20)

DEC 2 3 1996

ATTACHMENT 1 TO LR-N96400 SALEM GENERATING STATION UNIT 2 RADIAL PEAKING FACTOR LIMIT REPORT DEC 2 3 1996 This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.

The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 10 shall be:

1.

For all core planes containing Bank "D" control Rods:

FxyRTP ~ 2.05 for all core elevations (INCORE axial points 1 through 61, inclusive).

2.

For all unrodded planes:

Fxy RTP ~ 1.69 for all core elevations (INCORE axial points 1 through 61, inclusive).

These Fxy (z) limits were used to confirm that the heat flux hot channel factor Fa(z) will be limited to the Technical specification values of:

Fa (z) ~ [2.32/P]

[K(z)]

for P > 0.5, and Fa (z) ~ [4.64]

[K(z)] for P ~ 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banks C and D during operation, including the accompanying variation sin the axial xenon and power distributions as described in the "Power Distribution Control and Load Follow Procedures", WCAP-8385, September, 197 4. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 1 OCFR50.46.

See Figure 1 for a plot of [Fa T *Pre1] versus Axial Core Height.

1OF2

2.6 2.4

. 2.2

,.. M

[J c

2.0

~

a..

u

• I-1.8 r:::r LL. -

~

E 1.6 1.4 a 1.2 1.0 0 2

.ATTACHMENT 1 TO LR-N96400.

SALEM GENERATING STATION UNIT 2 RADIAL PEAKING FACTOR LIMIT REPORT Maximum (FqT*Prel) versus Axial Core Height During Normal Core Operation I 6, 2.321 r---....... ~

~

DEC 2 3 1996 HO.B, 2.1a l

- :']L.

ur -

u L..,_

u_

~-

II II

- *- n--* l

~

l

~

\\,

12, 1.s l-4 6

8 10 12 Core Height (feet) 2 OF 2