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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 Serial No. 86-298 Office of Nuclear Reactor Regulation NO/PML/acm Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-280 PWR Project Directorate No. 2 50-281 Division of PWR Licensing-A 50-338 U.S. Nuclear Regulatory Commission 50-339 Washington, D.C. 20555 License Nos. DPR-32 DPR-37 NPF-4 Gentlemen: NPF-7 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 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 | |||
- - - - - - 8--860530 86060601 05000280-PDR ADOCK PDR p | |||
.. e 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 | |||
Revision as of 00:54, 21 October 2019
| ML18149A174 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 05/30/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM 86-298, 8680530-2, NUDOCS 8606060198 | |
| Download: ML18149A174 (27) | |
Text
{{#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 Serial No. 86-298 Office of Nuclear Reactor Regulation NO/PML/acm Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-280 PWR Project Directorate No. 2 50-281 Division of PWR Licensing-A 50-338 U.S. Nuclear Regulatory Commission 50-339 Washington, D.C. 20555 License Nos. DPR-32 DPR-37 NPF-4 Gentlemen: NPF-7 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 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
- - - - - - 8--860530 86060601 05000280-PDR ADOCK PDR p
.. e 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
[...IV'-LV.:I" ' - A-\tocir1 r.A.e.n+ 1 R-1208731-001 REGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE Nv*:.: ~q:_ .. F AC I L I T Y I MP L E ME N T A T I O N 03131/86 FACILITY: SURRY 1 PLANT LOCATION: 17 MI NW OF NEWPORT NEWS, VA LICENSED POWER: 2441 MWT PROJECT MANAGER: T. CHAN DOCKET NUMBER: 050-00280 DESIGN POWER: 0788 MWE BRANCH CHIEF: L. RUBENSTEIN ARCH/ENGINEER: S&W NSSS VENDOR: WEST LIC. ASSISTANT: VACANT IE INSPECTOR: D. BURKE LIC ACT LICENSEE TAC NO. MPA I TITLE COMPLETE STATUS DATE M08327 A-01 10 CFR 50.55 ACG> - ISI 02107183C-M08102 A-02 APPENDIX I - ALARA 06/19/84C. C.o...-..p\Q..~ o<., /19/B+ : Ar.\~nd,...e.-,.t, 97 M06964 M08638 A-03 A-04 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS APPENDIX J - CONTAINMENT LEAK TESTING 02121119c 05.119.18*1,C e M08S16 A-06 RESPIRATORY PROTECTION SYSTEM 091'111'79C M06102 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 03.111/80C i-M10496 A-10 CONTINGENCY PLANNING 09.t04.180C C.on.ple.+e.c\ ; o,/o~/<e:,o '. lt'""-~d"."~+ <c, I M10493 A-11 GUARD TRAINING PLANS 12/181'80C M10491 A-12 VITAL AREA ANALYSIS . 04.112.182C M11216 A-14 10C.FR ~O.S5 ACG) - INSERVICE TESTING 101'22/82C M127S3 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 041'15/80C M47S66 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04.112/82C MS1138 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 121'31/86 IM55745 A-18 TECH SPECS AFFECTED BY S0.72 AND S0.73 CGL 83-43> 021'27 /85C. M56490 A-18 TECH SPECS AFFECTED BY 50.72 AND S0.73 CGL 83-,3) 121'11/8SC ...... ___ _ l2./ll / S!l M59147 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 12/31/86 0 MS9988 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31/86_ M07906 B-01 DIESEL GENERATOR LOCKOUT 05/19/81C M08401 B-03 PWR MODERATOR DILUTION 06/081'81C M06711 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 03/04.180C 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 PAGE NO'*:: 4~~ F AC I L I T Y I MP L E ME N T A T I D N 03/31/86 SURRY 1 (CONTINUATION> LIC ACT LICENSEE TAC NO. MfLl TITLE COMPLETE. STATUS. Mil M07964 B-11 FLOOD OF EQUIPMENT IMPORTANT _TD SAfETY 12/181'80C Lo"'-fle.-kcl . 12../15/90 M08641 B-12 STEAM GENERATOR. TUBE INSf>_E~TIDN ...... _ . 02,,101'81C L ........ _M08506 B-14 CEA.GUIDE TUBE HEAR .. 07/07/80C M12160
- 8~16 EMERGENCY PLANNING AND REVISIONS 04/01/81C M08509 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 08/17/82C 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 B-22 . TECH SPEC SURVEILLANCE REQUIREMEN:rs FDR MECHANICAL 08/17(82C M10053 B-23 DEGRADED GRID VOLTAGE 10,os,s2c M42562 B-24 VENTING AND PURGING CONTAINMENTS HHIL E AT FULL POW 111'17/82C M1 0001 B-24 VENTING AND PURGING CONTAINMENTS WHILE.AT.FULL POW 04/02/80~
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J110234 _B-26 INADVERTANT SAFETY INJECTION DURING CDOLDOWN 091'141'79C M08538 B-30 STEAM GENERATOR REPLACEMENT PROGRAM 01/201'79C M07108 B-30 STEAM GENERATOR REPLACEMENT.PROGRAM ............ . 01/20/79C M07576 B-31 LONG SHAFT - -*---- LHSI
.
& OUTSIDE RECIRC. PUMP
-- - . -- -
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DEGRADATION 03/151'82C M08357 B-32 BLOCKED SI.. SIGNA_L DURING COOL DOWN. 041'01/82C M08683 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 111'131'80C M11091 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SERS 011'17/84C M47_396 B-41 FIRE. PROTECTION.- FINAL.TECH SPECS <INCLUDES SERS 111'181'82C iM11713 B-42 TMI FOLLOW UP - ALL PLANTS 011'30/81C. M1201 0 B-42 THI.FOLLOW UP~ ALL PLANTS 091'06/79C IM13128 B-42 . J_f"II FOLL.OH UP .::. ALL__ F'LANJS 051'28/80C M43153 B-43 PHR FEEDWATER LINE CRACKS 051'25.1S-2C
12087 31-001 REGUL AT ORY I N F O R MA T I O N T R A C KI NG S YS T EM PAGE NO. ',r 47 3~. F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 RRY 1 (CONTINUATION) LIC ACT LICENSEE AC NO. MPA I
- TITLE COMPLETE STATUS DATE 11777 8-:43 PWR FEEDWATER LINE CRACKS .. _______ . 10/j 7/7_9C _________________ _ CO""""ICL~ lc/1*;.f.,,_~--- -***- SEf!.
96_5_Z___ ____ 8:-_44 _____LESSONS LEARNED IMPLEMENTATION 04/24/80C 0653 B-44 LESSONS _LEARNED IMPLEMEN_TAJIOtL_ . 041'241'80C 0654 8-44 LESSONS LEARNED IMPLEMENTATION 04/24/80C
-
0655 B-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C c_o""-p~W . .1,../'Z...1,. [ec SE..~---**-*** 0656 8-44 LESSONS---*--*- LEARNED
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.
