ML18149A174

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Forwards Partial Response to 860430 Request for Status of Implementation of Generic Issues.Completed List Will Be Provided by 860815
ML18149A174
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 05/30/1986
From: STEWART W L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: DENTON H R, RUBENSTEIN L S
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM 86-298, 8680530-2, NUDOCS 8606060198
Download: ML18149A174 (27)
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{{#Wiki_filter:e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 w. L. STEW.A.BT VICE PRESIDENT NUCLEAR OPERATIONS May 30, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Lester S. Rubenstein, Director PWR Project Directorate No. 2 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 IMPLEMENTATION OF GENERIC ISSUES Serial No. NO/PML/acm Docket Nos. License Nos. 86-298 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 Your letters dated April 30, 1986 requested the status of implementation of various generic items for our Surry and North Anna Power Stations. A partial response to this request is provided in Attachments 1 and 2 for Surry and North Anna, respectively. We are working to identify the status of the remaining issues and will provide a completed list for each station by August 15, 1986. Our determination of completion status for those items indicated is based on a review of related Virginia Electric and Power Company and NRG correspondence. Where we were able to find a NRG or Company letter confirming actual completion of committed actions or NRG acceptance that the station was already in compliance with the requirements of the generic issue, we have considered the item to be closed, and the date of closure was taken as the date of the confirming letter. For other items such as ones for which your Safety Evaluation Report identified actions to be completed by the Company, we have located internal documentation of the date of commitment closure. If you have any questions, please contact us. 7JiJ!l;Jj W. L. Stewart Attachments

9-8--860530 86060601 05000280-PDR ADOCK PDR p

.. e VIRGINIA. ELECTRIC AND POWER COMPANY TO Harold R. Denton cc: Dr. J. Nelson Grace Regional Administrator NRC Region I I NRC Senior Resident Inspector North Anna Power Station NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A Mr. Leon B. Engle NRC North Anna Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A e [...IV'-LV.:I" '-R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N A-\tocir1 r.A.e.n+ 1 PAGE Nv*:.: ~q:_ .. 03131/86 FACILITY: SURRY 1 PLANT LOCATION: 17 MI NW OF NEWPORT NEWS, VA DOCKET NUMBER: 050-00280 LICENSED POWER: 2441 MWT DESIGN POWER: 0788 MWE ARCH/ENGINEER: S&W NSSS VENDOR: WEST IE INSPECTOR: D. BURKE TAC NO. MPA I M08327 A-01 M08102 A-02 M06964 A-03 M08638 A-04 M08S16 A-06 M06102 A-09 M10496 A-10 M10493 A-11 M10491 A-12 M11216 A-14 M127S3 A-15 M47S66 A-16 I MS1138 A-17 IM55745 A-18 M56490 A-18 M59147 A-20 0 MS9988 A-21 M07906 B-01 M08401 B-03 M06711 B-04 TITLE 10 CFR 50.55 ACG> -ISI APPENDIX I -ALARA SECURITY REVIEWS-MODIFIED AMENDMENT PLANS APPENDIX J -CONTAINMENT LEAK TESTING RESPIRATORY PROTECTION SYSTEM PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE CONTINGENCY PLANNING GUARD TRAINING PLANS VITAL AREA ANALYSIS 10C.FR ~O.S5 ACG) -INSERVICE TESTING QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT LIC ACT COMPLETE 02107183C-06/19/84C. 02121119c 05.119.18*1,C 091'111'79C 03.111/80C 09.t04.180C 12/181'80C . 04.112.182C 101'22/82C 041'15/80C QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04.112/82C INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 121'31/86 TECH SPECS AFFECTED BY S0.72 AND S0.73 CGL 83-43> TECH SPECS AFFECTED BY 50.72 AND S0.73 CGL 83-,3) 10 CFR 50.62 OPERATING REACTOR REVIEWS 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE DIESEL GENERATOR LOCKOUT PWR MODERATOR DILUTION REACTOR VESSEL OVERPRESSURE PROTECTION 021'27 /85C. 121'11/8SC ...... ___ _ 12/31/86 12/31/86_ 05/19/81C 06/081'81C 03/04.180C PROJECT MANAGER: T. CHAN BRANCH CHIEF: L. RUBENSTEIN LIC. ASSISTANT: VACANT LICENSEE STATUS DATE C.o...-..p\Q..~ o<., /19/B+ : Ar.\~nd,...e.-,.t, 97 e i -C.on.ple.+e.c\

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'. lt'""-~d"."~+ <c, I l2./ll / S!l CoC'\l.p_ltiU)\ _ : 03/o+ /so .. ~&\Q""b'\T sc... R-1208731-001 REGULA TD RY INF DR MAT ID N TR A-C .KING SYSTEM F A C I L I T Y I M P L E M E N T A T I D N SURRY 1 (CONTINUATION> TAC NO. MfLl M07964 B-11 TITLE FLOOD OF EQUIPMENT IMPORTANT _TD SAfETY LIC ACT COMPLETE. 12/181'80C 02,,101'81C M08641 _M08506 B-12 STEAM GENERATOR. TUBE INSf>_E~TIDN ...... _ . B-14 CEA.GUIDE TUBE HEAR M12160

  • 8~16 EMERGENCY PLANNING AND REVISIONS

.. 07/07/80C 04/01/81C 08/17/82C .. M08509 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS M1_ 0_273 B-20 CONTAINMENT LEAKAGE DUE TD SEAL DETERIORATION .. 08(251'80C . M10337 B-21 LOSS_ot=: 125-V DC.BUS VOLTAGE WITH.LOSS OF ANNUNCIA 031'01/82C M08513 M10053 M42562 M1 0001 'J110234 M08538 M07108 M07576 M08357 !M08683 M11091 M47_396 iM11713 I M1201 0 M13128 M43153 B-22 . TECH SPEC SURVEILLANCE REQUIREMEN:rs FDR MECHANICAL 08/17(82C B-23 DEGRADED GRID VOLTAGE 10,os,s2c B-24 VENTING AND PURGING CONTAINMENTS HHIL E AT FULL POW 111'17/82C B-24 VENTING AND PURGING CONTAINMENTS WHILE.AT.FULL POW 04/02/80~ .* _B-26 INADVERTANT SAFETY INJECTION DURING CDOLDOWN 091'141'79C B-30 STEAM GENERATOR REPLACEMENT PROGRAM 01/201'79C B-30 B-31 B-32 B-39 B-41 STEAM GENERATOR REPLACEMENT.PROGRAM ........... . LONG SHAFT LHSI & OUTSIDE RECIRC. PUMP DEGRADATION --*----. ---. . ---. -BLOCKED SI .. SIGNA_L DURING COOL DOWN. PHR PRESSURE -TEMPERATURE LIMIT TECH SPECS FIRE PROTECTION -FINAL TECH SPECS (INCLUDES SERS . 01/20/79C 03/151'82C 041'01/82C 111'131'80C 011'17/84C B-41 FIRE. PROTECTION.- FINAL.TECH SPECS <INCLUDES SERS 111'181'82C B-42 TMI FOLLOW UP -ALL PLANTS B-42 THI.FOLLOW UP~ ALL PLANTS B-42 . J_f"II FOLL.OH UP .::. ALL __ F'LANJS B-43 PHR FEEDWATER LINE CRACKS 011'30/81C. 091'06/79C 051'28/80C 051'25.1S-2C LICENSEE STATUS. Mil Lo"'-fle.-kcl . 12../15/90 PAGE NO'*:: 03/31/86 L ....... .

