ML20217D497
| ML20217D497 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/24/1993 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20217D186 | List:
|
| References | |
| FOIA-97-252 NUDOCS 9710030249 | |
| Download: ML20217D497 (115) | |
Text
_ .- _ - _ . _ _ . _
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I August 24, 1993
(
MEMORANDUM FOR: Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety FROM: Albert F. Gibson, Director Division of Reactor Safety
SUBJECT:
CHARTER FOR BRUNSWICK 1 READINESS INSPECTION The subject inspection should be scheduled for the period September 20 through October 1,1993 and should include the following evaluations of quality assurance, engineering, and operations:
e Ouality Assurance: Our 1992 appraisal of Brunswick Operations identified
" lack of critical self-assessment" as a root cause of 1
performance deficiencies. You should evaluate action planned and the effectiveness of ar. tion taken to improve performance in this area. Your inspection should include evaluation of assessments by QC and NAD and of the response of the line organization to these assessments.
Enaineerina: Your inspection should determine if significant deficiencies exist in tha processes for control of timeliness and quality of engineering work products.
The inspection should include evaluation of the processes for evaluation and prioritization of engineering backlogs and for maintaining the Q-List of safety related components.
Ooerations: Your inspection should determine if operators have been trained and procedures have been issued for plant modifications made during the current outage including reactor vessel water level and wet well vent modifications. In addition, the inspection should include assessments of the backlog of operator work-arounds and of the operations staffing and management oversite planned foc restart.
(0RIGINAl. SIGNED BY A. F. GIBSON)
Albert F. Gibson cc: S. D. Ebneter, RA E. W. Merschoff, DRP J. P. Jaudon, DRS j J. R. Johnson, DRP
- w. G. Rogers, DRS (bec see page 3) i
" l 9710030249 970929 1 PDR- FOIA k, " [B/5 3b^b fD{
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Thomas A. Peebles - 2 August 24,-1993 l
I bec: R. Prevatte. SRI
. C. Christensen. DRP D. Verrelli, DRP I
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M BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL n
4, # .
BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL PURPOSEt The ORAT Counterpart Team is to provide any information, documentation, and service required for the successful management of the Operational Readiness Assessment inspection at Brunswick.
l l
QMECTIVESt
- 1. Demonstrate the readiness of BNP r1 return to service by preparing for and responding to issues raised by the ORAT in a thorough and professional manner.
- 2. Eliminate any negative beliefs, impressions, or opinions expressed by the ORAT by demonstrating that the issue of j concern is known and is receiving the appropriate level of attention and action.
l
- 3. Provide efficient, professional, WORLD CLASS, care of the ORAT members.
EXPECTATIONSt
- 1. No new issues are identified.
- 2. There is no confusion or misunderstanding on the part of the ORAT.
- 3. Effective communication is maintained at all times between the ORAT and CP&L, and between the Counterpart Team and BNP.
- 4. All issues are pursued and satisfactorily resolved.
- 5. Prompt action is taken to answer any question and close any issue.
- 6. The ORAT leaves with a positive impression of BNP and its readiness to operate.
C:WISCcRAT. MAN Page 2 of 14
. s l BNP ;
l OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL 1
l OPERATIONAL READINESS ASSESSMENT TEAM MEMBERS 1 i j Peter Koltay Team Leader Stephen Guthrie QC/ Safety Verification / Management Staffing i Mike Markley Surveillance and Testing
! Andy Kugler Engineering and Technical Support Neil Hunemiller operations / Simulator Training Tom Johnson Maintenance / operations shift Activities l 5
Charles Payne operations / Simulator Training l
Ken Johnston Engineering and Technical Support
- Gene Carpenter QC/ Safety Verification / Management Staffing 4
i i
i 4
4 i
J l
1 4
i s
t 1
CAMISOORAT. MAN Pass 6 of 12 l
BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL SCHEDULE March 23 12:00 ORAT arrives onsite for " bagman" trip 13:00 ORAT badging 16:00 ORAT plant tour (conducted by Regulatory Compliance)
March 24 09:00 - Entrance meeting - Assembly Room 10:00 ORAT/ Counterpart Meeting following Entrance 13:00 - Systems and procedures review with 16:00 Counterpart Team March 25 09:00 - Systems and procedures review with 11:00 Counterpart Taam March 29 - ORAT onsite for inspection April 8 Location 2-018/020 09:00 Daily ORAT/CP&L Meeting 16:00 Daily Counterpart Team Meeting April 2 16:00 Counterpart Team audit meeting April 9 10:00 - ORAT Exit 12:00 Assembly Room C;4Gm0 RAT. MAN Pase 3 of 14 m
s BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL ORAT COUNTERPART TEAM NAME ORGANIZATION PHONE BEEPER Robert Godley Regulatory 457-2412 754-1199 (Team Leader) Compliance Jeanne McGowan Regulatory 457-2136 Compliance Annette Pope Operations 457-2670 754-0564 Dati Jeans way Terry E&RC 457-2526 754-1177 Chris Patterson Maintenance 457-2274 754-1193 Harlee Bordeaux QC 457-2359 754-1945 Bob Poulk Training 457-2314 754-0496 Neil Blair Work Control ? ?
Mike Bradley NAD 457-2235 754-1944 Ron Knott NED 457-3341 754-0433 Jack Turner 457-3428 -
Lee Gard Tech Support 457-2619 754-1171 C:\MLCORAT. MAN Page 4 of 14 3
BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL ORAT PREPARATION The purpose of an operational Readiness Assessment is to provide major input for the NRC's decision to allow BNP to resume power operation. For this purpose, the ORAT will examine safety significant activities such as control room operations, critical maintenance activities, and surveillances. In addition, major plant programs will be reviewed such as management work controls, use of operating Experience Feedback, self assessment capability, training, and Quality Assurance effectiveness.
It is vitally important that each member of the Counterpart Team be familiar with the status of the activities of his or he-organization and knowledgeable of the issues which are critical to BNP. Each member should review the various inspection reports from INPO, the NRC, and NAD for applicable issues and be prepared to provide information on how these issues are being resolved.
Additionally, schedules of major activities for the period of the inspection should be obtained.
Communications between organizations should be maintained to ensure responses to the issues are uniform and consistent.
C:4nmORAT. MAN Page 3 of 14
s l BNP l OPERATIONAL READINESS ASSESSMENT
- COUNTERPART TEAM MANUAL OPERAkiONAL READINESS ASSESSMENT TEAM MEMBERS
- I f Peter Koltay Team Leader i Stephen Guthrie QC/ Safety Verification / Management Staffing Mike Markley Surveillance and Testing I
Andy Kugler Engineering and Technical Support
] Neil Hunamiller Operations / Simulator Training l Tom Johnson Maintenance / operations Shift Activities Char'es e Payne Operations / Simulator Training 3
J Ken Johnston Engineering and Technical Support Gene Carpenter QC/ Safety Verification / Management Staffing
?
C;4GScollAT. MAN Pass 6 of 14 4
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I BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL OPERATIONAL READINESS ASSESSMENT MANUAL Attachment I is a copy of NRC Inspection Manual 93806, Operational Readiness Assessment Team Inspections. This manual will be used by the operational Readiness Assessment Team to conduct its '
inspection. A review of this manual will provide information on the scope of the inspection.
Attachment II is a copy of NRC Inspection Manual 0350, Staff Guidelines For Restart Approval. This manual establishes guidelines for approving restart of a nuclear power plant after a voluntary or involuntary shutdown as a result of a significant event, complex hardware problem, or serious management deficiency, including the development and review of a restart checklist for use by the NRC.
Attachment III is a copy of NRC Inspection Report 50-260/91-201 Browns Ferry Unit 2 Operational Readiness Assessment Team Inspection conducted in February through March of 1991.
Attachment IV is a copy of NRC Inspection Report 50-260/91-202 Browns Ferry Unit 2 Operational Readiness Assessment Team Followup Inspection conducted in April, 1991.
Attachment V is a copy of NRC Inspection Report 50-446/92-201 Comanche Peak Operational Readiness Assessment Team Inspection conducted in January of 1993.
The Counterpart Team members should review these documents for information relating their respective areas.
CAMEN. RAT. MAN Page 7 of 14 i
(
l BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL
- zona The attached forms are to be used by the Counterpart Team to facilitate efficient tracking and management of issues arising from l the ORAT inspection. In addition, these forms will be used to
] provide documentation of the interaction between CP&L and the ORAT.
I The individual Counterpart Team members are responsible for ensuring that those in their organizations who interact with the
- ORAT have been briefed on the use of the forms. In addition, the team members should ensure that the personnel in their respective areas are aware of the guidance provided by CP&L to employeen
, concerning NRC inspections and investigations.
Individuals interviewed or questioned by the ORAT are requested to complete an Interview Documentation Form. Completion of this form is not mandatory, i k'he Question Tracking Form (QTF) must be used to document all i questions and requests received from the ORAT. This form will be used to facilitate clear communications between CP&L and the ORAT, l track emerging issues, identify startup concerns, document resolution, and provide a mechanism with which to communicate concerns to BNP management.
The individual being asked the question is responsible for documenting the question on the QTF.
The questioned individual shall then have the ORAT inspector i review the question to ensure that the question, as written,
- is the question asked.
! The questioned individual shall then submit the QTF to the ORAT Counterpart Team for processing. -
l The appropriate Counterpart Team member shall assign a number, make two copies of the QTF, and assign an indc'idual with responsibility for answering the question.
The original QTF will be provided to the individual with responsibility for answering the question. The copy will be forwarded to the Counterpart Team leader for logging into the t
ORAT question database.
- C
- 403C@ltAT. MAN Pass 8 of 14
[
BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TE/M MANUAL Each Counterpart Team member is responsible for providing a status of open questions at the daily Counterpart Team meeting.
Once devaloped, the Counterpart Team member shall make a copy of the response or answer and:
If no commitments or startup issues are involved, present the original to the NRC ORAT inspector. If accepted, the Counterpart Team member shall provide the copy to the NRC ORAT inspector and return the original to the Counterpart Team leader for processing into the database.
If commitments or startup issues are involved, return the answer or response to the Counterpart Team leader for management review and concurrence. Once CP&L management concurrence has been obtained the Counterpart Team leader shall return the respc."se to the Counterpart Team member for submission to the ORAT inspector or to the responding individual for revision as appropriate.
If the response or answer is deemed unacceptable or in need of clarification by the ORAT inspector, the Counterpart Team member shall so note on the QTF objection and/or the request for clarification and return it to the Counterpart Team leader for processing and to the responding individual for resolution.
Note: The information on the QTFs will be loaded into a database on the lan. The file le in Q&A 4.0, Us\RC\0RATQTF To facilitate the daily Counterpart Team meetings, each Counterpart Team member should fill out a Daily Debrief Form to document impressions, issues raised, questions asked, and answers provided, c.\M1moltAT. MAN Page 9 of 14
j l
e BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL INTERVIEW RECORD FORM i serial # Date:
Interviewee:
NRC Inspectors COMPLETE THE FOLLOWING (USE ADDITIONAL SHEETS AS HECESSARY)
- 1. What were the major topics discussed?
- 2. What questions were asked?
(complete Question Tracking Forms as necessary and attach to this form)
- 3. What concerns were exprested by the NRC inspector?
- 5. Other comments C:405coRAT. MAN Pge 10 of 14
BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL QUESTION TRACKING FORM ,
Question #: DATE:
l submitted by:
GMT Inspector Question or request Responding Individual Response due data Responses commitment made? Yes / No Startup requirement? Yes / No Commitment COMMITMENT TRACKING NUMBER:
(Assigned by Regulatory Compliance)
Followup requested by the NRC7 Yes / No Dates Additional action required (if any):
C:SuSCWRAT.MW Page il of 14
e BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL QUESTION TRACKING FORM INSTRUCTIONS It is vitally important that communications between CP&L and the ORAT are clear and complete. In order to facilitate this, individuals asked questions by the ORAT who cannot provide an immediate answer or which involve comsitments or startup issues are to complete this form.
Question #: Assigned by Regulatory Compliance l Date: Pill in the date in which the question was asked.
Submitted by: Fill in your name.
ORAT Inspector: Fill in the name of inspector asking the question Question or Till out the question or request and submit request: it to the ORAT inspector for verification that the question written is in fact the question that was asked. Make any revisions as necessary.
Responding Fill out the name of the individual to whom individual the question will be submitted to provide a response.
Response due date: Fill in.the date by which the response is to be provided to the ORAT inspector.
Make two copios of the form. Send one copy to the Counterpart Team leader to be logged in and the other to the individual assigned to answer the question.
I CMGSCM) RAT.W N Pags it of 14
,, l BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL QUESTION TRACKING FORM INSTRUCTIONS Response The individual assigned to provide the response to the question shall fill out this portion of the form. Attach additional sheets if necessary.
Cor.mitment made? If the response results in a commitment, indicate by circling yes and submit the response to the Counterpart Team leader for management review. If management concurs with the commitment, the form will be returned to the submitter for delivery to tho ORAT inspector.
Startup If the response results in a startup requirement? requirement or prestartup issue, submit the response to the counterpart Team leader for management review. If management concurs, the form will be returned to the submitter for delivery to the ORAT inspector.
Commitment: If the response involves a commitment, state the commitment in this area. Attach additional sheets as necessary.- Regulatory compliance will assign a FACTS action number to the commitmont once management concurrence has been obtained.
Followup If no further clarification is requested by requested by the ORAT inspector, indicate by circling no the NRC? and date the form in the area provided. If additional clarification is requested, indicate by circling yes and fill out the request on an additional QTF. Attach the original QTF with the nesw form and reroute.
Additional action List any additional actions which may need to required (if any): be taken for followup prior to routing of the
- completed form to the Counterpart Team Leader.
C:\MISOORAT. MAN Page il of 14
l e l
- l BNP OPERATIONAL READINESS ASSESSMENT COUNTERPART TEAM MANUAL DAILY DEBRIEFING REPORT s.rt.1 si ontei Counterpart Team Member ORAT Inspectors contacted overall Impression (s):
Issue (s) Raisedt Question (s) - Attach QTFs C:SQsC% RAT. MAN Pass 14 of 14
e i 8 Unit 2' Annun'Jictcr Statua Report Dato: 05/07/93 Shitt 19-07 P go 1 000 Lichted Annunsictcr Liot 000
{
2-A-4 1-8 STEAMLINE LO PRESS A hw ,,d ,,,33 I
Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - RX PRES < 850#
/UM d Status 2-A-4 2-8 STEAMLINE LO PRESS B Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - RX PRES < 8506
. Status 2-A-5 4-5 MSL CLOSURE TRIP BYPASS Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - NODE SWITCH NOT IN Status: RUN 2-A-5 5-5 PR CTNT HI/LO PRESS jpn. / Mode L Date Initiated: 05/05/93 WR/JO: 93-APZG1
,).,u Reason: p:q jy Status: y, 2-A-5 5-7 TURB STOP VLV CLOS TRIP Node L Date Initiated: 04/29/93 WR/JO:
Res. son: ACTUAL CONDITION - STOP VALVES CLOSED Status:
2-A-5 6-7 TURB CV FAST CLOC/SV/RPT TRIP DYPASS Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - RX POWER < 30%
Status 2-A-6 1-7 LPRM DOWNSCALE Mode L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION Status 2-A-6 3-2 RECIRC FLOW A LIMIT Mode: L Date Initiatad: 04 L2.3/93 - WR/JO:
ACTUAL CONDITION -QFW FLOh Act c i
2-A-6 6-3 PUMP A SEAL STAGING FLOW HI/LO Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - LOW Status
e Unit 2 Annun31st r Status Report D3to: 05/07/93 Shift: 19-07 Pug 3 2
, 000 Lichted Annunciot:r Lict 800 2-A-7 2-4 RECIRC FLON B LIMIT Mode: L Date Initiated: 04/29/93 WR/JO Reason: ACTUAL CONDITION - FW FLOW < 20%
Status:
2-A-7 5-5 PUMP B SEAL STAGING FLOW HI/LO Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - LOW
.. Status:
2-UA-23 3-4 E MOIST SEP LEVEL-LOW i Date Initiated: 04/29/93 Mode L WR/JO Reason: ACTUAL CONDITION - MSR NOT IN SERVICE l Status:
2-UA-23 3-5 W MOIST SEP LEVEL-LON Mode: L Date Initiated: 04/29/93 WR/JO i Reason: ACTUAL CONDITION - MSR NOT IN SERVICE Status 2-UA-23 4-4 E RENEATER FIRST STAGE LEVEL HI LO Mode: L Date Initiated: 04/29/93 WR/JO: NA Reason: ACTUAL CONDITION - MSR NOT IN SERVICE Status:
2-UA-23 4-5 W REHEATER FIRST STAGE LEVEL HI LO Mode: L Date Initiated: 04/29/93 WR/JO:
Reason:
Status:
2-UA-23 5-1 TURBINE BYPASS VALVES OPEN Mode: L Date Initiated: 05/05/93 WR/JO:
Reason: ACTUAL CONDITION Status:
2-UA-23 5-4 E RENNATER 2ND STAGE LEVEL HI/LO Mode: L Data Initiated: 04/29/93 WR/JO NR Reason: ACTUAL CONDITION - MSR NOT IN SERVICE Status:
2-UA-23 5-5 W REHEATER 9ECOND STAGE LEVEL HI-LO Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - MSR NOT IN SERVICE Status:
Unit 2 Annun310tcr StOtuo Rcp3rt Dato: 05/07/93 shift: 19-07 POgo 3 000 Lichted Annungioter Lict 000 3
2-UA-13 1-7 GEN PCB A OPEN ,
Mode L Date Initiated: 04/29/93 WR/JO 1 Reason ACTUAL CONDITION - U/C 1 Status:
g ,c (,,,gu $nWre (0 yd L*d 2-UA-13 1-8 GEN PCB B OPEN Mode L Date Initiated: 04/29/93 WR/JO Reason: ACTUAL CONDITION - U/C ,
.. Status 2 - t'? - 6 5-2 CB MECH RN BSTR FAN 2A-BF.CB FAIL Mode: L Date Initiated: 05/02/93 WR/JO: 92.ATAC1 I
Reason: FAN OFF Status: INTERRUPTED 2-UA-4 1-4 RFP B TURBINE TRIPPED Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION Status 2-UA 4 2-10 HD DEAERATOR LEVEL HIGH-LOW Mode: L Date Initiated: 04/29/93 WR/JO 93-ANTW1 Reason: FAULTY LEVEL SWITCH Status: PLANNED 2-UA-4 3-8 FW HEATER 2A LEVEL HIGH-LOW Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: HEATER NOT IN SERVICE Status 2-UA-4 39 FW HEATER 25 LEVEL HIGH-LOW Mode: L Date Initiated: 04/29/93 WR/JO:
Reasont HEATER NOT IN SERVICE Status:
2-UA-4 4-8 PN HEATER 3A LEVEL HIGH-LOW Mode L Date Initiated: 04/29/93 WR/JO:
Reason: HEATER NOT IN SERVICE Status:
2-UA-4 4-9 FW HEATER 3B LEVEL HIGH-LOW Mode: L Date Initiated: 04/29/93 WR/JO Reason HEATER NOT IN SERVICE Status:
e Unit 2 Ahnunsicter Stotuo R: port Dato: 05/07/93 Shift: 19 07 Pcg3: 4 000 Lichteu Annunsictor Liot 800 2-UA-4 5-5 RFP A SEALWATER LOW FLOW /MI DP Mode L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL l CONDJTION - SEAL WATER ISOLATED Status: Sq u/ fro m W ,b r y , y o. q ,L 2-UA-4 5-9 FW HEATER 4R LEVEL HIGH-LOW Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: HEATER NOT IN SERVICE
.. Status l
2-UA-4 6-2 RFP A TURB OIL COOLER TEMP HIGH I Mode: L Date Initiated: 05/05/93 WR/JO 93-AQMA1 ,
Reason: '
Status 2-UA-4 6-5 RFP B SEALWATER LOW FLOW /HI DP Mode: L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION - SEAL WATER ISOLATED Status:
2-UA-1 1-5 CW SCREEN A Mode: L Date Initiated: 05/05/93 WR/JO 93-AQGB1 Reason: DIFF HIGH OR STOPPED Statues p &(&l (/r &
2-UA-1 6-10 RFP B MCU UNDERVOLTAGE Xode: L Date Initiated: 04/25/93 WR/JO Reason: MI-10-519F PAGE 11 LOCAL Status IN PROGRESS 2-UA-3 1-7 AREA RAD MONITORS DOWNSCALE Mode: L Date Initiated: 04/29/93 WR/JO: 93-AIQS1 Reason: ARM 2-29 DOWNSCALE Status: PLANNED 2-UA-3 1-8 DEMIN WATER STROAGE TANK LEVEL HI/LO Mode: L Date Initiated: 05/01/93 WR/JO:
Reason: FAILED LEVEL TRANSMITTER Status 2-UA-2 1-6 HYDROGEN IN GENERATOR PRESS HI-LO Mode: L Date Initiated: 04/29/93 WR/JO Reason: ACTUAL CONDITION - PRESS LOW Status
I Unit 2 Annun31cter St.otus Report DatO: 05/07/93 shift 19-07 P g0: 5
- 000 Lichtcd Annun31ct r Lict *00 1 2 UA-2 2-10 H2 VENT LINE PRESS NIGH Mode
- L Date Initiated: 04/29/93 WR/JO:
Reason: ACTUAL CONDITION DUE TO PURGING PROC.