_D659_________ B-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C ~0660 B-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C ~0661 B-44 LESSONS LEARNED IMPLEME_NTATION 041'241'80C ~0662 8-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C ~0663 8-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C 0664 8-44 LESSONS LEARNED IMPLEMENTATION 04/24/80C 0665 8-44 LESSONS LEARNED IMPLEMENTATION 041'241'80C 2937 8-45 WASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 041'201'81C 2101 2579 8-46 8-46 ANALYSIS OF TURBINE DISC CRACKS ANALYSIS OF TURBINE DISC CRACKS 051'021'81C 081'191'81C e 12687 8-47 ECCSJ CLAD SWELLING AND RUPTURE 091'12180C 12976 8-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 10/141'83C ~7402 8-49 PWR CONTROL ROD MISALIGNMENT 061'171'82C 11878 8-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 111'261'80C t3203 8-54 LESSONS CATEGORY A TECH SPEC 091'201'81C
-1208731-001 REGULAT ORY I N F O R MA T I O N T R AC KI NG S YS T EM PAGE N0°.'*: 47'1.
F AC I L I TY I MP L E ME N T A T I O N 03/31/86 URRY 1 (CONTINUATION) LIC ACT LICENSEE AC NO. MPA I TITLE COMPLETE
- STATUS DATE
- 42867 ... 8-59 MASONRY WALL DESIGN 03/31/86 ---* ---- ______ J _ ~ ----*---!----------------- --
42468 8-60 ****- ENVIRONMENTAL QUALIFICATION
.
03/12/85C I 8-61 LOSS *-*OF NON CLASS IE I&C POWER 07/28/82C. --------*** __ . --*** ____ ______ __ _ . _ --* _______ *--* ___ j_ .. - --- - --- . _ ___ ____ - 4~!_08 - . 42779 8-62 ESF RESET CONTROL DESIGN DEFICIENCY 03/11/82C 143942 B-63 INTERIM PROCEDURES FOR SHORT TERM_BLACKOUT 09/21/81 C 47167 B-66 8-69 NATURAL CIRCULATION COOLDOWN IE8 80-4 MAINSTEAM LINE BREAK.WITH CONTINUED FEEDW 10/19/83C 07/14/82C e 46_862 46636 B-70 FATIGUE _TRANSIENT LIMIT TS_ __ _ __. 05/25/82C .
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49762 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER_82-16) 03/28/84~. 152805 B-76 ITEM 1.1 - POST TRIP REVIEW; PROGRAM DESCRIPTION & 04/01/85C Co..-.c.pt~-k..d 4../1 /es se:. '2.. - 52886 B-77 ITEM 2.1 ~ EQUIPMENT_CLASSIFICATION &_VENDOR INTER 04/30/86 52967 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/13/85C ~ ...... p1.c2...-i:e.d IZ./J ?./85 :=>E..12.. 53048. 8-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/06/85C -~Pl.L~ \I / (o /B5 s~ 53103 8-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 12/13/85C Co~l.L-k!...O 12/ 13/e,s 5.E.R... 53156 8-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 05/03/8SC .co ...,c.pla.kd 5 /3 /85 SE.~ 153198 8-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 03/31/86 154573 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS_83-:- 10/15/84C 153638 B-85 SALEM ATWS 1. 2 DATA CAPABILITY 06/12/85C lo/12../S5 153721 B-86 SALEM ATWS 2.2 S-R COMPONENTS 01/31/87 153804 8-87 SALEM ATWS 3.2.1 & :s'.2.2 S-:-R COMPONENTS 12/13/8SC Cb.-.c.pl.Q.{eO IZ../1?./e,.s S.~ 153887 B-88 SALEM ATWS 3.2.3 T.S. S-R COMPONENTS 11/06/8SC Cb..... p1e.-led \\ I ~Ls£. _ .sc..rz.. 153943 B-89 SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS 01/31/87 155380 B-90 SALEM ATWS 4.3 WAND B&W T.S. 03/31/86
R-1208731-001 REGULAT ORY I N F O R MA T I O N T RAC k I NG S YS T EM PAGE Nb.: 4~5 F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 SURRY 1 CCONTINUA TI ON) LIC ACT LICENSEE TAC NO. ~ TITLE COMPLETE. STATUS DATE I M54114 ____ B-92 SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES 12/_13/85C ! ~o.....,ple_+w\ IZ. /I?,/ eJ5 5 E.~ M54031 B-93 SALEM ATWS_~.5.2 & 4.5.3 TEST ALTERNATIVES 01/31/87 .. '*~ . **- - .- M08251 C-01 _____ P_W~_ SECONDARY. WATER CHEMISTRY MONITORING REQUIREME 12/18/80C l2./'1S{SO .. k--.t~Nui+_ G,2. M08617--------C-04 FILTER __TECH SPECS _. __ . 01~.1_7/84C. : I , _..1 . I/ 1-=F /e4 : A.-,c,e,.,d~+ . 92. ..
