ML20155G956

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

ML20155G956
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/01/1986
From:	Hood D Office of Nuclear Reactor Regulation
To:	Tucker H DUKE POWER CO.
References
NUDOCS 8605090427
Download: ML20155G956 (15)

Text

f Docket Nos.: 50-369 and 50-370 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242

Subject:

Implementation of Generic Requirements - McGuire Nuclear Station 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 document- l ation on the status of power reactor licensees' implementation of approved >

regulatory improvements.

To assist me in developing this information for McGuire Nuclear Station, please review the enclosed plant-specific list, add omitted significant actions to the i list, and provide the date that all aspects of each identified requirement were u 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 pre- ,

cise dates. Rather, I will accept readily-known or best-estimate dates for '

actions that have been completely implemented. For exampic, 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 l 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, i 8050{0 8f0h o p Darl Hood, Project Manager PDR PWR Project Directorate #4 P Division of PWR Licensing-A

Enclosure:

As stated '

cc: See next page

_ DISTRIBUTION:

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4, ,o 01 MAY 19c. 0 .

Docket Nos.: 50-369

• and 50-370 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 1

Subject:

Implementation of Generic Requirements - McGuire Nuclear Station 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 document-ation on the status of power reactor licensees' implementation of approved regulatory improvements.

To assist me in developing this information for McGuire Nuclear Station, 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 " 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 pre-cise 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, 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,

$ U N-Darl Hood, Project Manager PWR Project Dirc:torate #4 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page

{ _o

i t i l Mr. H. B. Tucker  !

, Duke Power Compar.y Catawba Nuclear Station -

f cc: i

[

William L. Porter, Esq. North Carolina Electric Membership  :

i Duke Power Company Corp.  !

P.O. Box 33189 3333 North Boulevard i

Charlotte, North Carolina 28242 P.O. Box 27306 .

Raleigh, North Carolina 27611 l l J. Michael McGarry, .III, Esq.

I

Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative,

. and Reynolds Inc. >

i' 1200 Seventeenth Street, N.W. P.O. Box 929 4 Washington, D. C. 20036 Laurens, South Carolina 29360 ,

.~

North Carc, lina MPA-1 Senior Resident Inspector  !

4 Suite 600 Route 2, Box 179N l

! 3100 Smoketree Ct. York, South Carolina 29745 i P.O. Box 29513 l Raleigh, North Carolina 27626-0513 Regional Administrator, Region II .i U.S. Nuclear Regulatory Comission, i

! Mr. C. D. Markham 101 Marietta Street, NW, Suite 2900 l Power Systems Division Atlanta, Georgia 30323 Westinghouse Electric Corp.

l P.O. Box 355  !

Pittsburgh, Pennsylvania 15230 Robert Guild, Esq.  !

2759 Rosewood Drive  ;

e NUS Corporation Columbia, South Carolina 29205 i j 2536 Countryside Boulevard ,

l 4

Clearwater, Florida 33515 Palmetto Alliance t 2759 Rosewood Drive i l Mr. Jesse L. Riley, President Columbia, South Carolina 29205 i Carolina Environmental Study Group 'j'

854 Henley Place Karen E. Long

Charlotte, North Carolina 28208 Assistant Attorney General N.C. Department of Justice  !

Richard P. Wilson, Esq. P.O. Box 629 i' i Assistant Attorney General Raleigh, North Carolina 27602

! S.C. Attorney General's Office l P.O. Box 11549 Spence Perry, Esquire l i

Columbia, South Carolina 29211 Associate General Counsel i Federal Emergency-Management Agency Piedmont Municipal Power Agency Room 840 l

' )

100 Memorial Drive 500 C Street j Greer, South Carolina 29651 Washington, D. C. 20472 l Mark S. Calvert, Esq. Mr. Michael Hirsch Bishop, Liberman, Cook, Federal Emergency Management Agency  :

j Purcell & Reynolds Office of the General Counsel i 1200 17th Street, N.W.. Room 840

Washington, D. C. 20036 500 C Street, S.W.  !