Status gggy/g 2-UA-2 2-3 MOTOR SUCTION PUMP RUNNING
- Mode
- L Date Initiated: 04/29/93 WR/JO, Reason: ACTUAL CONDITION
. Status 2-UA-2 4-2 TURNING GEAR OIL PUMP RUNNING l
Mode L Date Initiated: 04/29/93 WR/JO: i Reason: ACTUAL CONDITION <
Status l 2 UA-2 5-4 MAIL OIL PMP DISCH PRESS LOW FAIL Mode L Date Initiated: 05/03/93 WR/JO Reason: ACTUAL CONDITION Status 2-UA-2 6-10 GEN CORE MONITORING TROUBLE Mode: L Date Initiated: 04/29/93 WR/JO Reason: ACTUAL CONDITION - NO FLOW, DEENERGIZED Status 2-UA-5 2-1 DRYWELL CHILLER TRIP Mode: L Date Initiated: 05/01/93 WR/JO Reason: ACTUAL CONDITION Status 4p, 4/,,)
2-UA-12 6-2 CHILLER CLG. TOWER Mode: L Date Initiated: 05/05/93 WR/JO: 93-APUN1 Reason: A FAN SNUTDOWN Status 2-UA-25 1-3 CONTAINMENT ATMOS DIV II O2-H2 HIGH Mode: L Data Initiated: 05/05/93 WR/JO:
Reason: DIV II O2 H2 HIGH Status: ACTUAL CONDITION 2-UA-25 2-7 CONTAINMENT ATMOS DIV I O2-H2 HIGH Mode: L Date Initiated: 04/29/93 WR/JO Reason: ACTUAL CONDITION Status:
1 #
i.
1 Unit 2 Annunsict2r stotus Rep 3rt Dato: 05/07/93 shift 19-07 POgo 6
- 000 Lighted Annun310ter Lict 000 2.UA-25 4-5 CAD LN2 STOR VAC LO j Mode L Dste Initiated
- 05/01/93 WR/JO: 93-ANNF1 1 Reason: ACTUAL CONDITION 4
Status: PRESCNEDULED !
1 I
i 2-UA-28 5-3 CMLORINATION SYSTEN TROUBLE Mode: L Date Initiatedt 05/07/93 WR/JO: i Reason: CL - CAN BE CONNECTED
. . Status TRIP CALIB UNIT CARD OUT OF FILE 2-UA-41 1-2 i Mods: L Date Initiated: 04/23/93 WR/JO j Reasons
- Statues i l
[ 2-UA-44 1-3 VRIP CALIn UNIT SIGNAL TROUELE
} k ode L Date Initiated: 04/29/93 WR/JO i Riason:
l 3.atus i
i 2-UA-44 4-1 2ND STAGE l Mode: L Date Initiated: 05/05/93 WR/JO:
) Reason: DILUTION STN FLOW T.ON l 5tatus: ACTUAL CONDITION ;
i j 2-UA-44 4-3 AFTER CNDSR COND. LEVEL HIGH/ LOW j Mode: L Date Initiated: 04/29/93 WR/Jos
- kaason: ACTUAL CONDITION - LON
, 54ntus J
l i 2-UA-44 4-4 HV(C SYSTEN TROUhLE i Mrdes L Date Initiated: 04/2P/93 WR/JO Reason: SYSTEM SHUTDOWN utatus: 1 i"
2-UA-48 5-3 AOG SYSTEN OUTLEY FL3W/ TEMP HIGN i Mode: L Date Initiated: 0505933 NR/JO: l l Reason: ACTUAL CONDITION j Status i
i 2-UA-48 6-2 AOG BLDG RAD HIGH Made: L Date-Initiated: 05/01/93 WR/JO: ' 93-AJIF1 Reason: INVESTIGATING Status INVESTIGATING i
j i
E
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__ _ ~ _ -- .. . . _ . - . _ _ - . _ _ _ . - - . _ - - . . - - . - - _ - . - - - - _ - . . - - - - . - - - _ _ _ . - .
e Unit 2 Annun310 tor StOtus R port Dato: 05/07/93 Shitt 19-07 Pcg3: 7 3
000 Lightcd Annunciotar Liot 000 !
2-UA-45 1-3 TRIP CALIB UNIT SIGNAL TROUBLE Node: L Date Initiated: 04/29/93 WR/JO Reason:
Status 2-UA-45 4-1 2ND STAGM Mode: L Date Initiated: 05/05/93 WR/JO Reason: DILUTION STN FLOW LOW
. Status: ACTUAL CONDITION 2-UA-45 4-4 HVAC SYSTEM TROUBLE Node: L Data Initiated: 04/29/93 WR/JO:
Reasona SYSTEM SHUT DOWN Status
SUMMARY
- Lighted: 57 *****
e C9&L Carolina Power & Light Company Brunswick Nuclear Plant April 27,1993 MEMORANDUM TO: C. Robertson J. Titrington M. Hoffley G. Miller Startup Duty Managers FROM: J. Anthony Dobbs l
SUBJECT:
First Assessment Hold Point, AP.2 As described in our Startup and Power Ascension Performance Objectives and Management Plan, the first of four Assessment Hold Point (AHP) reviews is scheduled for April 28 from 4:00 PM 6:00 PM in TAC, Conference Room 1 B.
l l
Managers should be ready to discuss current conditions and emergent issues withir, their organizations since their affirmations of reaJiness in accordance with OPN-31. Since this first AHP is contemporaneous to our recent affirmations, significant additional information is not expected. This AHP will however, confirm our readiness for rod pull and will gain approval from the NRC to achieve enticality on Unit 2. Topics for discussion include:
i e Performance of plant systems and equipment, o Nature and quantity of emergent material discrepancies.
Performance of personnel during the execution of operations, testing, and maintenance activities, and, e
Adequacy of procedures and processes to support startup and continued plant operations.
Discussions from each organization should focus on these topics addressing the issues, corrective actions taken, and long term action plans where performance is less than expected. Subsequent Assessment Hold-Point reviews during our power ascension will focus on the effectNeness of actions taken to correct less than expected periormance.
The agenda for Wednesday's meeting is attached, kW- -
g L
JAD/tsc Attachment
(
cc: C. S. Hinnant R. A. Anderson R. L Prevatte 4
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f AGEMDA Assessment Nold-Point, AP-2 Wednesday, April 28, 1993 4 00 PM - 6:00 PM TAC, 1-3 I. Operations............................ John Titrington II. Maintenance........................... Mike Heffley III. Technical Support..................... Garry Miller IV. E & R0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Carlton Robertson
- v. Temporary organisation................. Duty Managers The purpose of this meeting is to present our readiness to proceed with pull-to-criticality to the Unit 2 Plant General Manager and to address any issues' that arise.
The Unit 2 . Plant General Manager will then request permission from the Site Director, operations and the Vice-President, BNP to continun with reactor startup.
The Vice-President, BNP will then contact the Region II Administrator with the NRC to gain final approval for rod-pull.
_. . . _ _ . _ _ _ _ _ _ _ . _ _ _ _ , . _ _ . ._ _ _ _ _ . . _ - _ , _ __. -_ ._ _ _ _ _ _ _ . . ._ _ m . _
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$ 101 MARitTTA ST Rttf.N.W.
ATLANT A.GEoRol A 30333
, %, . . . . . p' AP8 9 1993 Docket Nos. 50 325, 50 324 License Nos. DPR 71, DPR 62
- Carolina Power and Light Company ATTH
- Mr. R. A. Watson Senior Vice President
- Nuclear Generation P. O. Box 1551 Raleigh, NC 27602 Gentlemen:
SUBJECT:
BRUNSWICK UNIT 2 RESTART ISSUES On January 22, 1993 and March 10, 1993,
. requestod that Emergency Diesel Generator CarolinaPower&LightCompany(CP&L)d (EDG) No. I testin uirements an the methodolog or post-startup, respectively, be revised. y for establishiing corrective actions as pre g req We have evaluated your submittal on EDG No. I and are satisfied that its crankshaft is adequate to meet its intended function. Further, your root cause analysis of the damuged compor.cnts and thair repair is satisfactory, and the performance of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliability run un EDG No. 1 is acceptable.
, We have also reviewod your char.9es to Drunswick Nuclear Plant Procedure PN-30,
, Integrated Recovery Methodology. We concur that the changes to the procedure
! will still provide an adequate review and approval process for the unit's backlog of items.
l Furthermore, we have reviewed your Unit 2 Startup and Power Ascension Perfor-mance Objectives and Management Plan. We concur with your Logic Plan of AssRssment llold points and Decision Points. As discussef. in the April 5, 1993 meeting, you will obtain concurrence of the Regional Administrator prior to proceeding past each assessment hold point.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter will be placed in the NRC Public Document Room.
Sincerely, f . .. $ W9W
.b 111s W. erschoff, Director Division of Reactor Projects cc: (See page 2) .
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t UNITED STATES ofM* D ,$o,, NUCLEAR REGULATORY COMMISSION RecioN n
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- j' 101 MARIETTA STHEET.N.W.
AT L ANT A, GEOROl A 30323
/ APR 9 1993 Docket Nos. 50 325, 50 324 License Nos. DPR 71 DPR 62 i
i Carolina Power and Light Company l ATTN: Mr. R. A. Watson Senior Vice President l Nuclear Generation P. O. Box 1551 Raleigh, NC 27602 Gentlemen:
SUBJECT:
BRUNSWICK UNIT 2 RESTART ISSUES On January 22.-1993 and March 10, 1993. Carolina Power & Light Company (CP&L) rcquested that Emergency Diesel Generator (EDG) No. I testin the methodology for establishing corrective actions as pre g or requirements and post-startup, respectively, be revised.
We have evaluated your submittal on ElG No. I and are satisfied that its-crankshaft is adequate to meet its intended function. Further, your root cause analysis of the damaged components and their repair is satisfactory, and the performance of a 24-hour reliability run on EDG No. 1 is acceptable.
We have also reviewed your changes to Brunswi' Nuclear Plant Procedure PN 30, Integrated Recovery Methodology. We concur w t the changes to the procedure will still provide an adequate review and approval process for the unit's backlog of items.
Furthermore, we have reviewed your Unit 2 Startup and Power Ascension Perfor-mance Objectives and Management Plan. We concur with your Logic Plan of Assessment Hold point:: and Decision Points. As discussed in the April 5, 1993 meeting, you will obtain concurrence of the Regional Administrator prior to proceeding past each assessment hold point.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter will be placed in the NRC Public Document Room.
Sincerely, a
%[.kh16W
& 111s W. erschoff, Director Division of Reactor Projects cc: (See page 2)
. .s 2 93 Carolina Power and Light Company 2 cc: R. A. Anderson Ms. Gayle B. Nichols Vice President Staff Counsel Brunswick Nuclear Project SC Public Service Commission l P. O. Box 10429 P. O. Box 11649 j Southport, NC 28461 Columbia, SC 29211 i M. Brown Plant Manager Unit 1 Brunswick Steam Electric Plant P. 0. Box 10429 Southport, NC 28461 C. Warren Plant Manager Unit 2 Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 Mr. Mark S. Calvert Associate General Counsel ,
Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 Kelly Holden Board of Commissioners P. O. Box 249 Bolivia, NC 28422 Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environment, Health & Natural Resources P. O. Box 27687 Raleigh, NC 27611 7687 H. A. Cole Special Deputy Attorney General State of North Carolina P. O. Box 629 Raleigh, NC 27602 Robert P. Gruber Executive Director Public Staff - NCUC P. O. Box 29520 Raleigh, NC 27626 0520
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NLMORANDUM FOR: Stewart D. Ebne ur kenional Administrator ikon: Jon R. Johnson. Deputy birector Division of Reactor Pro.iects bllDJLCI: bhuuSWICK UNIT 2 RESTART STATUS 1 hi s nmmor and un. is to inform you of the status of Carolina Power and Light Enmpany's (CP8L) actions to implement the Drunswick Confir mator y Action Letter (CAL) dated December 10. 1992.
On opril 21. 1992. bruni.witL Units i and 2 shutdown oue to seitmic concerns with the reinforced masonry w.J15 separating the emergency dichel generators (LDD).
Following the shutdoun, additional civil and structural concerns were identified.
On July 23. 1992, 'P&L submitted its Pre-startup Plan. the first version of its improvenient plan with specific corrective actions needed to be talen. Revised plans for the Corporate Improvement Initiatives (CII) and the lirunswick Three-Year Plan were submitted on November 30. and December 15, 1992, respectively.
The actions specified in Enclosure 3 of the July 23, 1992 letter acre confirmed in the CAL. The cal additionally confirmed inspection and repair requirements for the EbGs.
In addi tion to the short-term actic , rtquired prior to startup of Unit 2, your letter of June 23, 1992, required CP8L to address long-term corrective actions to address root causess of performance problems: (1) establish management expoetations and standardst (2) improve senior management involvement with the sta. ion including oversight and communications: (3) correct process deficiencies in the work control process and (4) rectif y the inef fective self-assessment and cor r ective action programs. In response, the licensee developed the CII and the Drunswick Three-Year Plan. These actions have resulted in new CP&L management 1 rom the Pret.ident and Chief Operating Of ficer to the Plant Manager, changes in the Brunswich site organization. new oversight committees, improved self-assessment, and new work control processes. Progress in these areas is tufficient to see finprovemen ts at Brunswick. Furthermore, the licensee has orced to meet at least every two months to discuss the progress in implementing the CII and the Three-Year Plan.
lused on the independent inspections and reviews conducted by the NRC staf f and described in Enclosure 1 (Brunswick Restart Review Plan) and Enclosure 2 l (brunswick Speci fic Restar t Ist.ucs), the licensee has satisfactorily completed:
(1) the Unit 2 related corrective actions committed to in Enclosure 3 of the July 23,1992 letter s (2) 24-hour endurance test runs on all four ED0s following thorough inspection / repair activities; and (3) reviews of equipment, personnel and proceues to assure readiness for restart.
An Operational Readiness Assessment Team (ORAT) inspection from March 29 to April 9 1993, concluded that the depth and capability of the CP&L staff, the organization structure and interfaces, and in-place programs are adequate to suppori Unit 2 restart and operations. The four weaknesses identified by the )
l ORAT (i.e.. alternate safe shutdown drill, main tenan ce procedure backlog, l-
0 i Stewart 1). Ebneter <
maintenance backlog, and operator aids) have been addressed by the licensee and verified by inspection lo be adequate to support Unit 2 restart.
