ML18018B972

Responds to NRC 850325 Request for Addl Info Re Responses to Generic Ltr 83-28.Reactor Trip Sys Components Reviewed & Identified as safety-related on Component Level Q-list

ML18018B972
Person / Time
Site:	Harris
Issue date:	05/31/1985
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
GL-83-28, NLS-85-186, NUDOCS 8506060496
Download: ML18018B972 (33)

Text

REGUL, INFORMATION DISTRIBUT YSTEM (RIDS)

ACCESSION NBR 5 8506060496 DOC ~ DATE t 85/05/31 NOTARIZED! NO DOCKEiT' FACIL:50 000 Shear on Har ii ris Nucl ear~ Power Pl anti Uni t- Car ol ina 05000400 AUTH ~ NAME>> AUTHOR AFFILIATION

'ZIMMERMANpS,R. Carolina Power 8 Light Co ~

RECIP ~ NAME>> RECIPIENT AFFIL'SATION, DENTON H-,RE Office>> of Nuclear Reactor Regulationr Director n

SUBJECT!= Responds to NRC 850325 request for addi, info .re responses to Generic Ltr 83. 28 'eactor 'trip sys components rev{ewed 8 identified as safety related on- component level Q lists DISTRIBUTION CODE! A055D. COPIES RECEIYED:LTR 'NCL 'IZE'.

TITLE'i OR/Licensing Submittal: Salem ATHS Events GL-83. 28 NOTES!

RECIPIENT >>COPIES RECIPIENT COPIES ID>> CODE/NAME( LTTR ENCL ID CODE/NAME" LVTR ENCL NRR LB3>> BC 01 '3 3 INTERNAL: ACRS 6 6 ADM/LFMB 0 ELD/HDS1 1 0 IE/DI 1 IE/DQAVT 1 1 NRR/DE/EQB 1-NRR/DE/MEB 1 1 NRR/DHFS/HFEB 1 NRR/DHFS/LQB 1 1 NRR/DL DIR 1=

NRR/DL/GRAB 1 1 NRR/DL/SSPB 1 NRR/'L/TAPMG 1 1 NRR/DS I/ASB 1 NRR/DSI/ICSB 2 2 N "/PS B 1 NRR/DS I/RSB 1 1 G FIL 00 1-RONa 1 1 EXTERNAL': 24X 1 1 LPDR 03 NRC; PDR, 02 1 1 NSIC 05 TOTAL NUMBER OF COPIES REQUIRED'TTR 32'NCL>> 30

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'I CNK Carolina Power 8 Light Company SERIAL: NLS-85-186 MAY 31 $ 85 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO.50-000 GENERIC LETTER 83-28 REQUEST FOR ADDITIONALINFORMATION RESPONSES

REFERENCE:

March 25, 1985 letter from George W. Knighton (NRC) to Mr. E. E. Utley (CPdcL)

Dear Mr. Denton:

Carolina Power R Light Company (CPttrL) encloses for your review our responses to the request for additional information supplied by the NRC Staff via the referenced letter.

Carolina Power R Light Company considers this information sufficient to resolve this issue. If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, S. mmerman Manager Nuclear Licensing Section SRZ/GAS/mf (1531GAS)

Enclosure Cct Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Mr. D. Lasher (NRC-RRAB) Mr. 3. L. Kelley (ASLB)

Wake County Public Library 411 Fayettevilte Street 0 P. O. Box 1551 o Raleigh, N. C, 27602 8506060496 85053i PDR ADDCK 05000400 A PDR+

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Question Item 2.1(part 1) - Incomplete Supply a statement confirming that reactor trip system components were reviewed and that they are identified as safety-related on documents, procedures, and information handling systems.

Response

The reactor trip system components were reviewed and they are identified as safety-related on the component level Q-list. This Q-list is used as input for plant documents, procedures and information handling systems. A copy of the reactor protection system and rod control system portions of the Q-list is provided for your information (Attachment 1). The reactor trip and bypass breakers are included on the rod control system portion of the Q-list and are shown as Q-Class "A", or safety-related. Q-Class "E" components are non-safety related. "For further information on preparation and control of component level classification, refer to the response to Item 2.2.1.

