ML20209G032

Forwards Updated Regulatory Trending Sys Implementation Rept,Listing Dates When Regulatory Improvements Implemented

ML20209G032
Person / Time
Site:	Maine Yankee
Issue date:	08/28/1986
From:	Whittier G Maine Yankee
To:	Thadani A Office of Nuclear Reactor Regulation
References
7983L-SDE, GDW-86-198, MN-86-108, NUDOCS 8609120345
Download: ML20209G032 (9)

Text

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MAIRE HARHEE MOMICPOWERCOMPARUe avaugray,?n"eya's h (207) 623-3521 O August 28, 1986 MN-86-108 GDH-86-198 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Ashok C. Thadani, Director PHR Project Directorate #8 Division of Licensing

References:

(a) License No. DPR-36 (Docket No. 50-309)

(b) USNRC Letter to MYAPCo dated April 28, 1986 (c) MYAPCo Letter to USNRC dated June 6, 1986 (MN-86-75)

Subject:

Implementation Status of Approved Regulatory Improvements Gentlemen:

Enclosed is an updated version of the Regulatory Trending System Implementation List for Maine Yankee which was transmitted in Reference (c),

in response to your letter, Reference (b).

The completion dates indicated on the enclosed listing are best estimates of the dates when the regulatory improvements were implemented according to our understanding of the entries. Some of the entries on the attached list are not applicable to Maine Yankee and these are marked with an "NA".

As we indicated in Reference (c), some caveats apply to the enclosed Implementation Status Report:

(a) " Complete" (C) indicates based upon our review that Maine Yankee commitments to satisfy the applicable regulatory activities have been implemented. Complete does not mean that Maine Yankee is in verbatim compliance with the NRC regulatory position or that the NRC has completed their final review of the issue.

(b) This information neither implicitly nor explicitly constitutes any commitment either in content or schedule to future regulatory actions, or modifys any previous Maine Yankee commitment pertaining to the listed regulatory actions.

CO 8609120345 860320 ADOCK .,

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. . M AINE Y ANKEE ATOMIC FOWER COMPANY United States Nuclear Regulatory Commission Page Two Attention: Mr. Ashok C. Thadani, Director MN-86-108 He want to thank you for the assistance provided by your staff in completing the table.

Please contact us if you have any questions or require additional information.

Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY 0)hW G. D. Whittier, Manager Nuclear Engineering and Licensing GDH/bjp Enclosure (7 Pages) cc: Dr. Thomas E. Murley Mr. Pat Sears Mr. Cornelius F. Holden 7983L-SDE

R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.: 2 FACILITY IMPLEMENTATION 03/31/

FACILITY: MAINE YANKEE PLANT LOCATION: 10 MI N OF BATH, ME LICENSED POWER: 2630 MHT PROJECT MANAGER: P. SEARS DOCKET NUMBER: 050-00309 DESIGN P0HER: 0825 MHE BRANCH CHIEF: A. THADANI ARCH / ENGINEER: 58H NSSS VENDOR: COMB LIC. ASSISTANT: P. KREUTZER IE INSPECTOR: C. HOLDEN LIC ACT LICENSEE TAC HO. MPA 8 TITLE COMPLETE STATUS p_Alf A

M08323 A-01 10 CFR 50.55 A(G) - ISI 05/08/83C M07752 A-02 APPENDIX I - ALARA 04/28/85C O M06323 A-02 APPENDIX I - ALARA 01/01/70C C 76 M07016 A-03 SECURITY REVIEHS-MODIFIED AMENDMENT PLANS 02/23/79C C. /777 M08897 A-04 A-09 APPENDIX J - CONTAINMENT LEAK TESTING 05/01/83C C IfN

/7N M11380 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 05/19/80C O M10730 A-10 CONTINGENCY PLANNING 09/15/82C C /

M10734 A-11 GUARD TRAINING PLANS 09/15/82C C I M10732 A-12 VITAL AREA ANALYSIS 04/14/82C O /

M10858 M12562 A-14 A-15 10CFR 50.55 A(G) - INSERVICE TESTING 02/24/83C b /hf3 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/11/80C C /777 M51103 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 11/30/86 In ccmpIde-M55296 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/26/84C C-- /

M59110 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 12/31/86 ' # "'I Of0fedC m M59961 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31/86 Ce /T N06537 B-02 FIRE PROTECTION 04/24/78C C- I

'M00386 B-03 PHR MODERATOR DILUTION 07/10/81C C  !

M03741 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 02/27/81C 0--  !