Dated on these independent inspections conducted at Et ru'iswi c k, the staff (Region 11 and NRR) recommends approving the resumption of routine operations of Drunswick. Unit 2 in accordance with the facility Technical Specification. In accordance with Regional Office Notice No. 2201, dated April 9,1993, Augmented Inspection coverage will be in place to monitor and assess the startup. This coverage commenced on- April 27, 1993, and wil1 continue until the unit has demonstrated successful steady state operation.
4 i
4 Jon R. Johnson i
Enclosures:
- 1. Restart Review Plan
- 2. Drunswick Specific Startup Issues w/ attachment .
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-Stewart D. Ebneter RII DRP RII DRP RII DRP R11:DRP RII DRS RII DRP RII DRP PCarro11stj idiolbrook C0gle L0arner JLonahan RPrevatte HChristensen 04/ /93 04/ /93 04/ /93 04/ /93 04/ /93 04/ /93 04/ /93 RII DRS RII DRS RII DRS RII DRS RII DRSS RII:DRP HRR J1tlake NShymlock CJtilian TPeebles ItCline DVerrelli PMilano 04/ /93 04/ /93 04/ /93 04/ /93 04/ /93 04/ /9304/ /93 NRR NRR RII DRS RII DRSS JMitchell SVarga AGibson PStohr 04/ /93 04/ /93* 04/ /93 04/ /93
t Stewart D. Ebneter ENCL.0_pVRE 1 RESTART REVIEW PLAN DRUN3 WICK _ STEAM ELEC_TRIC STATJ_0_N I. RESTART CONDITIONS IMPOSED THROUGH CONFIRMATORY ACTION LETTER OF DECEMBER 18, 1992 A. Licensee Completion of Specific Issues Described in Enclosure 3 to CP&L Letter of July 23, 1992 ACTION RESP. STATUS ORG.
_._ _. ___._~ _. ___ . .. .
. . . . . nunumanyequem numaganummmmmmmmum A Equipment Cerrosion Problems Inspect for. completion of repairst Al Service Water Lubrication t:ater pipe R-II l03/04/93 C supports IR 93-02 A2 Verify completion of walkdown of non-pipe R-la 04/23/93 C support STSI items and pipe supports. IR 93-15 Inspect repairs complete for identified deficiencies.
A3 Seismic instrument racks R-II 77t??t?? C IR 93-16 Verify acceptability of drywell liner = /C22@ 04/23/93 C corrosion repair. 48 IR 93-15 B Deferred Equipment Maintenance Issues.
Inspect for completion of repairs /testina Di Spring tension on 400 VAC emerg bus R-II 77t??t?? C feeder breakers IR 93-19 B2 UPS primary inverter. Unit 1 R-II 12/03/92 C IR 92-42 B3 Battery discharge testing. Unit 1 R-II 12/03/92 C IR 92-42 D4 Turbine-exciter coupling chanaecut and R-II 01/28/92 C alianment. Unit 2 IR 92-44 B5 Turbine partial are admission R-II 01/20/93 C modification. Unit 2 IR 92-44 D6 Turbine control valve power packs and R-II 02/26/93 C chanae out of EHC accumulators. Unit 2 IR 93-01
t Stewart D. Ebneter D7 4L cylinder inspection on EDD-3. R-II 02/02/93 C IR 93-03 Review video inspection records and NRR/ENED 03/04/93 C evaluation of root cause of high exhaust IM temperature.
A. Licensee Completion of Specific issues Described in Enclosure a to LP&L Letter of July 23, 1992 (Continued)
ACTION RESP. STATUS ORG.
B0 Reactor feed pump 2D wear rina R-II 02/26/93 C IR 93-01 B9 [See "V. ITEMS TRACKING FOR COMPLETION POST-STARTUP"3 D10 Emera busses current transformers R-II 12/03/92 C IR 92-42 B11 Stack rad monitor isokinetic probe mods R-II 10/02/92 C IR 92-25 C Potential Structural Deficiencies.
Inspect for completion of repairs:
C1 Phase 1 (reactor buildina) and Phase 2 R-II 04/23/93 C
, (drywell) MSVP walldowns. Verify IR 93-15 adequacy of procedures for walldowns.
Review bounding load studies, and NRR/ECOB 10/14/92 C evaluate procedures and acceptance LL criteria for structural steel deficiencies.
C2 Restoration of 5 reinforced concrete non- R-II 03/04/93 C load bearina wall panels in EDO Buildina IR 93-GI _
C3 Masonry block walls structural anale R-II 03/04/93 C restraints in EDO Duildina IR 93-02 Review safety evaluation of walls based NRR/ECOD 04/23/93 C on noted deficiencies. LL C4 Review to verify appropriate R-II 03/04/93 C classification on non-safety masonry IR 93-02 walls C5 Removal of non-functional through bolts R-II 03/04/93 C in EDO buildina walls IR 93-02 C6 Intearity inspection of safety-related R-II 04/23/93 C masonry block walls IR 93-15
e Stewart D. Ebneter -
6-C7 Repairs to upgrade Control Building R-II 03/04/93- C seismic walls needed for post DBE IR 93-02 habitability C8 Review of IE Dulletin 80-11 Program and R-II 03/04/93 C address deficiencies noted IR 93-02 4
e .
Stewart D. Ebneter A. Licensee Completion of Specific Issues Described in Enclosure 3 to CP8L
, Letter of July 23, 1992 (Continued)
ACTION RESP. STATUS ORD.
C9 Qualify EDG exhaust line supports for R-II 03/04/93 C tornado loadina IR 93-02
, Review 50.59 evalaution for combined NRR/ECGD 04/23/93 C effects of short-tere qualified LL structural conditions o"
C10 Review of IE Bulletin 79-k4 Program for R-II 04/23/93 C determine if methods would have IR 93-15 identified masonry wall bolt problem C11 Evaluate li.censee calculations and R-II 04/23/93 C verify input assumptions for interim IR 93-15 seis:nic qualification of SWS pumps NRR/ECGD 04/23/93 C SE ,
r C12 Evaluate (c.blel STSI Program NRR/ECGD 10/14/92 C 3 ',4 g SE
??t??t??
R-II C
- ) IR 93-20 I C13 Repairs of retirc system ring header R-II 04/23/?3 C hanaers IR 93-15 i C14 Desian and installation of additional R-II 03/04/93 C supports for SWLW pipino IR 93-02 C15 Seismic repairs of NCCs R-II 03/04/93 C IR 93-02 D Dacklogs of Temporary Conditions and Operator Work-Arounds.
Inspect for adequacy of corrective measures D1 STSI temporary conditions la stated goals R-II 04/02/93 C IR 93-10 D2 Hon-STSI temporary conditions to stated R-Il ??t??t?? C acals IR 93-16 D3 Reduce number of operator work-arounds to R-II 04/02/93 C stated goals IR 93-10
, ORAT 04/16/93 C LL D4 Reduce backloa of corrective maintenance P<-II 77/77/77 C to stated coals IR 93-16 ORAT 04/16/93 C LL
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Stewart D. Ebneter A. Licensee Completion of Specific Issues Described in Enclosure 3 to CP&L Letter of July 23. 1992 (Continued)
ACTION RESP. STATUS ORO.
mumuumummunmuummuummummmmmme DS Reduce backlog of preventative R-II ??/??/?? C maintenance to stated goals IR 93-16 ORAT 04/16/93 C 4
LL Review implementation of Proc. PN-30 to R-II 04/23/93 C prioritize maintenance backlog IR 93-16 ORAT 04/16/93 C LL E Equipment Deficiencies Discovered During Walkdowns Inspect for' completion of repairs:
El Hot side waltdown inspections * ' R-II 03/04/93 C IR 93-02 ORAT 04/16/93 C LL 4 E2 Cold side walldown inspections 2 R-II 04/02/93 C IR 93-10 OPAT 04/16/93 C LL F Other Specific Items.
Vrrify completion or inspect as needed:
F1 CSne "V. ITEMS TRACKING FOR COMPLETION POST-STARTUP"]
F2 Repairs to neutron monitorino detectors R-II 02/26/93 C IR 93-01 F3 Unit i Secondary Containment Isolation R-II 03/30/93 C Test IR 93-12 F4 4tV bus cross-tie modification R-II 12/03/92 C IR 92-42 Review of ongoina maintenance and ORAT 04/16/93 C surveillance activities LL Review Brunswick Unit 2 Integrated R-II s' '0 ' '?: - C Startup Plan LL CAJ A.
- naterial Condition Walt. downs of areas agreed to by DSLP and R-11 o
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4 Stewart D. Ebneter ,
B. Correction of Deficiencies with Emergency Diesel Generators a
' ACTION '
RESP. STATUS ORG.
_ ununumuseumummuuammungsmusum Inspect repairs and testing on EDG-1 R-II 04/02/93 C IR 93-10 i Verify satisfactory completion of inspection R-II 04/02/93 C of other EDGc IR 93-10 4
Review licensee's failure and fatioue NRR/ENEB 03/24/93 C analyses reports on EDO-1. Prepare letter NRR/EELD .351 3 LA i addressing EDG-1 endurance testina.
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r Stewart D. Ebneter C. Readiness Review of Equipment and Personnel ACTION RESP. STATUS ORO.
sammusumununusnum Monitor performance of PN-31. Line. ORAT 04/16/93 C Management Self-Assessment of Readiness for LL Restart of BNP Unit 2. .
De mt impact o inas . s. R-II 77/77t!? C s iedu l e , , ORAT In, ction. IR 93-19 Monitor conduct of Nuclear Assessment Dept. R-II 77/77t?? C Readiness Restart Evaluation. Det reine IR 93-19 impact of fin nas on readiness. . h dule. ORAT 04/16/93 C and sta of the h RAT Ins b on. LL Verify successful completion of major activities on integrated S/U Schedule.
including
- a. C ritainment ILRT R-11 03/30/93 C IR 93-12
, b. System Readiness Turnovers, especially ORAT 04/16/93 C common (shared) systems, with emphasis on LL
{ post maintenante testing
- c. Chlorine Detection Modifications R-II 77t??l?? C f --
-w IR 93-16 _
(--d. Completion of Material Walkdowns R-II 04/02/93 C n own Observe operator simulator training. R-II 04/23/93 C including the nuclear engineers, focusing on IR 93-06 start-up, turbine control, and E0Ps. . ORAT 04/16/93 C LL m+. mm-~ -4 ...,,.s.m , m n , s m ,e s,m - %e,,
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@ptis%% tuMWMW FM%C BWMTW Review of Brunswick Procedure PN-30 to R-II 77t??t?? C verify satisfactory prioritiration of IR 93-16 maintenance work items. Sample deferred ORAT 04/16/93 C work items to verify implementation LL acceptable.
Review of Priority 1-4 items that will not R-II 77t??l?? C be completed prior to restart. Confirm the IR 93-16 preparation of enaineering justification and . ORAT 04/16/93 C risk assessments. Veri-fy satisfactory. LL Review justification and safety evaluation R-II 77/77/77 C of Temporary Conditions existing at startup. IR 93-16 En . TC C t - tm Luvi. cvoilaute anu fuii i- ORAT 04/16/93 C i n e n r n n r a t p e, all Tre - LL
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1 Stewart D. Ebneter C. Readiness Review of Equipment and Personnel (Con't)
ACTION RESP. STATUS 1 ORO.
Assess the scope, adequacy, and R-II 77/77/77 C implementation of the Minor Maintenance IR 93-16 Program. ORAT 04/16/93 C LL Neetina with HRC to discuss Motor-Operated HRR/EMED 02/17/93 C Valve Test Program implementation. Review MS the status of open items from submittal of R-II GLD9-10. Inspection Report 50-325,324/91-31, and others noted.
HRC review and acceptance of the Power R-II 04/09/93 C Ascension Plan,' including desired HRC hold LL points.
Assess effectiveness of Manager / Peer R-II 04/02/93 C Observer Proaram (DSEP AI-101) IR 93-10 ORAT 04/16/93 C LL Degin ORAT Inspection NRR/RSID 03/29/93 C Provide preliminary inspection findinas and NRR/RSIB 04/16/93 C recommendation to Regional Administrator. LL Followup with written Inspha. tion Report. HRR/RSID
[See "V. ITEMS TXACKING F00 COMPLETION POST-STARTUP"]
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3 ,a Stewart D. Ebneter II. CORPORATE IMPROVEMENT INITIATIVES AND ltRUNSWICK 3-YEAR PLAN ACTION RESP. STATUS ORG.
mms Assess the CP&L Corporate Improvement R-II 02/01/93 C s
Initiatives and Brunswick 3-Year Plan to LL s ensure that issues identified as root causes NRR/PD21 02/01/93 C" of poor performance have been addressed and. LL appropriate corrective measures developed. NRR/RPEit 02/01/93 C LL Evaluate all proposed schedules for action NRR/PD21 03/15/93 C completion, especially those which are IM changes to previous licensee commitments: HRR/DE 03/15/93 C (See 3-YR Plan) IM NRR/DSSA 03/15/93 C IM 4
R-II 03/08/93 C 1
IN Request additional information on the R-II 03/08/93 C implementation -accountability, and LL acceptance criteria /monitorino for actions.
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. Stewart D. Ebneter III. COORDINATION WITH INTERESTED ADENCIES 1 ACTION RESP. STATUS i
, ORO.
i Federal Emergency Management Agency I
- a. Advise FEMA Headquarters of restart and NRR/PEPB 04/06/93 C determine if there are any outstanding IN issues or concerns regarding offsite emergency preparedness,
- b. Provide information concerning offsite NRR/PEPB 04/06/93 C emergency preparedness to NRR/PD21 and IN Region II.
- c. Inform licensee of any offsite emergency P.-I I 03/05/93 C preparedness concerns. LL
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1 Stew rt 9.'Ebneter 3 IV. ASSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS ACTION RESP. STATUS ORG.
- j. mm NR9 Issue license amendments applicable to
, unit startups
- a. ECCS Instrument Rack NRR/IIICB 02/04/93 C
. LL
- b. CDEAF Chlorine Detection Subsystem NRR/PD21 03/22/93 C LL HRR arant reliefs to 10 CFR 50.55a on ASME NRR/ENCD 02/08/93 C
, Code IST and ISI relief requests LL
- NRR/ENCB 02/23/93 C 5
LL a
Actions to address the Enforcement Action R-II 12/15/92 C for RV water level event have been resolved LL 2
Inform ACRS of restart activities and NRR/PD21 02/05/93 C determine interest in meetina on Drunswick. IM l Prepare Commission Information Paper on unit NRR/PD21 04/23/93 C
} restart. IM R-II to provide input. R-II 03/08/93 C IM Determine need for completion of BWR water NRR/HICD 04/23/93 C level modifications prior to startup. IM NRR/PD21 04/23/93 C IM s -n um . .t . m em .su spumy . , -
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.Melhods for Documentina Closure:
IR - Region II.or NRR inspection report SE - Safety Evaluation Report IM - Internal Memorandum MS - Meeting Summary LL - Letter to licensee T - Target date C - Closure date
