ML20058K812

From kanterella
Jump to navigation Jump to search
Forwards Bibliography of IIT Documents Placed in PDR in Sept 1990 to Assist in Finding Info Re Site Incident on 900320
ML20058K812
Person / Time
Site: Vogtle  
Issue date: 12/03/1993
From: Barth C
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
To: Kohn M, Lamberski J
KOHN, KOHN & COLAPINTO, P.C. (FORMERLY KOHN & ASSOCIA, TROUTMANSANDERS (FORMERLY TROUTMAN, SANDERS, LOCKERMA
Shared Package
ML20058K783 List:
References
93-671-01-OLA-3, 93-671-1-OLA-3, LBP-93-22, OLA-3, NUDOCS 9312160033
Download: ML20058K812 (42)
v • d • e


Text

s s

^

p ricv e

UNITED STATES 1

E Il j NUCLEAR REGULATORY COMMISSION-WASHINGTON, D.C. 20556-0001

6. '

g DEC 0 31993 53 P ~5 i' : T 3 John Lamberski, Esq.

Troutman Sanders NationsBank Building Suite 5200 600 Peachtree Street, N.E.

Atlanta, Georgia 30308 Michael D. Kohn, Esq.

Kohn, Kohn and Colapinto, P.C.

517 Florida Ave., NW Washington, DC 20001 In the Matter of GEORGIA POWER COMPANY, et al.

(Vogtle Electric Generating Plant, Units 1 and 2)

Docket Nos. 50-424-OLA-3, 50-425-OLA-3 ASLBP No. 93-671-01-OLA-3

Dear Mr. Lamberski and Mr. Kohn:

Pursuant to the Board Order of November 17, 1993, LBP-93-22, the NRC Staff will nake the requested Office of Investigations (OI) materials available to both Georgia Power Company and the Intervenor, Mr. Mosbaugh on December 20, 1993.

The OI documents and tapes are located at our Atlanta, Georgia office. Arrangements to review and copy these documents and tapes will be coordinated by Regional Counsel, Carolyn Evans, and Larry Robinson, consistent with their other NRC responsibilities.

A number of requests relate to documents generated by the Incident Investigation Team (IIT) which reviewed the facility following the site incident on March 20, 1990.

IIT documents were placed in the Commission's Public Document Room (PDR) here in Washington.

To assist you in finding that information, I am enclosing a bibliography of IIT documents placed in the PDR in September 1990.

See Blanton memorandum of February 13, 1992.

Mr. Lamberski has filed interrogatories upon the Staff for information held by NRC personnel in the Spring of 1990.

We will make every effort to also provide responses to these interrogatories by December 20, 1993.

/!

9312160033 931206 PDR ADOCK 05000424 O

PDR i

s J. Lambarcki and M. Kohn If you have questions regarding discovery, please call Mitzi Young, Ed Reis, or myself.

Sincerely,

/LA a2J Charles A. Barth Counsel for NRC Staff cc:

Service List

Attachment:

As stated i

i I

i i

\\j

\\

1

s

+'sp* *%y#e UNITED STA1ES g

NUCLEAR REGULATOR'I COMMISSION wAsHmorow.o.c.acens g

j

%..... /

FEB 131992 MEMORANDUM FOR:

Cherie Siegel, Management Analyst Office for the Analysis and Evaluation of Operational Data FROM:

Jimmy-D. Blanton, program Assistant NUDOCS Section 1

Document Management Branch Division of Information Support Services Office of Information Resources Managenent l

SUBJECT:

DOCUMENTATION FOR NUREG-1410 i

I have received the documentation provided in support of NUREG-1410, " Loss of Vital AC Power and the Residual Heat Removal System During Mid-Loop Operations at Vogtle Unit 2 on March 20, 1990."

There are approximately 875 documents which will be reviewed, encoded, microfilmed, reproduced and sent to both the Central Files and the NRC PDR.

This is an extensive and complex set of documentation which will require a significant level of effort to assure each document within the submittal is appropriately cross referenced with each other as well as the NUREG itself.

I have initiated a review to assure everything. listed in your January 16, 1992, note to me is accounted for and that the documents do not contain any proprietary or copyrighted information.

I anticipate completion of this process, including the reproduction and distribution to the PDR, by the end of this month.

Subsequently, the documents will be processed through NUDOCS and be made available on microfiche as time permits.

If you have any questions or require further information, please contact me on extension 24570.

M Ji D.

Blanton, Program Assistant NUDOCS Section Document Management Branch Division of Information Support Services Office of Information Resources Management 1

l l

3 September 14, 1990 BIBLIOGRAPHY 1.

Memorandum from J. Taylor to the Commission dated 3/23/90; j

Subject:

Investigation of March 20, 1990 Event at Vogtle Nuclear Power Plant Involving loss of offsite Power on Demand at Unit 1 2.

Documents Collected and Provided by Augmented Inspection Team (AIT) 2-1 Instruction Manual For S & C Circuit Switches (Outdoor 230kv) 2-2 Instruction Manual For Westinghouse Type Co Overcurrent Relays 2-3 Instruction Manual For ASEA Type RADSE Transformer Differential Protective Relays 2-4 Instruction Manual For Brown Boveri Type AOT, AOK

& AOS High Voltage Current Transformer 2-5 Instruction Manual For General Electric Type PVD Differential Voltage Relay

  • 2-6(124)

Nuclear Plant Maintenance Work Order No. 28900466

  • 2-7(267)

Bechtel Drawings 1X3D-AA-A01A (Main One Line -

Unit 1) 2-8 Bechtel Drawings 2X3D-AA-A01A (Main One Line -

Unit 2) 2-9 Bechtel Drawings AX3D-AA-A01A (Main One Line -

Common Units 1 & 2) 2-10 Bechtel Drawings AX3DLO60 (Switchyard General Arrangement)

, 2-11 Bechtel Drawings 1X3DH7Al (Low Voltage Switchyard Plan) 2-12 Ccmpany Services /GPC Drawing AX3D-BA-L55A (230kV Offsite Source No. 1 C.T. & P.T. Connecting -

Sheet 1) i 2-13 Bechtel Drawings 2X3D-BB-BOIL (Elementary Diagram

-Electrical System Generator Tripping) 2-14 Southern Company Services /GPC Drawing AX3D-BA-L57D (500kV PCB No. 161520 Close & Trip No. 1) 2-15 Southern Company Services /GPC Drawing AX9D-AA-L50T (500kv PCBs No. 161520/161620/161660 Single Line) 2-16 Southern Company Services /GPC Drawing AX3D-BA-L55A (230kV Offsite Source No. 1 C.T.

& P.T.

Connecting - Sheet 1) 2-17 Southern Company Servicec/0?C Dra.r'eg.': _st.

da -

L55B (230kv offsite Source No. 1 '. ~

8 D.C.

Connecting - Sheet 1) 2-18 Southern Company Services /GPC Drawing AX3D-BA-L55C (230 Offsite Source No. 1 Diff. & Backup i

Relaying) i

  • Refer to document number in parentheses i

1

)

~

s

~

a Southern Company Services /GPC Drawing AX3D-AA-2-19 L50B (230kV Single Line For PCBs 161760/161860/161960)

Bechtel Drawings 2X3D-AA-B04A (Three Line Diagran

+

2-20

- Unit 2 AC Generator)

Bechtel Drawings 2X3D-AA-B02A (One Line - Relays &

2-21 Meters For RATS)

Bechtel Drawings 2X3D-AA-B01A (Relays & Meters -

2-22 Generator, Main, & UAT)

Bechtel Drawings 1X3D-BH-B55B (Res. Aux. XFMR 2-23 INXRB CKT Switcher)

Southern Company Services /GPC Drawing AX3D-AAL50A 2-24 (500kv & 230kv Sunstation Single Line Index Drawing)

Nuclear Plant Maintenance Work Order No. 18906364 2-25 2-26 Southern mpany Services /GPC Drawing AX3D-BA-L52R Southern Jo=pany Services /GPC Drawing AX3D-BA-2-27 L52N Elementary Southern Co pany Services /GPC Drawing AX3D-BA-2-28 L52P Diagrams For 230kv PCB Southern Company Services /GPC Drawing AX3D-BA-2-29 l

L52Q No. 161860 Southern Company Services /GPC Drawing AX3D-BA-2-30 L52S Southern Company Services /GPC Drawing AX3D-BA-2-31 L52H Southern Ccupany Services /GPC Drawing AX3D-CA-2-32 L72 K 2-33 Bechtel Drawing 1X3D-AA-D03B (4160 V Switchgear 1BA03)

  • 2-34(2-40)Bechtel Drawing IX3D-AA-D03A (4160 V Switchgear) l Bechtel Drawing IX3D-AA-D02B (4160 V Switchgear 2-35 IAA02)

Bechtel Drawing 1X3D-AA-D02A (4160 V Switchgear 2-36 1BA02)

Bechtel Drawing 1X3D-AA-D01A (4160 V Switchgear 2-37 1NA01)

Bechtel Drawing 1X3D-AA-D04A (4160 V Switchgear 2-38 1NA04)

Bechtel Drawing 1X3D-AA-D02A (4160 V Switchgear 2-39 ANA02)

Bechtel Drawing 1X3D-AA-D03A (4160 V Switchgear 2-40 ANA03) 2-41 Bechtel Drawing AX3D-BA-D02C (4160 V Breaker ANA0203) 2-42 Bechtel Drawing AX3D-BA-D03C (4160 V Breaker AcacLay

+

Gechtel Drawing AX3D-BA-D03B (4160 V Breaker

'e' ANA0301) 2-44 Bechtel Drawing 1X3D-BA-D01J (4160 V Breaker 1NA0111)

  • Refer to docu=ent number in parentheses 2

~

~~

~

Bechtel Drawing 1X3D-BA-D04D (4160 V Breaker 2-45 1NA0412)