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i M0851_8_...... _C:::06 ~UMP. SUPPORT-LAMELtAR_JEARING 04/17/81C ,! M08620 __ C-07 ... FUl:L. HANDtING__AC.Cil>ENT INSIDE CONTAINMENT 01/16/85C M08084 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 05/16/84C M43667 C-14 AUXILIARY FEEDWATER_SEISMIC QUALIFICATION_ 08/20/82C M52276 C-15 CONTROL OF HEAVY LOADS - PHASE II CFOLLOWUP OF MPA_ 06/28/8SC I M58094 C-16 _____UTILITY_ R_ESPDNSES TO STAFF RECOMMENDATIONS CONCERN 01/31/86C I
. I M07875 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 D-04 PWR REACTOR VESSEL __ <<;:AVITY:_ SEAL RING MISSILE POTENT OZ/10/84C M08521 D-10 ASYMMETRIC LOCA LOADS 02/01/84C M08999 D-11 ...... J:ISSION GAS RELEASE 02/2S/80C :co-pl~-kd .... Z/.z.s/eo
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M12277 D-15 HIGH ENERGY LINE BREAK & .CONSEQUENTIAL SYSTEM FAIL_ .... 02/02/84C ....... M13076 M43011 D-16 D-17 REVIEW OF CORPORATE MANAGEMENT CAPABILITY DEFINITION OF OPERABLE
.05/22/81C 01/01t70C e
M55908 0-19
- DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15) 09/27/85C 1
M10388 E-05 H N-1 LOOP OPERATION 01/30/8~ M44059 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/06/82C :C..O.-.plLW \'l../2.2,/e,o : :CE.I ft 80-+D M44130 F-02 I.A.1.3 SHIFT MANNING 11/05/81C ,c..o~lf.4-e-d i 11/2.o/s 1, re:4-~ e\ -31 M44201 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 11/05/82C leo~ui+-t.9 / 9 /~/ 8 I i IE.If. a, -2.2
-1203131-001 REGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE NO.-, 476',,
F AC I L I TY I MP l E ME N T A T I O N 03/31/86 URRY 1 CCONTINUA TI ON) LIC ACT LICENSEE AC NO. .MfA._! TITLE COMPLETE STATUS >>.lli 144272 F-04 I.C.1.2/3,A EMERGENCY OPERATING PROCEDURES GENERIC 06/13/84C .. - . --** ..... .! -
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44342 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 11/05.185C 47255 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11/05/81 C 47327 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/05/81C 51208 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/10/84C 51288 F-09 I.D.2 SAFETY PARAMETER DISPLAY
-- - -*-
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05.t02/85C -i-- .. 44409 F-10 11.B.1 RCS HIGH POINT VENTS 09.112/83C 47978 F-11 11.B.2 PLANT SHIELDING 10.131/83C 44480 F-12 II.B.3 POST ACCIDENT SAMPLING 02/27.t84C 44551 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/05.t82C 44622 F-14 11.D.1 RV AND SY TRAINING 01/31/86 12639 F-15 11.E.1.1 AFW SYSTEM EVALUATION 04.t27.t82C 2-/ 1/95 - .IE.Iie . B4:-lO 44694 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08.107/81C .U>-.pla~ 2..I, J95 .. ::C.EI.'2 .. 'B-4 -10 44733 F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION 08.t07/81C , <!..el~ I.A-\.e..d . _Z, I , /8 S . :c.e.xe. S4- IO . 44819 F-18 11.E.4.1 DEDICATED HYDROGEN PENETRATION 08/24/81C ______ .. :C.O~la.~. 0/zB/81 SE.~. 44890 F-19 11.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 12/07/82C C0n.t.pla...~ . 12./=,. /82.. se:e ..,/ ~~Jg+
~496_1 45032 F-20 F-21 II.F.1.1 II.F.1.2 NOBLE GAS MONITOR IODINE/PARTICULATE SAMPLING 10/01/81C 10.101/81 C e 45103 F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/07.t82C 47639 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04.t22.t83C 47710 F-24 II.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 04.122/83C 47781 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/22.t83C 45173 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09.121/84C
R-1208731-001 REGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE Nb. : r,.:77_ F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 SURRY 1 (CONTINUATION) LIC ACT LICENSEE TAC NO, MfLl TITLE COMPLETE STATUS DATE M46907 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/15/84C ._ I M47821 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/09/84C ' II M45251 F-36 II.K.3.1 AUTO PORY ISOLATION 09/16/83C 1--- - -- M45297 F-37 II.K.3.2 REPORT _ON PORV FAILURES 09/16/83C !*-**. -' M45383 F-38 II.K.3.3 REPORTING SY AND RV FAILURES AND CHALLE 02/11/82C i ...... !. ***--*- e I M45414 F-39 II.K.3.5 AUTO TRIP OFRCPS _____ .... 02/22/83C. M45463 F-40 II.K.3.9 PID CONTROLLER 08/28/81C I - M45493 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 08/28/81C ***.* --+- I
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M45523 F-42 11.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 08/24/81C l
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M45866 F-57 I I. K_. 3. 30_ SB LOCA "1ETHODS 05/24/85C --------1------***-----****--**---------- - *I - M48206 F-58 II.K.3.31 COMPLIANCE WITH10 CFR_S0.46 12/31/.86 .. ** t-- -- ..... I ......... **---***- ......... ---* ... - i I M45985 F-63 III.A.1.2 TECHNICAL SUPPORT.CENTER 01/01/87- - ---- *- --.. - -* ..... ----/--- -------***-- ... -- . - *--. .... .. . . -* .. M46056 F-64 III.A.1.2 OPERATION~L_S_UPPORT CENTER 01/01.187 --* *****-* M46128 F-65 III .A.1 .2 EMERGENCY DPERATIONS _FACI_LITY ..... . 01/01,.18~ . . -; __ ,. M46200 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C M46272 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE_ro MEET RULE 05/13/83C ------------* 01/01/87
.M46344 M46415 F-68 F-69 III,A.2.2 III.D.3.3 METEOROLOGICAL DATA UPGRADE IMPLANT RADIATION MONITORING 02/19/82C M46484 F-70 'III.D.3.4 CONTROL ROOM HABITABILITY 06/28/82C M56170 F-71 I.D.1.2 DETAILED CONTROL
. . ROOM REVIEW CFOLLOWUP TO 06/30/86 M49681 G-01 REACTOR COOLANT PUMP TRIP CD660 - II.K.3.5) 05/31/86