??/??/?? --Date IR to be issued
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,. l Stewart D. Ebneter ,
V. ITEMS TRACKING FOR COMPLETION POST-STARTUP A. REGION 11 AND NRR ITEMS ACTION RESP. STATUS ORO.
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Stewart D. Ebneter BRUNSWICK UNIT 1 SPECIFIC STARTUP ISSUES (OPEN AND CLOSED) 4/2e/93 CP8L SUtGECT RESPONSIBLE CLOSURE tt/REF NRC STATUS INDIVIDUAL (IR 11)
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(UNIT 1) COLEY
- F1 CORRECT LEAKAGE ON Uu!T.1.EW.CUECK. VALVE, WHITENER OPEN DRYWELL.C00LEC.AUD MSIV F022B (93-12)
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PM DIGITAL FEEDWATER MODIFICATION (UNIT 1) NELSON 89-001 PM 92-91 RHR SW B00 STER PUMP UPGRADE (UNIT 1) PREVA1TE A2 WALKDOWN OF NON-PIPE SUPPORT STSI ITEMS LENAHAN AND PIPE SUPPORTS IN HIGH CORROSION AREAS A3 SEISMIC INSTRUMENT RACK CURROSION REPAIRS LENAHAN/
(TS CHANGE ISSUED) PREVATTE C1 PHASE I (REACTOR bulLDINOS) AND PHASE II LENAHAN/
(DRYELLS) MISCELLANEOUS STEEL WALKDOWNS BAOCHI AND DOUNDING LOAD STUDIES C12 THIRD-PARTY REVIEW OF STSI PROGRAM LENAHAN Stewart D. Ebneter BRUNSWICK UNIT 1 SPECIFIC STARTUP ISSUES (OPEN AND CLOSED)
CP&L SUBJECT RESPONSIBLE CLOSURE lt/REF tiRC STATUS INDIVIDUAL (IR 11)
C15/LER SEISMIC REPAIRS OF tlCCs LENAHAN OPEN 2-92-05 (93-02)
Di REDUCTION OF STSI BACKLOG (TO BE CLOSED PREVATTE INCONJUNCTION WITH 50.59 INTEORATED REVIEWS)
D2 REDUCTION OF .1EMPORARY CONDITIONS PREVATTE D3 REDUCTION OF OPERATOR WORK-AROUNDS PREVATTE D4 REDUCTION OF CORRECTIVE MAINTENANCE OUTAGE PREVATTE DACKLOG
, D5 REDUCTION OF PREVENTIVE MAINTENANCE OUTAGE PREVATTE BACKLOG El ll0T SIDE WALKDOWN INSPECTION PREVATTE/
LENAHAN E2 COLD SIDE WALKDOWN INSPECTION PREVATTE/
LENAHAN e
Stewart D. Ebneter Attachment 1 INSPECTION ITLMS DESIONATED BY NRC DRUN3 WICK ASSESSMENT PANEL AS REQUIRING REVIEW BEFORE UNIT 2 RESTART IJErl SUlGECT LEVIEW DOCUMEHI LER 2-90-00 Reactor trip due to blown feedwater logic fuse IR 93-01 LER 2-90-16 Reactor trip due to blown feedwater logic fuse IR 93-01 LER 2-92-03 CBEAF outside design basis IR 93-10 LER 2-92-06 Missing CRD scram discharge IR 93-15 line pipe supports LER 2-92-08 NSW through-wall pipe leakage IR 93-10 to ED0s LER 1-92-12 Deficient EDO building wall IR 93-15 seismic support bolting and inadequate fire barrier wall gap material
, LER 1-92-16 Inadequate fire seals around IR 93-19*
EDO pedestals LER 1-92-17 Incomplete closure of ITE type IR 93-19*
K-3000 breaker contacts LER 1-92-18 Failure of CBEAF to meet single IR 93-16*
failure criteria P21/91-05 Potential f ailure of Smit 00 1R 93-01 torque switch roll pins P21/91-07 Shaft cracking on Sulzer IR 93-19*
Bingham Reactor Recirculation Pumps IFI 90-19-04 Long-term corrective action IR 93-06 for operator training VIO 91-01-01 Failure to meet procedure IR 93-10 prerequisites (work control)
VIO 91-02-01 Improper 0-ring Ittbricant on IR 93-16*
E0 solenoid valves VID 91-02-02 Installation and testing unpacked IR 92-44 valves t
Stewart D. Ebneter ll!iti EQi9ECT REVi[_W DOCUNEld (cont'd)
VIO 91-06-02 Failure to perform diesel repairs IR 93-10 with approved procedures (work con tr ol )
VIO 91-06-03 Failure to follow procedure and IR 93-10 perform double verification (work control)
VIO 91-26-01 Failure to follow procedures or IR 93-10 inadequate procedures (worL control)
IFI 91-28-02 Review offsite training course IR 93-18*
description and documentation V10 92-01-01 Inadequate procedure during IR 93-10 EDO cleahing (work control)
DEV 92-04-01 Failure to meet commitment IR 92-44 regarding PMTR V10 92-06-01 Failure to conduct EP related IR 93-04 training VIO 92-11-01 CBEAF nystem inoperable IR 93-10 VIO 92-11-02 NAD performina inspections in IR 93-01 areat assessing IFI 92-14-01 Evaluate attachm6nts to masonry IR 93-20*
block walls IRI 92-14-02 Complete evaluation and repairs IR 93-15 to pipe supports UNR 92-14-03 Possible deficiencies in HVAC, IR 93-20*
conduit, and structural steel supports VID 92-14-05 Failure to perform timely IR 93-20*
operability review of structural ster't deficiencies VIO 92-15-01 Tailure to conduct engineering IR 93-20*
evaluations VIO 92-15-02 Inadequate procedural controls IR 93-10 VIO 92-15-05 Failure to maintain configuration IR 93-16*
control r
Stewart D. Ebneter 1115 SUBJECT REVIEW DOCUMENT (cont'd)
, VID 92-15-06 -Failure to include safety-related IR 93-13 supports in ISI program IFI 92-16-01 Offsite notification problems IR 93-10*
during 1992 annual exercise f
IF1 92-16-02 Failure of mission teams to IR 93-04 effectively mitigate plant accident r.onditions 1
IF1-92-17-02 Lack of command and control IR 93-04 during aon-radiological hazard IFI 92-17-03 Inappropriate personnel IR 93-04 protective actions during chlorine release IFI 92-17-04 Review security and plant IR 93-04 procedure for commonality of terminology IFI 92-17-05 Review respiratory training for IR 93-04 1
security personnel IFI 92-17-06 Certification program adequacy IR 93-04 regarding toxic gan response IFI 92-17-07 Procedure continuity regarding IR 93-04 non-radiological events URI 92-10-01 Welding qualification of MCC IR 93-02 anchorage
-IFI 92-18-02 Feedwater line problem due to IR 93-15 transient VIO 92-21-02 Inadequate clearances and board IR 93-16*
board walkdowns URI 92-27-01 ISI program systew Soundaries IR 93-13 VIO 92-27-02 Phase II walldown deficiencies IR 93-15 URI 92-27-03 Poten tially overspanned conduits IR 93-15 VIO 92-33-01 Failure to take adequate corrective IR 93-15 action with regard to welding procedure deficiencies VIO 92-34-01 Watchstanding with inactive IR 93-06 license URI 92-34-02 Service water leaks IR 93-01 URT 92-34-03 Welding program problems IR 93-16*
,=
Stewart D. Ebneter lifd1 SUIGEC_L REVI_EW_J_0CUMENT Q
(cont'd)
V10 92-35-01 Failure to follow procedure IF 93-16*
regarding reactor vessel drain down IFI 92-36-01 Upgrade EP training program IR 93-18*
IFI 92-36-02 Develop and implement procedure IR 93-04 for back calculating field data to source term IFI 92-40-01 Recirculation system piping IR 93-20*
4 whip restraint clearance VIO 92-44-01 Overtwrauing RHR valves IR 93-16*
(work control)
URI 92-47-01 Natorial control weaknesses IR 93-13 4 in welding shop issue room VIO 93-02-01 Failure to evaluate corrosion IR 93-15 of U1 and U2 drywell liner plate IFI 93-02-02 Corrosion of Nelson studs on IR 93-20*
RHR SW booster pump embedded plates URI 93-02-03 HSW pump short-term qualification IR 93-15 URI 93 02-04 Pipe support PS 3568 IR 93-15 IFI 93-10-02 Seismic qualification of CAC 1R 93-19*
systems IFI 93-10-03 Molded case circuit breaker IR 93-16%
replacement IFI 93-10-04 TSC/ EOF diesel generator IR 93-16*
deficiencies URI 93-10-06 Deferral of PMs (refuel and IR 93-19*
greater frequency)
- (NOIE: Asterist items have been inspected, but inspection reports had not been issued at the time this list was compiled.)
. - ~ _ . . __ _ _ ._ _ _. _ _.. _ . _ _
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', e REQUIRING RESOLtlTION REFORE BRUN$ WICK UNIT 2 RESTART l $UBJECT REME$
11Di
- P21/91 07 Shaf t cracking on Sulzer 93 16 OPEN (Awaiting review of (Prevatte) Bingham Reactor Recirculation CP&L's final r? port)
Pumps olf! 91-28 02 Offsite Training Course Descriptions To be CLOSED in 93-10 (Sartor)
- lFI 92-14 01 (Lenahan)
Evaluate Attachments to masonary biock walls 92 40 OPEN
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- URI 92 14 03 Possible deficiencies in HVAC, pY M (Lenahan) conduit, and structural steel supports j oV10 92-14-05 failure to perform timely operability 1 33,y q (Lenahan) review of structural steel deficiencies OV10 92 ', 01 failure to conduct timely engineering To be CLOSED with 92 5 05 (Lenahatc evaluations Itg,.tB O eV10 92 21 02 Inadequate clearances and board walkdowns 9316 OPEN (OK - To be evaluated (Prevatte) furtherduringstartup) i olF1 92 40 01 Recirculation system piping restraint i3"IO (Lonahan) olFI 93 02-02 Corrosion of nelson studs on embedded plates 93-LO (Lenahan) olf! 93-10 02 Seismic qualification of CAC systems To be CLOSED in 93 19 5
(Prevat:e) olf! 93 10 06 Deferral of PMs (refuel and greater To be CLOSED in 9319 STeIF (PrevAtte) frequency) 14 g oLER l 92 16 EDG pedestal Rotofoam seals To be left OPEN in 93-19 T -
(Prevatte) EDG Operability not affected) oLER 2-92 17 incomplete closure of ITE K-3000 93-17 OPEN (awaiting resolution (Shymlock) breaker contacts of 4.16 kv circuit breakers) c0 RAT issues ASSD communications, operator (Prevatte) aids, and maintenance procedure revision backlog olR 91 09 EDSFI issues ==4.K 11l@
(Shymiock) ()
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PREVA1TE TO EVALUATE: ROT 0 FOAM 93 08 CD:4/23/93 REMOVAL /EDG OPERABILITY / UNIT RESTART
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OIL ITEMS (SEE ATTACHED) SAR10R OilITEMS(SEEATTACHED) PAYNE CP&L 2X LOCA LOGIC RELAY TESTING SHYMLOCK LETTER DATE0:
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.. .... . . . . . . . . :,....-..<.....< . v wwn,, e.a RESTART REVIEW PLAN BJtDNSWICK STEAM ELECTRIC 51A110N
- 1. RESTART CONDITIONS IMPOSED 1HROUGil CONFlRMATORY ACTION LETTER OF DECEMBER 18, 1992 A. Licensee Completion of Specific issues Described in Enclosure 3 to CP&L Letter of July 23, 1992
. = . .
ACTION RESP. STATUS med N musuunummumummma A Equipment Corrosion D M4f's inspect for completion of cepairst
~
Al Service Water Lubrication Water pipe R II 01/30/93 C supports IR 93-02
' A2 Verify completion of walkdown of non pipe R-II 03/19/93 C support 5151 items and pipe supports. IR 93-15 Inspect repairs complete for identified deficiencies.
A3 Seis'nic instrument racks R-Il 03/31/93 C IR 93-10 Verify acceptability of drywell liner NRR/ECGB 02/28/93 C corros1on repair.__
_ LL B Deferred Equipment Maintenance issues, inspect for completion of repairs / testing:
~
BlSprinftensionionI480VACMemorgEbus ? ~ R-IIl '02/28/93? IT-fender! breakers '
+
-IR 93-17 B2 UPS primary inverter, Unit 1 R !! 12/08/92 C 1R B3 Battery discharge testing, Unit 1 R-!! 12/03/92 C IR B4Turbineexcitercouplingchangeoutand R-il 01/28/92 alignment, Unit 2 C IR 92 44 B5 Turbine:part'iallarc~admissi~n o R 11' 7
" modification; Unit 2 05/04/93 iT
'IR'92 44 B6 Turbine control valve power packs and R II 01/30/93 C i change out of EHC accumulators, Unit 2 IR 93 01 .
B7 4L cylinder inspection on EDG 3. R-Il 01/30/93 0 IR 93 03 Review video inspection records and evaluation of root cause of high exhaust NRR/EMEB 03/04/93 C IM temperature.
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Licensee letter of Completion of Specific Issues Described in Coclostre 3 to CP&L July 23,1992(Continued)
ACTION RESP. STATUS ORG.
manwwwumummuunnamuuammum
'BB Reactor feed pump 2B wear rin9 R-!! 01/30/93 C 1R 93 01 B9Conhol' rod,drivepumpIBi, c RkIIP i'L O5/31/93
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B10 Emerg busses current transformers R-!!
12/03/92 C IR 92-42 Bil Stack rad monitor isokinetic probe mods R-II 10/02/92 C IR 92-25 l C Potential Structural Deficiencies, inspect for completion of repairs: _
ClPhase1(reactorbuilding)andPhase2 R.II 03/05/93 C (drywell) MSVP Walkdowns. Verify IR 93-1S adequacy of procedures for walkdowns.
Review bounding load studies, and evaluate procedures and acceptance NRR/ECGB 10/14/92 C LL criteria for structural steel deficiencies.
C2 Restoration of 5 reinforced concrete non- R-Il 01/14/93 C load bearing wall panels in EDG Building- IR 93 02 C3'Masonryjbiock wallsitiudtUral:a'nfle' , R(II ' " '02/2d/9f.Cl restrai,nts;infEDG' Building? . .;F - -
'IR'93-02l I .Revie'w safet'yleva ation of walls:' based
- NRR/ECdDJ 02/28/93. - Ti on noted deficiencies. ~' ~ ~"
Ll; "
C4 Review to verify appropriate' R II 02/28/93 C classification on non safety masonry IR 93-02 walls C5 Removal of non-functional through bolts R II 01/30/93 C in EDG building walls IR 93-02 C6 Integrity inspection of safety-related R-II 03/05/93 C masonry block walls IR 93-15 C7 Repairs to upgrade Control Building R-ll 02/28/93 C seismic walls needed for post DBE 1R 93 02 habitability C8 Review of IE Bulletin 8011 Program and R-Il 02/28/93 C address deficiencies noted
_._ _IR 93-02
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1.icensee Letter Completlun of Specific Issues Described in Enclosure 3 to CP&l.
of July 23,1992(Continued)
ACTION RESP. STATUS ORG. . .
C9 Qualify EDG exhaust line supports for R il
, tornado loading 02/28/93 C IR 93 02 cReview;50'.I59levalaudon:foricombiriel. -
leffeetstoflshort-tem:qualifled . ' , NRR/"ECGN l03/15/93 "
J. T.
'~ L.L "
.itructural-conditions "
+ 'i' "
i C10 Review of IE Bulletin 79 14 Program for R !!
- 03/05/93 C
! determine if methods would have IR 93 15 identified masonry wall halt problem
' Cll"Edluate llicensee$ai cul ations DaiO l " .
'NRR/ECGBi (02/28/931 ;'T'
'l Verify, input.assumptionssfor! interim ,W ~
SE '4 '
-seismic : qualification of SWS' pumps " .;
Clh"Enlu,' ate lBech@lFSTSI Programh; . ; 1,-
~;9 .. + - ;p .NRR/Er.GB l 'ld/i4/92.
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,H R-!!' ' :lR 03/19/93'93 e15;Q 9 T'.
Cl3 Repairs of recirc system ring header R II 10/20/92 C hargers IR 93-15 Cl4 Design and installation of additional R-Il 01/30/9' C
. supports for SWLW piping IR 93-02 CIS Seismic repairs of HCCs R il 01/30/93 C 1R 93-02
~
0 Backlogs of Temporary Conditions and operator Work-Arounds.
Inspect for adequacy of correctivo measures:
01 STS! temporary conditions to stated goals R-il 04/09/93 C IR 93 10 02 Non STS! temporary conditions to stated R-!!
goals 04/09/93 C IR 93 16
~
D3ReduceEnumber!ofoperatorwod'aroundsto. i iR-l1l !" -04/09/93h C-
" stated goalsi, :f?;' ="
. ,_ . . . IR!93fl0i.
, ,,,'.T'..-.~,
,- , ,. i ORA.Th 04/21/93',',m ' ' TJ
.IR.' W &
D4 Reduce backlog of corrective maintenance R-II to stated goals 04/09/93 C IR 93-16 ORAT 04/21/93 1
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1.icenseo Completion of Specific issues Described in Enclosure 3 to CP&L Letter of July 23,1992(Continued)
ACTION RESP. STA105 ORG.
~
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m ,. ' R I I. :. 04/09/93 ': Cl imaintenance.to stated goalsi. ~
IR 93-16.
a ORAT! 'T l04/21/93
- l R ~ ' '
LReviewLimplementationlof! Proc.;PN 30 to R II- 04/23/93- T:
lprioritizemaintenan.ccbackl,og. ' ~ . M 1R' l. . . 7. "i.
. 1 ., ORAT. 04/21/93. T'
'IR
~
E Equipment Deficiencies Discovered Dur1ng Walkdowns Inspect for completion of repairs:
lEl'llotsside' walkdown ? inspections *".'.w-- IR. ii .F. / '02/28/934 -
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.E2. Cold: side lWalkdown Inspections.'J ' R-ll:
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om 02/28/93 C-IR 93 "
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'04/21/.93
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F Other Specific Items. -
Verify completion or inspect as needed:
.F1 Correct l leakage on:'!
'R-!!! I
'03/05/931 Tl
.'a,.FWcheckvalve' hinge. pin (4 .
, J' ulR. 5 ' '
- b..MSIV.packin9" -
1 T - -
TF c.Drywell. cooler (N2)
F2 Repairs to neutron monitoring detectors R !! 01/30/93 C IR 93 01 F3 i s econda ryjcon t a i nment il s ol a t'i on . . -R'il: 0/05/93; Tl F4 4kV bus cross-tie modification R-II 12/03/92 C IR 92 42
' iReview of ongoing: maintenance Ynili
- survalliance activities
' ~ ..
ORAT . 04/2f/93! T"
'IR ~ ~ ;
ReviewBruswickilntegratedStartup$PI'ani ^ R II. . '03/15/93l JT4 a?,Uniti2 ' ' '
LL:
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nl04/15/93 ' s1
- ~tiaterial Condition ~ Walkdowns of arcas agreed to ti[BELP ggg g-l}
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Correction of Deficiencies with Emergency Diesel Generators Inspect repairs and testing on EDG 1 2.L -
R ll 01/30/93 C IR 93 10 Neriffratisfittery: completion.0f9nspection. Ull: ~ 03/31/93: 1:
of other EDGs' a: ' ~~
~'; "7'
- lRi93e10 j I Review licentae's failure and fatigue NRR/EMER 03/24/93 C analysos reports on EDG 1. Prepare letter IM NRR/EELB
, addressing EDG-1 endurance testing. '
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. .. .... .. .. ....m. .....o. m:= =
mu 4
6-C. Readiness Review of Equipment 6nd Personnel ACTION RESP. STATUS ORG.
tionitor performance 'of PN-31. Lt.ine . R !! .-
Hanagement Self-Assessment of Readiness: for 04/09 T )
Restart of BNP Unit 2.- '
- lR ' /93 - </
Determine. impact of findings on. readiness, R-il' [
schedule,:and NRC ORAT' Inspection. 04/09/93' .T IM Monitor conduct'of.Niscipar Assessment Dept. R-11 -
04/09/93 1 I
Readinoss.Rostart; Evaluation. Determino impact of" findings-on'roadiness, schedule.-
- lR- )d 2
i and start'of the NRC 0 RAT Inspection. -
Verify successful. completion of major.
activities"on:IntegratedS/USchedulo,: _ --
including:= .
