ML18092B145
| ML18092B145 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1986 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| TASK-***, TASK-TM NUDOCS 8605160478 | |
| Download: ML18092B145 (12) | |
Text
Docket Nos. 50-272 and 50-311 Mr. C. A. McNeill, Jr.
Vice President - Nuclear April 30, Public Service Electric and Gas Company Post Office Box 236 NRC PDR Gray Fi 1 e H. Thompson C. Vogan S. Scott Hancocks Bridge, New Jersey 08038 J. Partlow E. Jordan Dear Mr. M~~~d111~
The Comptroller General in a Report to the Congress dated September 19, 1984, stated 11 NRC needs better management controls to ensure implementation of generic issue solutions.
11 To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactor licensees* implementation of approved regulatory improvements.
To assist me in developing this information for Salem Units 1 and 2, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirement were completed/implemented or are expected to be completed.
For each requirement that has been completed, enter 11completed 11 under the Status column and the date the item was completed.
For requirements that have not been completed/
implemented, provide the projected date and enter 11projected 11 under the Status column.
I do not expect or want a major effort made to obtain precise dates.
Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented.
For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time.
For projected completions/
implementations in 1986, use month and year.
Use year only for projections thereafter.
Please provide a response in the form of a marked up listing by May 31, l 986.
In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.
This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.
-s6o5lb047er 866436 ---
PDR ADOCK 05000272 P
~**
Enclosure:
As stated cc w/enclosure:
See next page Sincerely,
/s/DFischer Don~ld C. Fischer, Senior Project M~nager PWR Project Directorate No. 3 Division of PWR Licensing-A, NRR OFC
- PAD#3
- PAD#3
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DATE :4/~0/86
- 4/~o/86
- 4/J;-~/86 I
Mr. C. A. McNeill Public Service Electric & Gas Company Salem Nuclear Generating Station cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric & Gas Company P. 0. Box 570 - Mail Code TSE Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Public Service Electric & Gas Company Post Office Box E Hancocks Bridge, New Jersey 08038 Robert Traae, Mayor Lower Alloways Creek Township Municipal Hall Hancocks Bridge, New Jersey 08038 Thomas Kenny, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, New Jersey 08625 Frank Casolito, Action Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628 Richard B. McGlynn, Co111JT1ission Department of Public Utilities State of New Jersey 101 Commerce Street Newark, New Jersey 07102 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, Pennsylvania 17120 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, New Jersey 08038 Mr. Bruce A. Preston, Manager Licensing and Regulation Public Service Electirc & Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 I
R-1208731-001 R E G U L A T 0 R Y I N F 0 R M A T I 0 N T R A C K I N G S Y S T E M FACILITY IMP L E.M ENT AT I 0 N FACILITY: SALEM 1 PLANT LOCATION: 20 MI S OF WILMINGTON, DEL DOCKET NUMBER:
050-00272 LICENSED POWER: 3338 MWT DESIGN PnWER:
1090 MWE ARCH/ENGINEER:
PUBSERVE NSSS VENDOR:
WEST IE INSPECTOR:
L. NORRHOLM I
I ITAc NO.
MPA #
I M06659 A-01 M08154 A-02 M06981 A-03 M08825 A-09 I
IM1 0743 A-10 I
1M10738 A-11
- M1 0746 A-12
- M11224 A-14 IM47078 A-16 I tM51128 A-17 I
iM55736 A-18
- M59136 A-20 TITLE 10 CFR 50.55 ACG) - !SI APPENDIX I -
ALARA LIC ACT COMPLETE 08/12/81C 12/05/84C SECURITY REVIEWS-MODIFIED AMENDMENT PLANS 02/23/79C PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 07/2S/80C CONTINGENCY PLANNING
. 09/12/80C GUARD TRAINING PLANS 05/12/81C VITAL AREA ANALYSIS 04/12/82C 10CFR 50.55 ACG) - INSERVICE TESTING 04/12/83C QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 11/06/81C INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 06/17/85C TECH SPECS AFFECTED BY 50.72 AND 50.73 CGL 83-43) 05/13/85C 10 CFR 50.62 OPERATING REACTOR REVIEWS N//*S /
PROJECT MANAGER: D. FISCHER BRANCH CHIEF:
S. VARGA LIC. ASSISTANT:
L. PARRISH LICENSEE STATUS DATE PAGE NO.:
430 03:i'~V86 M59978 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE
~
M07905 B-01 DIESEL GENERATOR LOCKOUT 09/29/78C M07063 B-02 FIRE PROTECTION 11/20/79C M08398 B-03 PWR MODERATOR DILUTION
. 04/29/82C M06744 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 02/21/80C IM07287 B-07 STEAM GENERATOR FEEDWATER FLOW INSTABILITY 11/03/79C M08170 B-08 PWR HPSI-LPSI FLOW RESISTANCE 11/28/80C M07842 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 11/09/79C L_
-- -*--- --------~------ --
R-1208731-001 SAL EM 1 TAC NO.
