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 R CAROLINA POWER & LIGHT CO.
To:	DENTON H R 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 ris Nucl ear~Power Pl anti Uni t-ii 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 ID>>CODE/NAME(NRR LB3>>BC 01 INTERNAL: ACRS ELD/HDS1 IE/DQAVT NRR/DE/MEB NRR/DHFS/LQB NRR/DL/GRAB NRR/'L/TAPMG NRR/DSI/ICSB NRR/DS I/RSB RONa>>COPIES LTTR ENCL'3 3 6 6 1 0 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME" ADM/LFMB IE/DI NRR/DE/EQB NRR/DHFS/HFEB NRR/DL DIR NRR/DL/SSPB NRR/DS I/ASB N"/PS B G FIL 00 COPIES LVTR ENCL 0 1 1-1 1=1 1 1 1-EXTERNAL':

24X NRC;PDR, 02 1 1 1 1 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED'TTR 32'NCL>>30 C~p ()(,, Hsr+61 l l<<I q s)Ff(pffft q I('l I ((1H n~,'i')1<<, l<<s'(l<<~'1~s+'.~1~<<(f~'~<<sPtM'>>2 fft4~P<<($);(1 I~1 1 Pi,1 erg<<,H<<l'H ys<<P s(4s H,-I<<f I'I'ln<<;a4 I 1<<H(kj+<<fl sn se earn w (I<<P Pff I IIP((I)~ff'c.'f tl('fr 451'f.,t]f 1,~rp~g 1 ll'(p pli o<<lr Is HTf 1 P,J H ('"I I ,r7I I<<H g

I CNK Carolina Power 8 Light Company MAY 31$85 SERIAL: NLS-85-186 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 ADDITIONAL INFORMATION 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, SRZ/GAS/mf (1531GAS)Enclosure S.mmerman Manager Nuclear Licensing Section Cct Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)

Dr.3.Nelson Grace (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)

Mr.D.Lasher (NRC-RRAB)

Wake County Public Library Mr.Wells Eddleman Mr.3ohn D.Runkle Dr.Richard D.Wilson Mr.G.O.Bright (ASLB)Dr.3.H.Carpenter (ASLB)Mr.3.L.Kelley (ASLB)8506060496 85053i PDR ADDCK 05000400 A PDR+411 Fayettevilte Street 0 P.O.Box 1551 o Raleigh, N.C, 27602

~0 i".'P$E 6 PA<:l"j 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 5 6 7 8 9 10 ll l2 13 l4 I5 16 17 I8 19 20 21 22 23 24 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 5:l 54 55 56 57 58 59$0 CPL&L CP RUN DATE~05/14/85 RUG T IMF.13.24.52 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO 17C5 HARGETT PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPh'IENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1080 REACTOR PROTECTION SYSTEM+DFG SOLID STATE PROTECTION CABINET A TRAIN A 8 TRAIN 8 I A A SAFEGUARDS TEST CABINET TRAIN A TRAIN 8 AUX ILL IARY RELAY RACKS DFH A 8 DFL AUX RELAY RACKS AUX RELAY RACKS AUX RELAY RACKS TRIP STATUS LIGHT BOX STEAM GENERATORS STEAM GENERATORS

&TURBINE REACTOR COOLANT SYSTEM NIS&CONTAINMENT PRESSURE SWITCH.CONTROL MODULE ELECTROSWITCH TYPE STEAMLINE ISOLATION II STEAMLINE ISOLATION I STEAMLINE ISO.RESET TRAIN A STEAMLINE ISO.RESET TRAIN 8 STEAMLINE S.I.BLOCK RESET A STEAMLINE S.I.BLOCK RESET 8 PRZR PRES.S.I.BLOCK RESET TR-A PRZR PRES.S.I.BLOCK RESET TR-8 S.I.RESET TRAIN A MCB S.I.RESET TRAIN A ACP S.I.RESET TRAIN 8 MCB S.I.RESET TRAIN 8 ACP F.W.ISO.BYPASS VALVES RESET A F.W.ISO.BYPASS VALVES RESET 8 N33A SOURCE RANGE BLOCK RESET N338 SOURCE RANGE BLOCK RESFT N38A INTERMEDIATE RANGE BLOCK N388 INTERMEDIATE RANGE BLOCK N47A POWER RANGE BLOCK N478 POWER RANGE BLOCK SWITCH//1 REACTOR TRIP/CLOSE SWITCH//I S.I.ACTUATION SWITCH//2 REACTOR TRIP SWITCH//2 S.I.ACTUATION REAKER, 120VAC INSTRUMENTATION CIRCUIT SAFEGUARDS TEST CAB.A 2 3 DFM OFN CS-SLIISAB Cs-SLISAB Cs-SLSLRA CS-SLSLRB CS-1008SA Cs-100858.Cs-141SA CS-14158 CS-455.1SA CS-455.2SA CS-455.3SB CS-455.458 CS-810SA CS" 810SB CS-88SA Cs-88SB CS-89.ISA CS-89.158 CS-89.2SA Cs"89.2SB CS-92.1SAB CS-92.2SAB CS-94.1SAB CS-94.2SAB DLX 8 1A-51"3-A A n A A h n A A TAG NUMBFR PAGE 293 REP E888-01 FOAM 0I13 I02/83)1583