-12087 31-001 URRY 1 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N (CONTINUATION)

LICENSEE :AC NO. MPA I

  • TITLE LIC ACT COMPLETE STATUS DATE PAGE NO. ',r 47 3~. 03/31/86 111777 8-:43 PWR FEEDWATER LINE CRACKS .. _______ . 1 0/j 7/7_9C _________________

_ CO""""ICL~ lc/1*;.f.,,_~--- -***-SEf!. !~96_5_Z___ ____ 8:-_44 _____ LESSONS LEARNED IMPLEMENTATION 04/24/80C i 30653 B-44 LESSONS _LEARNED IMPLEMEN_TAJIOtL_ . 30654 8-44 LESSONS LEARNED IMPLEMENTATION 30655 B-44 30656 8-44 ~0657 B-44 ~0658 B-44 I . LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION ---*--*--*-*.. . -..... . LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION ~_D659 _________ B-44 I ~0660 ~0661 ~0662 ~0663 0664 0665 B-44 LESSONS LEARNED IMPLEMENTATION B-44 LESSONS LEARNED IMPLEME_NTATION 8-44 LESSONS LEARNED IMPLEMENTATION 8-44 LESSONS LEARNED IMPLEMENTATION 8-44 LESSONS LEARNED IMPLEMENTATION 8-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C 04/24/80C 041'241'80C 041'24/80C 041'241'80C 04/241'80C 041'241'80C 041'241'80C 041'241'80C 041'241'80C 041'241'80C 04/24/80C 041'241'80C 2937 8-45 WASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 041'201'81C 2101 2579 12687 12976 ~7402 11878 t3203 8-46 ANALYSIS OF TURBINE DISC CRACKS 8-46 ANALYSIS OF TURBINE DISC CRACKS 8-47 ECCSJ CLAD SWELLING AND RUPTURE 8-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 8-49 PWR CONTROL ROD MISALIGNMENT 051'021'81C 081'191'81C 091'12180C 10/141'83C 061'171'82C 8-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 111'261'80C 8-54 LESSONS CATEGORY A TECH SPEC 091'201'81C c_o""-p~W . .1,../'Z...1,. [ec Co"-plJI.~ +-IL"-Jso SE..~---**-*** S~IZ.. -e R-1208731-001 1 SURRY 1 TAC NO. MPA I ~42867 ... 8-59 ' M42468 8-60 ~4~!_08 8-61 42779 8-62 1143942 B-63 '147167 B-66 ~46_862 8-69 46636 B-70 ~49762 B-72 '152805 B-76 152886 B-77 152967 B-78 153048. 8-79 153103 8-80 153156 8-81 153198 8-82 154573 B-83 153638 B-85 153721 B-86 153804 8-87 153887 B-88 153943 B-89 155380 B-90 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE N0°.'*: 47'1. 03/31/86 (CONTINUATION) LIC ACT LICENSEE TITLE MASONRY WALL DESIGN ENVIRONMENTAL QUALIFICATION COMPLETE

  • STATUS DATE
  • 03/31/86 ---* ----______ J _ ----*---!---------

03/12/85C I 07/28/82C.

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__ . --*** _ ___ ______ _ _ _ . _ --* _______ *--* ___ j_ .. --------. _ ___ ____ -****-. LOSS OF NON CLASS IE I&C POWER *-* -. ESF RESET CONTROL DESIGN DEFICIENCY INTERIM PROCEDURES FOR SHORT TERM_BLACKOUT NATURAL CIRCULATION COOLDOWN 03/11/82C 09/21/81 C 10/19/83C IE8 80-4 MAINSTEAM LINE BREAK.WITH CONTINUED FEEDW 07/14/82C FATIGUE _TRANSIENT LIMIT TS_ __ _ __. 05/25/82C NUREG 0737 TECH SPECS (GENERIC LETTER_82-16) 03/28/84~. ITEM 1.1 -POST TRIP REVIEW; PROGRAM DESCRIPTION & 04/01/85C ITEM 2.1 EQUIPMENT_CLASSIFICATION &_VENDOR INTER 04/30/86 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/13/85C ITEM 3.1.3 -POST MAINTENANCE TESTING -CHANGES TO 11/06/85C ITEM 4.1 -REACTOR TRIP SYSTEM RELIABILITY -VENDO 12/13/85C ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 05/03/8SC ITEM 4.3 -AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 03/31/86 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS_83-:- 10/15/84C SALEM ATWS 1. 2 DATA CAPABILITY SALEM ATWS 2.2 S-R COMPONENTS SALEM ATWS 3.2.1 & :s'.2.2 S-:-R COMPONENTS SALEM ATWS 3.2.3 T.S. S-R COMPONENTS SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS SALEM ATWS 4.3 WAND B&W T.S. 06/12/85C 01/31/87 12/13/8SC 11/06/8SC 01/31/87 03/31/86 e ! . ' . Co..-.c.pt~-k..d 4../1 /es se:. '2.. -...... p1.c2...-i:e.d IZ./J ?./85 :=>E..12.. -~Pl.L~ \I / (o /B5 s~ Co~l.L-k!...O 12/ 13/e,s 5.E.R... . co ... ,c.pla. kd 5 /3 /85 SE.~ lo/12../S5 Cb.-.c.pl.Q.{eO IZ../1?./e,.s S*.~ Cb ..... p1e.-led \\ I ~Ls£. _ .sc..rz.. R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C k I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE Nb.: 4~5 03/31/86 SURRY 1 C CONTINUA TI ON) TAC NO. TITLE _M54114 ____ B-92 SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES B-93 LIC ACT COMPLETE. 12/_13/85C 01/31/87 ' M54031 M08251 SALEM ATWS_~.5.2 & 4.5.3 TEST ALTERNATIVES .. *~ . **--. -C-01 _____ P_W~_ SECONDARY. WATER CHEMISTRY MONITORING REQUIREME 12/18/80C M08617 C-04 FILTER __ TECH SPECS _ .. __ . 01~.1_7/84C. 04/17/81C 01/16/85C

*-M0851_8_ ...... _C:::06 M08620 __ C-07 ... ~UMP. SUPPORT-LAMELtAR_JEARING FUl:L. HANDtING __ AC.Cil>ENT INSIDE CONTAINMENT M08084 M43667 M52276 M58094 M07875 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 05/16/84C C-14 AUXILIARY FEEDWATER_SEISMIC QUALIFICATION_

08/20/82C C-15 CONTROL OF HEAVY LOADS -PHASE II CFOLLOWUP OF MPA_ 06/28/8SC C-16 _____ UTILITY_ R_ESPDNSES TO STAFF RECOMMENDATIONS CONCERN 01/31/86C D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE_WITH 10_CFR-OS/09/79C M07857 ........ _D-03 PRESSURIZER HEATUP RATE ERROR 09/27/78C M11974 M08521 M08999 M12277 M13076 M43011 M55908 1 M10388 M44059 M44130 M44201 D-04 PWR REACTOR VESSEL __ <<;:AVITY:_ SEAL RING MISSILE POTENT OZ/10/84C D-10 ASYMMETRIC LOCA LOADS 02/01/84C D-11 ...... J:ISSION GAS RELEASE 02/2S/80C D-15 HIGH ENERGY LINE BREAK & .CONSEQUENTIAL SYSTEM FAIL_ .... 02/02/84C ...... . D-16 REVIEW OF CORPORATE MANAGEMENT CAPABILITY .05/22/81C D-17 DEFINITION OF OPERABLE 01/01t70C 0-19

  • DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15) 09/27/85C E-05 H N-1 LOOP OPERATION F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR F-02 I.A.1.3 SHIFT MANNING F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 01/30/8~ 01/06/82C 11/05/81C 11/05/82C LICENSEE I STATUS DATE ! ~o.....,ple_+w\