R-120.8731-001 REG.UL ATOR Y INFORMATION TRACKING SYSTEM PAGE NG. : 47.8 FACILITY IMP LEM.ENT AT ION 03/31/86 FACILITY: SURRY 2 PLANT LOCATION: 17 Ml NW OF NEWPORT NEWS, VA LICENSED POWER1 2441 MWT PROJECT MANAGER: T. CHAN DOCKET NUMBER: 050-00281 DESIGN POWER: 0788 MWE BRANCH CHIEF: L. RUBENSTEIN ARCH/ENGINEER: S&W NSSS VENDOR: WEST . LIC. ASSISTANT: VACANT IE INSPECTOR: D. BURKE LIC ACT LICENSEE TAC NO. Hf.LI TITLE COMPLETE STATUS DAT!;_ }'.1083_36 A-01 10 CFR SO.SS ACG) - ISi 02/07/83C M08103 A-02 APPENDIX I - ALARA . _________06119184C M08367_ . A-03 SECURITY REVI_EWS-MODIFIED AMENDMENT PLANS 02".27!79C ___________ .--- ___ _ M08639 ______ A-04 APPENDIX.J - CONTAINMEN,: LEAK TESTING 05119181C_ M08515 A-06 . RESPIRATORY PROTECTION -SYSTEM 09111/79C _ . __ . __ . M11389_. A-09 . PRES_SURE __VESSEL BEL T_LINE _MATERIAL SURVEILLANCE----------* 0311.1 !80C ________ -***----*-***---* i--****--****--****------**** *-*.. ***- ................ *****--**-*-***-*****---*-****-********** M1049S A-10 Cotft:INGENCY_ PLANNI_NG____________ .. 09104180C M10494 A-1J GUARD TRAINING PLANS_ __ _____ _ 12/.18/80C.. ____ . M10492 A-:-1.2 . _VITAL. AREA ANALYSIS. . 04112/82C ______ ......... M11217 _ A:-:14_ 1 OCFR SO. SS ACG) - _INSERVICE TESTING . . ________ ... 10/22/82C___ _ M12754 A-1 S QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARA_T _ 04IJS180C _"1_41_~6_7 . A-16
----- ----- QUALIFICA_TIONS Of EXAMINATION,INSPEC.IION, TESTING 04112/82C M51139 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF _AN_ACCIDEN_ 12/31186 M56491 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 COL 83-43),,c_;,Q612/11185C ICo ""'I' J 1~,4,c.d M59148 A-20 10 CFR_ SO. 62 __0PERATING REACTOR REVIEWS 12/31186. I M59989 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31186 M07907 B-01 DIESEL GENERATOR LOCKOUT OSl19181C t M07221 B-02 FIRE PROTECTION 09119179C I M10812 B-02 FIRE PROTECTION 09/19179C M08402 B-03 PWR MODERATOR DILUTION 06/08181C
R-1208731-001 REGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE NIJ. : 'i19. F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 SURRY 2 CCONTINUA TI ON> LIC ACT LICENSEE TAC NO, MPA I TITLE COMPLETE STATUS DATE M08343 8-04____REACTOR VESSEL OVERPRESSURE PROTECT.ION -----*------ 03/04/80C. lc..o".'4-pl~:1*~.d 3/4/eo A,..,,.~e,,,f ss
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_,:1_066_97 ______ B-11 ________nooD Of__ EQUIPMENT_ _I_Mi:'llR:J:~NI..J_O _SAFEJ)'________ _ 12/18/80C ' __ :CJ:> .-.y, l¢:kd I 'Z. /ia / So St. e, M08642 B-12 STEAM GENERATOR TUBE INSPECTION 12/20/79C M08507 B-14 CEA GUIDE TUBE WEAR 07/07/80C _ M12161 __ B-16 ____ EMERGENCY_PLANNING_AND REVISIONS 04/01/81C M08510 B-17 M1 0214 _____B-:-20 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION_ 08/17/82C 08/25/80C e M10338 8-21 LOSS O_F_J 25"'.'V DC BUS VOLTAGE WIJl:I__LOSS OF ANNUNCIA 03/01/82C M08512 8-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 08/17/82C M10054_~--- 8-23 DEGRADED GRID VOLTAGE 10/0S/82C M42563 8-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 11/17/82C M10009 8-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 04/02/80C I M10235 8-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 09/14:l79C M08537 8-30 _STEAM GENERATOR REPlACEMENT PROGRAM 01/20/79C _M0.8366 B-30 .. STEAM GENERATOR REPLACEMENT PROGRAM 01/20/79C. M08368 8-31 LONG SHAFT LHSI & OUTSIDE RECIRC. PUMP DEGRADATION 03/1S/82C M08364 B-32 BLOCKED SI SIGNAL DURING COOLDOWN 04/01/82C M08684 8-39 PWR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/SOC 3/ 4/80 M11092 B-41 FIRE PROTECTION - FINAL TECH SPECS CINCLUDES SER s 01/17/84C FIRE PROTECTION - FINAL TECH SPECS CINCLUDES SER s 0 M47397 8-41 11/_18/82C Mt 1714 8-42 TMI FOLLOW UP - All PLANTS 01/30/81 C M12011 8-42 TMI FOLLOW UP - All PLANTS 09/06/79C M13129 B-42 TMI FOLLOW UP - All PLANTS 05/28/SOC s/z.e/e,o
R-1208731-001 R E G U L A T O R Y I N F O R MA T I O N T R A C K I N G S YS T EM PAGE No*:: 480. F A C I L I T Y I MP L E ME N T A T I O N 03/31/86 URRY 2 (CONTINUATION) LIC ACT LICENSEE AC NO I .MfU TITLE COMPLETE . STATUS DATE I
~3_! 5~ _______ B:::4} _______PWR FEEDWATER__ LINE_ CRACKS_...... ------**-*---****---..-*-*--*--- -------..*-------***05/_25/82C.
M11778 ______ B_:::_~3 ___ PWR FEEDWATER LI_NE_CRACKS_______________ ----- 02/25/80C
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130671 130672 B-44 B-44 LESSOt-lS LEARNED IMPLEMENTATION LESSONS L_EARt-l_ED_ IMPLEMENTAJ.ION__________ _ 04/24/80C. _____ ....... _04/24/80C e 30673 B-44 ___ Lf:S~ON~ __ LEARNED IMPLEMENTATION_ ........ ___ ... . . 04/24/80C 130674______ ~-::~_,_____ _LE_S~ONS _Ll;A~NED _JMPLEMENJ"ATION____ . __ ________ __ ... __ 04/24/80C -1 130675 B-44 LESSONS__ LEA_RNED IMPLEMENTATION ------------------ _04/24/80C 130676 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/SOC 130677 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/80C ~30678 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/SOC 130679 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/80C 130666 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/80C 130667 B-44 LESSONS LEARNED IMPLEMENTATION 04/24/SOC .Cb ""'4'( tied 4/ZAr/B,O ~12938 B-45 WASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C 112580
- B-46 ANALYSIS OF TURBINE DISC CRACKS 08/19/81C 112688 B-47 Eccs,_CLAD SWELLING AND _RUP_TURE_ ... -** .... _09/12,(80C ... :Cof'\.\.p LG..-k.d . 9 /iz./ac .
112977 B-48 ADEQUACY OF_STATION ELECTRIC DISTRIBUTION_VOLTAGE 10/14/83C__ . ~47403 B-49 PWR CONTROL ROD MISALIGNMENT 06/17/82C 111879 B-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 11/26/80C 143204 B-54 LESSONS CATEGORY_A TECH SPEC 09/29/81C
-1208731-001 REGULATORY INFORMATION TRACKING SYS T* EM PAGE NO; ,'. 481*..
F AC I L I T Y I M P L E M E N T A T I O N. 031'31/86 URRY 2 <CONTINUA TI ON) LIC ACT LICENSEE At NO. MPA I TITLE COMPLETE i STATUS DATE I 42102 ____ 8-57 -*** DHR_CAPABILITY *-------------------* -*-*** _____ _ 42868 B-59 MASONRY HALL DESIGN 05/12/81C ___ ,_03/,3_1!86_________ ,}, ..... -- _.