' _a
- a. Containment llRT R-II' 02/28/93" C 1R~
b.' System' Readiness Turnovers, especially ORAT'. 04/21/93; _T common l(shared) systems,.with.emphasision- IR-1 c.' post maintenance testing;. .
Chlorine Detection Modifications:
R-II .
03/17/93[, LC ~
IR 93-16 d.J Completion of Material Walkdownsi R-il
- m 03/17/93 C IR 93 Observe operat'or simulator- training.) U . R211 including.the nuclear engineers, focusing on:
, 03/12/93 ' :TJ .
1 IR 1 '
start-up, turtino control;.and.EOPs. ._
ORAL 04/21/93: ~ '
1 IR..
Acceptanto of the completion 'of sp' plicable R-11. 03/20/93: T-
. material maintenance deficiencies. tracked on- :lR 4 Rllstatussummary(otherthannoted-in~ ,
Section'I.A)~.
~
Review of Drunswick Proceduro PN 30 to; R II 03'12/93 verify satisfactory prioritization of: ,- IR~
/ T
-maintenance work items.jSample' deferred: ORAL work ; items' to : verify 3 implementation; 04/21/93 T-acceptable, ,
IRl-ReviewofPriorityIl-4:ltem$5thatNill'not ~
g be completed" prior to restart; u Confirm the '
R-il:
~
04/09/93 'T IR . ' ' _ . '
pre)aration of engineering justification-and. ORAT~. 04/21/93L "T-ris< assessments; Verify satisfactory.- :IR ~
Review justification'and safety evaluation R-Il of Temporary Modifications existing at 04/09/93 1 startup. Ensure TH_ Status Book available :1RL ORAT. 04/2t/93_
and fully incorporates all TMs. " ~
IR" T
is
e
. . . . , . . . . . . . . . . . ~
w vv am- r. u 7
.C. Readiness Review of Equipment and Personnel (Con't)
' ACTION RESP. STATUS ORG.
ammesanamesiame susanimummes Assessftheisco'pe, adequacy.1and i 1 '
m iR '
NM(p f implementation'.ofithe Minor.. Maintenance II' ' 03/12/931 IT.
I R'. . L Program...
ORAT! .. ,04/09/93 i T-1R-Meetin9 with NRC to discuss Motor Operated Valve Test Program implementation. Review NRR/EME8 02/17/93 C MS l
the status of open items from submittal of R-Il GL89-10, inspection Report 50 325,324/91 31,
, and others noted.
Meeting [ widen'CLto"R discuss? electrical' NRR(EELU. 05/12/93:;.JT.
systems modifications and'engineeringt .
. MS :t : . . .
evaluations.wlth regard to licensing.b' asis- NRR/SPSBL 05/12/93:"* 'T; and 'riskcreduction. - ' "~
MSf
~
!!nst'a11ation.of. Hardened Wenell Veri **@ NRR/"PD21l'03/12h3l EIl iompleteL Review-the: 50.59 safety'- :, . . . ' . , ~ IM evaluation;
~
p,.'nll.::
- 7. NRR/SCSBl '03/12/93.. (Tn in NRCirefiew an'd?a'edepidace of the '03/12/93; Ascension lf,lan,Lincludingl, desired lNRC. hold. l Power.Rd ; ... 11
- ,. LL: ^ '" " "
T:.
points'.
'" ' ~"
Assess effectivenessf of man'agenent" walk-
' ' ' ' R !!l .04/09/93I LU downs
.lRE L .
~ ., ,
',~ ORAT: 04/21/93)
- (T!
IR:
- Begin ORAT1 Inspection' ' '.. '. -
Provide:preliminaryLinspectiontfhdings and'
.NRR/RSIB '
03/29/93: I. T
- recommendatiotic to' Regional ' Administrator.
NRR/RSIBL 04/09/93! :Tl Tollowup with WrittenFinspection Report.J IR e ' " -
Review of ORAT' findings:Lforl impact ong. gm R-II. 04/09/93- iTl readinossifor::r'
+ ~ estart.'
. . . IM: m
':. 'NRR.
^'
' 04/09/93 T IM.
.W 89 m_____.__ ___m --
-- . ...-.c... .a , , m ,m,, y,g I 8-
- 11. CORPORATE IMPROVEMENT INITIATIVES AND BRUNSWICK 3 YEAR PLAN
~ ;
~ _.
ACTION RESP. STATUS i ORG.
Assess the CP&L Corporato Improvement R-II 02/01/93 C Initiatives and Brunswick 3-Year Plan to IM ensure that issues identified as root causes NRR/PD21 02/01/93 C of poor performance have been addrersed and IM appropriate corrective measures developed. NRR/RPEB 02/01/93 C IM Evaluateiall'. proposed schedules' foFaction
'NR'R/PD21C ' ' LO3/15/93'4 T:
1 completion 6 :sspeciallt those 'which areW j MS . J. '.
changes lto previous;1icensee commitments:. S -
NRR/DEl, (See3-YR: Plan)-.. e ~
a + 03/16/93 MS N :,.. ' lT 1
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. : _ ,' . 7 , '.
ii:
v
.. - '- , 1RR/ DSS.A'. -
,; g3 03/1$/.93 - @
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03/15/. 93 ;'. :d-I g
nS; 4;, -
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.i. ; ' ..
- Reque s t :. a dd i t i o n a l l.'i ri fo rma t i on ; on"the r implementation,-laccountabilityFand: . : RIIl
,, : 03/12/93 : '"1..T :
LL. '
acceptance ? criteria / monitoring- for. actions. '
' ~ '
! BI'P Closcout: #'
. ! NRR ~ < 0Q01/93 :m?
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9-111.
ASSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS AC110N RESP. STATUS J
ORG.
uunumme====-
NRR lssue lleense amendments applicable to unit startup:
- a. ECCS Instrument Rack NRR/lf!CB 02/04/93 C LL j b. CBEAF Chlorino Detection Subsystem NRR/PD21 03/22/93 C D g.
LL i
NRR grant reliefs to 10 CFR 50.55a on ASME
! NRR/EMCB 02/08/93 C 3
Code IST and 1S1 relief requests ll l NRR/EMCB 02/23/93 C LL
) . Actions to address the Enforcement Action R ll 12/15/92 C l
for RV water level event have been resolved LL
} Inform ACRS of restart activities and NRR/PD21 02/05/93 C determine interest in meeting on Brunswick.
osi IM f
Pf e pa re ' Commi s s i ori91 n f o rma't i on . nee 6tilidjNRR/PD21; it. Lo3/15/9E -;T: <>###
restart.- _ [ . . f y ,% " " ' ? 6- '
- lN? :,
- g- ney . 3 ., -
.+.
...,: ; ') .( .v .
m yw.,1,,,..
R 7il',to'. provide y- input. ,, .
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.03/08/9M "i T '
IM ~~~' '"'
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- Issue. letter!.aftesdetermining
- allCAle -
R- ! !i . ,;-. 04/16/93 'Ti
- Econditionsibeing metiand'authorizes'lisensee; '"
LL;. w:
'totrestart facility-
~
~
pt Det' ermine'needjorcompletioniofBWR!. water. ~NRR/lilCBl. 03/N/93 '*"T level: modifications pri.06 to startupi: ' "
~
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.NRR/PD21- 03
, ~. .
- n/12/937
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IV.. COORDINATION WITH INTERESTED AGENCIES ACTION RESP. STATUS ORG.
mummmmmmmm-federah[mergsnd) Management' Agency-n
~
f:V
- T
'S:-
' 1 .. j,J ., .,
, s. , ;';
. :. J.,
ndvise: FEMA Headquerters of rest'aEUand' NRR/.PEPB, .03/19/93; a'.;
a determiner ;ifJthere are any(outstanding;, ;, . ;1M ; ,, i. . .
<T1 lissues .or: concerns regarding'offsite . ;f
- l
" emergency? preparedness..- ..- .t . . - . . ..H cWM
.b~.,.; Provide information.concerning. of fsits . ~
NRR/.PEPB 03/24/931J.'1..
- emergency. preparednee::.to -NRR/PD21 :and,7 LL' ~ -
, Region ':lliz a . L !.M i - - -
c.' Inform)1icensee 'of- any:offsiteiemergency',: , .R Ili
' > preparedness concerns.~- a . ' ' '
-
- 03/29/93!..:'T
- Lt. -
' Appropriate:Stite and'Yocal OfflElals?
2 R 11
~
.04/05/93F 'T Local! News' Medin' "":n 2 : '
'R D 04/09/93. :T' Methods for Documentina Closure; 1R - Region 11 or NRR inspection report SE.- Safety Evaluation Report IM - Internal Memorandum MS - Meeting Summary LL - Letter to licensee or file T ' Target date C Closure date 4
9 4
e
6 6
"Line Management self-Assessment of Readiness to Restart BNP Unit ,
2", OPN-31 Status summary: April 20 ,1993 Three elements are established within this self-assessment process:
- 1) System Readiness,
- 2) Organisational Readiness, and
- 3) Operational Readiness
- 1) system Readiness The System Readiness element of the restart self-assessment process supplements the methodology detailed within the " Integrated Recovery Methodology" process, OPN-30. The results of the OPN-30 process produced the scope of forced outage work necessary to support safe and reliable operation. Scope addition and deletion methods are also provided with necessary approvals for each. The OPN-30 process essentially concludes for each system with the "Pinal System Readiness Review" for each system, followed by Acceptance by Operations (SOP-4.8) when the outage work scope and other necessary activities required for reactor startup are completed.
The System Readiness element (Affirmation Form - Attachment 4) is completed to ensure thats the OPN-30 process is complete, the system engineer walkdown has been completed, the necessary testing is included in g the startup testing plan, and the remaining backlog is properly O prioritized and proper compensatory measures are established, if f
.. necessary, for the activities not completed.
f Most of the OPN-30, Final System Readiness Reviews, have been completed (87 of 89).S The remaining two are near term and are pending engineering closure of a control room HVAC issue. These two should be complete by Wednesday, April 21. g[ cg% .
[/,/ 32 6 g Most of the CPN-31, System Roadiness Affirmations, have also been completed (63 of 89). _
The remaining affirmations should complete later this week.
OPN-31 also established the requirement for a Collective Evaluation of system readiness. This collective evaluation was completed o g rji1 J3.
The remaining items required for Unit 2 startup were reviewed (see
- Collective Evaluation of syst3m Readiness" - attached). Completion of the current outage scope and necessary emergent items will complete these identified outstanding activities.
Past performance, especially related to systema performance and material condition, were also reviewed. The potential impacts, compensatory actions, and long-term corrective actions for each problem area were also reviewed (see " Unit 2 System and Equipment Problems and Follow-up Actions" g#
W e
attached).
l
- 2) organisational Readiness j l
OPN-31 establishes the requirement for review of readiness of specific organisations to support safe and reliable startup and power operations.
y Meetings with the Vice-President, BNP and each of these organisations have
\ been conducted since early Februe' The bases for review of readiness for each organization included the following generic topics: staffing,.
training, compliance with cegulations, emergency preparedness, industry operating experience, procedures, work processes, ACRs, FACTS items, NAD
1ssues and INPO findings, corrective action effectiveness, root cause f determination, and critical self-assessment. In addition to these generic j jj review topics, specific areas were identified from previous performance Y for review by each organization.
{
Following the series of reviews, the Vice-President, BNP has concluded thatc111_ o f 1.21> organizations are ready to support safe and reliable p7 startup and power operations. Operations is currently scheduled for their
- ( final readiness review Thy pd v1 3 April 22 fram 3 : 30end - s e insaa- The NRC kb '
resident and staff are encouraged to attend.
f,o v/
I<v 3) operational Readineess
( CPN-31 also requires that each shif t supervisor af firm for himself and his operating crew that they are rear *y to support safe and reliable startup y( and power opsration. This affirmation is based upon staffing and
()O( qualifications; training, including requalification, procedural, and
- 8. f startup and power ascensions plant material condition, including operator work-aroundet adequacy of control room work anvironment; adequate configuration control previsions, and :learly communicated expectations relative to conduct of operations.
/
DPN-31 also established _the_ requirement ~ for a Collective Evaluation of e operational readinessJ This collectiv, evaluatien was completed on_Anril k'
t 12~tod resulted several required actions to be completed prior to Unit 2
{'startup. (see attached meno Dobbs-to-Warren, 4/12/93)
\ -. . - -
e :
OLLECTIVE EVALUA MON OF SYSTEM READINESS APEil 14,1993 - Revision 2 M6-30 SOS PM-31 ret 4Aff98G STARTtF CODED ITEMS REneARKS EYS SYSTEM O NAME F.S.R.R. SIGN ATT.4
- 12. Apr-33 Complete pnmordy coldwesono and sensing Ene fes.
1005 Nuclem Bader EWR 10851 let pump flow centwenon: neid mea corwiete precedure rewmon reguared.
EWR 11893 - EO enefyme for SRV (ASCO solensed wafweet. NED reports EER 93 288 carglese.
WR/JO S3-ALLX1 -ipotes steelde end bestors on the MSL tunnet tervereture emitches. EER 934324 WIP by NED. Addsmonal hoseers on order, to ornwe FnJoy.
01-Mar-93 PMTRs fosowing evadebaty of both RHR Loope 1011 PCis Neutron Marutonng O2 Mer 93 06- Apr-93 12- Apr-93 None (see belowl 1050 1050 SRM O2 Mer-93 06 Apr-93 12 Apr 93 Nne Ne menrEcont issues O2 Mar-93 06 Apr-93 12 Apr S3 None h ogreEcont issues 1050 lRM O2 Mar-93 06- Apr-93 12-Apr 33 None Refer to Metenced Rowear 1050 APRM/LPRM O2 Mar-93 11- Apr-93 12- Apr-33 None Refer to Mstancel Reveeer (TIP electron cs).
1050 TIP 03 Mer 93 15-Mar 33 12-Apr 93 (see belowl fees basew) 1065 Rod Control System 03 Mer-33 15 Mar-33 12-Apr-93 None Refer to PN-31 octaceanent 1065 RWM 03 Mer-33 15 Mar-93 12- Apr 33 None h segrencent issues 1065 RMCS 05-Apr-93 14- Apr-93 (see belowl (see below) 1070 CRD/RPts 1070 CRD Hydraulic 05- Apr-93 14- Apr-33 Reper h TG8 Chargyng Proesure Irunceman Reper CRO tronometter power suppey shot has unacceptable apple.
03-Mer 93 15 Mar-33 12- Apr-93 Ene Refer to PN-31 ertschment 1065 RPIS 07- Apr-9) 12-Apr 93 bne h ssyuncont issues 1080 CPS 01-Mar-93
OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 (
l SY3 SYSTEM PN-30 SOS PN-31 REMAIPMNG STARTUP COCED TTEMS REMARG O NAME F.S.R.R. SIGN ATT.4 2013 RWCU 04 Mer 93 2 WR/JOs for flow iracetor protdems and contro5er Refer to Motoncel Review Ori _3.
protAems Inspect pipeng for fore +gn metenal. FsN and went.
09 Apr 93 Work closure in progrees Refer to Mosencel Rowew fPurry ed ed&tione, recere 2020 Reactor Recwculetson iociation wafve leek ogo, and pechng).
03 Mar-33 28 Mar 93 09 Apr 93 None No agrwfecent issues 2035 Core Sprey 28-Feb 93 26 Mar 93 08. Apr 93 None PM to repiece SLC accurnulators and releef welves are 2040 SLC in 3-Year Plan. Conemue eefuelinspectone of occumuletars uned replacement complete Resofwe F016 insteRed backwords PCIS issue Refer to Mstoneel Rowew IKeep fd) 2045 Residual Heat Removal 24 Mar 93 Several wrescellaneous WRtJOs 01- Apr-93 08 Apr 93 09 4 93 PT 11.1.2 ocheduled for power esconoson. No segraficant issues 2055 f.DS & SRVs 2070 CAC 09- Apr-9 3 Need N2 on CAC and CAD tank for wenous PMTR's.
N2 to ernwe 4/13. Also PM 93409 tutung instoned en drywee red moretor. Duelirocateen on V-49 must be corrected.
Resolve potential Pnmery Conrewwnent leek path Refer to Mstencel Rewew (TOPAZ Inverters and groep.
2095 HPCI 27-Mar 93 fo#owing DC bus loss. fsNI.
03 Mar 93 02-Apr 93 Reperloose fles condwt to V8. Refer to Mstoncel Rewow (TOPAZ kworters and Keep-2100 CCIC Resolve potentral Pnmery Concernment seek path fel.
_ _ _ _fo8owmg DC bus loss. __ . . _ _
l s
I 4
IOLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 l
PN-30 SOS PM-31 MEMAINING STAftTUP CODED ITEMS REneanKS BYS SYSTEM
- NAME F.S.R.R. SaGN ATT.4 2115 Process Sampimo Systems 12-Mer-93 25 Mer-93 12- Apr-93 kne h a '- -4ioeu e 25 Mar-93 12-Apr 93 None h eyelicent issues 2115 Rm Bldg Sem 12-Mer 93 3100 Turb Bldg Sam 12-Mer-93 IS Mar-33 12-Apr 93 None b esoneficare issues 02 Mor-93 19 Mar-93 12-Apr-93 kne h aspedbeantisowee 7075 RW Bldg Sem Post- AM.;; Sampimg 12-Mar 93 06-Apr 93 12- Apr 93 None h espedicent isowee 2117 12 Mer 93 16 Mar 93 09- Apr-93 Ene h espe 6 cent issues 2190 Press supp/Toeus Dren 2190 Torus Drem Syssem 12 Mar 93 16 Mar 93 12- Apr 93 hoe h moro6mnt issues 2190 Pressure Suppression 12 Mar 93 16-Mor 93 OS- Apr 33 None h myofecent issues l 05- Apr 53 07-Apr-33 (see beleert (see belowl 3020 Men Steem'EHC 05- Apr-33 07-Apr-93 Remove pene ire hengere instesed for condenser cooling 3020 Men Steam Instem turtoiselencer en TSI cabinet. m
- to Hestencel Reeiew " ; ^ ' a weton seals.