CPLSL CO Ri/N DATE 05/i4/85 RUN TIME 13.24.52 h EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO 17CS HARGETT PLANT 03 PAGE 294 REP EB88-01 UNIT SYSTEM SYSTFM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 13 14 15 1G 17 18 19 20 A A h A h A h 1080 REACTOR OLX 1A-51-7 1A-S 1"8 1A-53"7 1A-53-8 18-52-7 16-52-8 18-54-3 1B-S4-7 18-54-8 OMA PROTECTION SYSTEMh BREAKER,120VAC INSTRUMENTATION CIRCUIT RPS CHAIN I TRAIN A RPS CHAIN I TRAIN B RPS CHAIN III TRA1N A RPS CHAIN III TRAIN B RPS CHAIN II TRAIN h RPS CHAIN I I TRAIN B SAFEGUARDS TEST CAR.R RPS CHAIN IV TRAIN A RPS CHAIN IV TRAIN 8 SWITCH, CONTROL MODULE ELECTROSWITCH TYPE 21 22 23 24 25 26 27 28 29 30 31 32 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 cs-458.isn CS-458.258 FhiZ 10212-16 102 12-18 1E212-21 1E212-23 1E212-25 FKA 18-2 IZP UPP-1-17 RWST S.I.RESET TRAIN A RWST S.I.RESET TRAIN 8 BREAKER,120V POWER PANEL AUX REALY RACK//2 nux RELAY RhcK//i TSLB-4 8 BPLB TSLB-3 TSLB-182 BREAKER, 120V UNINTERRUPT PANEL AUX RELAY RACK//1 120 VAC FUSED SWITCH FUSED SWITCH I Al>th Ilh h'I<Ilhlflhl 1584 J~

CPL&L CO RUN DATE 05/23/85 RUN TIME 17.34.53 A uc 6 cw EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7CS G.SINDERS PLANT 03 iQ PAGE 2 REP EB88-01 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1065 , OD C NTROL Y TEM CQY BREAKER, 480V AUX.BUS 1D2-6D MG SET MOTOR 1A 1E2-2A MG SET MOTOR 18 DFV BREAKER, DC DISTRIBUTION PANEL DP-1A-SA-18 GENERATOR OUTPUT 1A DP-1A-1-18 SERVES ROD DRIVE PWR SUPPLY CUB 1 DP-1A-2-18 SERVES ROD DRIVE PWR SUPPL CUB 2 OP-18-58-18

.GENERATOR OUTPUT 1B LES INDICATOR, SPEED MCB-1C SI-408 INDICATOR, SPEED MCB-1C LEU SWITCH, MOTOR DISCONNECT 102-6D SWITCH, MOTOR DISCONNECT 1E2-2A SWITCH, MOTOR DISCONNECT LEV REGULATOR, VOLTAGE 1A ROD DRIVE VOWER SUPPLY CUB 1B ROD DRIVE POWER SUPPLY CUB 2 LEW SHUNTS, AM&REV.CURR RELAY, 1200A, SMV 1AA SHUNTS, AM&REV.CURR RELAY, 1200A, SMV 1AB SHUNTS, AM&REV.CURR RELAY, 1200A, SMV TAG NUMBER 29 30 31 32 1AC 1BA 188 1BC SHUNTS, AM&REV.CURR RELAY;1200A, 5MV SHUNTS, AM&REV.CURR RELAY, 1200A, SMV SHUNTS, AM.&REV..CURR RELAY, 1200A, SMV SHUNTS, AM&REV.CURR RELAY, 1200A, 5MV 33 34 35 36 37 38 39 40 LEX SWITCH, OVER-TEMP ALARM OTS-1 ROD DRIVE POWER SUPPLY CUB OTS-2 ROD DRIVE POWER SUPPLY CUB 2 LEY SWITCH.REV CURR ALARM 1A ROD DRIVE POWER SUPPLY CUB 1'1B ROD DRIVE POWER SUPPLY CUB 2 LEZ SWITCH.OVER-VOLT ALARM, ROD DRIVE 1A ROD DRIVE POWER SUPPLY CUB 41 42 43 44 E E'B LFA 1A 1B ROD DRIVE POWER SUPPLY CUB 2 SWITCH, MTR BKR TRIP ALARM'OD DRIVE POWER SUPPLY CUB 1 ROD DRIVE POWER SUPPLY CUB 2 45 46 47 48 LFC SWITCH, ROD LIFT DISCONNECT CBA-1 CONTROL BANK A MECH CBA-2 CONTROL BANK A MECH 2 CBA-3 CONTROL BANK A MECH 3 49 50 51 52 53 54 55 se 57 58 59 60 E E E CBA-4 CBA-S CBA"6 CONTROL BANK A MECH 4 CONTROL BANK A MECH 5 CONTROL BANK A MECH 6 FORM 0113<02I83)15