(1531GAS/Alf )

1 CPL&L CP EQUIPMENT DATA BASE SYSTEM PAGE 293 RUN DATE~05/14/85 QUALITY LIST REP E888-01 RUG T IMF. 13. 24. 52 DELIVER TO 17C5 HARGETT PLANT 03 5 UNIT SYSTEM SYSTEM NAME 6 EQUIPh'IENT CODE EQUIPMENT DESCRIPTION 7 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBFR 8

9 I 1080 REACTOR PROTECTION SYSTEM+

10 DFG SOLID STATE PROTECTION CABINET ll A A TRAIN A l2 A 8 TRAIN 8 13 DFH SAFEGUARDS TEST CABINET l4 A TRAIN A I5 8 TRAIN 8 16 DFL AUXILLIARY RELAY RACKS 17 AUX RELAY RACKS I8 2 AUX RELAY RACKS 19 3 AUX RELAY RACKS 20 DFM TRIP STATUS LIGHT BOX 21 STEAM GENERATORS 22 STEAM GENERATORS & TURBINE 23 REACTOR COOLANT SYSTEM 24 NIS & CONTAINMENT PRESSURE 25 OFN SWITCH. CONTROL MODULE ELECTROSWITCH TYPE 26 CS-SLIISAB STEAMLINE ISOLATION II 27 Cs-SLISAB STEAMLINE ISOLATION I 28 Cs-SLSLRA STEAMLINE ISO. RESET TRAIN A 29 CS-SLSLRB STEAMLINE ISO. RESET TRAIN 8 30 CS- 1008SA STEAMLINE S.I. BLOCK RESET A 31 Cs-100858 STEAMLINE S.I. BLOCK RESET 8 32 . Cs-141SA PRZR PRES. S. I. BLOCK RESET TR-A 33 CS-14158 PRZR PRES. S. I. BLOCK RESET TR-8 34 CS-455. 1SA S. I. RESET TRAIN A MCB 35 CS-455.2SA S. I. RESET TRAIN A ACP 36 CS-455.3SB S.I. RESET TRAIN 8 MCB 37 CS-455.458 S.I. RESET TRAIN 8 ACP 38 CS-810SA F.W. ISO. BYPASS VALVES RESET A 39 CS" 810SB F.W. ISO. BYPASS VALVES RESET 8 40 CS-88SA N33A SOURCE RANGE BLOCK RESET 41 -A Cs-88SB N338 SOURCE RANGE BLOCK RESFT 42 A CS-89. ISA N38A INTERMEDIATE RANGE BLOCK 43 n CS-89. 158 N388 INTERMEDIATE RANGE BLOCK 44 A CS-89.2SA N47A POWER RANGE BLOCK 45 A Cs"89.2SB N478 POWER RANGE BLOCK 46 h CS-92. 1SAB SWITCH //1 REACTOR TRIP/CLOSE 47 n CS-92.2SAB SWITCH // I S. I . ACTUATION 48 A CS-94. 1SAB SWITCH //2 REACTOR TRIP 49 A CS-94.2SAB SWITCH //2 S. I. ACTUATION 50 DLX 8 REAKER, 120VAC INSTRUMENTATION CIRCUIT 51 1A-51 "3 SAFEGUARDS TEST CAB. A 52 5:l 54 55 56 57 58 59