! Washington, D. C. 20472 l j Brian P. Cassidy, Regional Counsel l l Federal Emergency Management Agency, j j Region I i J. W. McCormach P0CH i Boston, Massachusetts 02109  !

i  !

il R-1208751-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 20 FACILITY IMPLEMENTATION 04/28/O FACILITY: MCGUIRE 1 PLANT LOCATION: 17 MI N OF CHARLOTTE, NC LICENSED POWER: 3411 MNT PROJECT MANAGER: D. HOOD DOCKET NUMBER: 050-00369 DESIGN P0HER: 1150 MHE BRANCH CHIEF: B. YOUNGBLOOD ARCH / ENGINEER: DUKE NSSS VENDOR: HEST LIC. ASSISTANT: M. DUNCAN IE INSPECTOR: H. ORDERS LIC ACT LICENSEE TAC NO. MPA 8 TITLE COMPLEIE STATUS RAIE M51104 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 06/16/86 M55720 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-45) 03/14/86C

'M59111 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S /

M59962 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31/87 M12165 B-16 EMERGENCY PLANNING AND REVISIONS 07/08/81C M42538 B-60 ENVIRONMENTAL QUALIFICATION 03/01/33C

,M43051 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACK 0UT 04/01/81C M51644 B-66 NATURAL CIRCULATION C00LDOWN 09/30/83C M46843 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 11/17/81C M49740 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 03/29/83C M52771 B-76 ITEM 1.1 - POST TRIP REVIENs PROGRAM DESCRIPTION & 05/30/85C M52852 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 10/30/86 M52933 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 10/31/85C

,M53014 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 10/31/85C M53078 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 10/31/85C 4

M53131 B-81 ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT PROG FOR R 06/30/86 "M53179 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/00/85C s' M54544 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 08/03/84C

,M53604 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/21/85C M53687 B-86 SALEM ATHS 2.2 S-R COMPONENTS 10/30/86 I:

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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 26

{ FACILITY IMPLEMENTATION 04/28/8 MCGUIRE 1 (CONTINUATION)

LIC ACT LICENSEE I TAC NO. MPA 9 TITLE COMPLETE STATUS DAIE M53770 B-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 10/31/85C

'M53853 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/31/85C

~M53918 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86

'M55361 B-90 SALEM ATHS 4.3 H AND B&W T.S. 06/30/86 M54080 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 10/31/85C M53997 B-93 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES 04/31/87 -

s M47127 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 03/12/85C M47125 C-14 AUXILIARY FEEDH4TER SEISMIC QUALIFICATION 11/23/81C M52242 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLONUP OF MPA 03/12/85C M58068 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C

_M55874 D-19 DIESEL GENERATOR. RELIABILITY TECH SPECS (GL 84-15) 12/02/85C M44032 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 06/12/81C

'M44102 F-02 I.A.1.3 SHIFT MANNING 02/28/83C i

M44173 F-03 1.A.2.1 UPGRADING OF RO AND SRO TRAINING 01/23/81C iM44244 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 01/23/81C

• M44314 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 01/23/81C M59277 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 02/28/87 M47227 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/15/81C M47299 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 04/15/81C F-08 I.D.1.1. DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 08/02/83C s' fM51174 M51254 F-09 I.D.2 SAFETY PAR'4 METER DISPLAY SYSTEM 06/31/86 iM44383 F-10 II.B.1 RCS.HIGH POINT VENTS 01/23/81C M47950 F-11 II.B.2 PLANT SHIELDING. 01/01/81 C s

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R-1208731-001 REOULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO.* 23 FACILITY IMPLEMENTATION 04/28/O MCGUIRE 1 (CONTINUATION)

LIC ACT LICENSEE TAC MO. MPA 6 TITLE COMPLETE STATUS DAIE M45481 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 04/15/81C M45511 F-42 II.K.3.12 ANTICIPATORY TRIP DN TURBINE TRIP 04/15/81C M45838 F-57 II.K.3.30 SB LOCA METNODS 02/28/83C