N07191 B-07 STEAM GENERATOR FEEDHATER FLOH INSTABILITY 03/12/80C C I M08168 B-08 PHR HPSI-LPSI FLOW RESISTANCE 09/27/79C C l7N e

t-1208751-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.: 254 FACILITY IMPLEMENTATION 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE FAC NO. MPA 8 TITLE COMPLETE STATUS PA.Tf, 107845 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 12/07/79C C N77 106580 B-11 FLOOD OF EQUIPMENT IMPORTANT TO SAFETY 10/19/81C C, Ifb 107517 B-14 CEA GUIDE TUBE HEAR 09/21/81C C SY 112140 B-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C C. /Ib 108904 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS C 110313 04/30/86 T/56 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C //4 110375 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C /VA 108905 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/06/81C O  !

110032 B-23 DEGRADED GRID VOLTAGE 03/27/84C (.-

142587 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL PDH 07/19/83C (- I[84 110215 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 10/22/80C O /i 110250 B-26 INADVERTANT SAFETY INJECTION DURING C00LDONN 09/14/79C OA 108901 B-36 RESISTANCE TEMPERATURE DETECTOR (RTD) RESPONSE - C 07/24/81C A/A 108907 B-37 STEAM GENERATOR TUBE DENTING AND SUPPORT PLATE MOD 08/07/78C O H7f 108695 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C O I 149134 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 02/03/83C C /N

$11074 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 10/24/79C b I 11792 B-43 PHR FEEDHATER LINE CRACKS 07/31/80C O 43141 B-43 PHR FEEDHATER LINE CRACKS 05/25/82C b I 30561 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C (< l1 30562 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C C I 0563 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C C Iib 30564 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b e

R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.* 25 FACILITY IMPLEMENTATION 03/31/8 MAINE YANKEE (CONTINUATION)

LIC ACT LICENSEE TAC HO. MPA 8 TITLE COMPLETE STATUS DAIE M30365 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M30566 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M30567 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M30568 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C O  !

M30569 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C O M12364 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C O M30556 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M30557 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M30558 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 0 /

M30559 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C O  !

M30560 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C b M12876 B-45 HASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/23/81C O M12614 B-46 ANALYSIS OF TURBINE DISC CRACKS 09/04/81C b M1272P B-47 ECCS; CLAD SHELLING AND RUPTURE 09/10/80C O /

M12744 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 03/26/81C b M62111 B-57 DHR CAPABILITY 03/05/81C b M42893 B-59 MASONRY IIALL DESIGN 12/15/85C b b M42490 B-60 ENVIRONMENTAL QUALIFICATION 12/13/84C C l '/

M42683 B-61 LOSS OF NON CLASS IE I8C POWER 07/28/82C /VA -

"M42F56 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 04/05/82C A/A M47174 B-66 NATURAL CIRCULATION C00LDOHN 05/31/83C C Ib

.M47545 B-67 THERMAL SHOCK 02/03/83C C /((3

'M47029 B-67 THERMAL SHOCK 01/21/82C C /

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FACILITY IMPLEMENTATION 03/31/.

MAINE YANKEE (CONTINUATION) 1 i

LIC ACT LICENSEE jTAC NO. MPA 8 TITLE COMPLETE STATUS pflg Mt6042 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 07/26/82C O I M46614 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C Nb jM49739 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 07/14/83C b lM49613 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 12/02/83C O I/b iM51756 B-74 THERMAL SHIELD FOLLOW UP ANALYSIS 05/01/84C b jM52770 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 04/24/85C O N M52851 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 11/30/86 O 5[b jM52932 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST .*ROCEDU 05/30/86 O M33013 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 10/01/85C b /b lM33077 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 03/30/86 b  !

M53130 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 07/30/85C O' iM54543 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 01/29/85C b' M53G03 B-85 SALEM ATHS 1.2 DATA CAPABILITY 08/30/86 O  !

M53686 B-86 SALEM ATHS 2.2, -R C ONENTS 02/01/87 9 , e c

!M53769 B-87 SAL EM ATHS 3.2.1 5-hP-S-R COMPONENTS 10/30/86 O kN iM53852 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/01/85C b  !

4 iM53917 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 10/30/86 0 /7I3 iM54079 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 03/30/86 C I jM53996 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 10/30/86 _ ,b ,k 1 M08240 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 02/27/81C C

/ T 'll M08908 C-04 FILTER TECH SPECS 11/30/78C C, J f17[

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C-1208731-001 REGULAT0RY INF0RMAT ION TRACKING SYSTEM PACE NO.: 25 FACILITY IMPLEMENTATION 03/31/8 tiAINE YANKEE (CONTIflUATION)

LIC ACT LICENSEE TAC NO. MPA 8 TITLE COMPLETE STATUS p_Alg A

M43328 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 12/30/83C C NY N08059 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 01/01/70C b N M43653 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 05/14/85C b M52241 C-15 CONTROL OF HEAVY LDADS - PHASE II (FDLLOHUP OF MPA 06/28/85C b W, H58067 C-16 UTILITY RESPO!!SES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C b