$0 FOAM 0I13 I02/83) 1583

h CPLSL CO EQUIPMENT DATA BASE SYSTEM PAGE 294 Ri/N DATE 05/i4/85 QUALITY LIST REP EB88-01 RUN TIME 13.24.52 DELIVER TO 17CS HARGETT PLANT 03 UNIT SYSTEM SYSTFM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1080 REACTOR PROTECTION SYSTEMh 10 OLX BREAKER,120VAC INSTRUMENTATION CIRCUIT 11 1A-51-7 RPS CHAIN I TRAIN A 12 1A-S 1 "8 RPS CHAIN I TRAIN B 13 A 1A-53"7 RPS CHAIN III TRA1N A 14 A 1A-53-8 RPS CHAIN III TRAIN B 15 h 18-52-7 RPS CHAIN II TRAIN h 1G A 16-52-8 RPS CHAIN I I TRAIN B 17 h 18-54-3 SAFEGUARDS TEST CAR. R 18 A 1B-S4-7 RPS CHAIN IV TRAIN A 19 h 18-54-8 RPS CHAIN IV TRAIN 8 20 OMA SWITCH, CONTROL MODULE ELECTROSWITCH TYPE 21 cs-458. isn RWST S. I . RESET TRAIN A 22 CS-458.258 RWST S. I . RESET TRAIN 8 23 FhiZ BREAKER,120V POWER PANEL 24 10212- 16 AUX REALY RACK //2 25 102 12- 18 nux RELAY RhcK //i 26 1E212-21 TSLB-4 8 BPLB 27 1E212-23 TSLB-3 28 1E212-25 TSLB- 182 29 FKA BREAKER, 120V UNINTERRUPT PANEL 30 18-2 AUX RELAY RACK //1 31 IZP 120 VAC FUSED SWITCH 32 UPP-1-17 FUSED SWITCH 33 34 35 38 37 38 39 40 41 47 43 45 4G 47 48 49 50 5>

52 53 54 55 50 57 58 59 80 I Al>th Ilh h'I <Ilhlflhl 1584

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iQ A uc 6 cw CPL&L CO EQUIPMENT DATA BASE SYSTEM PAGE 2 RUN DATE 05/23/85 QUALITY LIST REP EB88-01 RUN TIME 17.34.53 DELIVER TO CPB 7CS G. SINDERS PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1065 , OD C NTROL Y TEM 10 CQY BREAKER, 480V AUX. BUS 11 1D2-6D MG SET MOTOR 1A 12 1E2-2A MG SET MOTOR 18 13 DFV BREAKER, DC DISTRIBUTION PANEL 14 DP-1A-SA-18 GENERATOR OUTPUT 1A 15 DP-1A-1-18 SERVES ROD DRIVE PWR SUPPLY CUB 1 16 DP-1A-2-18 SERVES ROD DRIVE PWR SUPPL CUB 2 17 OP-18-58-18 . GENERATOR OUTPUT 1B 18 LES INDICATOR, SPEED MCB-1C 19 SI-408 INDICATOR, SPEED MCB-1C 20 LEU SWITCH, MOTOR DISCONNECT 21 102-6D SWITCH, MOTOR DISCONNECT 22 1E2-2A SWITCH, MOTOR DISCONNECT 23 LEV REGULATOR, VOLTAGE 24 1A ROD DRIVE VOWER SUPPLY CUB 25 1B ROD DRIVE POWER SUPPLY CUB 2 26 LEW SHUNTS, AM & REV. CURR RELAY, 1200A, SMV 27 1AA SHUNTS, AM & REV. CURR RELAY, 1200A, SMV 28 1AB SHUNTS, AM & REV. CURR RELAY, 1200A, SMV 29 1AC SHUNTS, AM & REV. CURR RELAY; 1200A, 5MV 30 1BA SHUNTS, AM & REV. CURR RELAY, 1200A, SMV 31 188 SHUNTS, AM .& REV..CURR RELAY, 1200A, SMV 32 1BC SHUNTS, AM & REV. CURR RELAY, 1200A, 5MV 33 LEX SWITCH, OVER-TEMP ALARM 34 OTS-1 ROD DRIVE POWER SUPPLY CUB 35 OTS-2 ROD DRIVE POWER SUPPLY CUB 2 36 LEY SWITCH. REV CURR ALARM 37 1A ROD DRIVE POWER SUPPLY CUB 1 38 '1B ROD DRIVE POWER SUPPLY CUB 2 39 LEZ SWITCH. OVER-VOLT ALARM, ROD DRIVE E'B 40 1A ROD DRIVE POWER SUPPLY CUB 41 ROD DRIVE POWER SUPPLY CUB 2 42 LFA SWITCH, MTR BKR TRIP ALARM'OD 43 E 1A DRIVE POWER SUPPLY CUB 1 44 1B ROD DRIVE POWER SUPPLY CUB 2 45 LFC SWITCH, ROD LIFT DISCONNECT 46 CBA-1 CONTROL BANK A MECH 47 CBA-2 CONTROL BANK A MECH 2 48 CBA-3 CONTROL BANK A MECH 3 49 E CBA-4 CONTROL BANK A MECH 4 50 E CBA-S CONTROL BANK A MECH 5 51 E CBA"6 CONTROL BANK A MECH 6 52 53 54 55 se 57 58 59 60 FORM 0113 <02I83) 15