' M58041 F-57 II.K.3.30 SB LOCA METHODS 06/26/85C M48177 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 01/31/87 i M45957 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 02/28/83C M46028 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 02/28/83C M46100 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 02/28/83C M46172 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C M46244 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 02/28/83C

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M46316 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 04/30/86 M46387 F-69 III.D.3.3. IMPLANT RADIATION MONITORING 01/23/81C F-70 III.D.3.4 CONTROL ROOM HABITABILITY 01/23/81C fM46456 M56136 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 08/15/84C

~

' M49653 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5r 07/30/86 4

1

R-1208731-001 R E O U'l A T 0 R Y INF0RMATION TRACKINO SYSTEM PAGE NO. 22 FACILITY IMPLEMENTATION 04/23/C MCGUIRE 1 (CONTINUATION)

LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS RAIE M44452 F-12 II.B.3 POST ACCIDENT SAMPLING 01/01/82C M44523 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 08/15/81C M44593 F-14 II.D.1 RV AND SV TRAINING 05/15/86 M44642 F-15 II.E.1.1 AFH SYSTEM EVALUATION 04/15/81C M44684 F-16 II .E.1.2.1 AFH SYSTEM INITI ATION 01/23/81C M44721 F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION 01/23/81C M44791 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 01/01/82C M44862 F-19 II.E.4.2 CCHTAINMENT ISOLATION DEPENDABILITY 04/15/81C M44933 F-20 II . F.1.1 NOBLE GAS MONITOR 04 '15/81 C M45004 F-21 II . F .1. 2 IODINE / PARTICULATE SAMPLING 04/15/81C M45075 F-22 II.F.1.3 CONTAINMENT HIGN RANGE MONITOR 04/15/81C M47611 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 01/01/81C M47682 F-24 II.F.1.5 CONTAINMENT NATER LEVEL INSTRUMENT 01/01/82C M47753 F-25 II . F .1. 6 CONTAINMENT HYDROGEN MONITOR 01/01/81C M45146 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09/17/84C M55517 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 02/28/85C M46892 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 02/28/83C M47806 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 02/28/83C M45239 F-36 II.K.3.1 AUTO PORV ISOLATION 04/15/81C "M45285 F-37 II.K.3.2 REPORT ON PORV FAILURES 04/15/81C s' M45355 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 04/15/81C M45402 F-39 II.K.3.5 AUTO TRIP OF RCPS 04/15/81C M45451 F-40 II.K.3.9 PID CONTROLLER 01/23/81C I

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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 2^

FACILITY IMPLEMENTATION 04/28/

FACILITY: MCGUIRE 2 PLANT LOCATION: 17 MI N OF CHARLOTTE, NC LICENSED P0HER: 3411 MNT PROJECT MANAGER: D. HOOD DOCKET NUMBER: 050-00370 DESIGN POWER: 1180 MNE BRANCH CHIEF: B. YOUNGBLOOD ARCH / ENGINEER: DUKE NSSS VENDOR: HEST LIC. ASSISTANT: M. DUNCAN IE INSPECTOR: H. COTTLE LIC ACT LICENSEE TAC No. MPA 9 TITLE COMPLETE STATUS RAlg

. M51105 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 06/16/86 M55721 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 03/19/86C M59112 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S /

M57963 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/31/87

., M42539 B-60 ENVIRONMENTAL QUALIFICATION 05/31/83C 1

i M51645 B-66 NATURAL CIRCULATION COOLDOHN 09/30/83C l M48556 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/14/82C i M49118 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 11/24/82C

M52772 B-76 ITEM 1.1 - POST TRIP REVIEN; PROGRAM DESCRIPTION 8 05/30/85C

, M52853 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 10/30/86 lM52934 B-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 10/31/85C lM53015 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO ,

10/31/65C M53079 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 10/31/85C i M53132 B-81 ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT PROG FOR R 06/30/86

, M53180 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 06/00/85C M53,605 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/21/85C

{"M53588 B-86 SALEM ATHS 2.2 S-R COMPONENTS 10/30/86 **

M53771 B-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 10/31/85C

}M53854 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/31/85C

< M53919 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 i

- - _T- __ _- __-__m =-- e+- - w _ _ _ _ _ _- -_

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, R-1208731-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO.8 FACILITY IMPLEMENTATION 04/28/f i

