ML20203Q031

Requests Review of Encl plant-specific List,Adding Omitted Significant Actions & Providing Dates All Aspects of Requirements Completed/Implemented or Expected to Be Completed,By 860531

ML20203Q031
Person / Time
Site:	Maine Yankee
Issue date:	04/28/1986
From:	Sears P Office of Nuclear Reactor Regulation
To:	Randazza J Maine Yankee
References
NUDOCS 8605080546
Download: ML20203Q031 (9)

Text

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April 28, 1986 mem c) 8 Docket No. 50-309 Distribution: #Decitet4i1% NRC & L PDRs PKreutzer PSears PWR #8 Files OELD ACRS 10 EJordan --

JPartlow BGrimes FMiraglia Mr. J. B. Randazza AThadani Executive Vice President Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336

Dear Mr. Randazza:

The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." 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 the Maine Yankee Atomic Power Station, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the dates that all aspects of each identified requirements were completed / implemented or are expected to be completed. For each requirement that has been completed, enter " completed" 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 " projected" 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 /implementa-tions 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, 1986.

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.

Sincerely, l

/S/ I Patrick M. Sears, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B

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Enclosures:

As stated cc w/ enclosures:

See next page PWR# b D PWR#8 PSears;eh AThagani J/si/86 L g/86 N

8605090546 860428 PDR ADOCK 05000309~

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0 4-Mr. J. B. Randazza o Maine Yankee Atomic Power Company Maine Yankee Atomic Power Station cc:

Charles E. Monty, President Mr. P. L. Anderson, Project Manager Maine Yankee Atomic Power Company Yankee Atomic Electric Company 83 Edison Drive 1671 Worchester Road Augusta, Maine 04336 Framingham, Massachusetts 07101 Mr. Charles B. Brinkman Mr. G. D. Whittier Manager - Washington Nuclear Licensing Section Head Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc. 83 Edison Drive 7910 Woodmont Avenue Augusta, Maine 04336 Bethesda, Maryland 20814 John A. Ritsher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Mr. John H. Garrity, Plant Manager Maine Yankee Atomic Power Company P. O. Box 408

• Wiscasset, Maine 04578 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset Municipal Building U.S. Route 1 Wiscasset, Maine 04578 Mr. Cornelius F. Holden Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box E ,

Wiscasset, Maine 04578 l \

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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM 253 PAGE.NO.

FACILITY I M P L E M E N 1 A T I 0' N 03/31/86 FACILITY: MAINE YANKEE PLANT LOCATION: 10 MI N OF BATH, ME LICENSED POWER: 2630 MHT PROJECT MANAGER: P. SEARS DICKET NUMBER: 050-00309 DESIGN POWER: 0825 MHE BRANCH CHIEF: A. THADANI ARCH / ENGINEER: S&W NSSS VENDOR: COMB LIC. ASSISTANT: P. KREUTZER IE INSPECTOR: C. HOLDEN LIC ACT LICENSEE T4C NO. MPA 9 TITLE COMPLETE STATUS DAIE N08323 A-01 to CFR 50.55 A(G) - ISI 05/08/83C

. M07752 A-02 APPENDIX I - ALARA 04/28/85C M06323 A-02 APPENDIX I - ALARA 01/01/70C ,

M07016 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 02/23/79C M08897 A-04 APPENDIX J - CONTAINMENT LEAK TESTING 05/01/83C M11380 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 05/19/80C M10730 A-10 CONTINGENU? Pi4NNING 09/15/82C M10734 A-11 GUARD TRAlla;# t+ TAW 5 09/15/82C-M10732 A-12 VITAL AREA **J YMG 04/14/82C M10858 A-14 10CFR 50.35 A(0) - INSERVICE TESTING 02/ 24/83C M12562 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/11/80C MST103 A-17 INSTRUNENTATION TO FOLLON THE COURSE OF AN ACCIDEN 11/30/86 M55296 A-13. TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/26/84C M59110 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 12/31/86 M59961 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31/86 M06537 B-02 FIRE PROTECTION 04/24/78C M08386 B-03 PHR MODERATOR DILUTION 07/10/81C M06741 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 02/27/81C M07191 B-07 STEAM GENERATOR FEEDHATER FLON INSTABILITY 03/12/80C M08168 B-08 PHR HPSI-LPSI FLON RCSISTANCE 09/27/79C