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1 CPL&L CO EQUIPMENT DATA BASE SYSTEM PAGE 3 2 RUN DATE 05/23/85 QUALITY LIST REP EB88-01 .

3 RUN TIME 17.34.53 DELIVER TO CPB 7C5 G. SINDERS 4 PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1065 ROD CONTROL SYSTEM 10 LFC SWITCH, ROD LIFT DISCONNECT 11 E CBA-7 CONTROL BANK A MECH 7 12 E CBA.-B CONTROL BANK A MECH 8 13 CBB-1 CONTROL BANK 8 MECH 1 14 CBB-2 CONTROL BANK 8 5'IECH 2 15 CBB-3 CONTROL BANK 8 MECH 3 16 CBB-4 CONTROL BANK 8 MECH 4 17 CB8-5 CONTROL BANK 8 MECH 5 18 CBB-6 CONTROL BANK 8 MECH 6 19 CBB"7 CONTROL BANK 8 MECH 7 20 C88-8 CONTROL BANK 8 MECH 8 21 CBC-1 CONTROL BANK C MECH 22 CBC-2 CONTROL BANK C MECH 2 23 CBC-3 CONTROL BANK C MECH 3 24 CBC-4 CONTROL BANK C I'IECH 4 25 CBC-5 CONTROL BANK C MECH 5 28 CBC-6 CONTROL BANK C MECH 6 27 CBC-7 CONTROL BANK C MECH 7 28 CBC-B CONTROL BANK C MECH 8 29 CBD-1 CONTROL BANK D MECH 1 30 CBD-2 CONTROL BANK D MECH 2 31 CBD-5 CONTROL BANK D MECH 5 32 CBD-6 CONTROL BANK D MECH 6 33 SBA-1 SHUTDOWN BANK A MECH 1 34 SBA-2 SHUTDOWN BANK A MECH 2 35 SBA-3 SHUTDOWN BANK A MECH 3 36 SBA-4 SHUTDOWN BANK A MECH 4 37 SBA-6 SHUTDOWN BANK A MECH 6 38 SBA-7 SHUTDOWN BANK A MECH 7 39 SBA-8 SHUTDOWN BANK A MECH 8 40 SBA-9 SHUTDOWN BANK A MECH 9 41 SBB-1 SHUTDOWN BANK 8 MECH 1 42 S88-2 SHUTDOWN BANK 8 MECH 2 43 SBB-3 SHUTDOWN BANK 8 MECH 3 44 588-4 SHUTDOWN BANK 8 MECH 4 45 SB8-6 SHUTDOWN BANK 8 MECH 6 46 SBB"7 SHUTDOWN BANK 8 MECH 7 47 SBB-B SHUTDOWN BANK 8 MECH 8 48 SBB-9 SHUTDOWN BANK 8 MECH 9 49 SBC-1 SHUTDOWN BANK C MECH 1 50 SBC-2 SHUTDOWN BANK C MECH 2 51 SBC-3 SHUTDOWN BANK C MECH 3 52 53 54 55 56 57 58 59 60 FOAM 0113 (02I831 7i

~ I CPL&L CO EQUIPMENT DATA BASE SYSTEM PAGE 4 RUN DATE 05/23/85 QUALITY LIST RFP EB88-01 RUN TIME 17.34.53 DELIVER TO CPB 7CS G. 5 INOERS PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1065 ROD CONTROL SYSTEM ~