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/ 9 /~/ 8 I i IE.If. a, -2.2 I I . I .. j r-1203131-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P l E M E N T A T I O N ;URRY 1 C CONTINUA TI ON) "AC NO. .MfA._! TITLE LIC ACT COMPLETE 144272 44342 47255 47327 51208 51288 44409 47978 44480 44551 44622 12639 44694 44733 44819 44890 ~496_1 45032 45103 47639 47710 47781 45173 F-04 I.C.1.2/3,A EMERGENCY OPERATING PROCEDURES GENERIC F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 06/13/84C 11/05.185C F-06 I.C.5 F-07 I.C.6 FEEDBACK OF OPERATING EXPERIENCE 11/05/81 C CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/05/81C F-08 F-09 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA I.D.2 SAFETY PARAMETER DISPLAY SYSTEM ----*----*. -** -*** F-10 11.B.1 RCS HIGH POINT VENTS F-11 11.B.2 PLANT SHIELDING F-12 II.B.3 POST ACCIDENT SAMPLING F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE F-14 11.D.1 RV AND SY TRAINING F-15 F-16 F-17 F-18 F-19 11.E.1.1 AFW SYSTEM EVALUATION II.E.1.2.1 AFH SYSTEM INITIATION II.E.1.2.2 AFW SYSTEM FLOW INDICATION 11.E.4.1 DEDICATED HYDROGEN PENETRATION 11.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY F-20 II.F.1.1 NOBLE GAS MONITOR F-21 II.F.1.2 IODINE/PARTICULATE SAMPLING 10/10/84C 05.t02/85C 09.112/83C 10.131/83C 02/27.t84C 11/05.t82C 01/31/86 04.t27.t82C 08.107/81C 08.t07/81C 08/24/81C 12/07/82C 10/01/81C 10.101/81 C F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/07.t82C F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04.t22.t83C F-24 II.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 04.122/83C F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/22.t83C F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09.121/84C LICENSEE STATUS >>.lli .. -. --** ..... .! -,' -i--.. 2-/ 1/95 -.U>-.pla~ 2..I, J 95 , <!..el~ I.A-\.e..d . _Z, I , / 8 S . ______ .. :C.O~la.~. 0/zB/81 C0n.t.pla...~ . 12./=,. /82.. PAGE NO.-, 476',, 03/31/86 .IE.Iie . B4:-lO .. ::C.EI.'2 .. 'B-4 -10 :c.e.xe. S4-IO . SE.~. se:e ..,/ ~~Jg+ e ! R-1208731-001 SURRY 1 i TAC NO, MfLl 1 M46907 F-30 M47821 F-33 M45251 F-36 M45297 F-37 M45383 F-38 M45414 F-39 M45463 F-40 M45493 F-41 M45523 F-42 M45669 F-47 M48434 F-53 M45866 F-57 -M48206 F-58 M45985 F-63 M46056 F-64 M46128 F-65 M46200 F-66 M46272 F-67 M46344 F-68 . M46415 F-69 M46484 F-70 M56170 F-71 M49681 G-01 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N (CONTINUATION) TITLE II.K.2.13 THERMAL-MECHANICAL REPORT II.K.2.17 POTENTIAL FOR VOIDING IN RCS II.K.3.1 AUTO PORY ISOLATION II.K.3.2 REPORT _ON PORV FAILURES II.K.3.3 REPORTING SY AND RV FAILURES AND CHALLE II.K.3.5 AUTO TRIP OFRCPS _____ .... II.K.3.9 PID CONTROLLER LIC ACT COMPLETE LICENSEE STATUS DATE i PAGE Nb. : r,.:77_ 03/31/86 . __ I I I 1------! *-**. -' ...... !. I I -I ***.* --+-i l e -. ----------!I II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 11.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 06/15/84C 01/09/84C ' 09/16/83C 09/16/83C 02/11/82C 02/22/83C. 08/28/81C 08/28/81C 08/24/81C 08/08/83C 06/24/82C 05/24/85C 12/31/.86 .. 01/01/87 . -.. ----*****--* !" **-.... _,, ..... -----*-! II. K. 3 .17 ____ ECCS OUTAGES II.K.3.25 POWER ON PUMP SEALS I I. K_. 3. 30_ SB L OCA "1ETHODS II.K.3.31 COMPLIANCE WITH10 CFR_S0.46 III.A.1.2 TECHNICAL SUPPORT.CENTER III.A.1.2 OPERATION~L_S_UPPORT CENTER III .A.1 .2 EMERGENCY DPERATIONS _FACI_LITY ..... . III.A.1.2 NUCLEAR DATA LINK III.A.2.1 EMERGENCY PLAN UPGRADE_ro MEET RULE III,A.2.2 METEOROLOGICAL DATA UPGRADE III.D.3.3 IMPLANT RADIATION MONITORING 'III.D.3.4 CONTROL ROOM HABITABILITY I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP TO . . REACTOR COOLANT PUMP TRIP CD660 -II.K.3.5)

*---.. --* 01/01.187

--* *****-* 01/01,.18~ ... 07/30/82C 05/13/83C 01/01/87 02/19/82C 06/28/82C 06/30/86 05/31/86 I *, ! ** t----i -; __ ,. ' i i ! ) . . . . --*** *---------1------***-----****--**---------- -*I ..... I .........

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---* ... -I ..... ----/----------***-- ... --. -*--. .... .. . . -* .. ------------* i R-120.8731-001 FACILITY: SURRY 2 REG.UL ATOR Y INFORMATION TRACKING SYSTEM FACILITY IMP LEM.ENT AT ION PROJECT MANAGER: T. CHAN PAGE NG. : 47.8 03/31/86 PLANT LOCATION: 17 Ml NW OF NEWPORT NEWS, VA DOCKET NUMBER: 050-00281 LICENSED POWER1 2441 MWT DESIGN POWER: 0788 MWE BRANCH CHIEF: L. RUBENSTEIN ARCH/ENGINEER: S&W NSSS VENDOR: WEST . LIC. ASSISTANT: VACANT IE INSPECTOR: D. BURKE TAC NO. Hf.LI }'.1083_36 A-01 M08103 A-02 M08367_ . A-03 M08639 ______ A-04 TITLE 10 CFR SO.SS ACG) -ISi APPENDIX I -ALARA SECURITY REVI_EWS-MODIFIED AMENDMENT PLANS APPENDIX.J -CONTAINMEN,: LEAK TESTING M08515 A-06 RESPIRATORY PROTECTION SYSTEM . -LIC ACT LICENSEE COMPLETE STATUS DAT!;_ 02/07/83C . _________ 06119184C 02".27!79C ___________ .---___ _ 05119181C_ 09111/79C _ . __ . __ . M11389_. A-09 . PRES_SURE __ VESSEL BEL T_LINE _MATERIAL SURVEILLANCE----------* 0311.1 !80C ________ -***----*-***---* i--****--****--****------****

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M1049S M10494 M10492 A-10 Cotft:INGENCY_ PLANNI_NG ____________ .. A-1J GUARD TRAINING PLANS_ _ _ _ ____ _ A-:-1.2 . _VITAL. AREA ANALYSIS. 09104180C 12/.18/80C .. ____ . . 04112/82C ______ ........ . M11217 _ A:-:14_ 1 OCFR SO. SS ACG) -_INSERVICE TESTING . .. ________ ... 1 0/22/82C ___ _ M12754 _"1_41_~6_7 M51139 M56491 M59148 M59989 M07907 M07221 M10812 M08402 A-1 S QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARA_T _ 04IJS180C A-16 . ----------A-17 A-18 A-20 QUALIFICA_TIONS Of EXAMINATION,INSPEC.IION, TESTING 04112/82C INSTRUMENTATION TO FOLLOW THE COURSE OF _AN_ACCIDEN_ 12/31186 TECH SPECS AFFECTED BY 50.72 AND 50.73 COL 83-43),,c_;,Q612/11185C 10 CFR_ SO. 62 __ 0PERATING REACTOR REVIEWS A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE B-01 DIESEL GENERATOR LOCKOUT B-02 FIRE PROTECTION B-02 FIRE PROTECTION B-03 PWR MODERATOR DILUTION 12/31186. 12/31186 OSl19181C 09119179C 09/19179C 06/08181C I J Co ""'I' 1~,4,c.d I t I R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE NIJ. : 'i19. 03/31/86 SURRY 2 C CONTINUA TI ON> TAC NO, MPA I TITLE LIC ACT COMPLETE M08343 8-04 ____ REACTOR VESSEL OVERPRESSURE PROTECT.ION _,:1_066_97 ______ B-11 ________ nooD Of __ EQUIPMENT_ _I_Mi:'llR:J:~NI .. J_O _SAFEJ)' ________ _ -----*------ 03/04/80C. 12/18/80C ' 12/20/79C 07/07/80C _ 04/01/81C 08/17/82C 08/25/80C ! M08642 M08507 B-12 STEAM GENERATOR TUBE INSPECTION B-14 CEA GUIDE TUBE WEAR , M12161 __ B-16 ____ EMERGENCY_PLANNING_AND REVISIONS I M08510 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS M1 0214 _____ B-:-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION_ M10338 8-21 LOSS O_F_J 25"'.'V DC BUS VOLTAGE WIJl:I__LOSS OF ANNUNCIA M08512 8-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL M10054_~--- 8-23 DEGRADED GRID VOLTAGE 03/01/82C 08/17/82C 10/0S/82C M42563 M10009 M10235 M08537 _M0.8366 M08368 M08364 M08684 M11092 0 M47397 Mt 1714 M12011 M13129 8-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 11/17/82C 8-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 04/02/80C 8-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 8-30 _STEAM GENERATOR REPlACEMENT PROGRAM B-30 STEAM GENERATOR REPLACEMENT PROGRAM .. 8-31 LONG SHAFT LHSI & OUTSIDE RECIRC. PUMP DEGRADATION B-32 BLOCKED SI SIGNAL DURING COOLDOWN 8-39 PWR PRESSURE -TEMPERATURE LIMIT TECH SPECS B-41 FIRE PROTECTION -FINAL TECH SPECS CINCLUDES SER s 8-41 FIRE PROTECTION -FINAL TECH SPECS C INCLUDES SER s 8-42 TMI FOLLOW UP -All PLANTS 8-42 TMI FOLLOW UP -All PLANTS B-42 TMI FOLLOW UP -All PLANTS 09/14:l79C 01/20/79C 01/20/79C. 03/1S/82C 04/01/82C 11/13/SOC 01/17/84C 11/_18/82C 01/30/81 C 09/06/79C 05/28/SOC LICENSEE STATUS DATE lc..o".'4-pl~:1*~.d 3/4/eo A,..,,.~e,,,f ss ! __ : CJ:> .-.y, l¢:kd I 'Z. /ia / So St. e, e 3/ 4/80 s/z.e/e,o I R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE No*:: 480. 03/31/86 SURRY 2 (CONTINUATION) LIC ACT LICENSEE TAC NO I .MfU TITLE COMPLETE . STATUS DATE I ~~3_! 5~ _______ B:::4} _______ PWR FEEDWATER __ LINE_ CRACKS_ ...... ------**-*---****--- .. -*-*--*---

.. *-------***05/_25/82C.