~

2-46 Bechtel Drawing 1X3D-BA-D02C (4160 V Swgr 1AA02 INCM Brkr 1NXRB) 2-47 Bechtel Drawing 1X3D-BA-D02B (4160 V Swgr 1AA02 INCM Brkr 1NXRA) 2-48 Bechtel Drawing 1X3D-BA-D02D (4160 INCM Brkr 152-1AA0219 EDG) 2-49 Bechtel Drawing 1X3D-BA-D01C (4160 Swgr 1NA01 INCM Brkr 1NXRA) 2-50 GPC Procedure No. 13145-1 " Diesel Generators" 2-51 GPC Procedure No. 24614-1 " Train B Sequencer ACOT

& CAL" 2-52 GPC Procedure No. 27563-C " Generator And Engine Control Panel Functional Test" 2-53 Delaval Drawing 09-500-76021 Sh 1 2-54 Delaval Drawing 09-500-76021 Sh 2 2-55 Delaval Drawing 09-500-76021 Sh 3 Diesel Generator 2-56 Delaval Drawing 09-500-76021 Sh 4 Engine Control 2-57 Delaval Drawing 09-500-76021 Sh 5 Panel Schematics 2-58 Delaval Drawing 09-500-76021 Sh 6 2-59 Delaval Drawing 09-500-76021 Sh 7 2-60 Delaval Drawing 09-500-76021 Sh 8 2-61 Delaval Drawing 09-695-76021 " Engine Pneumatic Schematic" 2-62 Prints IX3D-AA-A01A, Rev. 16 1X3D-AA-F27A, Rev. 13 1X3D-AA-F28A, Rev. 14 1X3DDG020, Rev. 15 w/FCR 2-63 10 Mile EPZ Map 2-64 NOUE ED Checklist Of 3/23/90 2-65 EOF Personnel For 3/20/90 2-66 Security Emergency Response Organization for 3/20/90 2-67 TSC Personnel 3/20/90 2-68 CR Fersonnel 3/20/90 2-69 OSC Personnel 3/20/90 2-70 Training Records EOF 2-71 Communicator Package Consisting Of-Course Cc=pletion & Attendance Records Training Student Handout Dated 6/27/89 Lab / Performance Exercise Guides Lesson Plan RE LP 07001-02 Training Student Handout Dated 4/13/88 i

l Lessen "laa 8E LP 27001-01 2-72 Control Room Lavout*

Procedure 10003-C 3

i 2-73 Previous Inspection Report:

~

50-424,425 89-21 & 89-25 8/25-27/89 Exercise 50-424/425 88-38 & 88-42 8/15-19/89 ERF Appraisal 2-74 QA Open Item OQA-87-292 2-75 Safety Standard Handbook 2-76 Emergency Director Log 2-77 TSC Log 2-78 Emergency Notification Messages:

  1. 1
  1. 2
  1. 3
  1. 4
  1. 5
  1. 6 4
  1. 7
  1. 8
  • 9 2-79 EOF Manager Log 2-60 Met Info 2-81 Dictated From GEMA To VEGP (FAX 3/22/90)

Notification Information Assorted News Dispatcher & Newspaper Articles 2-82 2-83 Procedures:

91001-C, Rev. 7 91002-C, Rev. 15 91102-C, Rev. 6 91401-C, Rev. 5 91704-C, Rev. 8 2-84 GEK Training Student Handout Handbook For General Employee Badge Training 2-55 2-86 3/2/90 Test " Data Sheet 4" Of 91204-C & Data Sheet 73/20/90 Notes " Emergency Response" - From Region

~

2-27 II 2-58 3/21/90 Notes 3 Pgs. Notes 2-S9 8 Hr Report Dated 3/20-90 2-90 3/22 Results Sheet On Accountability & TSC l

Procedure Verification; 3/22 Restriction on Offsite Interaction - Phone Call: 1/22 BUENN Notes 2-91 3/22 Interview - Herb Whitener RII i

2-92 3/23 Notes CR Procedure Verification 2-93 RII Plant Note On Capt. T. Nash Interview Pauline Jenkins - Communication 2-94 Interview Theresa Jones - Communication 2-95 Interview Jimmy Cash - Operations Supt.

2-96 Interview William Burraister - Plant Duty Manager 2-97 Results Of Selected Samp11ng Of Empivyee

?-49 Security Bldg.

l i

2-99 E Plan Section H-3 " Activities And Staffing of Emergency Facility" 2-100 Interview John Hopkins - Shift Supt. Unit 1 (Interview Incomplete) 2-101 Interview Capt. William Johnson Accountability &

Log Form 2-102 Interview Lt. William Stewart Accountability 2-103 Historical Classification of Emergency & Phone Communication Notes

. Bob Trojanowski - RII GAO 2-104 E Plan, Section B, "Onsite Emergency Organization" 2-105 Results Of CR Walkdown Of Procedure File As Found 2-106 Backup ENN Description i

2-107 Met Bldg. Inspection Notes 2-108 Listing Of Onshift People For Inspection 2-109 Drug And Alcohol Screening Report On Donnie Willhite (Fuel Truck Driver) 2-110 Inventory Of Fuel Truck 2-111 Procedure 00656-C, Traffic And Parking Control, Rev. 0 2-112 Procedure 90015-C, Vehicle Access, Rev. 8 2-113 Procedure 00653-C, Protected Area Entry / Exit Control, Rev. 8 2-114 Procedure 70030-C, Traffic And Parking Control, Rev. 2

  • 2-115(2-112) Procedure 90015-C, Vehicle Access To The PA i

2-116 Procedure 00260-C, Hazardous Substance And Waste Control, Rev. 5 2-117 Procedure 00261-C, Fuel Oil Handling And Safety,

Rev. 5 2-118 The Alvin W.

Vogtle Electric Generating Plant:

Safety Standards 2-119 Figure 16-1 "Offsite AC" (FSAR)

  • 2-120(307)GPC - VEGP - Unit 1 Control Log - pp 5283-84 (3/20/90) 2-121 GPC - VEGP - Unit 2 Control Log - pp 2601-03 (3/20/90) 2-122 GPC - VEGP - Unit 1 SS Log - pp 5413-14 (3/20/90) 2-123 GPC - VEGP - Unit 2 SS Log - pp 2875-77 (3/20/90) 2-124 VEGP - Unit 2 Trip Report
  • 2-125(33) Proteus Alarn Printout - Unit 2 (3/20/90)
  • 2-126(32) Proteus Alarm Printout - Unit 1 (3/20/90) 2-127 DC 1-90-0097 (1A D/G Sequencer Prob) 2-128 Control Room Layouts 2-129 Procedure 13145-1, Rev. 20 " Diesel Generators" 2-130 Licensed Operator Training Materials For Loss of Electrical Power 2-lal Licensed Operrtor Training Materials rce L7cs OT Peeidual Heat Removal 2-132 Licensed Operator Training Materials For Emergency Plan I=plementing
  • Refer to document number in parentheses 5

2-133 Outside Operator Training Material For Diesel

~

Generator Operation 2-134 Procedure No. 12006-C Unit Cooldown to Cold Shutdown 3/8/90 2-135 Procedure No. 13005-1 Reactor Coolant System Draining 2-23-90 2-136 Procedure No. 13011-1 Residual Heat Removal System 3-26-90 2-137 Procedure.No. VEGP 00052-C Procedure No. 12007-C Refueling Entry 3-26-90 2-138 Procedure No. 12007-C Refueling Entry 3/8/90

~

2-139 Procedure No. 12000-C Refueling Entry 3/8/90 2-140 Procedure No. 18019-C Abnormal Operating Procedure Loss of Residual Heat Removal 3/8/90 2-141 Procedure No. 19100-C Emergency Operating Procedure ECA-0.0 Loss of ALL AC Power 3/16/90 2-142 Procedure No. 23985-1 RCS Temporary Water Level System Emergency Operating Procedure ECA - O>=0.0 Loss of All AC Power 5/12/89 2-143 Procedure No. 54840-1 Installation and removal instructions for the RCS Temp. Level Indication Tygon Tube and the Defeat of the Residual Heat Removal Suction valve auto clcsure interlock 2-144 0950076021 pp. 9 of 9 Delaval Drawing Engine Control Panel 2-145 0968876021 pp. 1 of 3 Devalve Drawing Engine and Skid Ele. Schem 2-146 1X4DB111 Rev. 17 P&I Diagram Reactor Coolant System No. 1201 2-147 1X4DB112 Rev. 24 P&I Diagram Reactor Coolant System No. 1201 2-148 1X4DB114 Rev. 25 P&I Diagram Reactor Coolant System No. 1208 2-149 1X4DB115 Rev. 23 P&I Diagram Chemical & Valve No.

1208 2-150 1X4DB116-1 Rev. 23 P&I Diagram Chemical & Valve No. 1208 2-151 1X4DB116-2 Rev. 16 P&I Diagram Chemical & Valve No. 1208 2-152 1X4DB117 Rev. 19 P&I Diagram Chemical & Valve No.

1208 2-153 1X4DB118 Rev. 20 P&I Diagram Chemical & Valve Nc 1208 2-154 1X4DB119 Rev. 21 P&I Diagram Safety Injection System No. 1204 2-155 1X4DB120 Rev. 15 P&I Diagram Safety Injection Systar du. '.204 2-156 1X4DB121 Dev. 25 P&I Diagram Safety Injection System No. 1204 2-157 1X4DB122 Rev. 27 P&I Diagram Residual Heat Removal System No.1205 6

Loss of All AC/4160V IE Power Lesson Plan 2-158

~

~

Briefing Book document for IIT Leader 3.

Harston, III fm S. D. Ebneter dtd 3/23/90.

G.