10 LFC SWITCH, ROD LIFT DISCONNECT 11 E SBC-4 SHUTDOWN BANK C MECH 4 12 E SBD-1 SHUTDOWN BANK D MECH 1 13 E SBO-2 SHUTDOWN BANK D MECH 2 14 E SBD-3 SHUTDOWN BANK D MECH 3 15 E SBD-4 SHUTDOWN BANK D MECH 4 16 LFD FUSE CHASE SHAWMUT AMP-TRAP, FUSE&VOLT 17 E 1 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT 18 E 2 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT 19 LFH PUSHBUTTON, TRIP TEST 20 E 1D2-6D PUSHBUTTON, TRIP TEST 21 E .1 E2-2A PUSHBUTTON, TRIP TEST 22 LFI PUSHBUTTON, CLOSE TEST 23 E 1D2-6D PUSHBUTTON, CLOSE TEST 24 E 1E2" 2A PUSHBUTTON, CLOSE TEST 25 LFL INDICATOR, TEMPERATURE, MCB 26 E T I -408A INDICATOR, TEMPERATURE, MCB 27 LFM SWITCH, TEMPERATURE, MCB 28 E TS-409 SWITCH. TEMPERATURE, MCB 29 LFN RECORDER, TEMPERATURE, MCB 30 E TR-408 RECORDER, TEMPERATURE, MCB 31 LFO RECORDER, POSITION 32 E ZR-409 RECORDER, POSITION 33 LFP BREAKER W STARTER, 480V MCC 34 E 1E11-6F BREAKER WITH STARTERS 480V MCC 35 LFR PUSHBUTTON 36 E 499-DOWN PUSHBUTTN, DOWN LCL CNTRL ST.499 37 E 499-UP PUSHBUTTON, UP LCL CNTRL ST.499 38 LFS SWITCH, CONTROL 39 E 1 "LS1 swrTCH, HorsT Upr ER LrMrT 40 E 1-LS2 SWITCH. HOIST LOWER LIMIT 41 E 1-LS3 SWITCH, GRIPPER ASSEMBLY RELEASE SOLENOI 42 LFV MOTOR, ROD DRIVE M-G SET 43 E 1A MOTOR, ROD DRIVE M-G SET 44 E 18 MOTOR, ROD DRIVE M-G SET 45 LFW RELAY 46 E JS/408 ROD CONTROL 47 LFX ROD SPEED CARD 48 E SK-408 ROD CONTROL 49 LFY SIGNAL CONDITIONER 50 E JY-408C ROD CONTROL 5'I E JY-408D ROD CONTROL

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52 53 54 55 56 57 58 59 60 FORM 0113 (02/83) 17

I' 1 CPLSL CO EQUIPMENT DATA BASE SYSTEM PAGE 5 2 RUN DATE 05/23/8P QUALITY LIST REP E888-01 3 %UN TIME 17.34.53 DELIVER TO CPB 7C5 G. SINDERS 4 PLANT 03 5 UNIT SYSTEM SYSTEM NAME 6 EQUIPMENT CODE EQUIPMENT DESCRIPTION 7 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 8