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ITEM 1.1 - POST TRIP REVIEH1 PROGRAM DESCRIPTION & 04/01/85C 4/ 1 /es 152887 B-77 ITEM 2.1 - ~QUIPMENT CLASSIFICATION & VENDOR INTER 04/301'86 52968--- ----~- B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/131'85C t -z-/i 3 / 8/S .SE.~. B-79 _____ I_TEM _3._1.3 - POST MAINTENAN~E TESl}NG __-___ CHANGES _t() ______ 11.t06/8SC ______________ -,-*- .... ,Cb.....,_pl.A~ I 53049 _,, J<o/85 se.~
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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* PAGE NO':: 482 F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 SURRY 2 (CONTINUATION> LIC ACT LICENSEE TAC NO. MPA I TITLE COMPLETE* STATUS .Dill I M55381 B-90
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-*! .. 1 M08085 C-10 CONTROL OF HEAVY LOADS OVER_ SP_ENT FUEL POOL (PHASE_ .... 05/16/84C I M43668 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICA"[ION _________________08/20/82C ;eo"'.'lpLQ:k.d
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1_44202 F-03 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.. . 1 M44273 F-04 I.C~1_.2/3.A EMERGENCY OPERATING PROCEDURES __ GE~ER.I.C 06/28/84C *-*- ----!- _ .-. ......... :** .... . ... . ........... . F-OS I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 11/0S/8SC L . . I F-06 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
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R-1208731-001 REGUt AT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE No::' 48A F AC I l I T Y I MP L E ME N T A T I O N 03/31/86 URRY 2 (CONTINUATION) LIC ACT LICENSEE AC NO. MPA I TITLE COMPLETE
- STATUS .Dill M47711 F-24 II. F, 1. 5 CONTAINMENT WATEI:(__ LEVE:t__ INSTRUMENT 04/22/83C M47782 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/22/83C M45174 F-26 II. F .2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09/21/84C M46908 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/15/84C M47822 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/09/84C 1145252 1145298 F-36 F-37 II.K.3.1 II.K.3.2 AUTO PORV ISOLATION REPORT ON PORV FAILURES ____________ _
09_/16J'83C 09/16/83C e 145384 F-38 II.K.3.l REPORTING SV AND RV FAILURES AND CHALLE 02/11/82C 45415 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C -... - L 45464 F-40 II.K.3.9 PID CONTROLLER 08/28/81C 145494 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 08/28/81C !
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145524 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 08/28/81C 145670 F-47 II. K. 3 .17 . ECCS OUTAGES 08/08/83C ____________ _ I 148435 F-53 II.K.3.25 POWER ON PUMP SEALS 06/24/82C i
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145867 F-57 II.K.3.30 SB LOCA METHODS 05/24/85C 143207 F-58 II.K.3.31 _ COMPLIANCE_ WITH 10 CFR 50.46 12/31/86 145986 146057 F-63 F-64 III.A.1.2 III.A.1.2 TECHNICAL SUPPORT CENTER OPERATIONAL SUPPORT CENTER 01/01/87 01/01/87 e 146~29_ .. F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 01/01/87. 146201 F-66 III.A.1.l NUCLEAR DATA LINK 07/30/82C 146273 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/13/83C 146345 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 01/01/87 146416 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/19/82C
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.!".!~6485_ _ F-70 .. I.~.LJ!~__3,.__4 __ CONTROL __ ROOM _HABITABILITY ...... ----****- _ -*---- .. _ ... 06/28/82C ___ .. _______________ ------+--.. *---*--- ------.. ________ -------*- ... 1.. __________________.. ______ __
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Ar-, ACl+lvlE.~*rr....2.- R-12087 31-001 R E G U L A T O R Y I N F O R MA T I O N T R A C K I N G S YS T EM PAGE NO.: 298 FACILITY IMP L .EM ENT AT ION 03/31/86 FACILITY: NORTH ANNA 1 PLANT LOCATION: 40 MI NH OF RICHMOND, VA. LICENSED POWER: 2775 MHT PROJECT MANAGER: L. ENGLE DOCKET NUMBER: 050-00338 DESIGN POWER: 0907 MHE BRANCH CHIEF: L. RUBENSTEIN ARCH/ENGINEER: S&H NSSS VENDOR: WEST LIC. ASSISTANT: VACANT IE INSPECTOR: M. BRANCH LIC ACT LICENSEE IA~ HQ, tteA....I UIL~ cor,PLETE" STATUS .DAll e,.oM JI.\E"NTII M12245 A-01 10 CFR 50.55 A<G> - ISi
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06/20/83C (. OIM \f' le. \-i?cl_ ,q%3 Stl2.. M08147 A-02 APPENDIX I - ALARA 05/05/83C 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 M11532 A-03 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS *o5/02/79C M11386 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURV Ell LANCE 06/041'76C Am~.newtt 2.o M11574 A-10 CONTINGENCY PLANNING 10/03/80C C..o IM\,P letecA \98'0 H11575 A-11 GUARD TRAINING PLANS 03/20/81C Co'N\r\~ l'l8 l A tVlell\QWI f V\t z. s M12089 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 02/13/8DC M48123 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/*05/82C C..0'<1'f te.tecl \9lf2.. NRC.. t..e.:~t.. 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 C O\M.\') \.e.kcl zlS5 Amevi&rnev,t ~3 pt" o.j e_(..{.e cl. . not sc:..h~d.uled. M59117 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S / M59965 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE c.o~yAe.t~ I Ii~ ~nj Le-1/Zifll 1jas (otn~TIJ ~~1/-,t/a-5 M12149 B-16 EMERGENCY PLANNING AND REVISIONS 08/21/80C C..OW\fl~ktl M13096 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 08/05/80C* Comf~~J.. l<t8D .A rnl!V\Cffi1&1.t I~ M46944 B-17 TECH SPEC SURVEILLANCE FDR HYDRAULIC SNUBBERS 11/05/81 C C..o IMf \.e kcA lq&I Am.~vtd.111\e. v1t 3 3 _Awte_wl rf\(:'V\t 33 M46946 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHAN.ICAL 11/05/81~ C..t>wtV)l..e tw.. I 't &-'I
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0 M48336 B-23 DEGRADED GRID VOLTAGE 12/281'79C Co11v1\ole.ted \'ti<} A rnevid. Jl'\evtC J(o . M42589 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 04/201'83C c~~\e..t-e<\ 1q&3 SER. M13116 B-24 VENTING AND PURGING CONTAINMENTS WHILE -AT FULL POW 11/21/80C (Cv,,'\~~d.. l980 N~C. Le..tler M10161 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 11/21/SOC C:.C,v.l\ 'f' le.~ \~iD N ~ c.. Le;tk:.,\.,