.. ____ lji **--**-**-*-**-**--***-**-1 1: ________________________ =~------___ --_-_*_--_*_-~_--- __ -*_--_*-_--*_--* M11778 ______ B_:::_~3 ___ PWR FEEDWATER LI_NE_CRACKS_______________

02/25/80C

_ _ _ _ __ __ ... _ M30668 ____ B-44 ____ LESSONS_J,EARNED IMPLEMENTATION ...... ______ *------------- ........... 04/_24/80C:: _________ _ '130669 1'130670 1130671 '130672 130673 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/SOC .... **-*----* .. **--*-*--------***--**--

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---* -**---*---- --*------- B-44 LESSONS LEARNED IMPLEMENTATION 04/24/SOC B-44 LESSOt-lS LEARNED IMPLEMENTATION 04/24/80C. B-44 LESSONS L_EARt-l_ED_ IMPLEMENTAJ.ION __________ _ _ ____ ....... _04/24/80C B-44 ___ Lf:S~ON~ __ LEARNED IMPLEMENTATION_ ........ ___ ... . 130674 ______ ~-::~_, _____ _LE_S~ONS _Ll;A~NED _JMPLEMENJ"ATION ____ . __ _ _______ __ ... __ . 04/24/80C 04/24/80C '130675 B-44 '130676 B-44 '130677 B-44 ~30678 B-44 130679 B-44 130666 B-44 130667 B-44 ~12938 B-45 112580

  • B-46 112688 B-47 112977 B-48 ~47403 B-49 111879 B-52 143204 B-54 LESSONS __ L EA_RNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION

_04/24/80C 04/24/SOC 04/24/80C 04/24/SOC 04/24/80C 04/24/80C 04/24/SOC WASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C ANALYSIS OF TURBINE DISC CRACKS 08/19/81C Eccs,_CLAD SWELLING AND _RUP_TURE_ ... -** .... ADEQUACY OF_STATION ELECTRIC DISTRIBUTION_VOLTAGE PWR CONTROL ROD MISALIGNMENT _ 09/12,(80C 10/14/83C __ . 06/17/82C REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 11/26/80C LESSONS CATEGORY_A TECH SPEC 09/29/81C . I I lc.o""-p l.Q....+Ea . ;. ... -+I u-/ e,o ____ ... $'. tse.. ____ .... . ........ :Co.-.A.f La...+.e.d' L/z._4/ 8 C . SE;f.. .. . e -1 .Cb ""'4'( tied 4/ZAr/B,O ... :Cof'\.\.p LG..-k.d . 9 /iz./ac . -1208731-001 URRY 2 REGULATORY INFORMATION TRACKING SYS T* EM F A C I L I T Y I M P L E M E N T A T I O N . <CONTINUA TI ON) PAGE NO; ,'. 481* .. 031'31/86 At NO. MPA I TITLE LIC ACT COMPLETE LICENSEE 42102 ____ 8-57 -*** DHR_CAPABILITY

  • -------------------*

-*-*** _____ _ 05/12/81C 42868 B-59 MASONRY HALL DESIGN ___ ,_03/,3_1!86 _________ ,}, ..... --_. 42469 42709 _B_-:-_lQ_~NV I R()tU'1ENJ A_L ____ QVAL:J fJ~AT IJJ,,_. .. _ ... ... .. ..... __ . *. . ..... ________ 03/_12/85C B-61 LOSS OF NON CLASS IE I&C POWER 42780 8-62 ESF RESET CONTROL DESIGN DEFICIENCY 43943 8-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT ----* ------------*-----*----------. **-------"-*-*-***-----*

_, -*-... , .....................

-.*... 47168 B-66 NATURAL __ C_IRCULATION COOLDOWN 07/28/82C 03/11/82C 09/21/81C

  • 10/19/83C 46863 B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDH 07/14/82C

_ _::.c.:c:,:_ ___ . .... . . 46637 149763 152~_06 152887 52968 -------~-B-70 B-72 8-76 --B-77 B-78 FATIGUE_J~~NSIENT LIM~~.TS _NUREG 0737 TECH_SPl;CS (GENERIC LETTER 82-16) ITEM 1.1 -POST TRIP REVIEH1 PROGRAM DESCRIPTION & ITEM 2.1 -~QUIPMENT CLASSIFICATION & VENDOR INTER ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 05/25/8ZC 03/28/84C 04/01/85C 04/301'86 12/131'85C i STATUS DATE I I "*-**1 ... --.............

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  • I t -z-/i 3 / 8/S _ ,, J <o/85 .SE.~. se.~ ~e.f... 8-80 153157 B-81 ,53199 8-82 154574
  • B-83 153639 B-85 153722 B-86 153805 B-87 153888 B-88 153944 8-89 I ITEM 4.1 -REACTOR TRIP SYSTEM RELIABILITY

-VENDO 12/131'85C 1 Cor.tpl.D.~

  • --12./1~/85 ITEMS _4. Z .t_~ ___ ,_~0 2_~2 ___ :PREVENJA.Il"~--fitA_I_N,:_PROG FOR R ITEM 4.3 -AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-SALEM ATWS 1.2 DATA CAPABILITY SALEM ATWS 2.Z S-R COMPONENTS SALEM ATWS 3. 2 .1 & 3. 2. 2 S_-R COMPONENTS . SALEM ATWS 3.2.3 T.S~ S-R COMPONENTS SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS 051'03/85.~----------------. ic.o"""-PLA-+e,L__

5 /3 /BS __ . :_ I 03/31/86 10/15/84C 06.112/85C 01/31/87 _ 12/131'85C _ 111'061'85C 01/31/87 I . I . I I I I .Co~p\..QJ.ed ! I i fU>--1 u..-k:d I :~""~:c-ed \ I .Co I 12../8'5 11.../1a Le~ ll / Of:, /'B':> . SE.~ e I R-12087 31-001 SURRY 2 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M

  • F A C I L I T Y I M P L E M E N T A T I O N (CONTINUATION>

LIC ACT LICENSEE TAC NO. MPA I TITLE COMPLETE* STATUS .Dill I PAGE NO':: 482 03/31/86 M55381 B-90 SALEM ATWS 4.3 WAND B&H T.S. 10/31/87 i i **------**-* -*--* ... . *-**-******-**-***

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M541_!5 ____ ~:_9~---s~~EM ATWS 4 .5 .1 DIVER_SE TR_Ii:>. F:EATU_~_ES _____________________ ---* 12/13_/85<: __ ~----______ . ______ !eo~p\..t.~-1 1 1 z. / 13-/ss. I ... _ s e:.ft. _____________ _ 1-~5_4~~2 ____ B-9_3 ____ ~A_LEM ATWS 4.5.2 & 4.5.3 TEST ALTERNATIVES _ 04/30/87_ ____ _ j_ __ . _1 _

  • __ l .. ___ *-*--__ _ M08252 c-01 ______ PWR_SECONDARY WATER_CHEMI~T.RY MONI!ORIN<3_REQU_IREf'1E__

12/18.180C ... ;eo~pLA..-k...d \ \"L/1,e,/eo ! h~ __ <a, i ! ! M08~!_6 _______ C-_O_~--__ [I~_TER TECH SPECS ----------*-*** _________________ _________ _ . _01(,?/84C. . .... ___ . ----b'""-plo:kd !_ ___ l/r1 /eA _ / M08517 **-* _ c_~o~ ___ _!Y.f'l~_SUPPORT-LAMELLAR _TEARING _____ ----*--*--*--*---------------** ... 04/171'81 c __________ ,. ___ -*** .... _ i-.-M08619 C-07 M08085 C-10 IM43668 C-14 M52277 C-15 ---------*----- M58095 C-16 -IM07876 D-02 M07858 I -* ------D-03 J"l1_1975 D-04 M08520 D-10 IM10000 D-11 I IM12278 D-15 1 M13077 D-16 I 1 M42186 D-17 IM43012 . D-17 M55909 D-19 M08514 E-03 M10389 E-05 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 01/16/85C CONTROL OF HEAVY LOADS OVER_ SP_ENT FUEL POOL (PHASE_ .... 05/16/84C AUXILIARY FEEDWATER SEISMIC QUALIFICA"[ION _________________ 08/20/82C __ --~ON_I~_OL_~I:: _ HEA~y_ JO~IJ_~ _: __ f>HASE II _ __( FOL LOWU~ __ Of: __ MPA UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN ------. -*-***-*-___ ECCS . ZIRC CLAD MODEL ERROR-COMPLIANCE WITH. 1 0 CFR.~ PRESSURIZER HEATUP RATE ERROR -** **----***-06/_28/85C 01 ! 31 /86C .... *-** ____ ..... 05/09/79C 09/27/78C 02/10/84C ! -*! ' ' .. 1 I ;eo"'.'lpLQ:k.d