'4~

1 CPL&L CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 DELIVER TO EQUIPMENT DATA BASE SYSTEM QUALITY LIST CPB 7C5 G.SINDERS PLANT 03 PAGE 3 REP EB88-01.UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 E E 1065 ROD CONTROL SYSTEM LFC SWITCH, ROD LIFT DISCONNECT CBA-7 CONTROL BANK A MECH 7 CBA.-B CONTROL BANK A MECH 8 13 14 15 16 17 18 19 20 21 22 23 24 25 28 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 CBB-1 CBB-2 CBB-3 CBB-4 CB8-5 CBB-6 CBB"7 C88-8 CBC-1 CBC-2 CBC-3 CBC-4 CBC-5 CBC-6 CBC-7 CBC-B CBD-1 CBD-2 CBD-5 CBD-6 SBA-1 SBA-2 SBA-3 SBA-4 SBA-6 SBA-7 SBA-8 SBA-9 SBB-1 S88-2 SBB-3 588-4 SB8-6 SBB"7 SBB-B SBB-9 SBC-1 SBC-2 SBC-3 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK D CONTROL BANK D CONTROL BANK D CONTROL BANK D SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C MECH 1 5'IECH 2 MECH 3 MECH 4 MECH 5 MECH 6 MECH 7 MECH 8 MECH MECH 2 MECH 3 I'IECH 4 MECH 5 MECH 6 MECH 7 MECH 8 MECH 1 MECH 2 MECH 5 MECH 6 MECH 1 MECH 2 MECH 3 MECH 4 MECH 6 MECH 7 MECH 8 MECH 9 MECH 1 MECH 2 MECH 3 MECH 4 MECH 6 MECH 7 MECH 8 MECH 9 MECH 1 MECH 2 MECH 3 FOAM 0113 (02I831 7i

~I CPL&L CO RUN DATE 05/23/85 RUN TIME 17.34.53 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7CS G.5 INOERS PLANT 03 PAGE 4 RFP EB88-01 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 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 5'I'~52 53 54 55 56 57 58 59 60 1065 ROD CONTROL SYSTEM~LFC SWITCH, ROD LIFT DISCONNECT E SBC-4 SHUTDOWN BANK C MECH 4 E SBD-1 SHUTDOWN BANK D MECH 1 E SBO-2 SHUTDOWN BANK D MECH 2 E SBD-3 SHUTDOWN BANK D MECH 3 E SBD-4 SHUTDOWN BANK D MECH 4 LFD FUSE CHASE SHAWMUT AMP-TRAP, FUSE&VOLT E 1 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT E 2 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT LFH PUSHBUTTON, TRIP TEST E 1D2-6D PUSHBUTTON, TRIP TEST E.1 E2-2A PUSHBUTTON, TRIP TEST LFI PUSHBUTTON, CLOSE TEST E 1D2-6D PUSHBUTTON, CLOSE TEST E 1E2" 2A PUSHBUTTON, CLOSE TEST LFL INDICATOR, TEMPERATURE, MCB E T I-408A INDICATOR, TEMPERATURE, MCB LFM SWITCH, TEMPERATURE, MCB E TS-409 SWITCH.TEMPERATURE, MCB LFN RECORDER, TEMPERATURE, MCB E TR-408 RECORDER, TEMPERATURE, MCB LFO RECORDER, POSITION E ZR-409 RECORDER, POSITION LFP BREAKER W STARTER, 480V MCC E 1E11-6F BREAKER WITH STARTERS 480V MCC LFR PUSHBUTTON E 499-DOWN PUSHBUTTN, DOWN LCL CNTRL ST.499 E 499-UP PUSHBUTTON, UP LCL CNTRL ST.499 LFS SWITCH, CONTROL E 1"LS1 swrTCH, HorsT Upr ER LrMrT E 1-LS2 SWITCH.HOIST LOWER LIMIT E 1-LS3 SWITCH, GRIPPER ASSEMBLY RELEASE SOLENOI LFV MOTOR, ROD DRIVE M-G SET E 1A MOTOR, ROD DRIVE M-G SET E 18 MOTOR, ROD DRIVE M-G SET LFW RELAY E JS/408 ROD CONTROL LFX ROD SPEED CARD E SK-408 ROD CONTROL LFY SIGNAL CONDITIONER E JY-408C ROD CONTROL E JY-408D ROD CONTROL FORM 0113 (02/83)17 I'