MCGUIRE 2 (CONTINUATION) i LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS DAlf M55362 B-90 SALEM ATHS 4.3 H AND B&H T.S. 06/30/86 ,

M54081 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 10/31/85C M53998 B-95 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/31/87 M52243 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDLLDHUP OF MPA 03/12/85C M58069 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C

. M55875 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 12/02/85C

' "*5340 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 03/28/87 M51175 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 08/02/83C 1

M51255 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/31/86 M54601 F-14 II.D.1 RV AND SV TRAINING d5/15/86

-M55513 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 02/28/85C M53288 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 09/17/84C M54985 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/05/84C M58042 F-57 II.K.3.30 SB LOCA METHODS 06/26/85C M58142 F-57 II.K.3.30 SB LOCA METHODS 06/26/85C M57576 F-58 II.K.3.31 COMPLIANCE HITN 10 CFR 50.46 01/31/87

-M59566 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 05/27/86 M59567 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 05/27/86

_ M59568 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 05/27/86 "M53287 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 01/30/86 s' M56137 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEN (FDLLONUP TO 08/15/84C M53290 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 07/30/86 l

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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 2' FACILITY IMPLEMENTATION 04/14/

FACILITY: MCGUIRE 1 PLANT LOCATION: 17 MI N OF CHARLOTTE, NC LICENSED POWER: 3411 MNT PROJECT MANAGER: D. HOOD DOCKET NUMdER: 050-00369 DESIGN POWER: 1150 MNE BRANCH CHIEF: B. YOUNGBLOOD ARCN/ ENGINEER: DUKE NSSS VENDOR: HEST LIC, ASSISTANT: M. DUNCAN IE INSP(CTOR: H. ORDERS TAC NO. MPA t _ _ , ,

TITLE M49653 G-01 MCGUIRE 1 - REACTOR COOLANT PUMP TRIP M44032 F-01 MCGUIRE - NUREG-0737 I.A.1.1 STA LONG TERM REQUIREMENTS M44102 F-02 MCGUIRE - NUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS M44173 F-03 MCGUIRE - NUREG-0737 I.A.2.1.4, UPGRADING OF RO AND SRO TRAINING M44244 F-04 MCGUIRE - NUREG-0737 I.C.1.2.A, INADEQUATE CORE COOLING GUIDELINES M44314 F-05 MCGUIRE - NUREG-0737 I.C.1.3A, ABNORMAL TRANSIENT OPERATOR GUIDELINES M59277 F-05 -MCGUIRE 1 - PROCEDURES GENERATION PACKAGE REVIEN (NUREG 0737 SUPPL.1)

M47227 F-06 MCGUIRE - FEEDBACK OF OPERATING EXPERIENCE (AP I.C.5)

M47299 F-07 MCGUIRE - CORRECT PERFORMANCE OF OPERATING ACTIVITIES (API.C.5)

M51174 F-08 MCGUIRE 1 - I.D.1.1 - DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN F-08 M51254 F-09 MCGUIRE 1 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM M47127 C-10 HEAVY LOADS POWER PLANTS (NUREG 0612)

M44383 F-10 MCGUIRE - NUREG-0737 II.B.1, RCS NIGH POIHT VENTS M47950 F-11 MCGUIRE - PLANT SHIELDING MODIFICATIONS (II.B.2.2)

M44452 F-12 MCGUIRE - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS M44523 F-13 MCGUIRE - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE "M44593 F-14 MCGUIRE 1 - RV AND SV TESTING **

M47125 C-14 MCGUIRE UNIT 1 - SEISMIC QUAL. OF THE AFH SYSTEM M44642 F-15 MCGUIRE - NUREG-0737 II.E.1.1, AFH SYSTEM EVALUATION M52242 C-15 MCGUIRE 1 - CONTROL OF HEAVY LOADS - PHASE II (FDLLOHUP OF MPASC-10)