R-1208731-001 REGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE NO. : 299 F AC I L I TY I MP L E ME N T A T I O N 03/31/86 NORTH ANNA 1 CCONTINUA TI ON) LIC ACT LICENSEE TAC NO. tteA.....l une COMPLETE STATUS ~ .M46507 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SERS 11/18/82C M43143 B-43 PHR FEEDWATER LINE CRACKS 05/25/82C M30694 B-44 LESSONS LEARNED IMPLEMENTATION 04!~3/80C c.~v~pLe._4-e_J. \980 C:.o""i>>~ l.ttte-}So
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M30695 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C M30696 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/SOC e,o mp ~.i.-ecA. \ <\ t O Sc R M30697 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C , c.,o *""1~ LeJ~_cl I <\ t0 SE 12. M30698 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C M30699 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/SOC CoW\ y,\.d-e.ol M30700 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/SOC uo\J"'-pLde~ M30701 B-44 LESSONS LEARNED IMPLEMENTATION 04/23/SOC ~rr,'f~~ M30702 B-44 LESSONS LEARNED IMPLEMENTATION 04/23.180C M30703 B-44 LESSONS LEARNED IMPLEMENTATION 04/23.IBOC U> VY'\ f' l,t_-f;eol M30704 8-44 LESSONS LEARNED IMPLEMENTATION 04/23/80C M30705 B-44 LESSONS LEARNED IMPLEMENTATION 04.123.IBOC M30706 M30707 B-44 B-44 LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION 04/23/80C e 04.123.IBOC M12524 B-44 LESSONS LEARNED IMPLEMENTATION 04.123/80C M12929 B-45 HASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 04.120.181C M12605 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/31.18..tC 0 M12680 B-47 ECCS; CLAD SHELLING AND RUPTURE 07.130/SOC C.OW\.{J\.Q_:k,c\ \ 1.j%5 Co,"'fll:j ~1r 12/23/85 Mt 3109 B-48 ADEQUACY OF. STATION ELECTRIC DISTRIBUTION VOLTAGE 11.113.184C M42113, B-57 OHR CAPABILITY 06/02/81C (_.C vY\ (J li_.{e_d._ ll ~ I Ar,,e,1dr~v1t .3 2 M42895 B-59 MASONRY HALL DESIGN 09.103.185
-12087 31-001 R EGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE NO.: 300 F AC I L I TY I MP L E ME N T A T I O N . 03/31/86 JRTH ANNA .1 CCONTINUA TI ON> LIC ACT LICENSEE TITLE COMPLETE STATUS ~ C.omment 12497 B-60 ENVIRONMENTAL QUALIF.ICATION I . 12/12/84C i2688 B-61 LOSS OF NON CLASS IE II~ POWER 07/28/82C 12759 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 09/Q4/81C Co'M f>\ e.kcl 08/20/81C C.OW\(> \e_ -\t_J.. i,3941 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT ,7152 B-66 NATURAL CIRCULATION COOLDOHN 10/19/83C 16845 B-69 IEB 80-~ MAINSTEAM LINE BREAK WITH CONTINUED FEEDH 09/30/82C ,9742 B-72 NUREG 0737 TECH SPECS* (GENERIC LETTER 82-16) 01/12/84C c.,o Q'(\ '(' ~e-te J.. 3\85 i2777 B-76 ITEM 1.1 - POST TRIP REVIEHJ PROGRAM DESCRIPTION & 03/29.185C ,2858 PfO~e.c.t e.cl l~i7 C.o."11,:n~ L1t.~ 7/~;p/8'S B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER
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i2939 B-78 ITEMS 3.1.1 & 3.1 .2 -POST MAINTENANCE TEST PROCEDU 12/06/85C i3020 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/21/85C ~~le.cl. II j S5 Seit i3081 B-80 ITEM 4 .1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 06.124.185C 4\ t5 SeR i3134 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROO FOR R 04/24.185C
\1..\it5 VMP°'Yljk~V' r~l*z.1185" i3181 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07.124/84C
- 4549 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 06.128/85C Co\8S seR .*
i3610 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/14/85C C.Ol'<\f \.efe.J. ,3693 flt"Oij~+eA. \°187 C.Ornf"<<'j ~ 7/26/85 B-86 SALEM ATHS 2.2 S-R COMPONENTS 12.130/86 ,3776 B-87 SALEM ATHS 3.2.1*& 3.2.2 S-R COMPONENTS 12/06/85C. py-oj~c.+e.cl. l 'it7 Co~CU\j lo~-. 1/-zk/KS ,3859 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11 /25/85C , * ,3921 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 ,5363 B-90 SALEM ATHS 4.3 HAND B&H T.S. ,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
R-1208731-001 R EGULAT ORY I N F O R MA T I O N T R A C K I NG S YS T EM PAGE NO.: 301 F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 NORTH ANNA 1 <CONTINUA Tl ON) LIC ACT LICENSEE TAC NO, .l1fA...1 TITLE COMPLETE STATUS ~ M47112 C-10 CONTROL OF HEAVY. LOADS OVER SPENT FUEL POOL <PHASE 05/2S/84C M43666 C-14 AUXILIARY FEEDWATER Sl:'ISMIC QUALIFICATION 01/21/SZC c..o~y>~~cl C-15 CONTROL OF HEAVY 'LOADS - PHASE II (FOLLOHUP OF MPA [)6/28/85C c.o I/'{\ IP Le__ W M52248
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M58071 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C M12270 D-15 HIGH ENERGY LINE BREAK I CONSEQUENTIAL SYSTEM FAIL 10/22/81 C M43030 D-17 DEFINITION OF OPERABLE 12/10/80C (_, (? v-J\ ~ LQ !"- \ q'r() M55880 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 06/30/86 ? ~ ec...\ed.. <o/8G (.,O VY\ \D(.Q-{e_q l919 A vnericlvne.n+ L~ M10406 E-01 SPENT FUEL POOL EXPANSIONS 08/17/79C CoW\ip~Jed.. 1'18.3 ;t"trR e, ~ - L~ M44038 f-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/25/82C M44107 F-02 I.A.1.3 SHIFT MANNING 06/30/83C C.o&Mv,lHe°'- l 98 l St.I'<
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M44178 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 06/0Z/81C C..cw.f le.H d.. M44249 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 11/15/84C ~ l l j ki\-~ 513ojE'tc, M44319 F-05 I.C.1.2/3.B PROCEDURES*GENERATION PACKAGES <NUREG 08/23/BSC \)~oje.L+e.cl se~ M47232 M47304 F-06 F-07 I.C.5 I.C.6 FEEDBACK OF OPERATING EXPERIENCE CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/20/81C 11/20/81C (.OW\lf \ e.+eek (.,o V'(\ p l(!.:~ d. se:ie. e MS1180 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 11/19/84C MS1260 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 04/25/85C tOlSG:> ~P~j ~Hf< 3r,/86 M44388 F-10 II.B.1 RCS HIGH POINT VENTS 10/09/83C s / 85 ::rc::nz es-' 1... M47955 F-11 11.B.2 PLANT SHIELDING 11/14/,UC 0 M44457 F-12 11.B.3 POST ACCIDENT SAMPLING OZ/27/84C !el'."~ g3-tfJ c.. o VY\ f lct. ted.. l (HJ M44S28 F-13 11.8.4 TRAINING FOR MITIGATING CORE DAMAGE OZ/OZ/82C Cbu,nfe"j l4~ \1lts/6'S M44598 F-14 II.D.1 RV AND SV i'KAININ&li:~TJNG 06/30/86 p("oJ ~c.--\-ed I'i B8 M44643 F-15 II.E.1.1 AFH SYSTEM EVALUATION CcYY\y,ld~d.. l't8 I ):ErR '\$\-\\ 06/0Z/81C