'M11102 D-04 PHR REACTOR VESSEL CAVITY SEAL RING MISSILE POTENT 05/08/80C O

'M08899 D-06 PEAKING MODEL CHAtlGE FOR CE REACTOR CORE 08/18/78C C IN-M08898 D-10 ASYMMETRIC LOCA LOADS 04/30/86 C /

M10099 D-11 FISSION GAS RELEASE 02/22/80C C I

'M12317 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C C IIH M43028 D-17 DEFINITI0!1 0F OPERABLE 01/21/81C (' /Y M55873 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 03/15/87 0 '

M11193 E-01 SPENT FUEL POOL EXPANSI0tlS 06/22/79C b Y M11283 E-03 CORE RELOADS REQUIRIflG PRIOR NRC APPROVAL 03/07/80C C N08900 E-06 CEA POSITION INDICATION FAILURES - CE 04/29/82C f M08902 E-07 REACTOR PRCTECTION SYSTEtt LOGIC - CE 03/31/82C C tt44031 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/12/82C C / 'l M44100 F-02 I.A.1.3 SHIFT MANNING 06/29/83C C Y M44172 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 11/18/82C C I' I}

'M44243 F-04 I.C.1.2/3.A EMERGEllCY OPERATING PROCEDURES GEllERIC 06/11/84C C 7[fh M44313 F-05 I.C.I.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 09/30/86 C, 3 /h6 M47225 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/18/82C C /771 h47298 F-07 I.C.6 CORRECT PERFORMAtlCE OF OPERATING ACTIVITI 01/18/82C C /

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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.: 25' FACILITY IMPLEMENTATION 03/31/8s MAINE YANKEE (CONTINUATION)

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M51173 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 10/10/84C b O[2I .

M51253 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 08/30/86 O b M44382 F-10 II.B.1 RCS HIGH POINT VENTS 09/08/83C C hI lib M47949 F-11 II.B.2 PLANT SHIELDING 08/15/83C C M44451 F-12 II.B.3 POST ACCIDENT SAMPLING 08/08/85C O M44522 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/18/82C O M44592 F-14 I I . D.1 RV AND SV TRAINING 07/30/86 C b/IT F-15 II.E.1.1 AFH SYSTEM EVALUATION /#b 7 #

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M43092 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 09/03/82C l- 0[2I M44745 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 09/03/82C b h/7I M44790 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 04/29/80C b M44861 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 10/14/82C C /I[3 M44932 F-20 II.F.1.1 NOBLE GAS MONITOR 01/27/82C C /TN)

M45003 F-21 II.F.1.2 IODINE /PARTICUL ATE SAMPLING 01/27/82C C /ff[

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M45074 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/22/82C C / 7D M47610 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 06/17/83C C /YE1 M47681 F-24 I I .'F.1. 5 CONTAINMENT HATER LEVEL INSTRUMENT 06/17/83C C /773 M4F752 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 06/16/83C (, /ff1 M45145 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 05/30/86 C /2[74 "M46891 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/06/84C C, $[7T M47805 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 10/11/83C 0 /f237 M45263 F-36 II.K.3.1 AUTO PORV ISOLATION 10/04/83C (, /973 M45309 F-37 II.K.3.2 REPORT ON PORY FAILURES 10/04/83C 4 /f[3

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FACILITY IMPLEMENTATION 03/31/8' MAINE YANKEE (CONTINUATION)

LIC ACT LICENSEE TAC NO. MPA 9 TITLE COMPLETE STATUS RAT.E M45354 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 09/15/82C 0 I90 M45430 F-39 II.K.3.5 AUTO TRIP OF RCPS 03/07/83C C 5[f6 M45640 F-47 II.K.3.17 ECCS OUTAGES 08/10/83C C /f[3 M48446 F-53 II.K.3.25 P0HER ON PUMP SEALS 12/22/82C C /7[A M45837 F-57 II.K.3.30 SB LOCA METHODS 10/30/86 C /ffI M48176 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 08/30/86 [/*C eck /Jf d f r c/c/

M45956 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 11/30/86 0 Yff, M46077 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 11/30/86 0 0/FY M46099 F-65 III.A 1.2 EMERGENCY OPERATIONS FACILITY 11/30/86 C 7[f6 M46171 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C 8/\

M46243 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/20/83C C /Y M46315 F-68 III.A.2.2 METEOROLCGICAL DATA UPGRADE 11/30/86 6 7((h M46386 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/23/82C C /9[/

M46455 F-70 III.D.3.4 CONTROL R00M HABITABILITY 03/01/83C C /9M M56135 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FDLLOHUP TO 08/30/86 fre ede /9[7 cheh/

M49675 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 05/30/86 C /9 7h O

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