9 1065 ROD CONTROL SYSTEM 10 LFY SIGNAL CONDITIONER

'11 JY-408E ROD CONTROL 12 JY"408J ROD CONTROL 13 JY-408K ROD CONTROL

'14 JYr408M ROD CONTROL 15 JY/408KP1 ROD CONTROL 16 PY-446 ROD CONTROL 17 QY-479 ROD CONTROL 18 SY-4080 ROO CONTROL 19 TD/4088 ROD CONTROL 20 TY-4088 ROD CONTROL 21 TY-408C iROD CONTROL 22 TY-408F ROD CONTROL 23 TY-408G ROD CONTROL 24 TY-408H ROD CONTROL 25 ." TY 408HP1 ROD CONTROL 26 NI G TR IP, SHUNT 27 BYA REACTOR SW GEAR BYPASS 28 BYB REACTOR SW GEAR BYPASS 29 RTA REACTOR SW GEAR 30 RTB REACTOR SW GEAR 31 NIH TRIP, UNDERVOLTAGE 32 BYA REACTOR SW GEAR BYPASS 33 BYB REACTOR SW GEAR BYPASS 34 RTA REACTOR SW GEAR 35 RTB REACTOR SW GEAR 36 025 BREAKER, REACTOR TRIP 37 BYA REACTOR SW GEAR BYPASS 38 BYA REACTOR SW GEAR BYPASS 39 BYB REACTOR SW GEAR BYPASS 40 BYB REACTOR SW GEAR BYPASS 41 RTA REACTOR SW GEAR 42 RTA REACTOR SW GEAR 43 RTB REACTOR SW GEAR 44 RTB REACTOR SW GEAR 45 027 CABINETS, POWER 46 SCD SHUTDOWN BK C GRP 1 & BK D GRP 2 47 1AC SHUTDOWN BANK A GROUP 48 180 SHUTDOWN BANK 8 GROUP 49 2AC SHUTDOWN BANK A GROUP 2 50 28D SHUTDOWN BANK B GROUP 2 51 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE 52 53 54 55 58 57 58 59 60 FORM 0113 (02I83) 18

P 1 CPL&L CO EQUIPMENT DATA BASE SYSTEM PAGE 6 2 RUN DATE 05/23/85 QUALITY LIST REP E888-01 3 RUN TIME 17.34.53 DELIVER TO CPB 7C5 G. SINDERS 4 PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1 1065 ROD CONTROL SYSTEM 10 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE 11 E CBA-1 (F-2) CONTROL BANK A 12 E CBA-2 8-10 CONTROL BANK A 13 CBA-3 (K-14) CONTROL BANK A 14 CBA-4 (P-6) CONTROL BANK A 15 CBA-5 (K-2) CONTROL BANK A 16 CBA-6 8-6 CONTROL BANK A 17 CBA-7 (F-14) CONTROL BANK A 18 CBA-B (r -10) CONTROL BANK A 19 CBB-1 (F-4) CONTROL BANK 8 20 CBB-2 (D-10) CONTROL BANK 8 21 CBB"3 K-12 CONTROL BANK 8 22 CBB-4 (M-6) CONTROl BANK 8 23 C88-5 (K-4) CONTROL BANK 8 24 CBB-6 (D-e) CONTROL BANK 8 25 C88-7 F-12 CONTROL BANK 8 26 CBB-B (M-10) CONTROL BANK 8 27 CBC-1 (D-4) CONTROL BANK C 28 CBC-2 (D-12) CONTROL BANK C 29 CBC-3 M-12 CONTROL BANK C 30 CBC-4 (M-4) CONTROL BANK C 31 CBC-5 (H-e) CONTROL BANK C 32 CBC-6 (F-8) CONTROL BANK C 33 CBC-7 H- 10 CONTROL BANK C 34 CBC-B (K-8) CONTROL BANK C 35 CBD-1 (H-2) CONTROL BANK D 36 CBD-2 (H-14) CONTROL BANK D 37 CBD-5 8-8 CONTROL BANK D 38 CBD-6 (P-8) CONTROL BANK D 39 SBA-1 (6-3) SHUTDOWN BANK A 40 SBA-2 (C-9 SHUTDOWN BANK A 41 SBA-3 d-13 SHUTDOWN BANK A 42 SBA-4 (N-7) SHUTDOWN BANK A 43 SBA-6 (d-3) SHUTDOWN BANK A 44 SBA-7 C-7 SHUTDOWN BANK A 45 SBA-8 G-13 SHUTDOWN BANK A 46 SBA-9 (N-9) SHUTDOWN BANK A 47 SB8-1 (E-5) SHUTDOWN BANK 8 48 588-2 (E-11) SHUTDOWN BANK 8 49 588-3 L-11 SHUTDOWN BANK 8 50 SB8-4 (L"5) SHUTDOWN BANK 8 51 S88-6 (6-7) SHUTDOWN BANK 8 52 53 54 55 56 57 58 59 60 FORM 0113 102183)