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R-1208731-001 REGULATORY INF0RMATION TRACKING SYSTEM PAGE NO. 24 FACILITY IMPLEMENTATION 04/14/

MCGUIRE 1 (CONTINUATION)

TAC NO. MPA 9 TITLE M58068 C-16 MCGUIRE 1 - UTILITY RESPONSES TO STAFF RECOMMENDATIONS M12165 B-16 MCGUIRE 1, EMERGENCY PLAN REVIEW M44684 F-16 MCGUIRE - NUREG-0737 II.E.1.2.1, AFM SAFETY GRADE AUTO INITIATION M44721 F-17 MCGUIRE - NUREG-0737 II.E.1.2.2, AFH SAFETY GRADE FLOW INDICATION M51104 A-17 MCGUIRE 1 - INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT (RG 1.97)

M55720 A-18 MCGUIRE 1 - TECH. SPECS, AFFECTED BY 50.72 AND 50.73 (GL 83-43)

M44791 F-18 MCGUIRE - NUREG-0737 II.E.4.1.2 M44862 F-19 MCGUIRE - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY M55874 D-19 MCGUIRE 1 - DIESEL GENERATOR RELIABILITY TECH. SPECS. (GL 84-15)

M59111 A-20 MCGUIRE 1 - 10CFR50.62 OPERATING REACTOR REVIENS - ATHS RULE M44933 F-20 MCGUIRE - NUREG-0737 II.F.1.1, NOBLE GAS MONITOR M45004 F-21 MCGUIRE - NUREG-0737 II.F.1.2, IDDINE/ PARTICULATE SAMPLING M59962 A-21 MCGUIRE 1 - 10CFR50.61 PRESSURIZED THERMAL SH0CK RULE REQUIREMENTS, PHASE 1 M45075 F-22 MCGUIRE - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR M47611 F-23 MCGUIRE - NUREG 0737 ITEM II F1.4 CONTAINMENT PRESSURE INSTRUMENT M47682 F-24 MCGUIRE - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR M47753 F-25 MCGUIRE - NUREG 0737 ITEM II F1.6 CONTAINMENT HYDROGEN MONITOR M45146 F-26 MCGUIRE - NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION M55517 F-26 MCGUIRE UNIT 1 - EVALUATE ICCI TECH. SPEC. REVISIONS; REF: DUKE LTR. 7/31/84 (SNM & RVLIS; GL 83-37)

"M46892 F-30 MCGUIRE 1 - II K2.13 THERMAL MECHANICAL REPORT s' M47806 F-33 MCGUIRE - NUREG 0737 ITEM II K2.17 POTENTIAL FOR VOIDING IN RCS M45239 F-36 MCGUIRE - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION M45285 F-37 MCGUIRE - NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES

$a R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 26 FACILITY IMPLEMENTATION 04/14/8 MCGUIRE 1 (CONTINUATION)

TAC NO. MPA 9 TITLE M45355 F-38 MCGUIRE - HUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES M45402 F-39 MCGUIRE - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS M45451 F-40 MCGUIRE - NUREG-0737 II.K.3.9, PID CONTROLLER M45081 F-41 MCGUIRE - NUREG-0737 II.K.3.10, ANTICIPATORY TRIP MODIFICATIONS M45511 F-42 MCGUIRE - NUREG-0737 II.K.3.12, ANTICIPATORY TRIP DN TURBINE TRIP M45838 F-57 MCGUIRE - NUREG-0737 II.K.3.30, SB LOCA OUTLINE M58041 F-57 MCGUIRE 1 - HUREG 0737, II.K.3.30, SB LOCA METHODS M48177 F-58 MCGUIURE 1 -NUREG 0737 II.K.3.31 COMPLIANCE HITN 10 CFR 50.46 M42538 B-60 MCGUIRE 1 - ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21)