  • ... -!* .. , PWR REACTOR VESSEL CAVITY __ SEAL RING MISSILE POTENT ... ------.. -------------------

* --ASYMMETRIC LOCA_L~ADS FISSION GAS RELEASE . _____ ....... ___ 02/01/_84C 02/25/80C HIGH ENERGY LINE.BREAK

& CONSEQUENTIAL SYSTEM FAIL 02/02/84C REVIEW OF CORPORATE MANAGEMEtU _CAP)'BILITY 05/22/81C DEFINITION OF OPERABLE 02/06/81C DEFINITI_O_N OF _OPERABLE . .. .... .. . 01/01/70C DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15> 09/27/85C CORE RELOADS REQUIRING PRIOR NRC APPROVAL W N-1 LOOP OPERATION 10/31/79C 01/30/81~,,. 1 *** -1 I i l .. -*--**---- .... i *1 I . i .. l z./z.s/so e R-1208731-001 R E O U L A T O R Y I N F O R M A T I O N T R A C k I N G S Y S T E M PAGE NO;:' 48'3 031'311'86 SURRY 2 11 TAC NO, M44060 Hf.LI F-01 I.A.1.1 C CONTINUA TI ON) TITLE F A C I L I T Y I M P L E M E N T A T I O N LIC ACT COMPLETE* LICENSEE STATUS DATE I SHIFT TECHNICAL ADVIS_O~-----**"**- ..... _. . _ OV06_1'82C !cOt--4'lA...-i...e_d [ 12,/22,/eo .. l IE.I£ .80. -_++ M44131 _________ F-02 _ I. A .1 ._3 __ , SHIFT _MANNING*-*- ...... _ ............ _ .... _ ... _ i i . ..... -...... , ... ____ 1J!_Q,5~8_1_ <<; _____ : :_ .. , --_,, ---** .. -1 ~IA.~. j ... ll / z.o /81 _ __;, __ ,r ~I Ii!. _,~ L-. ?>. L. .... '1_44202 M44273 F-03 F-04 F-OS F-06 . I : I.A.2.J UPGRADING OF RO AND.SRO TRAINING . .. 11/0S/82C _ ..... J6>""-f'u.k.d 1* 9/4-/.BI .. 1 .:t'EJ:,.~ et_-2..2.. . I.C~1_.2/3.A EMERGENCY OPERATING PROCEDURES __ GE~ER.I.C 06/28/84C

  • -*-----!-_ .-. .........
    • .... . ... . 1 ........... . L . . I I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 11/0S/8SC I.C.5 FEEDBACK OF OPERATING EXPERIENCE 111'051'81C

./e!c"4"'la...kd f 11 / 2.o / 81. : .Ie...I..~ Bl_:_ F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/0S/81C b'""'l'lo+e.D l t1/2.o/al '. Ie.I~ _81-3 I . F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/10/84C_.,, **--.. . I , I F-09 I. D. 2_ .. _____ .. SAFETY PARAMETER DI_SPLAY _~_Y'STEM OS/02/8SC ... ,! _ F-10 II.B.1 RCS HIGH POINT VENi:s ___ ... ____________ .. 09/12/_83C / . -*----;~1~*--*II.B.2 PLANT SHIELDING _______ ,, ______ 101'311'83C . . ,~~~-1.e..d: 10/31/e.3 .. , I.E.I'2. B3-2.3 I . _F-:12 II.B.3 POST ACCIDENT.SAMPUNG. . 02/27/84C i F-13 II. B, 4 TRAINING FOR MITIGATING CORE DAMAGE __ .. 111'051'82C ... I .. \ F-14 .II.D.1 RV AND SY TRAINING 01/311'86 ! . 44623 12640 4469S . F"."1 S __ II. E.1 .1 AFW SYSTEM EVALUATION 04/27/82C r-----*----

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'. Z../c/8.5 . IE.I~ 8~-ID ! C4'.>"4)l4:J-ed '.. 2/i/85 .'. 1.E.1~ .. 84-:-tO _ F-16 F-17 F-18 F-19 44962 F-20 4S033 F-21 45104 F-22 47640 F-23 II.E.1.2.1* AFW SYSTEM INITIATION .. ______ 08/07/81C II.E.1.2.2 AFH SYSTEM FLOW INDICATION 08/071'81C II.E.4.1 DEDICATED HYDROGEN PENETRATION 081'24/81C II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 12/071'82C II.F.1.1 NOBLE GAS MONITOR 101'011'81C II.F.1.2 IODINE/PARTICULATE SAMPLING 10/01/81C II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 011'071'82C II.F.1.4 CONTAINMENT PRESSURE INSTRUMEN.T 04/221'83C. . ' : Ctt,~-1-ea i I :* i :1-ed I !CJoN.p~ i I ' I I I ~r-.t.f'lL~ I I I ; ! . f ........... 'Z./ 1 /e5 ! .IE 12 "e,4-e _ atz..sts,

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  • 04/22/83C 04/22/83C M47782 M45174 M46908 M47822 F-26 II. F .2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09/21/84C F-30 II.K.2.13 THERMAL-MECHANICAL REPORT F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS '1145252 F-36 II.K.3.1 AUTO PORV ISOLATION F-37 II.K.3.2 REPORT ON PORV FAILURES ____________

_ 06/15/84C 01/09/84C 09_/16J'83C 09/16/83C '1145298 1145384 145415 145464 F-38 II.K.3.l REPORTING SV AND RV FAILURES AND CHALLE 02/11/82C F-39 II.K.3.5 AUTO TRIP OF RCPS F-40 II.K.3.9 PID CONTROLLER '145494 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 145524 145670 '148435 '145867 '143207 145986 146057 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP F-47 II. K. 3 .17 . ECCS OUTAGES F-53 II.K.3.25 POWER ON PUMP SEALS F-57 II.K.3.30 SB LOCA METHODS F-58 II.K.3.31 _ COMPLIANCE_ WITH 10 CFR 50.46 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 146~29_ .. F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 146201 146273 146345 146416 F-66 III.A.1.l NUCLEAR DATA LINK F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/22/83C 08/28/81C 08/28/81C 08/28/81C 08/08/83C ____________ _ 06/24/82C 05/24/85C 12/31/86 01/01/87 01/01/87 01/01/87. 07/30/82C 05/13/83C 01/01/87 02/19/82C LICENSEE STATUS .Dill ! . ! -I i -**"--*---*. --*--.\ PAGE No::' 48A 03/31/86 e -... -L e R-1208731-001 SURRY 2 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N (CONTINUATION) PAGE Nfl.': , 6~8*5 03/31/86 LIC ACT LICENSEE *1 TAC NO. MPA I TITLE COMPLETE* STATUS I DATE .!".!~6485 __ F-70 .. I.~.LJ!~ __ 3,. __ 4 __ CONTROL __ ROOM _HABITABILITY ...... ----****-_ -*----.. _ ... 06/28/82C ___ .. _______________

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2. ... -R-12087 31-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M FACILITY IMP L .EM ENT AT ION PAGE NO.: 298 03/31/86 FACILITY:

NORTH ANNA 1 PLANT LOCATION: 40 MI NH OF RICHMOND, VA. DOCKET NUMBER: 050-00338 LICENSED POWER: 2775 MHT DESIGN POWER: 0907 MHE ARCH/ENGINEER: S&H NSSS VENDOR: WEST IE INSPECTOR: M. BRANCH LIC ACT IA~ HQ, tteA....I UIL~ cor,PLETE" > M12245 A-01 10 CFR 50.55 A<G> -ISi 06/20/83C M08147 A-02 APPENDIX I -ALARA 05/05/83C M11532 A-03 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS *o5/02/79C M11386 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURV Ell LANCE 06/041'76C M11574 A-10 CONTINGENCY PLANNING 10/03/80C H11575 A-11 GUARD TRAINING PLANS 03/20/81C M12089 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 02/13/8DC M48123 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/*05/82C M51110 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN M54505 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 <GL 83-43) 02/01/85C M59117 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S / M59965 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M12149 B-16 EMERGENCY PLANNING AND REVISIONS 08/21/80C M13096 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 08/05/80C* M46944 B-17 TECH SPEC SURVEILLANCE FDR HYDRAULIC SNUBBERS 11/05/81 C M46946 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHAN.ICAL 11/05/81~ ,* 0 M48336 B-23 DEGRADED GRID VOLTAGE 12/281'79C . M42589 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 04/201'83C M13116 B-24 VENTING AND PURGING CONTAINMENTS WHILE -AT FULL POW 11/21/80C M10161 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 11/21/SOC PROJECT MANAGER: L. ENGLE BRANCH CHIEF: L. RUBENSTEIN LIC. ASSISTANT: VACANT LICENSEE e,.oM JI.\E"NTII STATUS .DAll (. OIM \f' le. \-i?cl_ ,q%3 Stl2.. C..o'W'-lj>le..kJ 'I gq Amenc:l.me~t 48' C..e>-v.t\~le.W \'1'l°l Arne~,cl~V\t '1 C..o IM\,P le tecA \98'0 Am~.newtt 2.o Co'N\r\~ l'l8 l A tVlell\QWI f V\ t z. s C..0'<1'f te.tecl \9lf2.. NRC.. t..e.:~t.. C O\M.\') \.e. kcl zlS5 Amevi&rnev,t ~3 pt" o.j e_(..{.e cl. . not sc:..h~d.uled. ~nj Le-1/Zifll c.o~yAe.t~ I Ii~ C..OW\fl~ktl 1jas (otn~TIJ 1/-,t/a-5 Comf~~J.. l<t8D .A rnl!V\Cffi1&1.t I~ C..o IMf \.e kcA lq&I Am.~vtd.111\e. v1t 3 3 C..t>wtV)l..e tw.. I 't &-'I _Awte_wl rf\(:'V\t 33 A rnevid. Jl'\evtC J(o Co11v1\ole.ted \'ti<} c~~\e..t-e<\ 1q&3 SER. (Cv,,'\~~d.. l980 N~C. Le..tler C:.C,v.l\ 'f' le.~ \~iD N c.. Le;tk:.,\., R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE NO. : 299 03/31/86 NORTH ANNA 1 TAC NO. tteA.....l C CONTINUA TI ON) une LIC ACT COMPLETE .M46507 M43143 M30694 M30695 M30696 M30697 M30698 M30699 M30700 M30701 M30702 M30703 M30704 M30705 M30706 B-41 FIRE PROTECTION -FINAL TECH SPECS (INCLUDES SERS 11/18/82C B-43 PHR FEEDWATER LINE CRACKS 05/25/82C B-44 LESSONS LEARNED IMPLEMENTATION 04!~3/80C ' B-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C B-44 LESSONS LEARNED IMPLEMENTATION 04/23/SOC B-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C B-44 LESSONS LEARNED IMPLEMENTATION B-44 B-44 B-44 B-44 B-44 LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION 8-44 LESSONS LEARNED IMPLEMENTATION B-44 LESSONS LEARNED IMPLEMENTATION B-44 LESSONS LEARNED IMPLEMENTATION M30707 B-44 LESSONS LEARNED IMPLEMENTATION M12524 B-44 LESSONS LEARNED IMPLEMENTATION M12929 B-45 HASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR M12605 B-46 ANALYSIS OF TURBINE DISC CRACKS 0 M12680 B-47 ECCS; CLAD SHELLING AND RUPTURE Mt 3109 B-48 ADEQUACY OF. STATION ELECTRIC DISTRIBUTION VOLTAGE M42113, B-57 OHR CAPABILITY M42895 B-59 MASONRY HALL DESIGN 04/23/80C 04/23/SOC 04/23/SOC 04/23/SOC 04/23.180C 04/23.IBOC 04/23/80C 04.123.IBOC 04/23/80C 04.123.IBOC 04.123/80C 04.120.181C 08/31.18..tC 07.130/SOC 11.113.184C 06/02/81C 09.103.185 LICENSEE STATUS c.~v~pLe._4-e_J. \980 C:.o""i>>~ l.ttte-}So e,o mp ~.i.-ecA. \ <\ t O Sc R , c.,o *""1~ LeJ~_cl I <\ t0 SE 12. CoW\ y,\.d-e.ol uo\J"'-pLde~ ~rr,'f~~ U> VY'\ f' l,t_-f;eol C.OW\.{J\.Q_:k,c\ (_.C vY\ (J li_.{e_d._ \ 1.j%5 ll I e Co,"'fll:j ~1r 12/23/85 A r,,e,1dr~v1t .3 2 -12087 31-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N . PAGE NO.: 300 03/31/86 JRTH ANNA .1 C CONTINUA TI ON> 12497 i2688 12759 i,3941 ,7152 TITLE B-60 ENVIRONMENTAL QUALIF.ICATION I . B-61 LOSS OF NON CLASS IE II~ POWER B-62 ESF RESET CONTROL DESIGN DEFICIENCY B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT B-66 NATURAL CIRCULATION COOLDOHN LIC ACT COMPLETE 12/12/84C 07/28/82C 09/Q4/81C 08/20/81C 10/19/83C 16845 B-69 IEB 80-~ MAINSTEAM LINE BREAK WITH CONTINUED FEEDH 09/30/82C ,9742 i2777 ,2858 i2939 i3020 i3081 i3134 i3181 ;4549 i3610 ,3693 ,3776 ,3859 ,3921 ,5363 B-72 B-76 B-77 B-78 B-79 NUREG 0737 TECH SPECS* (GENERIC LETTER 82-16) ITEM 1.1 -POST TRIP REVIEHJ PROGRAM DESCRIPTION & ITEM 2.1 -EQUIPMENT CLASSIFICATION & VENDOR INTER ITEMS 3.1.1 & 3.1 .2 -POST MAINTENANCE TEST PROCEDU ITEM 3.1.3 -POST MAINTENANCE TESTING -CHANGES TO 01/12/84C 03/29.185C 12/06/85C 11/21/85C B-80 ITEM 4 .1 -REACTOR TRIP SYSTEM RELIABILITY -VENDO 06.124.185C B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROO FOR R 04/24.185C B-82 ITEM 4.3 -AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07.124/84C B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-06.128/85C B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/14/85C B-86 SALEM ATHS 2.2 S-R COMPONENTS 12.130/86 B-87 SALEM ATHS 3.2.1*& 3.2.2 S-R COMPONENTS 12/06/85C. B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS B-90 SALEM ATHS 4.3 HAND B&H T.S. 11 /25/85C ,

  • 12/31/86 ,4086 .. B-92 SALEM ATHS 4. 5 .1 DIVERSE TRIP FEATURES ,4003 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 12/ 30.186 LICENSEE C.omment STATUS Co'M f>\ e.kcl C.OW\(> \e_ -\t_J.. c.,o Q'(\ '(' ~e-te J.. PfO~e.c.t e.cl ,oJ e.c.te~ ~~le.cl. C.Ol'<\f \.efe.J. flt"Oij~+eA.