3-1 Ltr to W. Confir=ation of Action Letter

Subject:

Site Area Emergency at Vogtle PNO-II-90-16,

Subject:

Unit 1 Loss Of Offsite Power (3/20/90) 3-2 Site Area Emergency at Vogtle PNO-II-90-16A,

Subject:

Unit 1 Loss of Offsite Power (3/21/90) 3-3 Augmented Inspection Team is PNO-II-90-16B,

Subject:

Dispatched to Vogtle Unit 1 (3/22/90) 3-4 3-5 EVENT NUMBER:

18024 (3/20/90)

NRC Staff Dispatches Augmented Inspection Team i

3-6 DRAFT:

to Vogtle Nuclear Power Plant NRC ENTRANCE (3/22/90) 3-7 Meeting

Purpose:

3-8 Status Summary 1:

(3/20/90) 3-9 Status Summary 2:

(3/20/90)

Alert Declared at Vogtle after Truck Hits 3-10 Article:

TcVer (3/21/90) -(The Augusta Chronicle)

Outage at Vogtle Means Moment of Fear of Some 2-11 Article:

(3/21/90) (The Augusta Chronicle) 2-12 Ouestions and Responses 3-13 Electrical Distribution Schematic Charts Site Area Emergency (3/20/90) 3-14 VR-1 Update 1500 3/22, Site Area Emergency (3/20/90) 3-15 VR-2 Update 1500 3/23, 3-16 Attention - Quarantine List and Licensee Restrictions 3-17 Chart - D/G Testing Unit 1 (3/24/90)

Event 3-18 1st Draft of GPC's Event critique (uneventful). Loss of

Title:

3-19 Pcwer Level / Mode and L. per:51; Fquipmunt/Abnctmal system Alignment (Info) 7

4 i

)

4-20 Interview Notes (3/20/90 (3/23/90) 3-21 Interview List t

3-22 Miscellaneous Notes t m Assigned to Rick Kendall l

3-23 Status of AIT Charter I e(3/24/90) notes (Items Nos. 5 & 6)

(3/25/90) w/ Paul Kochery (10:30 a.m.)

3-24 Discussionfrom Rick Kendall 3-25 offsite Commendation 5a 3-26 cnsite Notification 5b 1 Auxiliary Building Radwaste 3-27 GPC, Vogtle Plant, Unit Operator Log (3/20/90)

Unit 1 Outside ting Plant, 3-33 GPU, Vogt].e Electric GeneraArea Opera 3-34 Freliminary Thermocouple i

0) 3-35 Interview Schedule (3/23/9 (3/24/90) 3-36 Interview Schedule - AIT t Notes for Item 1 (3/24/90) r l

3-37 Warren Lyon - Status Repor Charter Item l

3, ter Item No.

3-38 Status Regarding AIT Char Description (3/24/90) (Testa)

(#4) 3-39 Status Regarding Summer (Trager) 3-40 Vogtle AIT Chart Item 7 Vogtle Switchyard of Potential Explosion in the Evaluaticn (3/24/90) 4.

Event Evaluation #1 (4/10/90)

Event Evaluation #2 (4/12/90) 4-1 Event Evaluation #2 Power Company 3/26/90 4-2 4-3 i

Entrance Presentation by Georg a IIT arrive at Vogtle Site 5

Subject:

PNO-IIT-90-02 3/26/90 6.

l 8

4 industry representatives on Waiver Agree =ents signed by (3) of compensation, Conflict of Interest and release of 7.

Investigation Information for industry participating in IIT 8.

Bulletin Board Notice Letter to Document control desk,USNRC from W. G. Hairston Nuclear Operation, Georgia Power Co., dated 9.

III, Sr. V. P.,

Subject Vogtle Electric Generating Plant Hardware 11/30/89.

Modifications pursuant to generic Letter 88-17 Letter to document control desk, USNRC from W. G. Hairston III, GPC, dated 2/2/89.

Subject:

Plant Vogtle - Units 1 10.

and 2, NRC docket 50-424, 50-425, Operating License NPF-68, Construction Permit CPPR-109 Response to Generic Letter 88-17 G. Hairston, Letter to document control desk, USNRC W.

11.

III,GPC, dated 12/29/88;

Subject:

same as #10 Sequence of Events Chronology of Site Area Emergency 3/20/90 12.

(Received 3/27/90) from license 13.

Letter to W.

G. Hairston, III, GPC, from A. R. Herdt, NRC, dated 7/31/89.

Subject:

Notice of Violation (Inspection Report Nos. 50-424/89-19 and 50-425/89-23) w/NRC Inspection Manual Tenporary Instruction 2515/101 1990 Local newspaper coverage - March 27, 14.

15.

Interoffice Memo from G. Bockhold, Jr., Plant Manager, to Vogtle Site Personnel dated 3/27/90.

Subject:

Vehicles in Perimeter Area Entrance Meeting with Licensee and Personnel Statements 16.

(3/26/90) 16-1 Entrance Meeting Notes 16-2 J. Hopkins - SS 16-3 R. B. Snyder - SS 16-4 P. Vannier - RO 16-5 K. Jones - CRO 17.

Order to quarantine 18.

Letter to C. C. Miller, Mgr. of Engineering, Vogtle, from W.

dated 2/16/90.

Subject:

Vogtle, Units 1 &

P.amsey. 7,,

C. Pinal Response to Request for Engir.eering Assistance.

1, Loss of becay Heat removal Analytical Studies

Attachment:

for Vogtle 1 & 2, A response to GL 88-17 9

4 0 001-C Continuing Training Student Handout No. GE-HO-88002,

Training--RHR Mid-Loop Oper" 19.

Training Lesson Plans:

No. GE-20.

Continuing Training--RHR Mid-Loop Oper.

l 20-A LP-88002-00-C l Oil Emergency Diesel Generator Auxiliaries Fue 20-B System No.

i NL-LP-11202-01-C i

No.

Emergency Diesel Generator General Overv ew 20-C NL-LP-11201-00-C NL-LP-Emergency Diesel Generator Auxiliaries No.

20-D 11203-02-C ECA-0.0 Loss of All AC Power 21.

EOP No. 19100-C, Revision 4, cedure No. 13427-2, 4160V AC IE Electrical Distribution, Pro 22.

Revision S d re No. 18031-Loss of Class 1E Electrical System, AO Proce u 23.

C, Revision 6 tdown, Procedure Boron Injection Flow Path Verification - Shu l

No. 14406-1, Revision 3 l

24.

i l Test Procedure l

Generator and Engine Control Panel Funct. ona No. 27563-C, Revision 2 25.

"A-TRAIN UNDERVOLTAGE TEST" Expiration T-ENG-90-11, Rev.

1, 26.

l Data:

4/8/90 B-Train Undervoltage Temporary Procedure No. T-ENG-90-12, 4

27.

l Sequencer Operability Tes.

Temporary Procedure No. T-ENG-90-13, 28.

Check Train B DCP Temporary Procedure No. T-ENG-90-14, Unit One S8-V1N0070 Sequencer Functional Test 29.

St.laencer T-ENG-90-15, Unit one Train A, DCP 88-VIN 0070 30.

Functional Test 19001576, 3/28/90 (D/G 1A)

Haintenance Work Order (MWO)

'1.

'U?)

  • (32)

Proteus Alarn Printout

  • 32.
  • Refer to document number in parentheses 10

33.

Proteus Alarn Printout (U2) 34.

List of Quarantined Equipment (Revised 3/29/90 Rev. 2) 35.

Personnel Interviews 35-1 K. Pope - SS 35-2 W.

Burneister - Unit Superintendent 35-3 N. Dewbre,. P. Jenkins, T. Jones - Shift Clerks 35-4 F. Thonpson - EGS; R.Moye - ESS 35-5 G. Bockhold - PM 35-6 D. Vineyard - SS 35-7 W. F. Kitchens - Ass't. PM 35-8 D. Hines, D. Daughhetee, E. Pickett, J. Stanley 35-9 J.

P. Cash - OS 35-10 T.

C. Eckert - Oper. Dept.

36.

List of quarantined equipment (Revised 3/29/90 Rev. 3) 37.

Personnel interviews

  • 37-1 W.

Johnson, W.

Stewart - Security 37-2 M. Lackey - Outage Planning Mgr.

37-3 M.

Lackey, R. Barlow, J. D'Amico - Scheduling 37-4 J. Roberts - EP 37-5 H. Handfinger - Maintenance Mgr.

37-6 G.

Brenenborg, I. Kochery 3E.

PNO-IIT-90-02A 39.

Training Lesson Plan No. NL-11204-OOC Energency Diesel Generator-Engine Control and Protection 5/11/89 40.

Procedure No. 13415-1,Rev.6, Reserve Auxiliary Transforners, 6/30/89 41.

Training Lesson Plan No. LO-LP-28201-09-C Sequence Operation, 7/26/89 42.

EOP No. 19101-C, ECA-0.1 Loss of all AC Power Recovery without SI Required 43.

Training Lesson Plan No. NL-11205-01C, Energency Diesel Generator Control and Protection, 8/29/89-44.

Training Lesson Plan No. LO-LP-11102-05-C Feargency Diesel Generator Auxiliaries Air Ster: System, 12/8/89 45.

Training Lesson Plan No. LO-LP-11001-06-C, Energency Diesel Generator Introduction and Overview, 12/11/89

  • SAFEGUARDS DOCUMENT NOT TO BE RELEASED 11

s 46.

Personnel Interviews Dannemiller, D. Huyck - Security E.

46-1 J. D. Jiles - Safety Specialist 46-2 R. Berry - Security 46-3 46-4 S. Chestnut -Training K. Stokes - Sr. Plant Eng.

l 46-5 13426-C, 4160V AC Common Procedure No.

1/26/90 47.

Non IE Electrical Distribution System, Training Lesson Plan No. LO-LP-11103-06-C Emergency Diesel Generator Auxiliaries:

48.

Combustion air and exhaust, 2/28/90 LO-LP-11104-C, Training Lesson Plan No.