R-1208731-001 R EGULAT ORY I N F. 0 R M A T I O N T RAC KI NG S YS T EM PAGE NO. : 30; F AC I L I T Y I MP L EM E NT AT I ON 03/31/81 NORTH ANNA 1 CCONTINUA TI ON) LIC ACT LICENSEE TAC NO, tlfA....I TITLE COMPLETE STATUS ~ Comm~w'\t M43191 F-16 II.E.1.2,1 AFH SYSTEM INITIATION 11.130.181 C c..o ""-'f IA.."\eel 2. / '8 '-/ l:e:r:R. e3-3( M44722 F-17 II.E.1.2.2 AFH SYS~M FLOH INDICATION 06.102/81C C,O~'-'f>le.kd_ 2. /'gt/ .IE-Z: R 8 3 - 3 I M44796 M44867 F:-18 F-19 11.E.4.1 11.E.4.2 DEDICATED HYDROGEN PENETRATION CONTAINMENT ISOLATION DEPENDABILITY
.. 1 0.120.182C 06.102/81C e
M44938 F-20 11.F.1.1 NOBLE GAS MONITOR 1 0.121.181 C . M45009 F-21 II;F.1.2 IODINE.IPARTICULATE SAMPLING 1 0.121/81 C M45080 F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR 02/05.182C H47616 F-23 11.F.1.4
- CONTAINMENT PRESSURE INSTRUMENT 04.121.183C U,Vll\\)~e:te.c-A \ o\8~ IEI~ 04- 33
- M47687 F-24 11.F.1 .5 CONTAINMENT HATER LEVEL INSTRUMENT 04.121.183C (..O~\ole..t-4i?.cl \0\8'-t l-EI!e. 81.{- 33 M47758 F-25 11.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/21.183C M45150 F-26 11.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 11.106.184C M46894 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06.105.184C M47808 F-33 11.K,2.17 POTENTIAL FOR VOIDING IN RCS 01.124.184C
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H45240 F-36 11.K.3.1 AUTO PORV ISOLATION 10.119.183C M45286 F-37 11.K.3.2 REPORT ON PORV FAILURES 10.119.183C M45360 F-38. 11.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06.102.181C M45403 F-39 11.K.3.5 AUTO TRIP OF RCPS 02.122.183C M45452 F-40 11.K.3.9 PID CONTROLLER 06.102.181C M45482 *F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 08.125(.81C 0 M45512 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 06.102/81C M45646 F-47 II.K.3.17 ECCS OUTAGES 08.117.183C M48424 F-53 II.K.3.25 POWER ON PUMP SEALS 06/22/82C M45843 F-57 II.K.3.30 SB LOCA METHODS 06/04/85C
R-1208731-001 R EGULAT ORY I N F O R MA T I O N T R A C KI NG S YS T EM PAGE ND.: 303 F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 NORTH ANNA 1 CCONTINUA TI ON) LIC ACT *ucENSEE IA~.HQ, MfA._J IIILI; t!U!leL~U STATUS ~ M48182 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 01/151'87 I M45962 F-63 III.A .1 .2 TECHNICAL SUPPORT CENTER 06/301'86 M46033 M46105 F-64 F-65 111.A.1.2 111.A.1.2 OPERATIONAL SUPPORT CENTER EMERGENCY OPERATIONS FACILITY 06/30/86
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061'301'86 e M46177 F-66 111.A.1.2 NUCLEAR DATA LINK 071'301'82C M46249 F-67 IILA.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 051'111'83C M46321 F-68 111.A.2.2 METEOROLOGICAL DATA UPGRADE 06/30/86 M46392 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 021'181'82C M46461 F-70 111.D.3.4 CONTROL ROOM HABITABILITY 031'201'84C M56142 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP TO 01/301'86 f'<'C>j ec::hc.l . C.ow.~j l..?fu1r ztu/&s M49665 G-01 REACTOR COOLANT PUMP TRIP CD660 - II.K.3.5) 04/30/16 p<"C>J e:.c:tQ~ LO\tV\fO'A'j L~ 5j3~~j,
R-12087 31-001 R EGULAT ORY I N F O R MA T I O N T RA C KI NG S YS T EM PAGE NO.: 304 F AC I L I T Y I MP L E ME N T A T I O N 03/31 /86 FACILITY: NORTH ANNA 2 PLANT LOCATION: 40 MI NW OF RICHMOND, VA LICENSED POWER: 2775 MHT PROJECT MANAGER: L. ENGLE DOCKET NUMBER: 050-00339 DESIGN POWER: 0907 MWE BRANCH CHIEF: L. RUBENSTEIN ARCH/ENGINEER: S&H NSSS VENDOR: HEST LIC. ASSISTANT: VACANT IE INSPECTOR: TAC NO. t1f.A...J TITLE LIC ACT COMPLETE
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STATUS LICENSEE
~ CJ:, vnm e.n t e H47503 A-02 APPENDIX I - ALARA 05/05/83C ~ple~J.. l \81.f Avnev-1cl.rt1ell'lt 3l M47562 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/05/82C c.n \-c').,\.e..\..-e.cl l'l %1.. N IR.C.. ~~ er H51111 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN M54506 A-18 TECH SPECS AFFECTED BY 50. 72 AND 50. 73 CGL 83-43) 02/01/85C c.omple.tt.cl "2.l&5 Ame.~~e..J; en A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S / f'l/\:,je.ct-~cl V\Ot S~u.t~d_
M59118 H59966 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE e.,o mflet-~ it ata c.owirit1"..) ~_ttw-- I( *2.~1s: 1 j8 5 G,vn p4~j Le#e-t- 1 j *3 I/ &t> H12150 B-16 EMERGENCY PLANNING AND REVISIONS 04/12/81C C,ovtlpl~ ttcl M46945 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 11/05/81C C..OV'II(' le Ho\. l q1 n A mevictrne."1..t 13 M46947 B1 22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 11/05/81C C..en1y,Le.*kc:l . 1qa,~ ,Am~-~cl.11>1eV1t; L~ M46508 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SERS 11/18/82C M48331 B:48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 11/13/84C M42540 B-60 ENVIRONMENTAL QUALIFICATION 12/12/84C M43948 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 08/20/81C M47153 B-66 NATURAL CIRCULATION COOLDOWN 10/19/83C M46846 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 09/30/82C M49743 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 01/12~-4C comf\e,~ 0185 S~f?.... 'M52778 B-76 ITEM 1 .1 - POST TRIP REVIEW; PROGRAM DESCRIPTION & 03/29/85C
~Wll°crnj Lit"tt~r 1jii.j&5 M52859 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 06/30/86 ~j~..\-~cl \'1B1 M52940 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/06/85C t) t"O,l U-te..cl 1ct 6"1 Cc""P"' 0:J le-tt-e...- 11 Uo /6-5 S£11{..