M43951 B-63 MCGUIRE 1 - STATION BLACKDUT PROCEDURES & TRAINING M45957 F-63 MCGUIRE - NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER M46028 F-64 MCGUIRE - NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER M46100 F-65 MCGUIRE - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY M51644 B-66 MCGUIRE 1 - NATURAL CIRCULATION C00LDOWN M46172 F-66 MCGUIRE 1 - III. A.2 NUCLEAR DATA LINK DATA M46244 F-67 MCGUIRE 1 - III . A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE MEET RULE M46316 F-68 MCGUIRE - NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE M46843 B-69 MCGUIRE 1 - PHR MSLB HITH CONTINUED FEEDHATER ADDITION M46387 F-69 MCGUIRE - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING M46056 F-70 MCGUIRE - NUREG-0737 III.D.3.4, CONTROL ROOM HABITABILITY **

M56136 F-71 MCGUIRE 1 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT - F-71 M49740 B-72 MCGUIRE 1 "NUREG 0737 TECH SPECS (GENERIC LETTER 82-16 82-16 OR 83-02)"

M52771 B-76 MCGUIRE 1 - ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND PROCEDURES S

O

08 i ,

. l R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.,8 26 FACILITY IMPLEMENTATION 04/14/O W UIRE 1 (CONTINUATION)

'AC NO. MPA 8 TITLE M52852 B-77 MCGUIRE 1 - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS M52933 B-78 MCGUIRE 1 - ITEMS 3.1.1 8 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONENTS M53014 B-79 MCGUIRE 1-ITEM 3.1.3 -POST-MAINTENAhCE TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS M53078 B-80 MCGUIRE 1 - ITEM 4.1 REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODIFICATIONS M53131 B-81 MCGUIRE 1 - ITEMS 4.2.1 8 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TRED M53179 B-82 MCGUIRE 1 - ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR H AND B & H PLANTS M54544 B-83 MCGUIRE 1 - TECHNICAL SPECIFICATIONS COVERED BY GENERIC LETTERS 83-36, 83-37 FOR NUREG-0737 M53604 B-85 MCGUIRE 1 - ITEM 1.2 - POST TRIP REVIEH-DATA AND INFORMATION CAPABILITY M53647 B-86 MCGUIRE 1 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMPONENTS C557? 0 B-87 MCGUIRE 1- ITEMS 3.2.1 8 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECOMMENDATIONS - ALL SR COMPON2 M53853 B-88 MCGUIRE 1 - ITEM 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH. SPEC. - ALL SR COMPONENTS M53918 B-89 MCGUIRE 1 - ITEMS 4.2.3 8 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS LIFE TESTING AND REPLACEM M55361 B-90 MCGUIRE 1 - ITEM 4.3 CTS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B8H PLANTS - TECH SPECS ,

M54080 B-92 MCGUIRE 1 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES M53997 B-93 MCGUIRE 1 - ITEMS 4.5.2 8 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTERNATIVES 8 TEST INTERVALS b ,e e - -. . - _ . - _ - . . . - _ _ _ _ _ . .. . . . . _ . - -. - --

R-1208731 -001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 26 FACILITY IMPLEMENTATION 04/14/O.

FACILITY: MCGUIRE 2 PLANT LOCATION: 17 MI N OF CHARLOTTE, NC LICENSED PDHER: 3411 MHT PROJECT MANAGER: D. HOOD DOCKET NUMBER: 050-00370 DESIGN POWER: 1180 Mile BRANCH CHIEF: B. YOUNGBLOOD ARCH / ENGINEER: DUKE NSSS VENDOR: HEST LIC. ASSISTANT: M. DUNCAN IE INSPECTOR: H. COTTLE TAC NO. MPA t TITLE M53290 G-01 MCGUIRE UNIT 02 - REACTOR COOLANT PUMP TRIP (REF: TACS 49653)

M55340 F-05 MCGUIRE 2 - PROCEDURES GENERATION PACKAGE REVIEW (NUREG 0737 SUPP/1)

M51175 F-08 MCGUIRE 2 - I.D.1.1 - DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN F-08 M51255 F-09 MCGUIRE 2 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM M54601 F-14 MCGUIRE 2 - II.D.1 - RV & SV TESTING M52243 C-15 MCGUIRE 2 - CONTROL OF HEAVY LOADS - PHASE II (FDLLONUP OF MPASC-10)