E=ergency Diesel Generator Auxiliaries Lube Oil 49.

3 and Crank Case Ventilation, 12/8/89 Training Lesson Plan No. LO-LP-11105-08-C, Emergency Diesel Generator Auxiliaries Jacket 50.

water cooling system, 12/8/89 Training Lesson Plan No. LO-LP-11101-07-C Diesel Generator Auxiliaries Fuel Oil System 51.

12/8/89 52.

Letter to J.

P. Kane, GPC, from W.C. Ramsey (unsigned and undated).

Subject:

Response to REA Loss of decay heal removal VG-9010, Energency Response Facilities Input l

53.

List, Revision 07.05, 12/11/86 14406-1, Revision 3, Frecedure No.

E0ron In]ection Flow Path Verification-l 54.

Shutdown, 2/6/89 VEGP Standing Order No. 1-90-05, l

55.

Energency Boration Flow Path, 3/1/90 56.

Mercrandum for A. Chaffee from S. Ebneter, undated (received 3/30/90).

Subject:

Designated l

l Regional Point of Contact Procedure No. 17038-1, Rev.7, Annunciator Response Procedures for ALB 38 on EAB Panel, 3/11/90 57.

i 58.

Frocedure No. 13011-1, Rev.16, KER System, 3/11/90 f

Vehicle Access Request, 3/20/90 59.

60.

(AOP) Procedure No. 18019-C,Rev.7, Loss of RHR,3/16/90 12

4 F

9 l

61.

PRB Comment Review Sheet (PRB-90-44) for Temporary Procedure No. T-ENG-90-14 GPC VEGP Handbook for General Employee Badge Training, GE-62.

HO-00101-001-C, Rev.

5, 10/23/89 w/ record of training dates t

for D. Willhite 63.

Event Report No. 1-90-003, Additional Support Items 64.

SPDS Checklist 65.

Items on Fuel Truck 3/2-30/90 1

66.

Photographs 66-1 Roll 1 - (3/24/90) 66-1-1 Voltmeters 66-1-2 Auto XFML No. 2 66-1-3 Auto XFMRs Nos. 1 & 2 66-1-4 Electrical Panel 66-1-5 Annunciators and Electrical Panel 66-1-6 Electrical Panel and Annunciator 66-1-7,8 14tdown/Chg. Flow and Bit Press 66-1-9 Accumulator Pressure Tanks 1 and 2 66-1-10 Accumulator pressure, Tanks 3 and 4 66-1-11 PROTEUS Computer Display 66-1-12 RWST Reset Switches (2) and RHR Suct Vent Line TRN-B 66-1-13 RHR to HL, RHR Suct Vent Line TRN-A, RWST Reset 66-1-14 RHR X Train A & B Outlet and Bypass 66-1-15 RHR Pump Pressure Trains A & B 66-1-16 Incore TC 66-1-17 Cperator Aid for mid-loop on RCS Loop 1 Hot Leg NR Level, and RCS Loop 4 Hot Leg WK Level 66-1-18 SI Pump Disch Trains A & B 66-2 Roll 2 - (3/24/90) 66-2-1,2 Plant Safety Monitoring System 66-2-3 Control Rod Position 66-2-4 RCS Flow Trip Alarms 66-2-5 PRZR Pressurizer, PRZK Spray, PRZK LVL i

66-2-6 RCS Press, RCS HL Temp 66-2-7 RCS CL Temp OP delta T, OT Delta T, Delta T 66-2-8 Chg. Flow. RC.c Icops 1-4, Delta T 66-2-9 Press, LTDN Flow, RCS Loop 4, RCS Temp Loop 3,

Delta T 66-2-10 RCS Loop 4, RCS Temp Loop 2, Delta T 66-2-11 Safety A, RCS Loop 1 HL Press, RCS Temp Loop 1, Delta T l

13

(Delta T, OP Dalta T, OT Delta T.

RCS Loop 4 T-AVG & RC Flow Loop 4)& RCS Flow Loop 4 66-2-12 RCS Loop 4,

& RCS Flow Loop 2 66-2-13 RCS Loop 2,

& RCS Flow Loop 1 1, Delta T i

66-2-14 RCS Loop 1 HL Press, RCS Temp Loop RCS Loop 1, 66-2-15 PRZR Relief Temp, RCS Loop 1 66-2-16 66-2-17 In Core TC Annunciators 66-2-19-23 Electrical Panel and 66-2-18

- Truck (3/25/90) 66-3 Roll 3 -

Rear View (180 to 195 feet) l 66-3-1,2 Blind Spot Assessment 66-3-3-6 Left View d area 1 66-3-7 Closeup of event-related damageCloseup o Fuel Can d area 2 66-3-8 66-3-9 66-3-11,12 Closeup of event-relateCloseup of event-relat d area 2 66-3-10 66-3-13 Fire Extinguisher 66-3-14 Fire Extinguisher 66-3-15 Inside Cab (Driver's Door Open) 66-3-16,17 Front View Windshield (from inside)through left and right 66-3-18 Front 66-3-20-23 Blind Spot Assessment 66-3-19 mirrors view Left side Lee, J. Aufdenkampe, W. F.

66-3-24 Personnel Interview of G.Burmeister & D. West 67.

Kitchen, W.

i Diesel Generator Failure Analys sD. DeLoach, J. Jackso l

68.

Personnel Interview:

Whitman 69 Photographs 70 (3/24/90)

R Level, and l

70-1 Roll 4 Operator Aid - RCS Loop 1 HL N l

Containment RCS Loop 4 HL WK LevelSI Sump Disch Tra 70-1-1 70-1-2 BIT Press Press Letdown /Chg. Flow, In Core TC 1

70-1-3 Proteus Co=puter:

70-1-4,5 Accumulator Level 70-1-6 RHR Pump Pressure

- Tne 10-1-/

(3/30/90)

Licensc:

70-2 Roll 5 - Photos provide by Welder Side View 70-2-1-3 70-2-1-4,5 Front View 14

w -- - -

71.

Meeting Attendance Record 71-1 IIT Entrance (3/26/90) 71-2 Diesel Generator (3/28/90) 71-3 Diesel Generator (3/30/90) 72.

Access Record History, 3/20/90 73.

Badge Record - 3/30/90 P

74.

Evaluations of Initial Plant Conditions - J. D'Amico Procedure No. PTDB-1 Tab 8.0, Rev. 2 - Pictorial Aids: RCS 75.

Elevations and Mid Loop Level Instrumentation (3/2/90) 76.

Procedure No. 18015-C, Rev. 5, Loss of Instrument Air 77.

Procedure No. 12000-C, Rev. 16, Refueling Recovery 3/8/90 t

78.

Procedure No. 12006-C, Rev. 15, Unit Cooldown to Cold Shutdown 3/8/90 79.

Procedure No. 12007-C, Rev. 14, Refueling Entry (Mode 5 to Mode 6), 3/8/90 80.

Procedure No. 13005-1, Rev. 10, Reactor Coolant System Draining, 2/23/90 B1.

Procedure No. 17006-1, Rev. 11, Annunciator Response Procedure for ALB 06 on Panel 1A2 on MCB, 3/6/90 l

82.

Sechtel Drawings IX3D-AA-G02 C, Rev.

6, Vital Inster. Distr. Pnis.

AX3D-AA-A01A, Rev. 13, Main One Line 1 & 2 l

AX3D-AA-F19A, Rev. 10, 480V Motor Control Center l

1X3D-AA-G05B, Rev. 14, 120V AC Non-Class IE key Instr.

1 AX3D-AA-HO1A, Rev.

9, TSC 125V DC/120V AC Non-Class IE Distr. Panels AX3D-AA-A01A, Rev. 16, Main One Line Unit 1 l

1 AX3D-AA-G02B, Rev. Main One Line Non-Class IE 12SV DC & 120V Ess. AC System 83.

MWO 18906587, SGW4, Unit 1, 12/23/89 84.

Procedure No. 25270-C, REv.6, SG Nozzle Dam Checkout, Installation and Removal 12/16/88 15 i

.4 85.

Procedure No. 18004-C, Rev. 6, AOP RCS Leakage, 12/9/90 86.

(AOP) Procedure No. 18006-C, Rev.

2, Fuel Handling Event, 8/4/88 87.

(AOP) Procedure No. 18020-C, Rev.3, Loss of Component Cooling Water, 2/14/90 88.

(AOP) Procedure No. 18021-C,Rev. 4, Loss of Nuclear Service Cooling Water System, 3/16/90 89.

Procedure No. 18034-1,Rev.

1, Loss of Class IE 125V DC Power, 9/12/89 90.

(AOP) Procedure No. 18028-C, Rev. 7, Loss of Instrument Air,

{

3/16/90 91.

(AOP) Procedure No. 18038-1, Rev. 10, Operation from Remote Shutdown Panels, 8/29/89 92.

Radiation Monitors Status 93.

Relief Request 7 and 11 (with accompanying documents) Safety Injection System No. 1204 94.

Procedure No. 00350-C, Rev.19, Work Request Program (12/27/89) 95-1.

MWO #18807746 3/31/90 95-2.

MWO #19001339 3/31/90 95.

Section 6.0, Administrative Controls (Vogtle 1 & 2) 97.

Information on Critical Safety Function Status Frees on SPDS (on EXF computer) 98.

Training Records: A.

L. Blalock, T. Redivannz, W. Hennessy, J.

D. Williams, W.

P. Stephens, W. M. Watkins, D. Haile, J.

W.

Covington, R.

LeGrand, G. J. Durrence 99.

