ML20203J864

Forwards marked-up Regulatory Info Tracking Sys Facility Implementation Listing Providing Status of Generic Issues, Per 860501 Request

ML20203J864
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	07/25/1986
From:	Leblond P COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
TASK-***, TASK-OR, TASK-TM 1907K, NUDOCS 8608060043
Download: ML20203J864 (8)

Text

. -. . .. -- _ -. _. -- ._

CommORWealth Etlison

. A3 One First Nabonal Plaz.7, Chicago, Illinois V

Address Peply to: Post Omco Box 767 Chicago, lilinois 60690 - 0767 i July 25, 1986 d-Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission

. Washington, DC 20555

Subject:

Zion Nuclear Power Station Units 1 and 2 Implementation of Generic Requirements NRC Docket Nos. 50-295 and 50-304

Reference:

May 1, 1986 letter from J. A. Norris to D. L. Farrar.

i

Dear Mr. Denton:

The referenced letter requested that Conunonwealth Edison Company provide the NRC with the status of a number of generic issues. A list of

! Multi-Plant Actions (MPA) was provided along with the request. The completed list is attached to this letter.

A number of the MPA descriptions were very cryptic. Thus, in many

cases it was impossible to accurately determine the-issue for which information was being sought. No information was provided for those issues

, and they were designated with a "?".

In addition, commonwealth Edison company cautions any potential users of this list to be wary of possible discrepancies. A strong effort

! has been made to supply as much information as possible, with approximately 90 man-hours being expended. However, as discussed above, some of the issues were vague and ill-defined and would require a much larger effort to completely research and validate the status. Thus, the best available information was supplied within the time available.

I l If any further questions arise concerning this matter, please i contact this office.

i' Very truly yours, P. C. LeBlond Nuclear Licensing Administrator j 1m 0o l cc: Resident Inspector - Zion <l ig l J. A. Norris - NRR

1907K 8608060043 860725 PDR ADOCK 05000295 p PDR

t-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.

• 567 FACILITY IMPLEMENTATION 03/31/86 FACILITY: ZION 1

'LANT LOCATION: 40 MI N OF CHICAGO, ILL LICENSED P0HER: 3250 MHT PROJECT MANAGER: J. NORRIS DOCKET NUMBER: 050-00295 DESIGN POWER: 1940 MHE BRANCN CHIEF: S. VARGA LRCH/ ENGINEER: S&L NSSS VENDOR: HEST LIC. ASSISTANT: L. PARRISH

[E INSPECTOR: M. HOLZMER LIC ACT LICENSEE FAC NO. MPA 8 TITLE COMPLETE STATUS jlAlg 106911 A-01 10 CFR 50.55 A(G) - ISI 08/08/80C (-- b Y 108130 A-02 APPENDIX I - ALARA 12/15/85 106554 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 03/14/79C 108862 A-04 APPENDIX J - CONTAINMENT LEAK TESTING 09/30/81C C s/27/# 5 M 48D 100089 A-07 APPENDIX G - FRACTURE TOUGHNESS 06/18/79C C ' */

• 108988 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 04/22/80C C. ' / #'/ U 110741 A-10 CONTINGENCY PLANNING 11/17/80C 110/39 A-11 GUARD TRAINING PLANS 01/15/81C f 110745 A-12 VITAL AREA ANALYSIS 04/13/82C [

51367 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEri P ITk7 575G A-18 LECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/30/85 6 sN4[gc Am).96/8d

'9160 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S / h /7EO N 0777 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE ( E'7/ N 07908 B-01 DIESEL GENERATOR LOCK 0UT 09/29/78C $

OG770 B-02 FIRE PROTECTION 03/10/78C P '987 '

08408 B-03 PHR MODERATOR DILUTION 02/21/79C I- I37Y

$00705 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 04/28/80C I- I h07810 B-07 STEAM GENERATOR FEEDHATER FLON INSTABILITY 10/01/79C  ?

08175 B-08 PHR HPSI-LPSI FLOH RESISTANCE 10/24/84C [

[ M- N '

07837 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 02/19/80C

-1208731-001 REOULATORY INF0RMATION TRACKING SYSTEM PAGE NO. 568 FACILITY IMPLEMENTATION 03/51/86 BON 1 (CONTINUATION)

LIC ACT LICENSEE 1 AC NO. MPA 9 TITLE COMPLETE STATUS JLQg 08869 B-14 CEA GUIDE TUBE HEAR 10/06/80C  ?

32129 B-16 EMERGENCY PLANNING AND REVISIONS 05/01/81C j g 11228 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 01/22/86C 10278 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C .

11144 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 07/13/77C  ?