M58039 C-16 MCGUIRE 2 - UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERNING STEAM GENERATOR 3 (GL 85-02)

M51105 A-17 MCGUIRE 2 - INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT (RG 1.97)

M55721 A-18 MCGUIRE 2 - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-43)

M55875 D-19 MCGUIRE 2 - DIESEL GENERATOR RELIABILITY TECH. SPECS. (GL 84-15)

M59112 A-20 MCGUIRE 2 - 10CFR50.62 OPERATING REACTOR REVIENS - ATHS RULE M59963 A-21 MCGUIRE 2 - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1 M55518 F-26 MCGUIRE UNIT 2 - EVALUATE ICCI TECH. SPEC. REVISIONS; REF: DUKE LTR 7/31/84 M53288 F-26 MCGUIRE UNIT 82 - NUREG-0737, II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION (REF: TACS 45146)

M54985 F-30 MCGUIRE 2, II.K.2.13, THFRMAL MECHANICAL REPORT M58142 F-57 MCGUIRE 2 - NUREG 0737, II.K.3.30, SB LOCA METHODS "M58042 F-57 MCGUIRE 2 - NUREG 0737, II.K.3.30, SB LOCA METHODS **

1157576 F-58 MCGUIRE 2 - NUREG 0737, II.K.3.31, COMPLIANCE WITH to CFR 50.46 M42539 B-60 MCGUIRE 2 - ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21)

M59566 F-63 MCGUIRE 2 - NUREG-0737 III.A.1.2 TECHNICAL SUPPORT CENTER S

c------------------- -_ __ _

R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.: 8 FACILITY IMPLEMENTATION 04/14/l MCGUIRE 2 (CONTINUATION)

TAC NO. MPA 9 TITLE P39567 F-64 MCGUIRE 2 - NUREG-0737 III.A.1.2 OPERATIONAL SUPT CENTER .

M59568 F-65 MCGUIRE 2 - HUREG-0737 III.A.1.2 EMERGENCY OPERATIONS FACILITY M51645 B-66 MCGUIRE 2 - NATURAL CIRCULATION C00LDOWN M53287 F-68 MCGUIRE UNIT 82 - NUREG-0737, III.A.2.2, METEOROLOGICAL DATA UPGRADE (REF: TACS 46316)

M48556 B-69 MCGUIRE UNIT 82: PHR MSLB HITN CONTD FEEDWATER ADDITION M49118 B-69 MCGUIRE UNIT #2: IEB-80-4 MSLB HITH CONTINUED FEEDWATER ADDITION M56137 F-71 MCGUIRE 2 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT - F-71 M52772 B-76 MCGUIRE 2 - ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND PROCEDURES M52853 B-77 MCGUIRE 2 - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS M52934 B-78 MCGUIRE 2 - ITEMS 3.1.1 8 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONENTS M53015 B-79 MCGUIRE 2-ITEM 3.1.3 -POST-MAINTENANCE TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS M53079 B-80 MCGUIRE 2 - ITEM 4.1 REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODIFICATIONS M53132 B-81 MCGUIRE 2 - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TRE[

M53180 B-82 MCGUIRE 2 - ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR H AND B & H PLANTS M53605 B-85 MCGUIRE 2 - ITEM 1.2 - POST TRIP REVIEW-DATA AND INFORMATION CAPABILITY-l M53688 B-86 MCGUIRE 2 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMPONENTS j M53771 B-87 MCGUIRE 2- ITEMS 3.2.1 8 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECOMMENDATIONS - ALL SR COMPON M53854 B-88 MCGUIRE 2 - ITEM 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH. SPEC. - ALL SR COMPONENTS M53919 B-89 MCGUIRE 2 - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS LIFE TESTING AND REPLACT "M55362 B-90 MCGUIRE 2 - ITEM 4.3(TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B8H PLANTS - TECH $EECS M54081 B-92 MCGUIRE 2 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES M53998 B-93 MCGUIRE 2 - ITEMS 4.5.2 8 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTERNATIVES 8 TEST INTERVALS

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