Information on Maintenance Personnel Training on Mid-Loop Ops 1

100. Precedure No. 00400-C, Rev. 11, Plant Design Control' 2/24/90 101. Request for 7ngi."ar: 1 5 Er. ice (trecedure No. 00400-C) of System 500 kV 16 J

I

..V 102. Relaying Data Sheet - Gen. No. 2 Main Bk. Primary 103. Sequence of Events w/ source of information 104. 2.0 Hardware Configuration 105. Vendor Document Status Sheet-Manual Change No. 76021-9, 9/9/86 106. Security Department Report No. 3941-90 107. Joint News Release - 3/20/90 108. MWO (continued) No. 19001576 109. T-ENG-90-11, Rev. 1, A-Train under voltage Test w/related MWO's 110. lA Diesel Generator Reference Material 111. 3/20/90 Logs: Unit 1 & 2 Shift Supervisor; 1 & 2 Control 112. Memo to G.

Bockhold from G. R.

Fredrick, dated 9/27/89.

Subject:

VEGP-1 and 2 QA Audit finding Report 350 113. Release #1 and # 2 - 3/20/90 114. OSC Lcg 115. MWO 18906328, 3/27/90 116. Attendance Roster - Diesel Generator Mtg. (3/31/90) l 117. Personnel Interviews:

117-1 K. Exly 117-2 P. Humphrey 117-3 J. Williams, D. Gustafson, G. McCarley 118. Operational Journals, 3/20, w/ Situation Chart 119. MWO No. 19001684, (3/31/90) Diesel Generator - To Verify F

Timing of Two Trips During LOSP 1

120. Personnel Interviews:

120-1 G. Schnieder (EP) e.d S. Threatt (PRF-EPC) 320-2 R. Dorman - Training j

17 I

~W 120-3 M. Cagle - Maintenance 120-4 S. Driver - Training i

120-5 D. Willhite - Truck Driver 120-6 E. J. Kozinsky - SS 120-7 S._ Young - PFS 121. Design Change Request No. 88-VIN 0070 w/ Design Change Package i

Closure - Train A & B Sequencer Panels 122. Operation and Maintenance Instructions (SFSS) w/ drawings 123. Vogtle Operating Records - VPO401GP 124. MWO 19001684 - 3/31/90 MWO 19001576 - 3/31/90 MWO 28900466 - 3/31/90 125. PROPRIETARY DOCUMENTS:

W FIELD SERVICE PROCEDURES

  • 125-1 MRS 2.2.2 GPC-1, Post Activity Sign-Off for Area i

Cleanliness 125-2 MRS 2.2.2 GPC-21 Rev. O, Nozzle Dam Hydrotest 125-3 MRS 2.2.2 GPC-22 Rev.

O, Nozzle Dam 125-4 MRS 2.2.2 GPC-23 Rev.

O, Nozzle Dan Manual 125-5 MRS 2.2.2 GPC-24 Rev.

O, Nozzle Dam, Leak l

Detection Manual 126. Procedure No. 29536-C, Outage Management Program (3/4/88) l i

127. Procedure No. 27505-C, Rev. 2, Opening and Closing Containment Equipnent Hatch (7/18/88) i 128. Procedure No. 10013-C, Rev.

6, Writing EOPs from the j

Westinghouse Energency Response Guidelines (9/22/88) 129. Procedure No. 29537-C, Rev. 1, Outage Scheduling (4/11/89) 130. Procedure No. 01000-C, Rev. 1, Managenent of Outages (6/9/89) 131. Procedure No. 10011-C, Rev. 13, Operations Procedure Preparation and Review Guidelines (7/5/89(

132. Procedure No. 10018-C, Rev. 11, Annunciator Control (9/26/89) 1 I

~43. T wredure Nc. 10000-C, Rev. 16, Conduct of Operations (3/??/90)

  • NOT TO BE RELEASED 18

]

g O

4 134. Procedure No. 11011-1, Rev. 7, RHR Removal System Alignment i

(4/18/89) 135. Te porary Change to Procedure Form (TCP) No. 13001-1-12 !

1, RCS Filling and Venting (Expiration Date:

4/6/90)

I 136. Procedure No. 14230-1, Rev. 4, AC Source Verification (7/27/88) 137. Procedure No. 91403-C, Rev. 4, Site Evacuation (12/6/88) 138. (EOP) Procedure No. 19101-C, Rev, 8, ECA-0.1 Loss of All AC l

Power Recovery Without SI Required (7/26/89) 139. Procedure No. 19111-C, Rev.

8, ECA-1.1 Loss of E=ergency t

i Coolant Recirculation (7/26/89) t 140. Procedure No. 13001-1, Rev. 12, Reactor Coolant System Tilling and Venting (10/10/89) i 141. System Block Diagrams - SFSS i

142. Bechtel Drawings:

i 1X4DB113, RTD BY-PASS REACTOR COOLANT SYSTEM NO. 1201 IX4DB100, P& ID'S AND FLOW DIAGRAM LEGEND AX3AE03-9-10, ELECTRICAL SCHEMATIC ZX3AE03-10-10, ELECTRICAL SCHEMATIC 143. Unit 1 D/G Trip Sensor History w/ Licensee's Draft Analysis of 1A Diesel Shutdown 144. FNO-IIT-90-02B - 4/2/90 145. Transcript:

Briefing Meeting - 3/28/90 I

i 146. Personnel Interviews 1-J.

Acree - SS 2-J. Aufdenkampe - Tech Support I

3 - F. Pope - EO 4 - S.

Owyoung 5-J. Ealick j

6 - M. Cagle 7 - M.

Lackey (3/30/90) 147. Transcil;*.:

therl?i

!!T and Licensee Personnel re Diesel Malfunction (1/30/90) 19

i

~

148. Transcript:

Meeting w/ Event Critique Team - 3/31/90 l

149. Personnel Interview - D. Hines - PE i

150. Transcript:

Discussion re Results of Testing on A-Diesel i

Perfor=ed on 3/30/90 I

151. Memo for A. Chaffee from G. Zech, dated 4/3/90.

Subject:

Lessons Learned:

Vogtle Site Area Emergency 152. Memo from M.

S.

Briney to G.

Bockhold, Jr., dated 4/3/90.

Subject:

Calcon Temperature Switches 153. PROPRIETARY DOCUMENTS (INPO)

  • Operating Experience close out Packages for the following:

i i

SOER 85-01 SER 17-88 SER 73-B3 SER 42-84 O&MR 272 SOER 85-04 OEMR 365 t

SOER 88-03 SER 5-89 SER 26-89 SER 36-88 SER 2-87 SER 35-86 I

SER 31-86 SER 23-86 SER 17-86 154. Calcen Switch Information i

155. Cuarantined Equipment List, Rev. 4 - 4/2/90 156. Meeting Attendance Record - Diesel Generator and IIT Exit -

4/2/90 157. Procedure 14980-1, Rev. 18 - Diesel Generator Operability Test (2/5/90) 158. Letter to Director, I&E, NRC, from B.

C. Guntrum, Mgr., QA, IMO.

Subject:

Notification of a Potential Defect in a component of a DSR or D99.V FtandP, D/c. t /2? /AR)

  • NOT TO EE RELEASED 20

u e

1

~

i l

159. VHS Video Tape Recording:

RER Mid-Loop OPS 160. Photographs 160-1 Roll 6 - (3/31/90) l 160-1-1,2 TSC 160-1-3-7 D/G 1A CK Control Panel i

160-1-8,9 D/G 1A CK Annunciator Panel 160-1-10

PSMS Codes 160-1-11 Plasma Display and Keyboard of PSMS 160-1-12,13 Proteus Computer 160-1-14-16 NSCW, CCW i

160-1-17,18 NSCW: Return Temp, Basin Lvl. & Hdr.

Press.

i 160-1-19 NSCW A Flow: Supply and Return 160-1-20,21 Misc. Status Lights for NSCW 160-1-22,23 CCW PMP-1, 3 460-1-24,25 Rx MW Wtr. to CCW 160-1-26,27 CCW Train A Surge Tank l

160-1-28,29 CCW Cnst. Spray, & SI Panels 160-1-30,31 RHR & CVCS, & Accum. Panels 160-1-32-33 RWST Level 160-1-34 Page 1 of D/G Procedure (13145-1) 160-2 Roll 7 - (3/31/90) 160-2-1-5 Jacket Water Pressure Sensor 160-2-6-9 Pressure Sensor 160-2-10,11 Lube Oil Pressure Sensors (3) 160-2-12-14 Lube Oil Temperature Sensor 160-2-15-25 Jacket Water Temperature Sensors (3) 160-2-26-31 Turbo Lube Oil Sensor j

150-2-32-34 Emergency Break Glass Start 160-2-35 Break Glass Hammer vs Flashlight Size 161. List of Vogtle 1 Event Headquarters Operations Center Participants 162. History of Quarantined Items 163. Quarantine Sign l

164. Unit 1 Second Refueling Outage Charts.

j 164-1 Electrica Jystem Work ll ; - 7 IR-1 Target vs. Actual Critical Peth 21 1

u 164-3 First Drain to Mid-loop 164-4 IR-2 Target vs. Actual Critical Path 164-5 D/G Activities /TRN B 164-6 D/G Activities /TRN A 165. Unit 1 First Refueling Outage Charts:

165-1 Mid-loop Work and Support 165-2 Electrical System Work 165-3 D/G Activities /TRN B 165-4 D/G Activities /TRN A 166. Photographs 166-1 Roll #8 - (3/31/90) 166-1-1 D/G Control Panel 166-1-2 D/G Control & Annunciator Panels 166-1-3,4 D/G Annunciator Panel 166-1-5 SI Signal 166-1-6,7 Emergency Start 166-1-8 Procedure Sec. 4.4.3.1 166-1-9 Procedure Sec. 4.4.3 166-1-10 Jacket Water Lv. In.

166-1-11,12 Jacket Water In 166-1-13,14 Generator Bearing Te=p.

166-1-15-17 Day Tank Level 166-1-18 D/G Control Panel 166-1-19-21 Local Remote Control Switch 166-1-22-25 D/G Back Panel (Inside) 166-1-26 Gaitronics Phone 166-1-27 Commercial Phone 166-1-28,29 Sound-Powered Phone 166-1-30 P.