MPA I M08658 B-13 1 M08823 I
B-14 IM12163 B-16 I
1M11227 B-17 I M10272 B-20 M10336 B-21 M08822 B-22 I
iM1 0050 B-23 I
1M08993 B-24
- M42561 B-24 iM07491 B-26 IM08682 B-39 IM11110 B-41
- M43739 B-41
- M11711 B-42 IM11776 B-43 I_
IM43150 B-43
- M12435 B-44
- M12935 B-45 iM12603 B-46 I
iM12686 B-47
- M13009 B-48
- M11877 B-52 R E G U L A T 0 R Y I N F 0 R M A T I 0 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 0 ~
C CONTINUA TI ON)
TITLE LIC ACT COMPLETE FUEL ROD BOW 09/26/79C CEA GUIDE TUBE WEAR 07/22/80C EMERGENCY PLANNING AND REVISIONS 04/01/81C TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02/02/82C CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 01/31/81C LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 11/09/79C DEGRADED GRID VOLTAGE 01/25/82C VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 01/31/81C VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05/19/83C INADVERTANT SAFETY INJECTION DURING COOLDOWN 11/09/79C PWR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C FIRE PROTECTION -
FINAL TECH SPECS CINCLUDES SER S 08/24/80C FIRE PROTECTION -
FINAL TECH SPECS CINCLUDES SER S 06/17/83C TMI FOLLOW UP -
ALL PLANTS 06/05/81C PWR FEEDWATER LINE CRACKS
- 09/26/79G PWR FEEDWATER LINE CRACKS 05/25/82C LESSONS LEARNED IMPLEMENTATION 03/21/81C WASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C ANALYSIS OF TURBINE DISC CRACKS 08/21/81C ECCS; CLAD SWELLING AND RUPTURE 09/12/80C ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 11/21/81 C REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACT!
02/24/81C LICENSEE STATUS DATE L
PAGE NO.:
431 03/31/86
R-1208731-001 R E G U L A T 0 R Y I N F 0 R M A T I 0 N T R A C K I N G F A C I L I T Y I M P L E M E N T A T I 0 N SALEM 1 (CONTINUATION)
TAC NO.
MPA #
TITLE LIC ACT COMPLETE M42100 M42866 M42467
[M42705
- M42776 M43936 M47162 I 1M46858
- M49754 IM52710 IM52795 I
iM52876
- M52957 1
1M53038 IM53093 I
I M53146
- M53192
- M54564 IM53628 I
l 1M53711 I 1M53794 1M53877 M53933 B-57 DHR CAPABILITY B-59 MASONRY WALL DESIGN B-60 ENVIRONMENTAL QUALIFICATION B-61 LOSS OF NON CLASS IE I&C POWER B-62 ESF RESET CONTROL DESIGN DEFICIENCY B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 03/06/81C 08/18/83C 12/05/84C 07/28/82C 06/04/81C 12/09/81 c B-66 NATURAL CIRCULATION COOLDOWN 08/15/83C B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDW 10/20/82C B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 07/31/84C B-76 ITEM 1.1 - POST TRIP REVIEW; PROGRAM DESCRIPTION &
12/05/84C B-76 ITEM 1.1 -
POST TRIP REVIEW; PROGRAM DESCRIPTION &
09/15/85C B-77 ITEM 2.1 -
EQUIPMENT CLASSIFICATION & VENDOR INTER 09/30/86 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 03/17/86C B-79 ITEM 3.1.3 -
POST MAINTENANCE TESTING -
CHANGES TO 12/06/85C B-80 ITEM 4.1 -
REACTOR TRIP SYSTEM RELIABILITY -
VENDO 03/17/86C B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/06/85C B-82 ITEM 4.3 -
AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 06/25/84C B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-04/01/86 B-85 SALEM ATWS 1.2 DATA CAPABILITY 05/30/86 B-86 SALEM ATWS 2.2 S-R COMPONENTS 01/01/87 B-87 SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 03/17/86C B-88 SALEM ATWS 3.2.3 T.S. S-R COMPONENTS 12/06/85C B-89 SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS 11/30/86
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S Y S T E M PAGE NO. :
432 LICENSEE STATUS DATE 03i'~.1/86 I
j
I I
I
!R-1208731-001 I
1*
ISALEM 1 I
I I
1TAC NO.