.8844 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 01/22/86C b 10061 5-23 DEGRADED GRID VOLTAGE 06/24/82C C 3/2M/ fd A"J 9 7[87 10200 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 08/14/80C P 42516 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL PON 09/28/83C P IM7 Y*'/d 9[o 30239 B-26 INADVERTANT SAFETY INJECTION DURING C00LDOWN 12/28/79C  ?

L:8488 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 04/22/80C [

C t9eI aJ M/d' 2 01071 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/17/83C 01718 B-42 TMI FOLLOW UP - ALL PLANTS 03/27/81C $

h1782 B-43 PHR IEEDHATER LINE CRACKS 02/25/80C C l9 &D 3159 B-43 PHR FEEDHATER LINE CRACKS 05/25/82C p0099 B-44 LESSCNS LEARNED IMPLEMENTATION 03/26/80C 7 20100 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 30101 5-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 20102 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C '

20103 B-44 LESSONS LEARNED IMPLEMENTnTION 03/26/80C l

30104 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 30105 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C l

30106 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C V

1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PA2E NO. 519

FACILITY IMPLEMENTATION 03/31/86 h0N 1 (CONTINUATION)

{

f LIC ACT LICENSEE

$fi_t1 MPA 9 TITLE COMPLETE STATUS RAIE 30107 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C f 60108 B-44 LESSONS LEARNED IMPLEMENTATION 03/26edOC -

0109 B-44 LESSONS LEARNED IMPLEMENTATION 05/26/80C 60110 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 0111 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C  ;

60112 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 2433 B-44 LESSONS LEARNED IMPLEMENTATION 06/02/80C y 2942 B-45 NASH 1400 EVENT V, " PRIMARY COOLANT SYSIEM PRESSUR 04/23/81C  ?

2587 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/19/81C P l9&1 66C twla wp t< e e '

-2692 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/12/80C C [3 8 l 3007 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 04/09/81C [

1885 B-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/15/80C f 2105 B-57 DHR CAPABILITY 06/22/81C S 2871 B-59 MASONRY HALL DESIGN 12/30/85 C IiN 2472 B-60 ENVIRONMENTAL QUALIFICATION 11/14/84C c. i9 85

~)716 B-61 LOSS OF NON CLASS IE ISC POWER 07/28/82C [

2788 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 08/10/81C C. I 18 O 3899 B-63 INTERIM PROCEDURES FOR SNORT TERM BLACKOUT 12/15/81C C. Ii 7187 B-66 NATURAL CIRCULATION C00LD0HN 08/09/83C C l3 N

'859 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITN CONTINUED FEEDH 01/26/83C C I3 EIN 643 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C  ?

9769 B-72 NUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 11/01/83C [$ 8 7 f

w2814 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 07/17/85C N

y _.

t-1208731 -0 01 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. '570 FACILITY IMPLEMENTATION 03/31/86 EION 1 (CONTINUATION)

LIC ACT LICENSEE FAC NO. MPA # TITLE COMPLETE STATUS p_Alg 452895 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 12/30/85 }

l 52970 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 07/05/85C w P 1 T8 7 g

'53057 1 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 04/30/86 H 53110 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO g 453163 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 06/20/85C N Nt l

153205 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 01/23/85C I 4 454580 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 10/10/85C 453648 B-85 SALEM ATHS 1.2 DATA CAPABILITY 12/30/85 f l e7 I U.

53731 B-86 SALEM ATHS 2.2 S-R COMPONENTS 03/30/86 -

453814 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 07/05/85C 9 p

'  ?

53897 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 04/30/86 3 f D% W 153950 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 10/31/86 3 0 q) l t-~ U L.

/

B-90 SALEM ATHS 4.3 H AND B&W T.S. IO 455387 l

12/30/85 54 b

f f Ff 54124 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 07/05/85C y 54041 B-95 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 03/30/86 08258 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 04/28/80C 7 108014 C-04 FILTER TECH SPECS 08/08/80C 7 08874 C-06 PUMP SUPPORT-LAMELLAR TEARING 01/27/81C 108876 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 03/02/79C c I9&2.(.')

l 108475 C-09 PHR AUX FH PUMPS 10/31/80C [

08092 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 03/22/84C c. 1/85 43G37 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 08/15/83C C, I9I3 152285 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPA 06/28/85C c 7/ & 5 k

t-1208731 -0 01 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NB.: 571 FACILITY IMPLEMENTATION 03/31/86 LION 1 (CONTINUATION)

LIC ACT LICENSEE FAC NO. MPA 8 TITLE COMPLETE STATUS p_tgg h59003 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 02/28/86C C. IiI b 07881 D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE HITH 10 CFR- 02/16/19C 0 407178 D-03 PRESSURIZER HEATUP RATE ERROR 01/16/79C 7 1