1 of Procedure 13145-1 166-1-31 Lube Oil Press 166-2 Roll E9 - (3/30/90) 166-2-1-7 Sensor Points on Blackboard. in Large Conference Rm (LCR) 3 166-2-8-10 Electrical Configuration of Vogtle Plant 166-2-11 Blackboard Note to IIT 166-2-12-19 Sensor Points on Blackboard in LCR l

166-2-20-34 Sensor Points on Blackboard in LCR showing steps to de-energize Sequencer on Panel i

22

1 166-3 Roll #10 - (3/26/90) 166-3-1,2 New Restricted Area Sign and Rope 166-3-3,4 D/G Panel 166-3-5 D/G Annunciator Panel 167. Procedure No. 00053-C D/G 1A - Temperature Monitoring and l

Recording (4/4/90) 168. Meeting Transcripts:

168-1 Telecon between IIT, Licensee Personnel, and RII i

Personnel.

168-2 D/G Meeting (4/2/90) 169. Technical Specifications - Vogtle Unit 1 - Sections 1-5

{

l 170. 1985 Maintenance Work Orders (MWOs) - History, Unit 1, D/G-l Sensor Switches 171. 1986 MWOs - History, Unit 1, D/G-Sensor Switches 172. 1987 MWOs - History, Unit 1, D/G-Sensor Switches 173. 1986 MWOs - History, Unit 1, D/G-Sensor Switches 174. 1989 MEOs - History, Unit 1, D/G-Sensor Switches 175. 1990 MWOs - History, Unit 1, D/G-Sensor Switches 176. 1988 MWOs - History, Unit 2, D/G-Sensor Switches 177. ERT Computer Points 175. D/G Ierperature Switch Calibratica Data Received from Licensee - 4/6/90 179. PROPRIETARY DOCUMENTS - WESTINGHOUSE

  • 179-1 Core Map - Instrument Locations 179-2 Reference Loading Pattern 180. D/G (1 A/1B) Start Logs i

161. Ltr to R. Newton, WOG, fm A. Thadani, NRC, dtd 12/11/89.

Subject:

Loss of RHRS Cooling While the RCS is Partially Tilled, WCAP-11916, July 1988, and Other Related WOG Activities