MPA #
- M55374 IM54104 IM54021
- M07642
- M07245 IM08826
- M08081
- M43661
- M52266 iM58084 M07874 I
IM07856 1M08824 1
1M08998 I M12276 I
iM4301 O IM55898
- M07158 IM07579 I,
tM11124
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COMPLETE SALEM ATWS 4.3 WAND B&W T.S.
04/30/86 S*ALEM ATWS 4.5.1 DIVERSE TRIP FEATURES 03/17/86C SALEM ATWS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/31/87 PWR SECONDARY WATER CHEMISTRY MONITORING REQUIREME 04/2~/80C PUMP SUPPORT-LAMELLAR TEARING 01/21/81C FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 11/28/79C CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL *(PHASE 06/22/84C AUXILIARY FEEDWATER SEISMIC QUALIFICATION 08/24/82C CONTROL OF HEAVY LOADS -
PHASE II' CFOLLOWUP OF MPA 06/28/85C UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 02/12/86C ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR-06/06/79C PRESSURIZER HEATUP RATE ERROR 07/27/79C ASYMMETRIC LOCA LOADS 06/30/86 FISSION GAS RELEASE 02/22/80C HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C DEFINITION OF OPERABLE 11/28/80C DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15) 09/12/85C SPENT FUEL POOL EXPANSIONS 01/15/79C SPENT FUEL POOL EXPANSIONS 01/15/78C SPENT FUEL POOL EXPANSIONS 06/01/79C I. A.1.1. SHIFT TECHNICAL ADVISOR
.
~----------------
S Y S T E M LICENSEE STATUS DATE PAGE NO. :
433 1
I 03/ 3.1/86 I
- R-1208731-001 REG u LAT 0 Ry I N F 0 RM A T"I 0 N T.RA c KI NG sys TE M F A C I L I T Y I M P L E M E N T A T I 0 N SALEM 1 (CONTINUATION)
TAC NO.
MPA I TITLE LIC ACT COMPLETE 1M44268 I
IM44338 I iM47251
- M47323 iM51198
'M51278 M44405 M47974 M44476 M44547 M44618 M44650 M44690 M44729 IM44815 I 1M44886 IM44957 M45028 M45099 rM47635 1
1M47706
- M47777 IM45169 I '
F-04 F-05 F-06 F-07 F-08 F-09 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG I.C.5 I.C.6 FEEDBACK OF OPERATING EXPERIENCE CORRECT PERFORMANCE OF OPERATING ACTIVITI I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA I.D.2 SAFETY PARAMETER DISPLAY SYSTEM F-10 II.B.1 RCS HIGH POINT VENTS F-11 II.B.2 PLANT SHIELDING F-12 II.B.3 POST ACCIDENT SAMPLING F-13 II.B.4 TRAINING _FOR MITIGATING CORE DAMAGE F-14 II.D.1 RV AND SV TRAINING F-15 II.E.1.1 AFW SYSTEM EVALUATION F-16 II.E.1.2.1 AFW SYSTEM INITIATION F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY F-20 II.F.1.1 NOBLE GAS MONITOR 06/07/84C 12/30/88 11/15/81 c 11/15/81 c 06/01/86 07/15/86 09/27/83C 01/31/83C 11 /04/83C 01/27/82C 05/30/86 09/20/82C 06/16/81C 06/16/81C 06/16/81C 04/11/82C 1 0/01 /81 c F-21 II.F.1.2 IODINE/PARTICULATE SAMPLING 10/01/81C F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 02/11/82C F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 09/28/82C F-24 II.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 09/28/82C F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 09/28/82C F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 19/24/84C LICENSEE STATUS DATE PAGE NO.:
434 037~1/86
_______________ __j
R-1208731-001 SALEM 1 1TAC NO.
MPA #
M46903 F-30 M47817 F-33 M45247 F-36 M45293 F-37 M45379 F-38 M45410 F-39 1M45459 F-40 M45489 F-41 M45519 F-42 M45665 F-47 M48431 F-53 M45862 F-57 M48201 F-58 M45981 F-63 M46052 F-64 M46124 F-65 M46196 F-66 M46268 F-67 M46340 F-68 M46411 F-69 M46480 F-70 M56160 F-71 M49669 G-01 REGULA T 0 RY INF 0 RM AT I 0 N TR A.CK I.NG SYSTEM F A C I L I T Y I M P
- L E M E N T A T I.0 N C CONTINUA TI ON)
TITLE II.K.2.13 THERMAL-MECHANICAL REPORT II.K.2.17 POTENTIAL FOR VOIDING IN RCS II.K.3.1 AUTO PORV ISOLATION II.K.3.2 REPORT ON PORV FAILURES LIC ACT COMPLETE 06/18/84C 0.1 /30/84C 10/06/83C 10/06/83C II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 02/21/82C II.K.3.5 AUTO TRIP OF RCPS II.K.3.9 PID 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.~
OPERATIONAL SUPPORT CENTER III.A.1.2 EMERGENCY OPERATIONS FACILITY III.A.1.2 NUCLEAR DATA LINK III.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 CFOLLOWUP TO REACTOR COOLANT PUMP TRIP CD660 - II.K.3.5) 02/22/83C 08/24/81 c 08/24/81 c 08/26/81 c 09/27/83C 06/28/82C.