1-1308731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 254 l FACILITY IMPLEMENTATI0'N 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE

~AC NO. MPA 0 TITLE COMPLETE STATUS Ralg 107845 B-09 CHARGING SYSTEMS PIPE VIBRATIGHS 12/07/79C 106580 B-11 FLOOD OF EQUIPMENT IMPORTANT TO SAFETY 10/19/81C 107517 B-14 CEA GUIDE TUBE HEAR 09/21/81C 112140 5-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C 108904 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 04/30/86

! 110313 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C I I 110375 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIA 02/28/82C 1

i 108905 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/06/81C -

j 110032 B-23 DEGRADED GRID VOLTAGE 03/27/84C 142587 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 07/19/83C 110215 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL PDH 10/22/80C

. 110350 3-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 09/14/79C 108901 B-36 RESISTANCE TEMPERATURE DETECTOR (RTD) RESPONSE - C 07/24/81C i 198907 B-37 STEAM GENERATOR TUBE DENTING AND SUPPORT PLATE MOD 08/07/78C 4

108695 B-39 PNR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C l 149134 3-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 02/03/83C l 111074 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 10/24/79C

-! 111792 B-43 PWR FEEDNATER LINE CRACKS 07/31/80C 143141 B-43 PNR FEEDHATER LINE CRACKS 05/25/82C l 130561 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C

- 130562 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130563 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C

! 130564 3-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C I

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t-1208731-001 REOULAT0RY INF0RMATION TRACKING SYSTEM PAGE No.: 255 rACILITY IMPLEMENTATION 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS MIf, 130565 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130566 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130567 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130568 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/8SC 130569 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 4 112364 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130556 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130557 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130558 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 130559 B-44 LESSONS LEARNED IMPLEMENTA(ION 04/29/80C 130560 B-44 LESSONS LEARNED IMPLEMENTATION 04/29/80C 112876 8-45 NASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/23/81C 112614 B-46 ANALYSIS OF TURBINE DISC CRACKS 09/04/81C 112727 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/10/80C 112744 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 03/26/81C 142111 B-57 DHR CAPABILITY 03/05/81C 142893 B-59 MASONRY HALL DESIGN 12/15/85C 142490 B-60 ENVIRONMENTAL QUALIFICATION 12/13/84C 142683 3-61 LOSS OF NON CLASS IE ISC PDHER 07/28/82C M42754 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 04/05/82C M47174 B-66 NATURAL CIRCULATION C00LDONH OS/31/83C M47545 B-67 THERMAL SHOCK 02/03/83C M47029 B-67 THERMAL SH0CK 01/21/82C

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1-1208731-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 256 FACILITY IMPLEMENTATI0'N 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE IAC NO. MPA 9 TITLE COMPLETE STATUS RAlf.

146842 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDM 07/26/82C 14G614 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C 149739 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 07/14/83C 140313 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 12/02/83C 151756 B-74 THERMAL SHIELD FOLLON UP ANALYSIS 05/01/84C M52770 B-76 ITEM 1.1 - POST TRIP REVIENs PROGRAM DESCRIPTION & 04/24/85C M52851 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 11/30/86 M52932 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 05/30/86 M53013 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 10/01/85C M53077 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 03/30/86 M53130 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 07/30/85C M54503 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 01/29/85C M53603 B-85 SALEM ATHS 1.2 DATA CAPABILITY 08/30/86 M53086 B-86 SALEM ATHS 2.2 S-R COMPONENTS 02/01/87 M53769 B-87 SALEM ATHS 3.2.1 4 3.2.2 S-R COMPONENTS 10/30/86 MS3852 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/01/85C M53917 B-89 SALEM ATHS 4.2.3 a 4.2.4 LIFE COMPONENTS 10/30/86 M54079 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 03/30/86 4

M53996 B-95 SALEM ATHS 4.5.2 4 4.5.3 TEST ALTERNATIVES 10/30/86 M08240 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 02/27/81C M08908 C-04 FILTER TECH SPECS 11/30/78C M08903 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C M08909 C-07 FUEL MANDLING ACCIDENT INSIDE CONTAINMENT 03/14/84C

1 t-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 257 FACILITY IMPLEMENTATI0'N 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE

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TAC NO. MPA 9 TITLE COMPLETE STATUS Dalf 143328 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 12/30/83C 108059 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 01/01/70C 143653 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 05/14/85C 152241 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDLLONUP OF MPA 06/28/85C 158067 U-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C 111102 D-04 PNR REACTOR VESSEL CAVITY SEAL RING MISSILE POTENT 05/08/80C 108899 D-06 PEAKING MODEL CHANGE FOR CE REACTOR CORE 08/18/78C 108898 D-10 ASYMMETRIC LDCA LOADS 04/30/86 110099 D-11 FISSION GAS RELEASE 02/22/80C 112317 D-15 HIGH ENERGY LINE BREAK 8 CONSEQUENTIAL SYSTEM FAIL 01/31/84C 143028 D-17 DEFINITION OF OPERABLE 01/21/81C 155873 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 03/15/87 l

111193 E-01 SPENT FUEL POOL EXPANSIONS 06/22/79C 111283 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 03/07/80C 108900 E-06 CEA POSITION INDICATION FAILURES - CE 04/29/82C

' 108902 E-07 REACTOR PROTECTION SYSTEM LOGIC - CE 03/31/82C 144031 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/12/82C 144100 F-02 I.A.I.3 SHIFT MANNING 06/29/83C 144172 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 11/18/82C 144243 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/11/84C 144313 F-05 I.C.1.2/3.3 PRDCEDURES GENERATION PACKAGES (NUREG 09/30/86 I 147226 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/18/82C M47298 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 01/18/82C 1

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t-1208731-001 REGULAT0RY INF0RMATION TRACKING SY$ TEM PAGE No.: 258 FACILITY I M P L E M E N T A T I 0'N 03/31/86 1AINE YANKEE (CONTINUATION)

LIC ACT LICENSEE rAC NO. MPA 0 TITLE COMPLETE STATUS RAIE 151173 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/10/84C 151253 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 08/30/86 144382 F-10 II.B.1 RCS HIGN POINT VENTS 09/08/83C 147049 F-11 II.B.2 PLANT SNIELDING 08/15/83C 144451 F-12 II.B.3 POST ACCIDENT SAMPLING 08/08/85C 14452? F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/18/82C 144592 F-14 II.D.1 R7 AND SV TRAINING 07/30/86 144664 F-15 II.E.1.1 AFM SYSTEM EVALUATION 06/04/84C 143092 F-16 II.E.1.2.1 AFM SYSTEM INITIATION 09/03/82C i

144745 F-17 II.E.1.2.2 AFM SYSTEM FLOW INDICATION 09/03/82C 140790 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 04/29/80C l 144861 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 10/14/82C 144932 F-20 II.F.1.1 NOBLE GAS MONITOR 01/27/82C 445003 F-21 II.F.1.2 10 DINE / PARTICULATE SAMPLING 01/27/82C i

145074 F-22 II.F.1.3 CONTAINMENT MIGN RANGE MONITOR 01/22/82C 1 147610 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 06/17/83C l 947681 F-24 II.F.1.5 CONTAINMENT NATER LEVEL INSTRUMENT 06/17/83C 447752 F-25 -II.F.1.6 CONTAINMENT HYDROGEN MONITOR 96/16/83C 145145 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEGUATE 05/30/86 l 146891 F-30 II.K.2.13 THERMAL-MECMANICAL REPORT 06/06/84C

~147805 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 10/11/83C 145203 F-36' II.K.3.1 AUTO PORY ISOLATION 10/04/83C 145309 F-37 II.K.3.2 REPORT ON PORY FAILURES 10/04/83C 1

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LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS JL41E M45354 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 09/15/82C M45430 F-39 II.K.3.5 AUTO TRIP OF RCPS 03/07/83C M45640 F-47 II.K.3.17 ECCS OUTAGES 08/10/83C

, M48446 F-53 II.K.3.25 POWER ON PUMP SEALS 12/22/82C M45837 F-57 II.K.3.30 SB LOCA METHODS 10/30/86 i

M48176 F-58 II.K.3.51 COMPLIANCE HITN 10 CFR 50.46 08/30/86

! M45956 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 11/30/86 M40027 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 11/30/86 M46099 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 11/30/86 M40171 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C l M46243 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/20/83C I M46315 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 11/30/86

! M46386 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/23/82C i

M46455 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/01/83C M56135 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEN (FOLLONUP TO 08/30/86 M49673 G-01 REACTOR COOLANT PUMP TRIP.(D660 - II.K.3.5) 05/30/86 d

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