5010 Doctrobydreuhe 24 Mer-93 07-Apr-93 14- Apr-93 meury wetted relevst-Control t 01-Mer 93 24 Mar 93 12- Apr 93 Startup testeg is rogsired, refer to PN-31 setectwnent 3025 Entractson Steam 26-Mar-93 13- Apr-93 has h mysticent issues 3030 MSR / Reheater Drame 01-Mar-33 3040 (mweary Steam 01-Mer 33 02 Mer-93 , 3 WRIJOs en Boder Adsustment of spnne con suppe-ts. 2A RFPT hensee Refer to Hestencel Rewew ifuse toduces and analog 3050 Feedwever Centref 10 Mar-93 edgusernents. cerWret system 8.
l l
.OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 PN-30 SOS PN - 31 REMAINING STARTUP CODED ITEMS REMAfMCS CYS SYSTEM O NAME F.S .R _R. SIGN ATT.4 3060 Hester Drems, Vente & 06-Mar 93 30 Mar-93 HD Pump 2A Section Une wefd reper et stenetwon Level Cc . trol supe support.
Cond / Feedwater System to Mer 93 31 Mar 93 12 Apr 93 None Refer to Wetencel Rewow tengpne dnven ed pumpt.
3070 06 Mar 93 31-Mer-93 (see belowl (see belowl 3073 Condensato Dommeralizers 3076 CFDs 02 Mar-93 03 Mer 93 12-Apr 93 None No oefecent sesues 3077 CDOe 06-Mer 93 31-Mer 93 Procedure cfsenge to 2-OP 32. Prevent cychng of RTP gland seal water essenend wefwee dunne startw.
Cond!Demm Wtr Storege & 16-Mer 93 18 Mer-93 12- Apr-93 None No og nficent issues 3080 Transfer 3080 Cond Makeup Water 01 Mar 93 18 Mar 93 12- Apr 93 None % wormfscent issues Tree:.. c.:
16- Mar-93 18 Mar-93 12- Apr 93 None No eigraficent issues 3070 Cond Transfer 12 Apr-93 None % ograficent issues 4005 Mien Condenser 01-Mer 93 10- Mer-9 3 Cond Aw RemoveuOff-ges 14 Mar 93 01- Apr-93 13- Apr-93 None % ogruficent issues 4010 Recomb 8
Cwcufsteg Water 25 Mar-93 01-Apr ?J isee belowl (see belowl 4015 22 Mar-93 01-Apr 93 12-Apr 93 None Refer to Estancel Rewow (bedweshmg end CWOD 4015 Cwcu!.emg punwsl.
Weter(AmerTop 01- Apr-93 12 Apr 93 None % og nfeent issues 4045 intake /Disch. 25 Mer-93 5255 Cerhod c Prot. Sye. 19 Mer 93 19 Mar-93 Anode replacement pendmg
r .-
- OLLECTIVE EVALUATION OF SYSTEM READINESS April 14.1993 - Revision 2 CVS SYSTEM - PN-30 SOS PN-31' MEMAINWeG STARTUP CODED ITD45 REteARKS
- NAME F.S.R.R. SIGN ATT.4 4040 Screen Wesh 2S +et>93 22 Mar-93 12-Apr-93 Mene Romewang corremen leeues cervected per 3-Year besserse TY-502. ese PE31 attactonere 4060 Serwce Weser 05-Mer 93 RHR SW beester purnp seal . , s and other WRf>Os.
4070 RBCCW 02 Mer-93 03-Apr-93 12- Apr-93 Mene Terg Med for TSCCW teners (2 934273) 4075 TBCCW 02 Mar-93 01- Apr-93 12- Apr-93 None h morehcent issuee 5005 Meen Turtwv 14 Mar-93 O2- Apr-93 13- Apr-93 bne h enero6 cent issues 5005 Turtune 02 Mar 93 01- Apr 93 13- Aor-93 kne h mero6 cont issuee 5020 Tuetnne Gen Lube Od 02-Mar-93 02 Apr 93 13-Ate-93 Ene No esonrheent 6esues 5035 Turreng Gear 1 +Mer-93 02- Apr-93 13- Apr-93 kne Refer to Hrotencel Rewow taureeng yearl.
2-SP-92412 Rowsed to work turveng geer enth reduced Mt purge.
Targ Med en Ngh speed dieeMernent.
5030 Enhaust Hood Spesy 02-Mer 93 19 Mer 93 13- Apr-93 None h menrEcera issuee 5025 Turtune Glend Seel 02-Mar-93 01- Apr-93 13- Apr-93 kne h esgrescere issues 5040 Men Generator 06 Mer-93 02 Apr frl (see belowl (see belowl
OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 i SOS PM - 31 MEMAsilNG STARTUP CODED ITEM 5 REmanRKS CVS SYSTEM PM-30
& NAME F.S.R A. SIGN ATT.4 06 Mer-93 02- Apr-93 32 AIUQ1 - Instes generator oral enester bruohoe 1-2 5040 Generator weeks before rollms the : " x
.aw.
92- AUPK1 - Megger the generator field wendwigo on a montidy bee e. Coeure of this WR/JO is ira progrose 93-AITE1 - Monitor enews genererer RTD's and thenvisca.x before end during power escenesen.
Open PMTR's : 33-AJDL1 - Venty proper temp indicesion durens etersup.
93- AEEQ1 - Venty proper larvgp indicamen dunne stortup.
32-AEET1 - Venty no CO2 leaks et speel p ece during geoems of gemretor.
13-Apr 93 Heat Immpo en cosector ringe
- m% nerefor Encster 06 Mer-53 02 Apr-93 Regular snapocean of cosector nage Open PMTR's : S2- ACRF1 - Venfy no sinnermal vdproton during startup - Kop-Ree Couptmg.
92-AEEQ1 - Venty no atmennel wibremen dunne stortup on #3 bearing. 92 AEETI - Venry no atmeernal weerseen during startup en #10 beenne.
06 Mer-93 02 Apr 33 Open WRt *0's: 33- ALRX1 - Check operemon of #2 5065 Gen lealeted Phase Sees (Mect4 fers for hi. .webreton.
Open PMTR's: 93-PVMOO1 - Check #1 fan _". -._.:
and proper belt seneson efter 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.
1 06-Mar-93 10- Apr-33 Open WRtJO's:
5050 Generator Gee 92-AEFW1 - Venty no leeks on the generator ges y,mg uoms soap inshble solueen when eystern is pressurized with H2 (with PMTRI.
32-AFDJ1 -instes H2 spool pnece fontfi PMTR1 Plent MOD S2-125 Acceptance Testme - Venty no leaks en the generator ges pipes nome soap bubble ectuson when system is pressurized with H2.
Open PMTR's : 33-AFE.1 - Venfy no CO2 leeltage et spool piece with everm et pressere.
Stator Coo 4mg 06-Mer-93 05- Apr-33 Generater Ste.or Coolmg runbecklennunesetor sleem 5055 testing wee Al-117.
OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2
. CYS SYSTEM PN-30 SOS PN - 31 REMA9ftNG STARTUP COOED ITEMS REMARICS O NAME F.S.R.R. SIGN ATT.4
.5060 Generator H2 Seal Od 06 Mer-93 27-Mer-93 13-Apr 93 None No agraficent issues l5075 DC Dstreution 27-Mer 93 30 Mer-93 (see belowl (see belowl 5075 24V DC Bettery 27-Mer 93 30 Mer-93 09- Apr-93 None No og*uficant issues 5080 24V DC Bettery 28 F493 30 Mer-93 09- Apr-93 None No esgruficent issues 5085 24V DC Detreution 28 Feb-93 30 Mar-93 09- Apr-93 None No agrufscent stowee 5215 Ernergency DC 11-Mar-9 3 30 Mar 93 09- Apr 93 None No og nficent issues
$230 250V DC Dst 11 -Mar-9 3 30 Mar 93 09 Apr 93 None No moreficant sesuee
$240125V DC Bett. 28 FetrS3 30 Mar 93 09 Apr 93 None No segraficent issues
$245125V DC Bett. & 11 Mer 93 30 Mer-93 OS- Apr 93 None No sigrufocent issues Cnt.
5255 Cathodic Protection 02-Mer 93 30 Mar-93 5090 48V DC Dested>ution 11-Mar-9 3 30 Mar-93 09- Apr-93 None No agraficent issues 5095 Desel Gen. 15-Mer 93 06-Apr-93 12- Apr-93 (see belowl (see belowl 5105 Desel Lube 04 Sys. 14 Mer 93 06- Apr 93 13.Apr 93 None No mornheent issues
$110 Dessi Jacket Water 14 Mer 93 06- Apr 93 13- Apr-9 3 None No agruheent issues 5111 DG SW & Derrun. 01-Mar-93 06- Apr 93 13- Apr 93 None No agraficant issues Water 5113 DG intelie & Enhaust 01-Mar-93 06- Apr 93 13- Apr-93 None No agrufcont issues 5100 D.esel Fuel Od 15 Mer 93 06 Apr 93 08- As r-93 None PM 81-084 to address fuel ed levelissues on 4< fey tanke is protected to be correleted May 30.1993 C202 Fuel Od Sye. 15 Mer-93 06- Apr-93 08- Apr-93 None No ogneficent issues 5112 DG Starteng Air 11-Mer-93 06-Apr-93 13- Apr-93 93-AMZZ1- 2-DSA-V88. stuck check welve. Irutseted No agraficare issues 4/13.
5095 D esel Gen. lErner Doct.) 15 Mer-93 21 Mar 93 10- Apr-93 None No agruheent issues r
.i OLLECTIVE EVALUATION OF SYSTEM READINESS Apr514,1993 - Rowision 2 SYSTEM F98-30 SOS PH - 31 N STARTW CMIED N N EYS s IGAME F.S.RJI. - 38G00 - -ATT.4' 5135 5estchyard IElece seell t o eder-93 07-Apr-93 lose belowl imme betowl 5135 230KV Sweechymed to Mar-93 07-Apr-93 09- Apr-93 Stone h mysteeset imouse 5145 S AT, UAT. MATS 16 Mar-93 07-Apr-93 09-Apr 93 Seesee See P =='sesume 5065 Gen lealeted Phase 184 der-93 07-Apr-33 Pendeng #2 Son super and #1 fan PaffR Bue IElecti 09-Apr-93 h eyeScent ' souse 5200 24KV S---f ird 16-Mar-93 07-Apr-93 90 ens .
525t* L --4 Protoceen 16 Mar-93 07-Apr-93 OS-Apr-93 fessee h W semisee 5260 Sete Grouselwig 10 Mar-93 07 Apr 93 09- Apr-93 Scene fee myeScent inesse 01-Apr-93 02-Apr-93 lose below) lose belowl 5185 AC Dietnbusson 28 M S3 02-Apr-93 OS- Apr-93 Itene ele mysEcont ieease 5185 200/120V AC Dest.
5195 Urenserruptede AC 28- M 93 02-Apr-93 08-Apr-93 feene Refer se P90 31 esencesument.
noter se sessences newe=s su per and Case anmereers.
5205 psorenes AC Lashesis 2s-Fah-93 02-Apr-93 OS-Apr-93 feene Its W isoisse 5210 Emergency AC 2S h 93 02-Apr-93 00-Apr-93 feene h amyshcent asemoe 244 der-93 02-Apr-93 10-Apr-93 10ane Reenatselinuent of 4 Kw beembers we eenanme poet 5170 4160 VAC oseremy used conseeeeed casequeseen deem is Deessedser 1994.
5175 400 VAC 01- Apr-93 02 Apr-93 WomengInouse bresher seestseen NER 934272) owmens IED e SESS EO sospense des 4MS.
vesene. ' . - , desensenamen ser eso vaC macc Powered Seeeey Asessed Ceneral Circense NER 93-017ee in empeosed due 4r14.
Cenossee e WsuO e ser Madce meester reposeeniones.
525p Sies cuado Troye & 01-Apr-93 07-Apr-93 09-Apr-93 scene see W m Conduit
r .- l
- OLLECTIVE EVALUATION OF SYSTEM READINESS Apr# 14,1993 - Revision 2 SYS SYSTEM PN-30 SOS PN - 31 NEMAseSsG STARTUP CODED ITEM 5 REteMus
- NAME F.S.R.R. SIGN ATT.4 5225 Freero Prot & Heat Treeme 28 Feb 93 28 Feb-93 OS-Apr 93 kne h swuncont soeues 05 Mer-93 18 Mer-93 13- Apr 93 None b engruEcont issuee 6004 ERFis Process Computer 01-Mar-93 22-Mar-93 12- Apr 53 None Refer to PN-31 mete fwnent.
6005 Refer to Histonest Rewow.
~
'M'_
6010 Ma n Con rol Board (RTG88 01-Mar-93 25-Mar-93 OS- Apr-93 Ene h _ __--.:issuee 6015 Annuncestor & Amv 01-Mer 93 15 Mer 93 OS- Apr-93 Ene h esenAcant issues A unciator Sys.
6020 Ausdeery Control Board 28-Fet> 93 28 Fab-93 09- Apr-93 None h esonecent issues I
&stion Systems 05 Mar 93 05 Mer-33 OS- Apr-93 (see belowl fece belowl 6030 C....
6030 PA System 28 Fet> 93 01 Mer-93 OS- Apr-93 None No engruheent issues 05-Mer-93 05 Mer-93 08- Apr-33 None No segru6 cont issues 6035 Commercial Phones
& Telecopiers 03 Mer-93 05 Mar-93 OS-Apr-93 None b esgreEcent issues 6040 Sound Power Phones 05-Mar-93 05 Mer-93 OS- Apr-33 None No segraficant issues 6055 FCC Ucensed Portetde Medios CD60 Microwave System 03 Mer-93 05-Mer-93 OS- Apr-93 None No segrufscent issues 03 Mar-93 05 Mer-93 OS- Apr-33 None Refer to PN-31 ottschment.
6080 Coswell Baech Refer to Mestoncel Rewow IOnendert.
Supv& Control Sys ,
6045 Licensed Base Station 28-Feb-93 01-Mar-53 08 Apr-93 Mone No esenrEcont issues Radeos
~
OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 J
gys SYSTEM PN-30 SOS PN - 31 met 4AssNG STARTUP CODED ITEMS ret 4MutS 0 NAME F.s.n.R. ssGN ATT.4 6075 Seisme Morutoring 28.Fotr$3 09 Mer-93 Reper anwhenol connector 23 Feb-93 28 Fe493 09- Apr-93 Ene No sepudicent issuee 6085 Secunty 6085 Secunty Convuter 28 FetrS3 28 Fet>S3 09- Apr-93 None h symficent iseuse 28 Fetr$3 29-Fet>93 09- Apr-93 None h m yuheentissuee 6095 Card Reeder/ Access Control 28 FetrS3 28-Fotr53 09 Apr-93 kne h espesscent assue.
G100 cosed Cercist TV System 28 Fotv93 28 FetrS3 09- Ape-93 None h segrwheent issues 6105 Intruseon Devices 2115 Fences & Genes 28 -Fot>93 28 Fot>93 09-Apr-93 None h anywheent issuee S120 Physicea Search 28-FotrS3 28 FetrS3 09- Ape-93 None h significerg issuee System 6125 Key Control & Hdwr 28 Feb 93 28 FetrS3 09- Apr-93 None h agrufocant issues Secunty ,
6130 Secunty 28-FotrS3 28 Fet>S3 09- Apr-93 None h agraficant issues Commurucation Sys S135 Inst. Air end Netrogen 02- Apr-93 OS-Apr-93 (see belowl (see belowl 8135 Inst. Air (includes N2 09 Mar-93 08 Apr-93 92-BDeCJ1,2,3.4 -Replace 24tIA-PCV-4013 (pressure CAD toducme wafwel with new wolve.
6152 Pneumatic Nitrogen 09-Mar-93 08- Ape-93 Linde to cornplete funemonet test. esper, and fe of U1 PNS tank by 4-18. U2 tordt hos been tested, permeNy feed and is ready for servece.
8270 Natrogen and Oft Geo 02-Apr-93 08- Apr-93 13-Apr 93 None b esenrlicent issues 6140 Service Air 09 Mer-93 06- Apr-93 93 AMAN 1: 2SA-706-2 Service Aar Needer eseleeon volve regulater has e blown diaphreyst.
93-AMAP1: Dme beets en 2A er carrynessor need ef,__..a. . (Found while perforrrens PMTMsl
- - - - - - _ _ - ___.- - ____________- _____-_ w
OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 SYS SYSTEM PN-30 SOS PN - 31 ftD4AINING STARTUP CODED ITEMS REMARICS 0 NAME F.S.R R. SIGN ATT.4 G175 Fue Protectron Systems 29 Feb-93 08 Mer-93 12- Apr 93 None lose belowl G175 FP System 28-Fot> 93 08 Mar-93 12- Apr-93 None Refer to PN-31 ettechments__U1 RX SLDG - S
- u. . _ . fire watches: U2 RX BLDG - 1 houvty two
^
weech: Centrol SLDG - 1 heurty fire welch:
SW BLDG - 2 contwiueue end 1 haiety two weech.