108872 D-10 ASYMMETRIC LOCA LOADS 02/01/84C C- 2.(,(r + 6 cc -

10004 D-11 FISSION GAS RELEASE 02/22/80C f 408878 D-14 REACTOR VESSEL HELD - HIRE DEFICIENCY C sjoyjg (, PTS sd.

04/01/80C 412282 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C k I"I ~ "'

443015 D-17 DEFINITION OF OPERABLE 06/22/81C C J/2.4[d M NN 155920 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 02/28/86C 9 I9I7 197553 E-01 SPENT FUEL POOL EXPANSIONS 03/29/79C C i990 01852 E-02 FUEL CASK DROP 04/21/80C 103431 E-05 H N-1 LOOP OPERATION 11/15/84C 444066 F-01 I.A.1.1 SHIFT TFCHNICAL ADVISOR 01/11/82C P T/ 8 6 144137 F-02 I.A.1.3 SHIFT MANNING 06/30/83C C. I983 444208 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 03/02/82C C. I981 44279 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 02/28/85C C 12./8 j 144349 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 01/30/88 P I987 4'47203 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/12/82C C I301 147335 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 01/12/82C C l T 8 2-.

151217 l

F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 09/15/86 P 17& P 151297 1

F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/22/84C C. I9%Z 44417 F-10 II.B.1 RCS HIGH POINT VENTS 09/09/83C C l3S3 447986 F-11 II.B.2 PLANT SHIELDING 04/12/83C C., IT83 w

=>1208731 -0 01 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 572 FACILITY IMPLEMENTATION 03/31/86 IEN 1 (CONTINUATION)

LIC ACT LICENSEE AC NO. MPA 0 TITLE COMPLETE STATUS RAJ,g 44487 F-12 II.B.3 POST ACCIDENT SAMPLING 06/22/84C C- 9/ 8'S 44558 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 05/28/82C C INE PCL to if A O 44530 F-14 II.D.1 RV AND SV TRAINING 01/30/86 C k 95 4 /ea/75 f ' /t h 46556 F-15 II.E.1.1 AFH SYSTEM EVALUATION 01/21/83C C. I9N 44700 F-16 II .E.1.2.1 AFH SYSTEM INITI ATION 04/20/81C 44739 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 04/20/81C (

44826 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 09/17/CIC C-44897 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 09/30/82C C l381 44918 F-20 II.F.1.1 NOBLE GAS MONITOR 09/23/81C P I98/

45039 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 09/23/81C E I 45110 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/08/82C C lCf &J 47647 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 09/09/83C P i 'l87 47718 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 09/09/83C C_ [ T 8,$

47789 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 09/09/83C C_ l q8}

45180 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE p l q gg 46913 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 10/26/83C C l 9 P4' 47827 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/16/84C C l *I b 45257 F-36 II.K.3.1 AUTO PORV ISOLATION 09/12/83C C I3E) 45303 F-37 II.K.3.2 REPORT ON PORV FAILURES 09/12/83C C I3 83 145390 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 09/17/82C C I '[ 8 1 45420 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C C.

45459 F-40 II.K.3.9 PID CONTROLLER 09/02/81C C l3b 45499 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 09/02/81C C [ g gl

t-12087 31 -0 01 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. '573 FAC1LITY IMPLEMENTATION 03/31/86 ILN 1 (CONTINUATION)

LIC ACT LICENSEE

'AC NO. MPA 3 TITLE COMPLETE STATUS RA.[f, 145529 F-42 II.K.3.12 ANTICIPATORY TRIP DN TURBINE TRIP 09/02/81C C I3 E l 145577 F-47 II.K.3.17 ECCS OUTAGES 08/09/83C C l3 b 148439 F-53 II.K.3.25 P0HER ON PUMP SEALS 05/26/82C C. I381 145873 F-57 II.K.3.30 SB LOCA METHODS 06/18/85C C 6/F5 148214 F-58 COMPLIANCE HITH 10 CFR 50.46 C- U85

• 145992 F-63 II.K.3.31 III.A.1.2 TECHNICAL SUPPORT CENTER 01/15/87 12/30/85 P I Ta 7

• "((

145014 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 12/30/85 C 145136 F-65 III.A.1.2 EMERGENCY OPERATTONS FACILITY 12/30/85 f lTI 146208 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C C. I 3 Ell-145280 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/16/83C C. !9E3 146351 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 12/30/85 P 1 T& 7 145422 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/19/82C C I3E1 146555 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 06/24/82C P Ii3 7 155182 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOHUP TO 06/30/86 f I3&7 149583 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 12/30/85 C [Tf3 L