I CPLSL CO EQUIPMENT DATA BASE SYSTEM PAGE 7 2 RUN DATE 05/23/85 QUALITY LIST REP EB88-01 3 RUN TIME 17.34.53 DELIVER TO CPB 7C5 G. 5INDERS 4 PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT .CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 1 1065 ROD CONTROL SYSTEM 10 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE 11 E SBB-7 (G-9) SHUTDOWN BANK B 12 E SBB-8 8-9 SHUTDOWN BANK B 13 SBB"9 (U-7) SHUTDOWN BANK 8 14 SBC"1 (E-3) SHUTDOWN BANK C 15 SBC-2 (C-11) SHUTDOWN BANK C 16 SBC-3 L-13 SHUTDOWN BANK C

\7 SBC-4 (N-5 SHUTDOWN BANK C I8 SBD-1 (F-6) SHUTDOWN BANK 0 19 SBD-2 (F-10) SHUTDOWN BANK 0 20 SBD-3 K-10) SHUTDOWN BANK D 21 E SBO-4 K-6 SHUTDOWN BANK 0 22 032 SETS, ROD DRIVE M.G.

23 E 1A MOTOR GENERATOR SET 1A (SOUTH) 24 E 1B MOTOR GENERATOR SET 1B (NORTH) 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43

. 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 END OF REPORT EB88-01 FORM 0113 (02I83) 20

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Question Item 2.l (part 2) - Incomplete Submit detailed information describing your vendor interface program for reactor trip system components. Information supplies should state how the program assures that vendor technical information is kept complete, current and controlled throughout the life of the plant and should also indicate how the program will be implemented at Shearon Harris, Unit l.

Rce~onse The Shearon Harris Nuclear Power Plant (SHNPP) reactor trip system is supplied by Westinghouse (NSSS vendor). CPRL has verified that Westinghouse Technical Bulletins applicable to Generic Letter 83-28 have been received. The recommendation of the Westinghouse Technical Bulletins on reactor trip breakers have been reviewed by CPdcL and acted upon. Westinghouse has incorporated return receipt letters into their Technical Bulletins. These return receipt letters are followed up by Westinghouse if the receipt is not returned within a reasonable time. Westinghouse is also providing an updated list of Technical Bulletins which CPRL will use as an additional tool in ensuring that applicable Technical Bulletins have been received. Westinghouse has issued a complete list of past recommendations on NSSS equipment. The index of recommendations is also updated periodically to ensure the plant is aware of issued recommendations.

Once the Technical Bulletins are received, the vendor recommendations are processed in accordance with our procedures dealing with Operational Experience Feedback. Vendor recommendations concerning plant equipment are tracked by the Onsite Nuclear Safety Unit in accordance with the above Operating Experience Feedback Program procedures.. This program ensures that the information is provided to Operations or Maintenance or other appropriate organizations for their use. The recommendations are tracked until final disposition occurs.

SHNPP has implemented procedures for initial review and revisions to the Technical Manual. Once the Technical Manual has been accepted for use by the Technical Support Unit, Document Control distributes the vendor manuals per Document Control Instruction.

7 At SHNPP, no distinction is made for on-site processing of vendor information for the reactor trip system components and other safety-related equipment. The current established controls provide for processing of vendor information with the same methodology established for Technical Manuals and Bulletins received.

In summary, CPRL believes the current vendor interface program for the reactor trip system components in conjunction with established plant procedures for maintenance, surveillance testing, equipment repair and replacement, and quality assurance program provide a comprehensive equipment reliability program throughout the life of the plant.

(1531GAS/Nf )

OO Question Item 2.2.1 - Incomplete Submit information on how equipment will be classified as safety-related and will be designated as such on plant documentation as requested in sub-items 2.2.l.l to 2.2.1.6.

Reeonse An established procedure exists at SHNPP for the preparation and control of a component level classification. By procedure, the quality classification of components for quality purposes is obtained by applying the quality designation inherent in existing controlled design documents such as flow diagrams, controlled wiring diagrams, etc. Safety-related components are classified as Q-Class "A" with non-safety/seismic, radwaste, fire protection, and non-safety classified as "B", "C",

"D", and "E", respectively. A component may meet more than one quality classification criteria; but in all cases, the highest quality class is the resultant quality classif ication.