' 12- Apr-93 None No sigraficent eesues G195 FP CO2 Sys. 28-Feb-93 08 Mer 93
$205 Halon Supply Syo. 28-Fot> 93 OS Mer-93 12-Apr-9 3 None Refer to PN-31 attachment 1 J.. -_ _ _ Fwe Watch for DG beoement Rodoform sesfe ereund pedestelo 28-Feb-93 08 Mar-93 12 Apr-93 kne Refer to Pf431 ottechments 1 hously fire watch for 0180 Fwe Detection RX Suilding (Penel142 hee venous rence elemanal 9300 Alt. Safe Shutdown 28 Feb 93 08 Mar 93 12. Apr-93 None No agraficant 6seves i
LO Storege and 02-Mer 93 10- Apr-93 No signrfacent issues
)G200 13-Apr-93 j None Condsteorung l 6210 Sswege Systems 02-Mer-93 02-Mer-93 (see belowl (see belowl C210 Sowege Treatment 02 Mer-93 02 Mer 93 12-Apr 93 None No agrarecent issues
$215 Sewege & Saratory 02 Mer-93 02 Mar-93 12 Apr-93 None No agraficent issues 6220 Storm. Roof. Geen 024Aer 93 02 Mer-93 Red enorwtor nuisance annuncsetor needs to be i resolved 1
. l
'4225 Misc Dreen 19 Mar-93 (see belowl teee belowl C225 fase Redweste/OA 19 Mer-93 Complete oily dran sump enodificenon PM 92407.
Deeen Sys.
6245 Laundry & Hot Shw. 02 Mer-93 12. Apr-93 None No sogenfocent resues 9015 Health Phy. Equep. 10 Mer 93 12- Apr 93 None No ognifecent issues l 9025 Radeocherrestry 02-Mer 93 12- Apr-9 3 None No mornficard issues l6235 Plant Desens 16-Mer-93 06 Apr-93 (see belowl 1see belowl
_.._ _. .m.. _ . . _ . _ . . . - - .m
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4 OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 PN-30 SOS PN 31 MEMANNG STARTUP CODED ITEMS PIEMARets SYS SYSTEM s NAME F.S.R.M. SIGN ATT.4 16-Mar-93 OS- A pr-93 12- Apr-93 None No segrvficent ieeuse 6235 Floor Drains 6240 Equipment Deeine 16-Mar-93 06-Apr 93 Resolve *xe drain with hole dnited J.'JEDT repair set closed on AMMS 01 Mer-93 02-Mer-9 3 WWV-95 check valve needs repair 6260 Well Water 10-Mar 93 26 Mar-93 12- Apr-93 None No eigewficant issuee
.6231 CNorination 01-Mer 33 02 Mar-93 12-Apr 93 None Refer to PN-31 ettectwnent.Suppfy pipe to cNonne 6265 Potable Water evaporotors is corroded. AccepteNo for now but ;
ehould be replaced soon to avoid lose of water needed to evaporate cNorme.
Derrun Water System 01-Mer-9 3 03 Mer-93 Potentief for RHf1 SW Booster Purry modification seef 6270 purge suppfy connecte.
t Coustic/ Acid Storage & 01.Mer-93 01-Mar-93 12- Apr-93 None No sigrwficent issues 6200 Transfer 6280 Coustic Storage & 01-Mer-93 01-Mar-9 3 12-Apr 93 None No sig uficant 6seves Transfer 01-Mer-93 01 -Mar-93 12- Apr-93 None No sigraficent issues 6282 Acid Storage &
Transfer 01-Mer-93 15-Mar-93 12 Apr-93 None No sigruficant issues 6281 Hydrogen Water Chemistry b
04-Mer-93 07- Apr-93 Reconnect MSL Rd Monrters and replace fuses Refer to Historical Rowsew (NUMAC LVPS fedures) 7005 Process Redterion Morutormo i
04-Mar-93 27-Mer-93 12- Apr 93 None No sigrsficent issues 70t5 Arse & Enstons Radiation
- e .*
April 14,1993 - Revision 2 OLLECTIVE EVALUATION OF SYSTEM READINESS PN - 31 ftEMAINING STARTUP CODED ITEMS REMARKS SY3 SYSTEM PM-30 SOS
- NAME F.S.R.R. SIGN ATT.4 i
01-Mar-9 3 01-Mar-93 WR/JO resolutson essociated with PM 0141 supports 7045 Solid Redweste for drain kne from RHft to SW cross connect.
08-Mar-93 12- Apr-93 93- ALYY1 stortg item on oily drain system and Refer to PN-31 attachment 7060 Liquid Redweste 02-Mar-9 3 tracked therein 12- Apr-93 None No migraficant issues 7070 Aug Off Gas Charcoal 09 Mer-93 11-Mar-93 Absorber 19 Mo' $? Resolve SBGT throtthng teet stops, provide offsite 7071 Standby Gas Treatment calculations, etc.). Complete CAC heet tracing for greb samples.
09- Apr-93 None No sigruficent issues 7105 IF-300 Cask 03-Mer-9J 03-Mar-93 12- Apr-93 None No sigruficent issues 7110 Fuel Pool Cooling & 08 Mar-93 16- Mer-93 Derruaeralizers (see below) (see below) 8020 P2netrations/ Cooling 20 Mar-93 - -
20 Mer-93 7 WRJO's, dryweN airlock house cleaning, 8020 Penetrations otrongbacks,inetag block wall; restore grading; repair insulation; restore CRO hatch.
13- Apr-93 None No sigraficent issues 8110 Penettation Cochng 20-Mer-93 07-Apr 93 (see below) (see below) 8015 C%midings, Structures &
Cranes 12-Apr 93 None No sigraficant issues 6070 Met & Env Systems 06-Mar 93 18 Mar-93 09- Apr 93 None No sigraficant issues 7095 Refuel Eqtapment 03 Mar-93 20 Mar-93 t
s .= ,
- OLLECTIVE EVALUATION 08F SYSTEM READINESS April 14,1993 - Revision 2 f,Y3 SYSTEM PN-30 ' SOS PN - 31 REMAINING STAftTUP CODED ITEMS REMAmsts
- NAME- F.S.R.R. SIGN ATT.4 8065 Structures & Cranes 07- Apr-93 08- Apr-93 13- Apr-93 None No eigraficent essues i
8195 Gentry Cranes 08-Mer-93 18 Mar 93 13- Apr-93 None No significent issues 8230 Ser. Water aldg. OS Mer-93 Water leakege into service water building resolution 8240 Reector Bldg. 07-Apr-93 IAsc WRJO*e for scaffold, temp shielding, floor pluge, insuletion, loose anchors and point (14). i 8270 AOG Bldg. 23 Mer-93 08- Apr-93 13- Apr-93 None No significent issues 8275 Storeroom / Hot Shop 08 Mar-93 18 -Mar-93 13- Apr-9 3 None No segnrficent issues i
8290 CtJorine 9tdg. 22 Mer 93 08- Apr-93 13- A pr-93 None No eigraficant issues 8291 Operatione Offices 16 Mer-93 18-Mar-93 13- Apr-9 3 None No eigraficent issues 8300 Adrrun Bldg 03 Mer 93 18 Mer-93 13- Apr-93 None No sigraficent issues 8304 Adnun. Annes 16 Mar-93 18 Mar-93 13- Apr-93 None No eigrefx:ent issues [
i 8306 Treirung/TSC Bldg. 22- Mer-93 08- Apr-93 13 Apr 93 None No eigruficent issues 8340 DG Bldg. 07- Apr-93 08- Apr-93 3 scaffold WR.lO's for PM 92-090 93- AKLZ1 blind fienge for temp power 8355 Control Bldg. 07-Apr-93 93-AGBL1 remove meterief from cable veutte C360 Service Bldg. 16-Mer-9 3 18 Mar-93 13- Apr-93 None No significant issues 8370 Turbine Bida. " 07- Apr-9 3 08- Apr-93 93- ALEQ1 insufetion repaire 83CO Redweste Bldg. 20 Mar-93 08- Apr-93 13-Apr 93 None No significent issues 8565 Doc. Control Bldg. 22-Mer-93 08- Apr-93 13- Apr-93 None No significant issues ;
9030 Safety Equipment 03 Mer-93 18 Mar-93 12- Apr-93 None No significant issues ,
KO75 Diesel Generator Building 28-Feb-93 18-Mer-93 12- Apr-93 Refer to PN-31 ottschment._ Roll fire doors #223 and '
HVAC 224 (under L%sel Blog 83401 are in closed positioen.
93-AK8X1 and Y1 are WtP. Doore require testing per FP PT. Doore e o in fed safe mode end (.s not peevent enheust from DG cous for ventdetion.
t i
l l
- OLLECTIVE EVALUATION OF SYSTEM READINESS April 14,1993 - Revision 2 j SOS PN - 31 REMAINING STARTUP CODED ITEMS REMARKS SYS SYSTEM PN-30
- NAME F.S.R.R. SIGN ATT.4 8185 Reactor Buildmg HVAC 05- Apr-93 Awaitmg Bettis Actuator parts due 4/14, then stroke BFIVe per PT 15.4A.
i Control Buildmg HVAC NED design to instem dempers in dragon's breath door. l 8220 l 04 Mar-93 12- Apr-9 3 None No eigruficent issues 8232 SW Bldg. HVAC 03-Mer 93 08 Mar-93 10 Mer 93 (see Lelow) (see below) 3250 #Asceneneous HVAC 08 Mar-93 12- Apr-9 3 None No sigraficent issues 8250 Service Bldg. HVAC 08-Mer-9 3 08 Mar-93 13 Apr 93 None No sigraficant issues 8565 Doc. Cntri. Bldg. 08 Mar-93 HVAC 08 Mar-93 13- Apr 93 None No sigraficant issues 8310 Auu. Boiler Bldg. 08 Mar 93 HVAC 08 Mar-93 13- A pr-93 None No sig'uficent issues 8035 Reley Budding HVAC 08 Mar-93 08 Mar-93 13- Apr-93 None No sigruficent issues 8290 Chlorine Oldg. HVAC 08 Mst-93 08 Mar 93 13- Apr-93 None No sigraficent issue +
8306 Trairung/TSC Btdg. 08 Mar-93 HVAC 10 Mar 93 13- Apr-93 None No sigraficant issues 8275 Storeroom / Hot Shop 08 Mar-93 HVAC 2B chiner head gedet- to cornplete 4/13. then 8260 Turtwne Bu# <1HVAC numerous chised water PMTRs.
12- Apr-93 None Refer to PN 31 ettechment Temp Mod 0-93 0343 8280 Redweste Budding HVAC 28-Feb-93 28 Feb-9'i' justefees desabled annunesator 1/2-UA-14.6-4. redweste static pressure diff. low.
08 Mar-93 13- Apr-93 None No sigraficant issues 8300 Adrrun./MWT Bldg. HVAC 08 Mar 93 03 Mer-93 13- Apr-93 None No sigraficent issues 8300 Admin. Bldg. HVAC 03 Mer 93
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UNIT 2 SYSTEh! AND EQUIPhiENT PROBLEhfS AND FOLLOW-UP ACTIONS Problem Description Impact Compensatory Actions IAng-Term Actions
- 1. I.PRhl spiking has been a recurrent problem, Can result in reducing Spike suppression cards have been installed PIDs 0075A and 0076A, LPRM Cable princip. ally due to age-- related degratiation of power when problems on KWU type detectors; spiking problems Replacements Inside and Outside the the cabling. Also, the KWU type detectors occur. should be reduced, but will require close Drywell, are in the 3-Year Plan for experience spiking due to time in life. monitoring when tested at full power. 1994 Onside) and 1997 (Outside). In addition, replacing KWU type detectors with GE spikeless type is planned during future rt$lacements.
- 2. Reactor recirculation pump motors may require A downpower and Pump motor 2A was worked in this outage. PID 07197A, Ten-Year Inspection of adding oil while at power. drywell entry would be The oilers are sud being placed in service Reactor Recirculation Pump Motors, is needed. this cycle since they appear to be in the 3-Year Plan for 1995 in both contributing to oil loss. An evolution to units. A GE design recommeudation add oil would normally be planned regarding oil for the motors has been concurrent with a downpower and drywell recently received, and is being studied entry for otherj-aons. by NED.
- 3. Topaz inverters have demonstrated Short-term Maintain available spare topaz inverters. PID 07148 Replace HPCI, RCIC, and performance problems in several systems such unavailability of IIPCI For example, due to unit I digital RPS Topaz Inverters, is in the 3-Year as llPCI and RCIC. Replacement parts and and RCIC. feedwater moJ, the existing equipment in Plan, scheduled for 1995 in unit 2.
retinbishments are unavailable froin the the feedwater control system is available to original manufacturer. be utilized as spares.
- 4. The Plant Process Computers Oloneywell Operator work arounds A backup plan for operating without the PID OI757A Process Computer 4010), are the oldest in the industry serving encountered during process contputer is in place and has been Replacement, is in the 3-Year Plan, this function, and have experienced a number computer down time. successfully used in previous occasions. A scheduled for 1994 completion.
of operational problems. Software versatility, This has delayed power backup computer program is snaintained on accuracy and other limitations, including spare maneuvering. a computer in Raleigh, which can accessed part and training service support, contribute to by the Nuclear Engineers via phone the problem. modem. The PT-l.!!, Core Performance Parameter Check, can be performed daily as required per this backup system.
- 5. Keep. fill station relief valves of ECCS systems Creates leakage to the Temporary modifications in place for Temporary modification to be are obsolete. floor, and results in setpoint changes between the pressure upgraded during next refuel outage.
operator work arounds. control and relief valves to allow more separation of the setpoints for keep fill stations.
S-J-25
1 Problem Description Impact Compensatory Actions Long-Term Actions
- 6. RWCU systems have experienced numerous There is no plant Procedure revisions have been initiated for A project has been initiated to add spurious isolations because of operating reliabihty impact of improved ihrection; valees have been vents to those pensions of the piping practices, maintenance practices, component these isolations. replaced climinating drd a denen of RWCU where air can become trapped.
f.ulures. I.ERs90-011, 91-008,91-010, 91 piping. Varisters havs een installed on the Installation of a NUMAC system to 012,90-007, 90 419,91-004, 91-006,91-009, Note: Spurious RWCU Riley SCAM Modules elimiaating replace the Riley SCAM Modules will isolations of the spurious isolations due to the performance further reduce the probability of 92-002 RWCU system are no of IIPCI MSTs. Maintenance is aware of RWCU isolations.
longer 1.ER reportable. the possibility of causing RWCU isolations while working in the RWCU cabinet and ,
exercises the apptopriate precautionary measures.
GE SIL 499 identified a potentially generic This can result in a full Prior to startup, higher rated fuses are Need to implement GE SIL 499 7.
scram if multiple being installed on MSL radiation monitors. "NintAC LVPS Reliability
- project.
problem that may result in prematute failure of the NUM AC Imw Voltage Power Supply failures IMSL Rad This is part of the SIL recommendations. Project is included in the BNP 3 Year Monitos). There have Plan. Installation is scheJuled during caused by high voltage transients. During a transient the LVPS v411 fail and may also been 20 LVPS failures refueling outages m 1995 for both cause the NUM AC line f.ise to open defeating since January 1990, units.
the redund. int LVPS and rendering the involving 14 NUMAC NUMAC drawer inoperative. LER 90417 drawers (MSL, RWM, SIAE).
Fuse failures and other problems in the Feed There have been 2 NED and TS are working on the single The long term project to eliminate this 8.
Water Control legic system have recurred. scrams due to this point fuse vulnerability issue, and will vulnerability is the Digital Feedwater within the past 3 years. research and identify other such fuses. Control modification, PID 04688A,
" Ibis information will be used to increase Feedwater Control System There exists the possibility of other single fuse the sensitivity of maintenance activities in Replacement, scheduled for 1994 in points such that, if blown, would result i.* a scram. l_ER 90o08, LER 90-016 the vicinity of these fuses. unit 2.
Plant shutdown could Plans exist for packing replacement and for N/A
- 9. Reactor recire isolation valves have been repacked with rope packing versus the be required to correct leak repair clamp on bonnet.
previous graphoil due to spacer problems with leakage.
the new split glands. Packingleakage possibihty exists. In addition, the body to bonnet leakage has been noted in past startups, but leakage often has stopped upon full heatup.
_miium. _mmea .
Problem Description Impact Compensatory Actions Long-Term Actions
- 10. The Reactor Feed Pump Turbine shaft driven Operation at reduced N/A PID 02317A, Replace Shaft Driven Oil od pump has limited operatmg range to supply power to make repairs Pump for RFP Turbine with Motor adequate od pressure. As a result, the could sesult if the Driven Pump, is in the 3-Year Plau, auxiliary motor driven oil pump must run motor driven pump with a 1995 unit 2 implementation centinuously to deliver adequate oil pressure. fails. (fhis pump has date.
j been very reliable.)
l
- 11. Mechanical and electronic parts failures in the There have been taree The mechanical portion of the tuibine and Additionally, an evaluation to replace Reactor 1 ecdpump Control system. PPDS power reductions (one pump were rebuilt last outage. The Motor the electro-mech.smcal ce ntrols is 0015, 1990 mechanical and two Gear Unit wdl be inspected, adjasteJ. and planned to be complete by August electrical failures) lubricated prior to startup. A RFP 1993.
during the last 2 years. reliability study is in progress to make )
recommendations for short and long term l improvements. l Turning gear for main turbine does not operate Can cause delays in A temporary mod is in place that removes Replacement of bull gear is scheduled l 12.
m fast speed due to a worn bull gear. power ascension, but the high speed function. Special procedure for next outage.
no operational is in place that defines required operator i I
problems at power. actions for operating lift pumps to compensate.
EllC system instabilities and component Turbine trips are a Mercury wetted relays have been replaced Replacement of mercury relays with 13.
possible result of EllC with new mercury relays. Seals are being electronic components. Replacement failures have occurred. Viton seals used EllC system are undergomg analysis for suitability. system probleins. evaluated by Milwaukee School of of the Viton seals with more suitable l material may be required depending on I Mercury metted relays have had past failures Engineering, plus liarris Plant has the same due to age, ca ssing turbine control valve seals installed, and their operational success analysis and operational esults. These with these seals is being monitored. areas are being evaluated.
testing to tesult in a scram.1.ER 92 001 Past power reductions Special procedures for velocity flushes are PID P0074 A, Installation of Anti-
- 14. Circulating water system debris filters require frequent backwashes. PPDS 0023,1990 have been necessary to have recently been deveksped wt ich will fouhng Coatings in Circulating Water perform these back not require a reduction in power to clean System, is in the 3-Year Plan, flushes. inlet piping. If a downpower would be scheduled for 1994 for unit 2. This required, the backwash evolution will be will reduce the marine growth im coordinated with power reductions for piping and tilters.
scheduled valve testing.