1 2 3 4 5 6 7 8 9 10'11 12 13'14 15 16 17 18 19 20 21 22 23 24 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 58 57 58 59 60 CPLSL CO RUN DATE 05/23/8P%UN TIME 17.34.53 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.SINDERS PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1065 ROD CONTROL SYSTEM LFY SIGNAL CONDITIONER JY-408E ROD CONTROL JY"408J ROD CONTROL TAG NUMBER JY-408K JYr408M JY/408KP1 PY-446 QY-479 SY-4080 TD/4088 TY-4088 TY-408C TY-408F TY-408G TY-408H." TY 408HP1 NI G BYA BYB RTA RTB NIH BYA BYB RTA RTB 025 BYA BYA BYB BYB RTA RTA RTB RTB ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROO CONTROL ROD CONTROL ROD CONTROL iROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL TR IP, SHUNT REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR TRIP, UNDERVOLTAGE REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR BREAKER, REACTOR TRIP REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR REACTOR SW GEAR REACTOR SW GEAR 027 CABINETS, POWER SCD SHUTDOWN BK C GRP 1&BK D GRP 2 1AC SHUTDOWN BANK A GROUP 180 SHUTDOWN BANK 8 GROUP 2AC SHUTDOWN BANK A GROUP 2 28D SHUTDOWN BANK B GROUP 2 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE PAGE 5 REP E888-01 FORM 0113 (02I83)18 P

1 CPL&L CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.SINDERS PLANT 03 PAGE 6 REP E888-01 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 1 E E 1065 ROD CONTROL SYSTEM 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE CBA-1 (F-2)CONTROL BANK A CBA-2 8-10 CONTROL BANK A 13 14 15 16 17 18 19 20 21 22 23 24 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 CBA-3 CBA-4 CBA-5 CBA-6 CBA-7 CBA-B CBB-1 CBB-2 CBB"3 CBB-4 C88-5 CBB-6 C88-7 CBB-B CBC-1 CBC-2 CBC-3 CBC-4 CBC-5 CBC-6 CBC-7 CBC-B CBD-1 CBD-2 CBD-5 CBD-6 SBA-1 SBA-2 SBA-3 SBA-4 SBA-6 SBA-7 SBA-8 SBA-9 SB8-1 588-2 588-3 SB8-4 S88-6 (K-14)(P-6)(K-2)8-6 (F-14)(r-10)(F-4)(D-10)K-12 (M-6)(K-4)(D-e)F-12 (M-10)(D-4)(D-12)M-12 (M-4)(H-e)(F-8)H-10 (K-8)(H-2)(H-14)8-8 (P-8)(6-3)(C-9 d-13 (N-7)(d-3)C-7 G-13 (N-9)(E-5)(E-11)L-11 (L"5)(6-7)CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROl BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK D CONTROL BANK D CONTROL BANK D CONTROL BANK D SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 FORM 0113 102183)

I CPLSL CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.5INDERS PLANT 03 PAGE 7 REP EB88-01 9 10 11 12 UNIT SYSTEM SYSTEM NAME EQUIPMENT.CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1 1065 ROD CONTROL SYSTEM 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE E SBB-7 (G-9)SHUTDOWN BANK B E SBB-8 8-9 SHUTDOWN BANK B TAG NUMBER 13 14 15 16\7 I8 19 20 SBB"9 (U-7)SBC"1 (E-3)SBC-2 (C-11)SBC-3 L-13 SBC-4 (N-5 SBD-1 (F-6)SBD-2 (F-10)SBD-3 K-10)SHUTDOWN BANK 8 SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK 0 SHUTDOWN BANK 0 SHUTDOWN BANK D 21 22 23 24 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 E SBO-4 K-6 SHUTDOWN BANK 0 032 SETS, ROD DRIVE M.G.E 1A MOTOR GENERATOR SET 1A (SOUTH)E 1B MOTOR GENERATOR SET 1B (NORTH)57 58 59 60 END OF REPORT EB88-01 FORM 0113 (02I83)20 h t 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

)

0 l y~4 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

)

e~~l.f j 1 4+

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.(1551GAS/mf) 0 4~t*r%

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.(1531GAS/mf

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