(1531GAS/mf )

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Question Item 2.2.2 Incomplete Submit detailed information describing your vendor interface program for all safety-related components. Information supplied should state how the program assures that vendor technical information is kept complete, current, and controlled throughout the life of the plant and should also indicate how the program will be implemented at Shearon Harris, Unit I. If the recommendations of NUTAC are to be implemented at Shearon Harris, Unit l, you need to supplement your response to address to concern about establishing and maintaining an interface with all vendors of safety-related equipment since the staff found NUTAC lacking in this respect.

Reeonse A unique aspect about SHNPP construction is the program of using permanent plant staff to order the initial loading of spare parts instead of depending on parts received only with initial equipment purchase. To support this program, a parallel effort is in process to systematically review all vendor technical manuals, starting with safety related vendors first. In this process, each vendor is contacted to verify the information is current, and maintenance personnel perform a review for adequacy of content. Once these technical reviews are completed, the manuals are accepted by Technical Support and sent to Document Control for distribution. As a result of these programs, SHNPP will be assured of having the latest technical manuals for safety-related equipment at time of fuel load.

With regard to continued maintenance of technical manuals, SHNPP intends to retain the function of technical manual upgrade in concert with our Operational Experience Feedback program, consistent with the NUTAC recommendations.

CP&L has reviewed the NUTAC Vendor Equipment Technical Information Program (YETIP) and believes that the NUTAC effort provides effective guidelines in establishing a vendor interface program. The VETIP as defined in the March 1980 NUTAC document is considered a valid response to Section 2.2.2 of the NRC Generic Letter 83-28. CPRL is in the process of implementing a program to meet the intent and guidelines of the NUTAC/VETIP.

(1531GAS/mf )

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Question Item 3.1.3 - Incomplete Results of review of test and maintenance programs shall identify any post-maintenance testing that may degrade rather than enhance safety and shall describe actions to be taken including submitting needed Technical Specification changes.

Item 3.2.3 - Incomplete Same at Item 3.1.3.

Response

CPdcL submitted the "pen and ink" version of the SHNPP Technical Specifications to the NRC on April 23, 1985. These Technical Specifications will undergo a detailed review by CPRL to assess the implementation of the required surveillances. This review will determine if the surveillances proposed by the SHNFP Technical Specifications (which are based upon NUREG-0052, Rev. 5, Westinghouse Standard Technical Specifications) can be implemented. Implicit in this assessment is that: (1) the surveillance does not damage the component, and (2) the applicable surveillance test(s) is/are required prior to declaring a component OPERABLE following maintenance which removes the component from service. The results of this review will be provided to the NRC as changes to the Technical Specifications during the review process for the SHNPP Technical Specifications. However, a specific submittal on the 3.1.3 and 3.2.3 items will not be made.

The Westinghouse Maintenance Manual for DS-016 reactor trip breakers has been received and reviewed. The appropriate maintenance procedures that implement the recommended maintenance action have been drafted.

(1531GAS/mf )

~0 P Question Item 0.5.2 - Incomplete Provide a description of the design provisions that will permit on-line testing of the reactor trip system.

Response

Refer to FSAR Section 7.2.2.2.3.10 (Revision 17) for a description of the design provisions that will permit on-line testing.

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Question Item 0.5.3 - Incomplete Provide results of review of existing or proposed intervals for on-line testing considering the concerns of 0.5.3.1 to 0.5.3.5 in the generic letter. Proposed Technical Specification changes resulting from this review shall be submitted for review.

Response

CPRL's November 7, 1983 submittal on Generic Letter 83-28 responded to this item. CPRL referenced WCAP-10271 "Evaluation of Surveillance Frequencies and Out of Service Times for Reactor Protection Instrumentation Systems" for reduced surveillance intervals for on-line testing of Reactor Protection System Channels.

This WCAP was approved by the NRC on February 21, 1985. CPRL's April 23, 1985 Technical Specification submittal incorporates the reduced surveillance intervals within the limitations of the NRC's SER.

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