py-oj~c.+e.cl. 3\85 l~i7 1q&1 II j S5 C.o."11,:n~ L1t.~ 7/~;p/ 8'S <'..:.ort1'f>~'C\J Lo.t\lr 7/ Zh/~ Seit 4\ t5 SeR \1..\it5 VMP°'Yljk~V' r~l*z.1185" Co\8S seR .* \°187 C.Ornf"<<'j 7/26/85 l 'it7 Co~CU\j lo~-. 1/-zk/KS R-1208731-001 NORTH ANNA 1 TAC NO, .l1fA...1 C-10 C-14 C-15 C-16 D-15 D-17 D-19 E-01 f-01 F-02 F-03 F-04 F-05 F-06 F-07 F-08 F-09 F-10 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE NO.: 301 03/31/86 <CONTINUA Tl ON) TITLE CONTROL OF HEAVY. LOADS OVER SPENT FUEL POOL <PHASE AUXILIARY FEEDWATER Sl:'ISMIC QUALIFICATION CONTROL OF HEAVY 'LOADS -PHASE II (FOLLOHUP OF MPA UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN HIGH ENERGY LINE BREAK I CONSEQUENTIAL SYSTEM FAIL DEFINITION OF OPERABLE DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) SPENT FUEL POOL EXPANSIONS I.A.1.1 SHIFT TECHNICAL ADVISOR I.A.1.3 SHIFT MANNING I.A.2.1 UPGRADING OF RO AND SRO TRAINING I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC I.C.1.2/3.B PROCEDURES*GENERATION PACKAGES <NUREG I.C.5 I.C.6 FEEDBACK OF OPERATING EXPERIENCE CORRECT PERFORMANCE OF OPERATING ACTIVITI I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA I.D.2 SAFETY PARAMETER DISPLAY SYSTEM II.B.1 RCS HIGH POINT VENTS LIC ACT COMPLETE 05/2S/84C 01/21/SZC [)6/28/85C ' 01/22/86C LICENSEE STATUS c..o~y>~~cl c.o I/'{\ IP Le__ W cofv\{> le~c\ (_, (? v-J\ LQ ? ec... \ed.. (.,O VY\ \D(.Q-{e_q CoW\ip~Jed.. C..cw.f le.H d.. \)~oje.L+e.cl (.OW\lf \ e. +eek (.,o V'(\ p l (!.:~ d. \ q'r() <o/8G l919 1'18.3 l 98 l \ Cj '2.. A vnericlvne.n+ L~ ;t"trR e, -L~ St.I'< ~llj ki\-~ 513ojE'tc, se~ se:ie. e tOlSG:> ~P~j ~Hf< 3r,/86 s / 85 ::rc::nz es-' 1... M47112 M43666 M52248 M58071 M12270 M43030 M55880 M10406 M44038 M44107 M44178 M44249 M44319 M47232 M47304 MS1180 MS1260 M44388 M47955 0 M44457 M44S28 M44598 M44643 F-11 11.B.2 PLANT SHIELDING 10/22/81 C 12/10/80C 06/30/86 08/17/79C 01/25/82C 06/30/83C 06/0Z/81C 11/15/84C 08/23/BSC 11/20/81C 11/20/81C 11/19/84C 04/25/85C 10/09/83C 11/14/,UC OZ/27/84C OZ/OZ/82C 06/30/86 06/0Z/81C F-12 F-13 F-14 F-15 11.B.3 POST ACCIDENT SAMPLING 11.8.4 TRAINING FOR MITIGATING CORE DAMAGE II.D.1 RV AND SV i'KAININ&li:~TJNG II.E.1.1 AFH SYSTEM EVALUATION c.. o VY\ f lct. ted.. l (HJ p("oJ ~c.--\-ed I 'i B 8 CcYY\y,ld~d.. l't8 I !el'."~ g 3-tfJ Cbu,nfe"j l4~ \1lts/6'S ):ErR '\$\-\\ R-1208731-001 R E G U L A T O R Y I N F. 0 R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE NO. : 30; 03/31/81 NORTH ANNA 1 C CONTINUA TI ON) TAC NO, M43191 M44722 M44796 M44867 M44938 M45009 M45080 H47616 M47687 M47758 M45150 M46894 M47808 H45240 M45286 M45360 M45403 M45452 M45482 0 M45512 M45646 M48424 M45843 tlfA....I F-16 F-17 TITLE II.E.1.2,1 AFH SYSTEM INITIATION II.E.1.2.2 AFH SYS~M FLOH INDICATION F:-18 11.E.4.1 DEDICATED HYDROGEN PENETRATION F-19 11.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY F-20 11.F.1.1 NOBLE GAS MONITOR F-21 II;F.1.2 IODINE.IPARTICULATE SAMPLING F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR F-23 11.F.1.4

  • CONTAINMENT PRESSURE INSTRUMENT F-24 11.F.1 .5 CONTAINMENT HATER LEVEL INSTRUMENT LIC ACT COMPLETE 11.130.181 C 06.102/81C

.. 1 0.120.182C 06.102/81C 1 0.121.181 C . 1 0.121/81 C 02/05.182C 04.121.183C 04.121.183C F-25 11.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/21.183C F-26 11.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 11.106.184C F-30 II.K.2.13 THERMAL-MECHANICAL REPORT F-33 11.K,2.17 POTENTIAL FOR VOIDING IN RCS ' 06.105.184C 01.124.184C F-36 11.K.3.1 AUTO PORV ISOLATION 10.119.183C F-37 11.K.3.2 REPORT ON PORV FAILURES 10.119.183C F-38. 11.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06.102.181C F-39 11.K.3.5 AUTO TRIP OF RCPS 02.122.183C F-40 11.K.3.9 PID CONTROLLER 06.102.181C

  • F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP F-47 II.K.3.17 ECCS OUTAGES F-53 II.K.3.25 POWER ON PUMP SEALS F-57 II.K.3.30 SB LOCA METHODS 08.125(.81C 06.102/81C 08.117.183C 06/22/82C 06/04/85C LICENSEE STATUS c..o ""-'f IA.. "\eel 2. / '8 '-/ C,O~'-'f>le.kd_
2. /'gt/ Comm~w'\t l:e:r:R. e3-3( .IE-Z: R 8 3 -3 I e U,Vll\\)~e:te.c-A

\ o\8~ IEI~ 04-33 * (..O~\ole..t-4i?.cl \0\8'-t l-EI!e. 81.{-33 R-1208731-001 NORTH ANNA 1 IA~.HQ, MfA._J M48182 F-58 M45962 F-63 M46033 F-64 M46105 F-65 M46177 F-66 M46249 F-67 M46321 F-68 M46392 F-69 M46461 F-70 M56142 F-71 M49665 G-01 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N C CONTINUA TI ON) IIILI; II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 I III.A .1 .2 TECHNICAL SUPPORT CENTER 111.A.1.2 OPERATIONAL SUPPORT CENTER 111.A.1.2 EMERGENCY OPERATIONS FACILITY 111.A.1.2 NUCLEAR DATA LINK IILA.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 111.A.2.2 METEOROLOGICAL DATA UPGRADE III.D.3.3 IMPLANT RADIATION MONITORING 111.D.3.4 CONTROL ROOM HABITABILITY I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP REACTOR COOLANT PUMP TRIP CD660 -II.K.3.5) LIC ACT t!U!leL~U 01/151'87 06/301'86 06/30/86 .. 061'301'86 071'301'82C 051'111'83C 06/30/86 021'181'82C 031'201'84C TO 01/301'86 04/30/16 *ucENSEE STATUS f'<'C>j ec::hc.l p <"C>J e:.c:tQ~ PAGE ND.: 303 03/31/86 e . C.ow.~j l..?fu1r ztu/&s LO\tV\fO'A'j L~ 5j3~~j,

  • R-12087 31-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N PAGE NO.: 304 03/31 /86 FACILITY:

NORTH ANNA 2 PLANT LOCATION: 40 MI NW OF RICHMOND, VA DOCKET NUMBER: 050-00339 LICENSED POWER: 2775 MHT DESIGN POWER: 0907 MWE ARCH/ENGINEER: S&H NSSS VENDOR: HEST IE INSPECTOR: LIC ACT TAC NO. t1f.A...J TITLE COMPLETE ' H47503 A-02 APPENDIX I -ALARA 05/05/83C M47562 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/05/82C H51111 M54506 M59118 H59966 H12150 M46945 M46947 M46508 M48331 M42540 M43948 M47153 M46846 M49743 'M52778 M52859 M52940 M53021 L__ __ ---A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN A-18 TECH SPECS AFFECTED BY 50. 72 AND 50. 73 CGL 83-43) 02/01/85C A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S / A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE B-16 EMERGENCY PLANNING AND REVISIONS 04/12/81C B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 11/05/81C B 1 22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 11/05/81C B-41 FIRE PROTECTION -FINAL TECH SPECS (INCLUDES SERS 11/18/82C B:48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 11/13/84C B-60 ENVIRONMENTAL QUALIFICATION 12/12/84C B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 08/20/81C B-66 NATURAL CIRCULATION COOLDOWN 10/19/83C B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 09/30/82C B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 01/12~-4C B-76 ITEM 1 .1 -POST TRIP REVIEW; PROGRAM DESCRIPTION & 03/29/85C B-77 ITEM 2.1 -EQUIPMENT CLASSIFICATION & VENDOR INTER 06/30/86 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/06/85C B-79 ITEM 3.1.3 -POST MAINTENANCE TESTING -CHANGES TO 11/21/85C PROJECT MANAGER: L. ENGLE BRANCH CHIEF: L. RUBENSTEIN LIC. ASSISTANT: VACANT LICENSEE CJ:, vnm e.n t e A vnev-1cl.rt1ell'lt 3 l STATUS ~ple~J.. l \81.f c.n \-c').,\.e..\..-e.cl l'l %1.. N IR.C.. er c.omple.tt.cl f'l/\:,je.ct-~cl e.,o mflet-~ C,ovtlpl~ ttcl C..OV'II(' le Ho\. C..en1y,Le.*kc:l . comf\e,~ ~j~..\-~cl t) t"O,l U-te..cl CP*"\' le.. tul "2.l&5 Ame.~~e..J; en V\Ot S~u.t~d_ it a ta c.owirit1"..) ~_ttw--I( *2.~1s: 1 j 8 5 G,vn p4~j Le#e-t-1 j *3 I / &t> l q 1 n A mevictrne."1..t 13 1 qa,~ ,Am~-~cl.11>1eV1t; L~ 0185 \'1B1 1 ct 6"1 11 ( 85 S~f?.... ~Wll°crnj Lit"tt~r 1jii.j&5 Cc""P"' 0:J le-tt-e...- 11 Uo / 6-5 S£11{.. R-1208731-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N NORTH ANNA 2 (CONTINUA Tl ON) TAC NO. MfA...J IJILe M53082 B-80 ITEM 4.1 -REACTOR TRIP SYSTEM RELIABILITY -VENDO I M53135 B-81 ITEMS 4.2.1 & 4.2.2 .,.PREVENTATIVE MAINT PROG FOR R M53182 B-82 ITEM 4,3 -AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC M54550 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-M53611 M53694 M53777 M53860 M53922 M55364 M54087 M54004 M47113 M43673 M52249 M58072 M55881 M44039 M44108 0 M44179 M44250 M44320 M47233 B-85 B-86 B-87 SALEM ATHS 1.2 DATA CAPABILITY SALEM ATHS 2.2 S-R COMPONENTS SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS B-90 SALEM ATHS 4.3 HAND B&H T.S. B-92 B-93 c-10 C-14 C-15 C-16 D-19 F-01 F-02 F-03 F-04 F-05 F-06 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL <PHASE AUXILIARY FEEDHATER SEISMIC QUALIFICATION CONTROL OF HEAVY LOADS -PHASE II CFOLLOHUP OF MPA UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) I.A.1.1 SHIFT TECHNICAL ADVISOR I.A.1.3 SHIFT MANNING I.A.2.1 UPGRADING OF RO AND SRO TRAINING I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC I.C.1.2/3,B PROCEDURES GENERATION PACKAGES CNUREG I.C.5 FEEDBACK OF OPERATING EXPERIENCE LIC ACT COMPLETE 06.i24/86C 04/24/85C O'J/24/84C ' 06'./28/85C 06/14/85C 12/30/86 12/06/85C 11/21/85C 12/31/86 12/30/86 12/30/86 05/25/84C 01/21/82C 06/28/85C 01/22/86C 04/25/85C 01/25/82C 06/30/83C 06/02/81C 06/0}/84C 08/23/85C t 1/20/81C LICENSEE STATUS c.o wtvi 1..*d-eJ._ 4 I ss e..o'.Nlfl~ ~cl 11.l~ C:.O\"r\\'tdecl p("O~~c.\-e_c.\.. p ("<:>J I!. c.A-e d.. <!.C>vYl'(lle. kJ... . c.e my,l~ kcl c.o*.~p~+d. c.o""'V)L..e. wl c.o~"' \OIR. t-t.c\ u:;, '"' f \t,. ~cl t;.O wt\<) le...-tect f'faj~c:kcl (.c,,{V\f \*.~-Cl 6/86 \'lo'L bjts <o 1s-s Yj~s l 't ?3 l (J~ l (1S2-PAGE NO.: 305 03/31/86 .se:~ G,""'~"j ~\lQ.-r-.5 .s.e,t Nf.C.. Le.-tiev-e. ComV,"~ Let{e..-,1nj8S Amer1cl1t)\Mt.. 48 TC!~ 8~ -1 *!) $ER. Cc\'l!.puv,j i..c~v-sj3c}E-G seR R-1208.7 31-001 R E G U L A T O R Y I N F O R M A T I O N T R A C K I N G S Y S T E M F A C I L I T Y I M P L E M E N T A T I O N NORTH ANNA 2 (CONTINUATION) TAC NO, Hf.A...J TJJLE LIC ACT COMPLETE M47305 M51181 M51261 M44389 M47956 M44458* M44529 M44599 M44644 M44685 H44723 M44797 M44868 M44939 M45010 H45081 M47617 M47688 M47759 0 M4S151 M46895 M47809 M45241 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/20/81C ' F-08 I.D.1.1 DETAILED.CONTROL ROOM DESIGN REVIEW PROGRA 11/18/84C F-09 I.D.2 SAFETY 'PARAMETER DISPLAY SYSTEM ~4/25/85C ' F-10 11.B.1 RCS HIGH POINT VENTS 10/09/83C F-11 11.B.2 PLANT SHIELDING F-12 11.B.3 POST ACCIDENT SAMPLING F-13 F-14 F-15 F-16 F-17 11.B.4 TRAINING FOR HITIGATlNG CORE DAMAGE 11.D.1 RV AND SV "'FRAININ8-TESTIN6 11.E.1.1 AFH SYSTEM EVALUATION II.E.1.2.1 AFH SYSTEM INITIATION II.E.1.2.2 AFH SYSTEM FLOH INDICATION F-18 11.E.4.1 DEDICATED HYDROGEN PENETRATION F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY F-20 II.F.1.1 NOBLE GAS MONITOR F-21 II.F.1.2 IODINE/PARTICULATE SAMPLING F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR F-23 11.F.1.4 CONTAINMENT PRESSURE INSTRUMENT F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 11/14/83C 02/27/84C 02/02/82C 06/30/86 06/02/81C 11/30/81C 06/02/81C 05/17/82C 06/02/81C 10/21/81C 10/21/81C 02/05/82C 04/21/83C 04/21/83C F-25 11.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/211.~.3C F-26 11.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 11/06/84C F-30 II.K.2.13 THERMAL-MECHANICAL REPORT F~33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS F-36 11.K.3.1 AUTO PORV ISOLATION 061'05/&4C 01/24/84C 101'191'83C LICENSEE STATUS Comp\.e~J.. f<'(;)~~~~cl c.owip~-\ecA. ~o~le.~J. r"('"cJ~ COIIYI\O\e. \-ed. C.1:>~f le. w c..o l"(I\? IR-\t.J.. l~ & I \C,8'3 l ct 8'2" \<i8'1 z. I ~'I '2. \ 64 C..o"""f>le\.e&. 1018-4 Cb'Mfl~~c.l 10/fs4 PAGE NO.: 306 03/31/86 J: Erle. 8 3 -0"1 . CoMfl'\j ~&r-u ("zs/.J. !'ETR. 8l-07 ):"ETf.. 83-'3 I IETlZ.. '5 -"31 e TEI~ 8-I -.3-3 J:Er 8'LI--3 3 R-1208731-001 NORTH ANNA 2 IAC HQ, HfA.....I M45287 F-37 M45361 F-38 M45404 F-39 M45453 F-40 M45483 F-41 M45513 F-42 M45647 F-47 M48425 F-53 M45844 F-57 M48183 F-58 M45963 F-63 M46034 F-64 M46106 F-65 M46178 F-66 M462SO F-67 M46322 F-68 M46393 F-69 M46462 F-70 M56143 F-71 'M49666 G-01 REGULATORY INFORM.AT ION TRACKING SYSTEM F A C I L I T Y I M P L E M E N T A T 1 0 N II .K.3.2 II.K.3.3 II.K.3.5 (CONTINUATION) UJLE REPORT ON PORV FAILURES ' REPORTINO~V AND RV FAILURES AND CHALLE AUTO TRIP 'of RCPS 11.K.3.9 PIO CONTROLLER II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS II. K*. 3 .12 ANTICIPATORY TRIP ON TURBINE TRIP II.K.3.17 ECCS OUTAGES II.K.3.25 POWER ON PUMP SEALS II.K.3.30 SB LOCA METHODS II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 III.A.1.2 TECHNICAL SUPPORT CENTER III.A.1.2 OPERATlONAL SUPPORT CENTER III.A.1.2 EMERGENCY OPERATIONS FACILITY 111.A.1.2 NUCLEAR DATA LINK 111.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE III.A.2.2 METEOROLOGICAL DATA UPGRADE III.D.3.3 IMPLANT RADIATION MONITORING III.D.3.4 CONTROL ROOM HABITABILITY I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOHUP TO REACTOR COOLANT PUMP TRIP CD660 -11.K.3.5) LIC ACT COMPLETE 10.119/83C 06.102.181C 02.122.183C ' **, 06.102.181C 08.125.181C 08"25.181C

  • 12.l 30.183C 06.122.182C 06.104.185C 01.115/87 06.130.186 06.130.186 06.130.186 07.130.182C 0S.111.183C 06.130.186 02.118.182C 03.120.184C 12.131.184 04.130.186 LICENSEE .SJATUS Mil PAGE ND. : 307 03.131/86

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