  • NOT TO BE RELEASED 23

~~~

~

.y

~

182. II Bulletins

~

7.82-1 No. 50-12 (5/9/80) 182-2 No. 86.01 (5/23/86) i 183. Information Notices 183-1 No. 80-20 123-2 No. 80-41 183-3 No. 81-09' 183-4 No. 81-10 183-5 No. 86-39 183-6 No. 86-74 l

183-7 No.86-101 183-8 No. 87-01 183-9 No. 87-23 183-10 No. 87-59 183-11 No. 89-41 183-12 No. 89-67 184. Me=orandum for T. Murley, NRC, and E. Beckjord, NRC, fm E.

dtd 5/18/87.

Subject:

Loss of Decay Heat Jordan, NRC, Removal Function at Pressurized Water Reactors with l

Partially Drained RCSs 185. NUREG/CR-5015; BNL-NUREG-52121, Improved Reliability of Residual Heat Removal Capability in PWRs as Related to Resolution of GI-99 186. Case Study Report AEOD/C503, Decay Heat Renoval Proble=s at U.S.

FRRs, 12/85 I

"ocu=entation of Special Test of RHR Lineup to be Used with 187. Fath to Loops 1&2 only ISB. MWos en S/G Manway and Nozzle Dams 185-1 No. 18906589 188-2 No. 18906581 188-3 No. 18906579

)

188-4 No. 18906580 188-5 No. 18906582 188-6 No. 18906588 188-7 No. 18906590 188-8 No. 18906587 sk?. O,erator Aids - Local Control Stations a

24

2 I

190. Ltr to USNRC Document Control Desk fm W. G. Hairston, III, GPC, dtd 8/15/89.

SUBJECT:

VEGP LER 50-425/1989-023 191. Selected Licensed Operator RHR Training Material 192. Selected Licensed Operator Annunciator Training Material 193. Selected PEO, D/G Training Material; Lessons Plans &

Response to Annunciators 194. Procedure No. 13431-1, Rev.

4, 120V AC IE Vital Instrument Distribution System (4/20/90) 195. Presentation to Region II NRC on Vogtle Site Area Emergency, March 20, 1990 (4/9/90 - by Licensee) 196. Generic Letters 196-1 No. 87-12, Loss of RHR While the RCS is Partially

)

Filled (7/9/87) 196-2 No. 88-17, Loss of Decay Heat Removal (10/17/88) 197. Memo for J.

P. Stohr, NRC, fm A. T. Boland, NRC, dtd 4/3/90,

Subject:

Critique of RII's Response to the Vogtle Incident 198. Appendix A to NRC TI 2575/103, Supplemencal Infor=ation, t

Containment Closure and Reactor Coolant System Level l

Instrumentation (2/26/90) 199. Letter to R.

C. Jones, NRC, from L. A. Walsh, WOG, dated 4/6/90:

Subject:

WOG Transmittal of Information Copy for Less of RHR While Operating at Mid-Loop Conditions Guideline and Background Documentation 200. Transcript:

Telephone Conversation w/IIT, Licensee, R-II (4/5/90) 201. NRC Personnel Interviews:

4/5/90 201-1 A. Thadani, NRR 201-2 W.

Lyon, NRR 202. Unit 1A Train D/G - Air Receiver Dew Point Measurements 203. Transcript:

Telephone Conference w/IIT, Licensee, R-II

(

IA/',,a, 25

I 2

204. Personnel Interviews:

4/6/90

~

L. Walsh, Seabrook (telecon) 204-1 D. Marksberry, NRC/AEOD 204-2 J. MacKinnon, NRC/AEOD 204-3 204-4 P. Ray, NRC/AEOD 204-5 D. Ross, NRC/AEOD i

Licensee, R-II 205. Transcript:

Telephone Conference w/IIT, (4/7/90)

Licensee (4/9/90) l 206. Transcript:

Telephone Conference w/IIT, l

207. NRC Personnel Interviews:

4/9/90 207-1 W. Hodges, R-I 207-2 G.

Zech, AEOD 208. IE Information Notices 208-1 No. 83-56 208-2 No. 84-42 (4/11/90) 209. Preliminary D/G Instrument Test Outline 210. Failures of Calcon Temperature & Pressure Sensors at Vogtle 1&2 211. NRC Information Notice No. 88-36 Licensee, R-II 212. Transcript:

Telephone Conference w/IIT, (4/10/90) 213. NRC Fersonnel Interviews:

4/10/90 213-1 R. Jones, DST 213-2 R. Eckenrode, HEAB 213-3 D. Tondi, ESS Tires To Core Uncovery Following Loss of RHR -

214. Graph:

During Mid-Loop Operations (4 loop W Plants Including Vogtle) - H. Ornstein (3/29/90) 215. Memorandum for M. W. Hodges, NRR, From J. E. Rosenthal, Additional Information on AEOD, dated 6/29/87;

Subject:

Loss of DHR at F'n'Rs with Partially Drained RCSs 26

g e

216. Memorandum for K. Kniel, RES, From J. E. Rosenthal, AEOD, dated 8/28/87;

Subject:

.BNLs 8/18/87 Presentation of the Results of Draft Report " Improved Reliability of RHR Capability in PWRs as Related to Resolution of GI-99" 217. Memorandum for T. E. Murley, NRR, from E. S. Beckjord, RES, dated 4/4/88;

Subject:

GI-99 Risk Assessment Results 218. Event Report #1-90-003, Loss of Off-Site and On-Site AC Power (1E); Date of Event:

3/20/90 219. Data Sheets - MWO 19000092 220. Data Sheets - MWO 19000093 221. Commitments and Commitment Change Reports for D/G Preventive Maintenance:

Report Nos. 9023, 9034 through 9038, 9052, 9082, 9086, and 13764 222. Data Sheets - MWO 19000094 223. Data Sheets - MWO 1T<000095 224. Letter to Director, IE/NRC, from L. R.

Block, QA Engineer, IMO, dated 5/12/BL;

Subject:

Additional Information to Supplement Letter of 4/29/88 225. Operation and Maintenance Manual, Appendix VII, Alarms and Safety Shutdowns (pp.

8-8, 8-8A) 226. Precedure No. 29101-C, Rev.

1, Emergency Lighting Surveillance (FSAR Fire Protection Surveillance), 12/5/89 227. Procedure No. 00414-C, Rev.

7, Operating Experience Program, 11/29/89 228. Procedure No. 11885-C, Rev. 10, D/G Operating Log, 5/11/89 228-1 Data Sheets, DG1A - 3/20/90 228-2 Data Sheet, DG1B - 3/23/90,

229. Videocassettes - GPC, Vogtle, March 1990 D/G Tests 230. Bechtel Drawings:

230-1 Lube Oil Piping Schematic 1X4AKO1-27-11 220-2 Starting Air Piping Scbcm.* tic *.XtAKn1 70 1?

27

.. = --

a

U 230-3 Jacket Water Piping Schematic 1X4AK01-26-11 230-4 4160V INCM.BRKR 152-1BA0319 (DG 1B) 1X3D-BA-D03D 230-5 4160V INCM.BRKR 152-1AA0219 (DG 1A) 1X3D-BA-D02D 231. Operating Experience Close-Out Packages for the following:

IN 88-36 IN 86-101 IN 87-23 IN 80-20 IN 84-42 IN 89-64 GL 87-12 IN 89-67 IE Bulletin No. 80-12 232. PROPRIETARY DOCUMENTS (INPO):*

SER 60-83 SER 79-84 233. Transcript:

Telephone Ccnference w/IIT, Licensee (4/11/90) 234. NRC Personnel Interviews:

4/11/90 234-1 S. Shankman, NRR 234-2 C. McCracken, NRR 234-3 H. Ornstein, AEOD 235. Maintenance Work Request (MWO 19001563) indicating when malfunction (communications failure) was recognized 236. Precedure to Test Annunciator Including First-Out (VEGP-1,1-3KJ,03,Rev.1) 237. VEGP Plant Review Board Meeting Minutes Which Include Discussion of Plant Condition on 3/20/90 238. Note to A. Chaffee, IIT, from R. Jones, RSB, dated 4/11/90;

Subject:

Documents Requested by IIT 239. MWO No. 19000909 (Data Concentrator) 2/22/90 240. Drawings:

240-1 Field Change Requests; Reference Drawing Numbers:

2X4AXO1-260 R/8 - Eng. Cont. Pnl. Schm.

2X4A<01-498 R/8 - Elec. Schm.

2X4AX01-361 R/8 2X4AX01-369 R/8

  • NOT TO BE RELEASED 28

240-2 VEGP Procedure No. 50009-C, As Built Notice No.

89-V1MO70A001 (1/18/90) 240-3 Bechtel Drawings:

1X4AK01-42-11 Engine Control Panel Installation 1X4AKO1-52-9 Engine Control Panel Schematic 1X4AK01-357-9 A.C. Schematic 1X4AK01-358-8 Control Schematic 1X4AK01-443-4 Engine Pneumatic Schematic 1X4AK01-458-7 Instrument Identification Schedule 2X4AK01-367-8 Engine Control Panel Schematics (2) r 2X4AK01-428-5 Engine Pneumatic Schematic 2X4AK01-459-6 Instrument Identification Schedule 241. Receiver Air Pressures Observed by Plant Personnel on 3/30/90 242. History (Unit 1 - From First RHR During Second Refueling Outage to Initiation of 3/20/90 Event) Defining " Windows" of Operational Configurations Potentially Affecting the NSSS, containment, and Supporting Systems 243. Licensing Document Change Request Pkg. No. FS 88-99-Rev. 1 244. Description of Electronic Data Reading ERF, Proteus and Fault Recorder 245. Transcript:

Telephone Conference w/IIT, Licensee, R-II (4/12/90) 246. NRC Persennel Interviews: 4/12/90 246-1 K.

Brock =an, R-II 246-2 S. Ebneter, R-II 246-3 F. Rosa, NRR 247. Outage Scheduling Infor=ation 248. RAT Scheduling Information 249. PRT, RCS, RWST, SG, TS Infor=ation 250. Letter tc C.

K. McCoy, GPC, from J.

L. Tain, Westinghouse, dated 3/16/90, w/RHR B Pump Vibration Data 251. MWO No. 1 0014'?, J/40/90 (D/G 1D)

I 29

U 252. MWO No. 19001433, 3/20/90 (D/G 1A) 253. MWO No. 19001537, 3225/90 (D/G 1B) 254. MWO No. 19001576, 3/28/90 (D/G 1A) 255. MWO No. 19001684, 3/31/90 (D/G) 256. D/G Punction Checkout Data 257. Transcript (unnonitored tape recording):

Teleconference w/IIT, Licensee, R-II (4/3/90) 258. Transcript:

Telephone Conference w/IIT, Licensee, R-II (4/13/90) 259. Transcript:

Telephone Conference w/IIT, Licensee, R-II (4/16/90) 260. GPC Personnel Interview:

R. Odon, G. McCarley, M. Sheibani (4/17/90) 261. VHS Audiocassetje:

Calibration Tests on Tenperature Sensor for D/G (4/18/90) 262. Meeting Attendance Records:

IIT Entrance Briefing (4/17/90); IIT Exit (4/18/90) 263. MWOs:

263-1 No. 18906592 - Containment Equipment Hatch (12/23/89) 263-2 No. 18906593 - Personnel Hatch (12/23/90) 264. Calcon Tenperature Switch Response Test on 4/4/90 265. Note to D.

Gustafson and K. Burr from R. Jones (GPC),

4/13/90; Sub-j ect:

Vibration Readings on Tenperature Switch Piping - 1A Diesel 266. Drawings:

As Built Notices No. 00517 No. 00121 No. 00122 30 m

.u.-.

Y i

267. Bechtel Drawings:

One Line Diagrams 1X3D-AA-E17A, Rev. 6 - 480V Switchgear 1BB16

^

1X3D-AA-E07A, Rev. 7 - 480V Switchgear 1BB07 1X3D-AA-E06A, Rev. 6 - 480V Switchgear 1BB06 1

1X3D-AA-E10A, Rev. 9 - 480V Switchgear 1NB10 1X3D-AA-D03B, Rev. 9 - 4160V Switchgear 1BA03 1X3D-AA-D03A, Rev. 8 - 4160V Switchgear 1BA03 1X3D-AA-E01A, Rev. 11 - 480V Switchgear 1NB01 1X3D-AA-E04A, Rev'. 6 - 480V Switchgear 1AB04 l

1X3D-AA-E05A, Rev. 8 - 480V Switchgear 1AB05 1X3D-AA-D02B, Rev. 6 - 4160V Switchgear 1AA02 1X3D-AA-D02A, Rev. 8 - 4160V Switchgear 1AA02 1X3D-AA-E16A, Rev. 5 - 480V Switchgear 1AB15 1X3D-AA-A01A, Rev. 16 - Unit 1 268. Deficiency Tracking System l

269. Containne7t Penetration Control Package (Procedures and i

Surveillance Task Sheets) 270. Letter to All Holders of RO and SRO Licences for PWRs from T.

E. Murley, NRC/NRR, dated 11/3/88;

Subject:

Operator l

Diligence While in Shutdown Conditions l

271. Letter to H.

P. Allen, Southern California Edison Co.,

from T.

E. Murley, NRC/NRR, dated 12/2/88;

Subject:

Loss of Decay Heat Renoval i

272. Calibration Data Sheets for Pressure Switch 273. Annunciator Response Procedures for ALB-09 i

273-1 Panel 1C1 on MCB 273-2 Panel 2C1 on MCB 274. ERT Conputer Points (continued) j 275. Training Student Handout - RHR System 1

276. Annunciator Response Procedures for ALB 36 on EAB Panel 277. Conoseal Status and Description at Time of site Area Energency on 3/20/90 (Note:

Drawing No. 1X6AB02-288-1 i

contains proprietary data *)

472. Procedure. No. 00200-C, Rev. 5 - Hazardous Substat. c ar.1 we.cre Contec1 (10/24/89)

  • NOT TO EE RELEASED 31

N Containment Building Penetrations Verification - Refue. ling 279.

279-1 Procedure'No. 14210-1, Rev. 4 279-2 Procedure No. 14210-2, Rev. 2 280. Bechtel Drawings:

