ML18106A582

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Provides Suppl Response to NRC Bulletin 96-01,as Committed to in 980408 Ltr.Response Contains Relevant Control Rod Drag Force Testing,Summary of Control Rod Drop Testing,Location of Each Assembly in Core,Control Rod Drop Time & Recoils
ML18106A582
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/28/1998
From: Eric Simpson
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, LR-N980208, NUDOCS 9805060316
Download: ML18106A582 (9)
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Text

{{#Wiki_filter: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 APR 2 8 1998 LR-N980208 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Ladies and Gentlemen: SUPPLEMENTAL INFORMATION IN RESPONSE TO BULLETIN 96-01 SALEM GENERATING STATION UNIT N0.1 DOCKET NO. 50-272 Public Service Electric and Gas (PSE&G) committed in letter LR-N96093 dated April 8, 1996, that a supplemental response to Bulletin 96-01 would be submitted within 30 days of completing control rod testing during the current unit restart activities. This supplemental response would include a summary of the testing data and verification of control rod operability. Attachment 1 contains the relevant control. rod drag force testing for Salem Unit .

1. Attachment 2 contains a summary of the control rod drop testing for Salem Unit 1 which includes the Beginning of Cycle (BOC) and End of Cycle (EOC) average assembly burn up distributions, the location of each assembly in the core, the control rod drop time, and number of recoils for each assembly.

As stated in the April 8, 1996 letter, based upon a historical review of reactor trip data for the past five years and rod drop testing for the last fuel cycle, all control rod were operable up to the current plant shutdowns for the Salem Units. Based on the rod drop testing data provided in Attachment 1 and 2, PSE&G has determined that the Salem Unit 1 control rods continue to maintain their operability. 

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  • 2 LR-N980208 If you have any questions concerning the above information, please do not hesitate to contact us.

C Mr. Hubert J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD

  • 20852 Mr. S. Morris (X24)

USNRC Senior Resident Inspector - Salem Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625 95-4933

ATTACHMENT 1 LR-N98208 

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  • 9.2.3 ATTACHMENT (3)

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SALEM

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SALEM Gb'NERATING STATION 

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ATTACHMENT 2 LR-N98208

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  • SALEM UNIT 1CYCLE13 "INITIAL HOT ROD DROP TIME DATA w.o. 950106135, 950727015 RCCA, '
  • Projected Drop
  • 4/15/98 Position Core BOC EOC Time No. of ID Location Burnup (MWD/MTU) Burnup (MWD/MTU) (Sec.) Recoils 1SA1 D4 15370 38265 1.33 6 1SA2 D12 15370 38265 1.33 6 1SA3 M12 15370 38265 1.34 6 A ,;?-.//7 1SA4 M4 15370 38265 1.35 5 ~ffJW:A.F!

2SA1 G5 . 24428 43166 1.35 4 Prepar~M 2SA2 E9 24428 43166 1.34 5 2SA3 J11 24428 43166 1.33 4 (\ 2SA4 L7 24428 43166 1.36 4 [ \-._ .01.Jt '1iJT r. )' N 1SB1 G3 15374 37070 1.34 6 ) Chcecked by Q 1SB2 C9 15374 37070 1.34 7 1SB3 J13 15374 37070 1.34 6 1SB4 N7 15374 37070 1.33 7 2SB1 C7 15328 37019 1.36 6 NOTE: Drop Time is 2SB2 G13 15328 37019 1.36 5 from Rx Trip Breaker 2SB3 N9 15328 37019 1.34 8 Shunt Coil energized 2SB4 J3 15328 37019 1.33 6 to Dashpot enty. 1SC1 H2 15910 35278 1.35 8 1SC2 BB 15910 35278 1.37 8 1SC3 H14 15910 35278 1.35 7 1SC4 PB 15910 35278 1.37 6 1801 F6 11354 34965 1.36 7 1802 F10 11354 34965 1.35 8 1803 K10 . 11354 34965 1.36 8 1804 K6 11354 34965 1.34 8 1A1 E3 19553 41240 1.32 6 1A2 C11 19553 41240 1.34 7 1A3 L13 19553 41240 1.33 6 1A4 N5 19553 41240 1.34 7 2A1 C5 19541 41184 1.37 7 2A2 E13 19541 41184 1.38 5 2A3 N11 19541 41184 1.37 8 2A4 L3 19541 41184 1.35 5 1B1 DB 15154 34213 1.34 5 1B2 MB 15154 34213 1.33 6 2B1 H4 15154 34213 1.32 5 2B2 H12 15154 34213 1.32 6 1C1 C3 0 17668 1.36 7 1C2 C13 0 17668 1.35 7 1C3 N13 0 17668 1.35 8 1C4 N3 0 17668 1.36 8 2C1 H6 14751 36981 1.33 8 2C2 FB 14751 36981 1.34 6 2C3 H10 14751 36981 1.33 7 2C4 KB 14751 36981 1.36 8 101 F2 13240 33237 1.39 6 102 B10 13240 33237 1.38 6 103 K13 13240 33237 1.38 5 104 P6 13240 33237 1.38 6 201 B6 13208 32979 1.38 6 202 F14 13208 32979 1.39 5 203 P10 '13208 32979 1.37 7 204 K2 13208 32979 1.39 5 205 HS 15167 38699 1.35 5 S:\RXENG\DOC\1C13RDTD.XLS Page 1}}

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