06/17/85C 01/1.5/87 12/30/87 12(30/87 12/30/87 07/30/82C 08/08/83C 06/30/87 02/01 /82C 01/31/84C 04/01/86 LICENSEE STATUS DATE PAGE NO. :
435 03/5_1/86
R-1208731-001 R E G U L A T 0 R Y I N F 0 R M A T I 0 N T R A C K I N G F A C I L I T Y I M P L E M E N T A T I 0 N
,FACILITY: SALEM 2 PLANT LOCATION: 20 MI S OF WILMINGTON, DEL 050-00311 LICENSED POWER: 3411 MWT DESIGN POWER:
1115 MWE DOCKET NUMBER:
I ARCH/ENGINEER:
PUBSERVE NSSS VENDOR:
WEST IIE INSPECTOR:
I I
I 1TAC NO.
MPA #
TITLE LIC ACT COMPLETE
- M48327 A-02 APPENDIX I -
ALARA 12/05/84C 09/03/82C 06/17/85C 05/13/85C iM46814 I
IM51129 M55737
- M59137 IM59979 I iM12164
- M46782
- M46781 IM46712 I
IM11712 I 1M48330
- M46813 IM42533 M43949 M47163
- M46859 1
1M49755 IM52796 I
1M52877
~
A-14 10CFR 50.55 ACG) - INSERVICE TESTING A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 CGL 83-43)
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 05/20/81C B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02/02/82C B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05/19/83C B-41 FIRE PROTECTION -
FINAL TECH SPECS CINCLUDES SER S 06/17/83C B-42 TMI FOLLOW UP -
ALL PLANTS 07/31/81C B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/02/82C B-59 MASONRY WALL DESIGN 08/18/83C B-60 ENVIRONMENTAL QUALIFICATION 01/14/85C B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12/09/81C B-66 NATURAL CIRCULATION COOLDOWN 08/15/83C B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDW 10/20/82C B-72 NUREG 0737 TECH SPECS CGENERIC LETTER 82-16) 07/31/84C B-76 ITEM 1.1 -
POST TRIP REVIEW; PROGRAM DESCRIPTION &
09/15/85C B-77 ITEM 2.1 -
EQUIPMENT CLASSIFICATION & VENDOR INTER 09/30/86 S Y S T E M PROJECT MANAGER: D. FISCHER BRANCH CHIEF:
S. VARGA LIC. ASSISTANT:
L. PARRISH LICENSEE STATUS DATE PAGE NO. :-
436 I o3/'31/86 I I
I I
________________________________________ j
R-1208731-001 R E G U L A. T 0 R Y. I N F 0 R M A T I 0 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 0 N SALEM 2 1 TAC NO.
I iM52958 I
1M53039
- M53094
- M53147 IM53193 1M54565
- M53629
- M53712 IM53795 I 1M53878 f M53934 IM55375 IM54105 I
IM54022
- M46815 IM43674 IM52267 IM58085 I 1M55899 iM44056 M44127 M44198
[M44269
~
~
I MPA #
B-78 B-79 B-80 B-81 B-82 B-83 B-85 B-86 B-87 B-88 B-89 B-90 B-92 B-93 C-10 C-14 C-15 C-16 D-19 F-01 F-02 (CONTINUATION)
LIC ACT TITLE
- COMPLETE ITEMS 3.1.1*& 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/06/85C ITEM 3.1. 3 - POST MAINTENANCE TESTING -
CHANGES TO 12/06/85C ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY -
VENDO ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/06/85C ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 06J25/84C TECH SPECIFICATIONS COVERED BY GENERIC LETTERS.83-04/01/86 SALEM ATWS 1.2 DATA CAPABILITY 05/30/86 SALEM ATWS 2.2 S-R COMPONENTS 01701/87 SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 03/17/86C SALEM ATWS 3.2.3 T.S. S-R COMPONENTS 12/06/85C SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS 11/30/86 SALEM ATWS 4.3 WAND B&W T.S.