Containment Building Piping Areas 281. Westinghouse Drawing:

Safeguard Actuation System -

PROPRIETARY

  • 282. Drawings:

Electrical, Control Systems, Mechanical, Nuclear Pressurizer Press control Steam Dump Control Rod Controls Steam Generator Trip Signals 283. Security Vehicle Log -3/20/90 284. NRC Personnel Interview:

J.

Calvo, NRR 285. MWOs:

285-1 No. 19001482 - D/G 1B 285-2 No. 19001542 - D/G B 285-3 No. 19001677 - D/G A 286. Deficiency Cards:

286-1 No. 1-88-3016 - D/G A 286-2 No. 1-88-3083 - D/G B 286-3 No. 1-88-3453 - D/G 1A 286-4 No. 1-90-0182 - D/G 1A 287. Infcrmation Notice No. 90-25:

Loss of Vital AC Power with Subsequent RCS Heat-Up 288. Interoffice Memorandum to C. K. McCoy, GPC, from M. J.

Ajluni, GPC, dated 10/16/89;

Subject:

Vogtle's Operations Experience Program Assessment 289. INPO Database KEYWORD; DIESEL 290. Vogtle Status of NRC and INPO Operating Experience Doicument Reviews as of 4/18/90 291. Bechtal D*avinos Rel&ted te Lighting

  • NOT TO BE RELEASED 32

m 292. Bechtel One-Line Diagrams:

~

Non-Class 1E Distr.' Panels i

480V Motor Control Center 293. Bechtel Drawings:

1K4-1208-486-01, Reactor Mead Vent 1K4-1201-064-02, RCS

~

2X6AB02-66-4, Reactor Vessel General Arrangements 294. VHS Audiocassette Tape:

D/G Local, Control Room, Sequencer, TSC Local; Counter Nos.:

0000-363 Procedural Steps to Reset Sequencer (3/29/90) 0364-969 DG1A Sensors (3/31/90) - Lube Oil High Temperature Switch, Lube Oil Low Pressure Switches, Jacket Water Temperature Switches, Turbo 011 Pressure Switch, Jacket Water Pressure Sensor and Governor 0970-1004 Back of DG1A Control Station 1005-1380 Tested Emergency Lighting 1381-1507 Scanned DG1A Control Panel

-1508 Headset and Extension Cord

-1536 Normal and Emergency Jacks for Cord 1550-1614 Overview of DG1A Room 1615-1668 Inside of DG1A Control Panel Showing Sensor Lines 1669-1810 Front of DG1A Control Panel Showing Emergency Start Button Using Break Glass Instrument (or Unscrew Glass) 1811-2207 Walkthrough of Emergency Start Procedure, SOP No.

13145-1, Section 4.4.3 (2043)

Operator Aid Needed:

Trips on Front Panel 2208-2837 First Out Walkthrough, Noting Annunciator Trips Provided (2289)

Operator Aid:

Stand for Procedures (2423)

Required by ARP to Log First Out and Report to Control Room (2544)

Tested Annunciators Using Annunciator Response Control Buttons (2740)

Must Report All Major Functions and Malfunctions (DG Trips, First Out According to Admin. 10000 Procedure; also 13145, 14980); If Tripped, Logged and Reported to Engineering 33

1 l

2838-2925 Front of DGlA Panel; Magnetized Procedure Book; Ties on First Out Discussed (Two valid Trips Simultaneously); one Reactor Trip is Eliminated or Might Not Work 2926-2993 Communication Phones:

Gaitronics, Commercial Headphones, Sound Powered, and Extension Cords (25 feet) 2994-3311 Technical Support Center 3312-3430 DG1A Annunciator and Control Panels (3329) -

Sticker on C-9 for MWO and Another Sticker (3400)

First out on Reactor Trip Shown (3429)

First out Response Control Buttons for Reactor System 3431-3500 Safety Parameter Display System (SPDS)

-3505 PROTEUS i

-3517 ERF 3526-3804 Walkthrough of Control Boards (3535)

Plant Status Monitoring System (RVLIS, Incores, etc.) on Plasma Screen (3621)

Relevant Indications (3636)

Reactor Vessel Level and RVLIS, Scanned (3680)

NCSW System (3703)

CCW System (3732)

RHR System (3800)

Tower Platform in Control Room 3805-3844 Jacket Water Temperature Sensor in I/C Shop 3845-4179 Unit 1 Control Room (4/2/90)

(3855)

Description of Response Control Buttons in Control Room for DG1A:

ACK, RESET, TEST, Including Contrast of What Happens at DGlA Local Control Station (4130)

Reactor Trip; First Out Described and Shuwn 4180-4322 Turbine Trip (on Back Panel); First Out Explained, Including Response Button Controls; Electrical Hydraulic Control Cabinet Shown (4290)

First Hit and Electrical Malfunction Reset Explained 4440-4934 DG1A Control Station (4625)

How to Clear F6 (Switch Not in Auto);

Clears Itself 4680-4878 Summary of What Operator Has to Do to Clear Audible Response Condition; Alarm Goes Solid (If in series, Silence, Acknowledge, Reset)

(4878)

How Operator Knows Condition is Cleared 492/.

END 34

.v 295. Spare Temperature Sensor Calibration Data 296. Test Procedure No. 17133 297. Security Access Printout for M. Lackey and S. Chessnut (3/20/90) 298. Letter to C. K. McCoy, GPC, from J. ' L. Tain, Westinghouse, dated 4/20/90;

Subject:

Vogtle, Unit 1, Vent Rate Through Reactor Vessel Head, Thermocouple Assemblies 299. Calcon Temperature and Pressure Switch Data (3 Volumes) 300. Letters to NRC Document Control Desk from W. G. Hairston, III, GPC, dated 4/19/90; Subjects:

300-1 VEGP LER, Loss of offsite Power Leads to Site Area Emergency 300-2 VEGP LER, Unit 2 Reactor Trip from Unit 1 Reserve Auxiliary Transformer Feeder Line Fault 301. Security Logs for Entering and Exiting Control Room, Containment, D/G Room (3/20/90) 302. PROPRIETARY DOCUMENTS (INPO)*

Operating Experience closecut Packages for the Following:

IN-81-09 SER-5-83 SER-38-83 SER-76-84 SER-36-87 SER-5-89 SER-74-81 SER-78-81 SER-87-8 O&MR-295 SER-15-87 SER-26-89 303. Wyle Laboratories Test Results - Temperature Sensors (submitted 4/26/90) 304. Response to Questions Regarding Containment LCO Logging, RCS Level, Gravity Feed

  • Not TO BE RETTASED 35 s

cm, o

I 305. Event Data Collection System - Equipment Locations Sketch 306. Wyle Laboratories Test Results - Temperature Sensors (submitted 4/27/90) 307. Unit 1 Control Log for 3/19/90 through 3/21/90 (pp. 5281-5287) 308. VEGP Plant Review Board Meeting Minutes Prior to the Event (3/2/90 through 3/19/90) 309. Wyle Laboratories Test Results - Temperature Sensors (submitted 4/30/90) 310. MWG for Head Removal / Replacement 311. Core-Exit Thermocouple Channel Calibration 312. Steam Generator Draving 313. RER Pump B Modification Data 314. Wyle Laboratories Test Results - Temperature Sensors (submitted 5/1/90) 315. Test Procedure for As-Received Testing and Calibration of Seven Calcon Model A3500-W3 Temperature Sensors (4/30/90) by Wyle Laboratories for GPC 316. VEGP Procedure No. 93240-C, Rev. BT, Reactor vessel i

Assembly / Disassembly Instructions 317. MWO No. 18905286 - #036 Check Valve 318. Letter to GPC, Attn. K. S. Burr, from Wyle Laboratories, dated 5/2/90;

Subject:

Reliability Evaluation Testing of Calcon Model A3500-W3 Temperature Sensors 319. Infor=ation Notices 319-1 No. 82-20 319-2 No. 86-09 319-3 No. 83-17 319-4 No. 83-51 319-5 No. 85-28 319-6 No. 85-73 319-7 No. 85 01 319-8 No. 84-69 319-9 No. 84-e9, Supplement 1 36

~..

o 319-10 No. 86-73 319-11 No. 88-75 319-12 No. 89-87 320. IE Bulletin 77-01, Pneumatic Time Delay Relay Satpoint Drift 321. IE Circular 77-16, Emergency Diesel Generator Electrical Trip Lock-out Features 322. MWO for Accumulator Isolation Valve 323. Note to W. Lyon, IIT, from J. F. D'Amico, GPC, dated 5/2/90; Re: Information on Seal Table 324. Pressurizer Detail Drawing 325. MWO for Charging Line Check Valve 036 and 035 326. Wyle Laboratories Test Results - Temperature Sensors (submitted 5/4/90) 327. Bechtel Drawings of Accumulator Isolation Valve 328. Clearance Sheet for Reactor Head Vent 329. Instruction & Operating Manual Series X12 & X16 Models Solid State Annunciator Systems 330. PROPRIETARY DOCUMENTS (INPO)

  • Operating Experience closecut Packages for the Following:

SOER 83-01 SOER 81-10 SOER 83-06 O&MR 97 O&MR 110 O&MR 334 SER 82-78 SER 82-079 SER 09-85 SER 25-85 SOER 86-003 SER 89-028 SOER 85-001 (also includes82-008 and 84-007)

SER 84-72 SER 88-031

'h0T TO BE RELEASED 37

<xam v i

O 331. Operating Experience closecut Packages for the Following:

IN 77-01 IN 80-41 IN 82-20 IN 83-17 IN 83-51 IN 84-69 (and Supplement 1)

IN 85-28 IN 85-73 IN 85-91 IN 86-70 IN 86-73 IN 88-75 IN 89-87 332. Wyle Laboratories Test Results - Temperature Sensors

-(submitted S/7/90) 333. Operating Experience Closecut Package for IMO Report 334. Deficiency Card No. 1900125 - S/G Manway 335. Bechtel Drawings:

Swing Check Valve 3-C88; Motor Op. Gate Valve Mod. 10001GM99FNH010 336. Draft " Corrective Actions for Site Area Emergency" and Unit 1 Status Report from 3-18 to 4-1-90 (submitted by licensee) 337. Memorandum to H. Wyckoff, EPRI, fro = J. O'Brien, EPRI, dated 5/11/90:

Subject:

Nuclear Plant Worker Capabilities Under Extreme Environmental Conditions 338. Letter to NRC Document Control Desk, from W.

G. Hairston, III, GPC, dated 5/14/90;

Subject:

Vogtle Electric Generating Plant Corrective Actions for Site Area Emergency 339. Cooper Industries Test Results - Pressure Sensors and Shutdown Logic Board (submitted 5/15/90) 340. Motor Control Center Load Lists for 1NBS, INBI, and 1ABA to 1ABF 341. Wyle Laboratories Test Report (Preliminary), dated 5/12/90,

" Reliability Evaluation Testing of Ten Calcon Model A3500-W3 Temperature Sensors" 342. List of Personnel On Site on March 20, 1990 38

su.

o I

343. Procedure No. 00150-C, Rev. 10, Deficiency Control (5/10/90) 344. Photographs - Switchyard Where Incident Occurred (Affected Pole, Puel Truck, Fallen Insulator) 345. D/G 1B Troubleshooting Plan; Procedure 22981-C, Calcon Pneumatic Temperature Sensor Calibration (telecopy received 5/24/90) 346. Unit One "B" D/G Sensor Testing Sequence of Events -

Preliminary (telecopy received 5/24/90) 347.

Unit One "B" D/G Sequence of Events (telecopy received 5/29/90) 348. Telephone Conversations at NRC Headquarters Operations Center on March 20, 1990 348-1 Unmonitored Transcript 348-2 Memorandum from E. Weiss, AEOD to C. Siegel, IIT, dated May 31, 1990;

Subject:

Transcript of Telephone conversations Relevant to the Vogtle Event 349. GPC Interoffice Correspondence from J. E. Swartzwelder to Department Heads dated 1/13/89; Re:

Deficiency Control and QA Audit and Surveillance Finding Trend Report for Vogtle Unit 1 350. Test Report No. 17133-1, " Reliability Evaluation Testing of Ten Calcon Model A3500-W3 Temperature Sensors," by Wyle Laboratories for GPC (May 12, 1990) 351. Letter to M. W. Hodges, NRC, from R. A. Newton, EOG, dated November 21, 1988, with enclosure, WCAP-11916 352. NRC Inspection Manual, Temporary Instruction 2515/101, " Loss of Decay Heat Removal" (GL 88-17) 353. NRC Inspection Manual, Temporary Instruction 2515/103, " Loss of Decay Heat Re= oval" (GL 88-17) " Programmed Enhancements (Long Term) Review" 39 N

--

Retrieved from "https://kanterella.com/w/index.php?title=ML20058K812&oldid=4470817"