M53021 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/21/85C CP*"\' le..tul 11 ( 85
R-1208731-001 R EGULAT ORY I N F O R MA T I O N T RAC KI NG S YS T EM PAGE NO.: 305 F AC I L I T Y I MP L E ME N T A T I O N 03/31/86 NORTH ANNA 2 (CONTINUA Tl ON) LIC ACT LICENSEE TAC NO. MfA...J IJILe COMPLETE STATUS ~ M53082 M53135 M53182 M54550 B-80 B-81 B-82 B-83 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO ITEMS 4.2.1 & I 4.2.2 .,.PREVENTATIVE MAINT PROG FOR R ITEM 4,3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-06.i24/86C 04/24/85C O'J/24/84C
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G,""'~"j ~\lQ.-r- .5 M53611 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/14/85C C:.O\"r\\'tdecl M53694 B-86 SALEM ATHS 2.2 S-R COMPONENTS 12/30/86 p("O~~c.\-e_c.\.. M53777 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 12/06/85C p("<:>J I!. c.A-e d.. M53860 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/21/85C M53922 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 M55364 B-90 SALEM ATHS 4.3 HAND B&H T.S. 6/86 M54087 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 12/30/86 M54004 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 12/30/86 M47113 c-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL <PHASE 05/25/84C
<!.C>vYl'(lle. kJ... . \'lo'L .s.e,t M43673 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 01/21/82C c.e my,l~ kcl bjts Nf.C.. Le.-tiev-e.
M52249 C-15 CONTROL OF HEAVY LOADS - PHASE II CFOLLOHUP OF MPA 06/28/85C c.o*.~p~+d. <o 1s-s ComV,"~ Let{e..-,1nj8S M58072 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C c.o""'V)L..e. wl Yj~s Amer1cl1t)\Mt.. 48 M55881 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 04/25/85C l 't ?3 TC!~ 8~ -1 *!) M44039 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/25/82C c.o~"' \OIR. t-t.c\ l (J~ l ~~ M44108 F-02 I.A.1.3 SHIFT MANNING 06/30/83C f u:;, '"' \t,. ~cl (1S2- $ER. wt\<) le...-tect 0 M44179 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 06/02/81C t;.O M44250 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/0}/84C f'faj~c:kcl Cc\'l!.puv,j i..c~v- sj3c}E-G M44320 F-05 I.C.1.2/3,B PROCEDURES GENERATION PACKAGES CNUREG 08/23/85C seR M47233 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE t 1/20/81C (.c,,{V\f \.~-Cl
R-1208.7 31-001 R EGULAT ORY I N F O R MA T I O N T R A C KI NG S YS T EM PAGE NO.: 306 F AC I L I TY I MP L E ME N T A T I O N 03/31/86 NORTH ANNA 2 (CONTINUATION) LIC ACT LICENSEE TAC NO, Hf.A...J TJJLE COMPLETE STATUS ~ M47305 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/20/81C Comp\.e~J.. l~ &I
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M51181 F-08 I.D.1.1 DETAILED.CONTROL ROOM DESIGN REVIEW PROGRA 11/18/84C M51261 F-09 I.D.2 SAFETY 'PARAMETER DISPLAY SYSTEM ~4/25/85C f<'(;)~~~~cl
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M44389 F-10 11.B.1 RCS HIGH POINT VENTS 10/09/83C M47956 F-11 11.B.2 PLANT SHIELDING 11/14/83C M44458* F-12 11.B.3 POST ACCIDENT SAMPLING 02/27/84C
~o~le.~J. \C,8'3 J: Erle. 8 3 -0"1 M44529 F-13 11.B.4 TRAINING FOR HITIGATlNG CORE DAMAGE 02/02/82C M44599 F-14 11.D.1 RV AND SV "'FRAININ8-TESTIN6 06/30/86 r"('"cJ~ l ct 8'2" . CoMfl'\j ~&r- u("zs/.J.
M44644 F-15 11.E.1.1 AFH SYSTEM EVALUATION 06/02/81C COIIYI\O\e. \-ed. \<i8'1 !'ETR. 8l-07 M44685 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 11/30/81C C.1:>~f le. w z. I~'I ):"ETf.. 83-'3 I H44723 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 06/02/81C c..o l"(I\? IR-\t.J.. '2. \ 64 IETlZ.. '5 ~ -"31 M44797 F-18 11.E.4.1 DEDICATED HYDROGEN PENETRATION 05/17/82C M44868 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 06/02/81C M44939 M45010 F-20 F-21 II.F.1.1 II.F.1.2 NOBLE GAS MONITOR IODINE/PARTICULATE SAMPLING 10/21/81C 10/21/81C e H45081 F-22 11.F.1.3 CONTAINMENT HIGH RANGE MONITOR 02/05/82C C..o"""f>le\.e&. 1018-4 TEI~ 8-I - .3-3 M47617 F-23 11.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04/21/83C M47688 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 04/21/83C Cb'Mfl~~c.l 10/fs4 J:Er ~ 8'LI- - 3 3 M47759 F-25 11.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/211.~.3C 0 M4S151 F-26 11.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 11/06/84C M46895 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 061'05/&4C M47809 F~33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/24/84C M45241 F-36 11.K.3.1 AUTO PORV ISOLATION 101'191'83C
- I R-1208731-001 REGULATORY INFORM.AT ION TRACKING SYSTEM PAGE ND. : 307 F AC I L I T Y I MP L E ME N T A T 1 0 N 03.131/86 NORTH ANNA 2 (CONTINUATION)
LIC ACT LICENSEE IAC HQ, HfA.....I UJLE COMPLETE .SJATUS Mil M45287 F-37 II .K.3.2 REPORT ON PORV FAILURES 10.119/83C
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M45361 F-38 II.K.3.3 REPORTINO~V AND RV FAILURES AND CHALLE 06.102.181C M45404 F-39 II.K.3.5 AUTO TRIP 'of RCPS 02.122.183C
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M45453 F-40 11.K.3.9 PIO CONTROLLER 06.102.181C M45483 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 08.125.181C M45513 F-42 II. K*. 3 .12 ANTICIPATORY TRIP ON TURBINE TRIP 08"25.181C
- M45647 F-47 II.K.3.17 ECCS OUTAGES 12.l 30.183C M48425 F-53 II.K.3.25 POWER ON PUMP SEALS 06.122.182C M45844 F-57 II.K.3.30 SB LOCA METHODS 06.104.185C M48183 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 01.115/87 M45963 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 06.130.186 M46034 F-64 III.A.1.2 OPERATlONAL SUPPORT CENTER 06.130.186 M46106 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 06.130.186 M46178 F-66 111.A.1.2 NUCLEAR DATA LINK 07.130.182C M462SO F-67 111.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 0S.111.183C M46322 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 06.130.186 M46393 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02.118.182C M46462 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03.120.184C M56143 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOHUP TO C..01'1-'Y,"i'\J Latte,;- ~jell~
12.131.184 'M49666 G-01 REACTOR COOLANT PUMP TRIP CD660 - 11.K.3.5) 04.130.186 C.ow,,r-~J Lttitet- s/~/ 8(.}}