04/30/86 SALEM ATWS 4.5.1* DIVERSE TRIP FEATURES 03/17/86C SALEM ATWS 4.5.2 & 4.5.3 TEST ALTERNATIVES
.04/31/87 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL CPHASE 06/22/84C AUXILIARY FEEDWATER SEISMIC QUALIFICATION 08/24/82C CONTROL OF HEAVY LOADS -
PHASE II CFOLLOWUP OF MPA 06/28/85C UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN.
02/12/86C DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15)
I.A.1.1 SHIFT TECHNICAL ADVISOR I.A.1.3 SHIFT MANNIN~
F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 09/06/85C 01/11 i82C 06/30/83C 01/31/81 c F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/25/84C LICENSEE STATUS DATE PAGE NO.. :
437 o3/.l1/86
I i
I IR-1208731-001 I
I I
ISALEM 2 I
I ITAC NO.
MPA I I
IM44339 I 1M47252 F-05 F-06 R E G U L A T 0 R Y I N F 0 R M A T I 0 N*
T R A C K I N G F A C I L I T Y (CONTINUATION)
TITLE I M P L E M E N T A T I 0 N LIC ACT COMPLETE I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 12/30/88 I.C.5' FEEDBACK OF OPERATING EXPERIENCE
- M47324 M51199 I
F-07
- I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI
'11/15/81 c 11/15/81 c 06/01/86, 07/15/86 09/27/83C 01/31/83C 11/04/83C 05/19/81C 05/30/86 09/20/82C 06/12/81 c 06/12/81C 08/24/81C 04/19/8.2C 1 0/01/81 c 10/01/81 c 01/31/81 c F-08 IM51279 F-09 I
M44406 F-10
- M47975 F-11
~M44477 F-12 I
!M44548 F-13 I
1M44619 F-14
- M44651 F-15 1M44691 F-16 I
IM44730 F-17 I fM4.4816 F-18
- M44887 F-19
' M44958 F-20 1M45029 F-21 i
M45100 F-22 M47636 F-23 1M47707 F-24 IM47778 F-25 I
M45170 F-26 M46904 F-30 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA I.D.2 SAFETY PARAMETER DISPLAY SYSTEM II.B.1 RCS HIGH POINT VENTS II.B.2 PLANT SHIELDING II.B.3 POST ACCIDENT SAMPLING II~B.4 TRAINING FOR MITIGATING CORE DAMAGE II.D.1 RV AND SV TRAINING II.E.1.1 AFW SYSTEM EVALUATION II.E.1.2.1 AFW SYSTEM INITIATION II.E.1.2.2 AFW SYSTEM FLOW INDICATION II.E.4.1 DEDICATED HYDROGEN PENETRATION II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY II.F.1.1 NOBlE GAS MONITOR II. F.1. 2 IODINE/PARTICULATE SAMPLING II. F.1. 3. CONTAINMENT HIGH RANGE MONITOR II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 09/28/82C II.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 09/28/82C II.F.1.6 CONTAINMENT HYDROGEN MONITOR 09/28/82C II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 10/24/84C II.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C S Y S T E M LICENSEE STATUS
- DAT!;
PAGE NO._: - 438 I 03i'3.V86 J
R-12087 31-001 R E G U L A T 0 R Y I N F 0 R M A T I 0 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 0 N
,SALEM 2 (CONTINUATION)
TAC NO.
MPA #
TITLE LIC ACT COMPLETE M47818 I IM45248 M45294 M45380 1M45411 M45460 M45490 M45520 I
M45666 M48432 M45863 M48202 M45982 M46053 M46125 M46197 M46269 M46341 M46412
'M46481 IM56161 I
M49670 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/30/84C F-36 II.K.3.1 AUTO PORV ISOLATION 10/06/83C F-37 II.K.3.2 REPORT ON PORV FAILURES 10/06/83C F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 02/26/82C F-39 II.K.3.5 AUTO TRIP OF RCPS F-40 II.K.3.9 PID CONTROLLER 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 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 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY F-66 III.A.1.2 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 F-70 III.D.3.4 CONTROL ROOM HABITABILITY F-71 G-01 I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP TO REACTOR COOLANT PUMP TRIP CD660 - II.K.3.5) 02/22/83C 08/24/81C 08/24/81C 08/24/81C 09/27/83C 06/28/82C 06/17/82C.
01/15/87 12/30/87
. 12/30/87
'06/30/87 07/30/82C 08/08/83C 06/30/87 01 /02/82C 01/31/81 c 04/01/86 LICENSEE
. STATUS DATE PAGE NO.. :. 439.
03/~/86
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