Operators must be Operators are familiar with the actions System is the long range plan for an
- 15. Quindar failures have caused loss of microwave si.pervisory controls for Caswell dispatched to manually needed uten dispatched to Caswell in the upgrade, currently with a 1999 Beach mean discharge equipment. Equipment take control. Also will event of failures. implementation target; carher is oIJ and not reliable. Equipment is obsolete, cause loss of status implementation date will be pursued.
and replaement parts orlen not attainable. monitoring and alarrns to the contsof room.
l L ._ . . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _
Problem Description - Impact Compensatory Actions IAng-Term Actions 16; Circulating water ocean discharge pumps Environmental Tech Additional PM routes have been An evaluation is in progress int :
experience periodic snosor trips. These are Specs non-comphance established. . Data coNection is in progress possibly replacing .me ,_".. - -_
synchron ms motors, versus induction, and '. ~on canal level is . to aid is norther e=h==cessents. For seneer with a induction niceer for have had several diode ring failures, dampened posenble. Redeced CW enasaple, she need for better rheostat sneermiseent operacion as canal level .
winding induced probleens, and degradation l intake flow could resek adjustment of the synchronous wohage was changes, which would reduce she -
due to cycling that is needed to control is power reductions. recently determined. start!stop demand shat is detrimental so .
discharge canal level. Ples high maineenance she synchronous anocers. >
costs.
- 17. lj hting g and communications power supply Failures cause a loss of Use of the reserve (hard) source estil the FID 07862A. Replace puheeng and rystem is aging and obsolete, with a history of site evacuation alarms, UPS would Ir eepaered. Sosne time delay Communications U .,n reliability problems. the PA, I of 2 security is needed nor the transfer over to abe Power Supply, is is she 3 Year Plan coenpasers, security reserve source. for'1995. SRG recomenended sneveng monitors, half of forward so 1994. MRO meeting control room halsing, scheduled for early April 1993.
card readers.
'18. Traversing in-Core Probe (l'IP) system TIP required for Co=s==== wish preventive meistessece PfD 06661'reepsests upgrade of the contains agmg and outdated electronics computer updases rouses; monsoor Tir coetrol higic and syssem, including replacement of all vulnerable to failure. Signal control switches during power sweech operation during use. control drawers.
have eshil sted intermittent signal transfer lo maneuvers; could delay logic circuits. Signal amp cards obsolete; with power ascension.
5 cards in stock.
s
- .4 Carshna power & Ught Company
- e e.n ecer.ioono.nc. Brunswick Nuclear Plant Apnl12.1993 MEMORANDUM TO: C. C. Warren J. G. Titrington FROM: J. Anthony Dobbs
SUBJECT:
Actions from Operational Readiness Collecave Evaluation in accordance with OPN 31, Revision 2, Secton 6.4.1.2, a collocave evaluation of operational readiness was completed on Apnl 12,1993 'me following summanzes the actions necessary to be completed pner to Unit 2 startup as agreeo dunng this coilecove evaluation.
- 1. Training covering the following topics will be Manager -
provided to Unit 2 shift operatng crtws prior to Operations, Unit Unit 2 startuo: 2
- a. Condenser Vacuum moorficatior- (for licensed operators)
- b. Stanoby Gas Treatment System m actficatons to address both the over pressunzaton and flow limitation issues
- c. Recent incustry thermo-hyoraulic insacility issues
- d. Rectreutaton Motor-Generator Set ventiation modificaton
- e. Minor changes resuiting from the review of the General Operating Procecures
- f. Startup and Power Ascension Conungency ;
Plan Training l l
t
- 2. Operating shift crew performance will be evaluated Manager -
and corrective actions taken ac necessary, at the Operations, Unit becinnina of each training week during cycle 3 of 2 licensed requalrfication training. This evaluaton will focus on "as-found' performance practces during the performance of Erl! gency Operating Procedures.
- 3. ACR 93-102 - Expiration of Fire Protection LCOs Manager -
due to failure to correct deficiencies. Operatons, Unit 2
- 4. MAC-93-032 - Inadvertent tnp of a running A. O. G. Manager -
building fan during fire detector testng. Operatons, Unit 2
- 5. MAC-93 033 - Shift operators were unable to Manager -
readily confirm the required position of a 230 Kv Operations, Unit breaker. After considerable researen the breaker 2 indication was unavailable due to a WR/JO and the breaker was in the correct (closed) position.
l S. ACR-93-118 - Failure to control Operator Aids in Manager -
! accordance with OP-41. Operations, Unit 2
Meetina Attendees-Plant General Manager, Unit 2 - C. Warren Manager - Operatons, Unit 2 - J. Titrington Startup Reaciness Manager - J. Dobbs Completon of the above items shall be in accordance with the guidelines for acton rtem closure provided wrthin RCl 05.2 (ACTION: Levis, Titrington)
J. Anthony'Dobbs xc: R. Anoerson S. Hinnant B. Levis i
i 1
' ~
CP&L Carolina Power & Light Company Brunswick Nuclear Plant
. a+. :wewoneence April 16, 1993 MEMORANDUM TO: Outage Directors FROM: R. H. Kitchen
SUBJECT:
Unit 2 Startup and Power Ascension Contingencies Attached is the updated listing of problems which have occurred on previous startups and planned actions to prevent or reduce the probability of recurrence.
Listed items are either scheduled in the outage, scheduled during startup, or complete, with the following exceptions:
Number Item Responsibility Status
/. 8 . a Develop a procedure to Maintenance Procedure requested fill and vent Main Staff 04/02/93.
Steam Line Flow Trans- OSPP-PIX-002 in mitters, review.
c.11 Review previous MST/PM I6C Planned prior to events with appropriate s tar :up ,
personnel.
C.13 Review with Operations Ops Warning labels to shifts that RPS bus be ins *.alled on RPS voltage adjustments Voltage adjust-will be made by Mainte- ment controls.
nance.
Please ensure the above items are resolved prior to startup. Status updates !
should be provided to me at extension 2802 or pager 754-0359. A written update on these items will be provided weekly at the outage meeting.
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I' BNP UNIT 2 STARTUP AND POWER ASCENSION wasamer.m,i FIAN 4 PROBLEM 1 CONTINCENCY; RESPONSIBILITY ~ STATUS /COINENTS
- 8. Due to condenser cooling crud a. Develop a procedure to fill. a.- Maint- a. OSPP-PIK002 in review may build up in MSL' flow and vent Main Steam Line Flow Staff transmitters instrument lines transmitters.
and cause spurious Group 1 b. Verify the following b. I6C b. Outage scheduled; isolation. Instruments fill and vented.
Reference:
Operations 2B21'PDT-N006A, N006B, N006C, N006D 2821-PDT-N007A, N0075, N007C, N007D 2B21-PDT-N008A, N0088, N008C, N008D 2B21-PDT-N009A,.N0098, N009C, N009D-(93-ANZF1, 93-ANZE1)
- 9. Lost coupling parts on HPCI/RCIC a. . Inventory and verify parts a. . Mech a. Complete have delayed previous startups. under control for HPCI and RCIC
Reference:
OM6M prior to startup.
- 10. RPV water level instrument a. Verify reference legs full a. Ops a. Complete. Performed spiking can cause scram. prior to startup by channel prior to mode change and
Reference:
Operations /I&C check on RPV drain down. daily by CO surveillance.
2821-LT-N017A-1 2B21-LT-N0175-1 2B21-LT-N017C-1 2821-LT-N017D-1
- 11. . Inadequate SPTMs points to a. Assess SPTMS points opera- a. Ops a. Complete support mode change. ble.
Reference:
Operations /0M6M b. Monitor SPTMS'RTDs for b. T/S b. In progress.
drift. Repair RTDs which indi-cate problems .
- 12. 4160 V equipment breaker a. Conduct a walk-thru of BOP a. Ops a. Complete. OP-50, charging springs off. Bus 4160 V breakers Check all a160 V Breaker Rack-in
Reference:
Operations charging spring motors on and procedure verifies.
springs charged.
- b. Perform PT-12.6, " Breaker b. . Ops b. Complete --Conducted Alignment surve111ance"'to Wekly verify E Bus breaker status.
RHK13 Page 3
. I BNP UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCY PLAN PROBLEM CONTINGENCY RESPONSIBILITY STATUS / COMMENTS
- 13. AOC Cuard Bed high moisture has a. Perform N2 drying of guard a. Ops a. Outage scheduled delayed startups. bed one week prior to startup
Reference:
Operations per 0?-33, Section 8.4.
- 14. Non-conservative APRM setpoints a. Conduct simulator training a. Training a. Complete have occurred at BNP and several on alternate power indications.
other plants, b. Licensed operators perform b. Ops b. Conducted routinely at
Reference:
' Operations hourly verification of APRM CAF power settings in conjunction with Period Core Evaluation (P1)
- 15. Improper operation of Reactor a. Cycle valves while obser- a. Ops /I&C a. Complete Head Vent Valves (2B21-F003 ving limit switch performance andF004). locally and RTGB indications.
Reference:
16C
- 16. Improper indication on CAC-V49 a. Replace CAC-V50 switch a. I&C a. Complete and V50 valves. cover.
Referance: I&C b. Replace quick disconnects. b. I&C b. Complete
- c. Energize and open CAC-V49 c. Ops /I&C c. Complete and V50 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then cycle valves to verify proper operation prior to startup.
- 17. Unreliable operation -G SJAE Hz a. Conduct Hz analyzer trai- a. Training a. Complete analyzers. ning for Maintenance prior to
Reference:
I&C startup.
- b. Ensure vendor representa- b. I&C b. Complete. Work tive is on site prior to start- Authorization in place.
up to replace columns or rebuild valves, if necessary.
- 18. SJAE valves in vertical runs may a. Set limit switches to a. I&C a. Complete bind (OG-V10, Vil, V13, and SJE- reduce potential tripping of V4;
Reference:
EWR #07539). the torque switch when the
Reference:
I&C valve " pops" out of the seat.
- b. Supply 24-hour coverage to b. Maint/ Ops b. Scheduled during support Operacions to stroke startup valves manually.
RHK13 Page 4
, . ~ . . . . . . _ . .
+. ..
l i
BOP UNIT 2 STARTUP AND POWER ASCENSION CONTINCENCY PIAN B. 165-1000 usic PROBLEM CONTINGENCY- RESPONSIBILITY STAIUS/ COMMENTS
- 1. RFPT fails to reset or trip from a. Conduct MI-10-519F, "Reac- a. Mech a. Scheduled during Control Room. tor Feedpump Turbine Overspeed startup
Reference:
Operations /I&C/ Technical Trip Test" prior to placing Support RFPT in service.
- b. Conduct PM 91-010. " Reactor b. OM6M b. Scheduled during Feedpump Logic Redesign" c--ry- s tartup tance testing.
Reference:
Operations operations. startup
- 3. SULCV fail open or shut, a. Verify full operation of a. Ops a. Scheduled during
Reference:
Operations /I&C/ Technical SULCV prior to startup per CP- startup Support 01, "Prestartup Checklist."
- b. Rebuild SULCV actuators and b. I&C install new valve positioners. b. Complete
- c. Install five micron air c. I&C filters to minimize air-related c. Complete problems.
- 4. Water in off-gas pipe caused by a. Perform service air purge a. Ops / T/S a. Outage scheduled valve failure for loop seal fill of SJAE per OP-30, Section 8.6.
at Off-Gas Drain Tank (loss of (Ensure drain cap is removed vacuum). from recombiner during this
Reference:
Operations evolution).
- b. Turn on recombiner heat b. Ops b. Outage scheduled strips and verify temperature rises to =400*F'(low tempera-ture indicates that the catalyst bed is wet).
- c. During startup, verify that c. Ops c. Scheduled during the Off-Cas loop seal level is startup normal twice per shift until
>50% power.
I RHK13 Page 5
.. s.
57 UNIT 2 STARTUP AND POWER ASCENSION CONTINCENCY F'AN PROBilM CONTINCENCY RESPONSIBILITY STATUS / COMMENTS
- 5. Steam packing exhausters have a. Verify Steam Packing a. Ops / T/S a. Outage scheduled been found filled with water on Exhauster is drained per OP-some startups. 26.1 Section 8.2. b. Ops / T/S b. Outage scheduled Re fe rence : ' Operations b. Verify Steam Packing Exhauster loop seal is filled with water to prevent loss of vacuum.
- 6. TIP drive / drawer failures have a. Exercise TIP system prior a. T/S a. Scheduled during held up power ascensions. to startup by performance of s tartup
Reference:
Operations PT-1.9E, " Axial Alignment of Traversing Incore Probes."
- 7. SRV tailpipe temperature a. Monitor SRVs closely during a. Ops a. Scheduled during increases may be observed. startup. (Reference EUR 8397) startup
Reference:
Operations /I&C b. -Operations review' actions b. Ops b. PLP-17 briefing at associated with stuck-open SRV power addresses this prior to performance of PT- issue.
11.1.2, " Automatic Depressuri-zation System and Safety Relief 3
Valve Operability Test"
- c. Verify spare; certify c. c. Complete replacement SRV base body, pilot, and solenoid valve.
- 8. Steam leaks in drywell or MSIV a. Conduct inspection at rated a. Ops /Maint/ a. Scheduled during pit. pressure. Evaluate repair T/S startup
Reference:
Operations requirements.
- ping" test as a. I&C a. Outage scheduled
Reference:
Operations one of the final drywell closeout items. (2MST-ADS 23R and 2MST-ADS 41R)
RHK13 Page 6
w g.
B~'P UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCT PLAN
' PROBLEM CONTINCENCY RESPONSIBILITY.- " STATUS / COMMENTS'
- 10. Possible problems with instru- a. Perform operability tests- a. Ops a. Outage scheduled ments worked on instrument rack of RHR, Core Spray, and SLC modification (PM 92-071). systems prior to startup.
Reference:
Operations / Technical b. Verify HPCI operability by b. Ops b. Scheduled during Support performance of PT-9.2, "HPCI startup System Operability Test" during startup.
- c. Verify Reactor Recircula- c. Ops c. Scheduled during tion instrumentation by perfor- startup mance of PT-13.3, " Reactor Re-circulatien Jet Pump Operability Below 25% Rated Power" and by Performance of PT-13.1, " Reactor Recirculation Jet Pump Operability."
- d. Channel check Main Steam d. Ops d. Scheduled during Line Flow Transmitters (2-C32- startup. CP-02, 03, and PDT-N003A, B, C, D). 04, check steam flow indications as part of alternate power indication.
- e. Verify the following e. Ops e. Scheduled during reactor instrumentation as startup required by CO DSR: 2B21-LT-NO36, NO37, 2B21-PT-N021 C and D, 2B21-PDT-N006A, N006B, N007A, N0078 N008A.' NOO88, N009A, N0095.
- 11. Delays in power ascension to a. Place Heater Drain system a. Ops a. Scheduled during allow cleanup of heater drains. in cleanup mode as'eerly as startup per CP-01.
Reference:
Operations possible per OP-35,.Section 5.1.
RHK13 Page 7
+ t. I BNP UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCY PLAN PRGBLEM CONTINGENCY RESPONSIBILITY STATUS / COMMENTS
- 12. PT 2.6.6 not performed before a. OG-03, " Primary Containment a. Ops a. Scheduled during and after each drywell entry and Access Control" controls dry- startup exit to verify operability, well entry at power and directs
Reference:
LER 1-91-008 performance of PT-2.6.6,
" Primary Containment Airlock l Interlock Operability Check" prior to and following each drywell' entry.
- b. Pre-job brief for drywell b. Ops b. PLP-17 brief at power entry should include require- addresses this issue.
ments for control and post-entry tests required.
13 Reactor Recirculation Valves a. Determine alternate packing a. T/S a. Complete 2B32-F023A, B, and F031 A B. style and verify that.it avail-have a history of leakage able on site.
problems. New style packing and b. Verify that an active, b. PATM b. Complete.. Work Auth.o-packing gland installed but approved contract exists wiht rization number ZS70130017 packing or flange leakage is a Leak Repairs, Inc.
significant possibility. c. Perform preliminary engi- c. T/S c. Complete neering for leak repair clamp or use of alternate packing and valve backseating.
RHK13 Page 8
BNP UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCY PIAN C. 1000 osit to Full Power PROBLEM -CONTINGENCY RESPONSIBILITY STATUS / COMMENTS
- 1. Fuse failure in FULC. a. Complete fuse investigation a. T/S a. Complete l
Reference:
LER 2-90-008 and 2-90-016 (EACTS Action Item 905820). '
- b. Complete fuse investigation (EACTS Action Item 9150005). b. T/S b. Complete
- 2. Water in main lube oil, a. Obtain chemistry analysis on a. E&RC a. After generator is
Reference:
Operations routine basis to verify accep- gassed.
table moisture level.
- b. Verify that main lube oil b. Ops conditioner is in service and b. Complete monitor on routine AO rounds.
- 3. Generator core monitor fails to a. OP-26, Section 8.19. Infre- a. Ops a. Complete reset. quent Operations, should be
(
Reference:
Operations revised to include Main Genera-tor Core Monitor startup testing.
- b. Perform OP-26. Section 8.19, b. Ops b. Scheduled during during main turbine-generator statup startup.
- 4. Suspended solids in RPV when HP a. Flush HP FW heaters back to a. Ops a. Complete FW heaters placed in service. condenser prior to startup per
Reference:
Operations OP-32, Section 8.13, Long Cycle Cleanup.
- 5. Main generator lockout and a. Verify visually that main a. T/S a. Complete turbine trip because of an generator and transformer trip improper relay setting. and lockout relays have correct
Reference:
Operations setting. (Located in Control Room Backpanel XU-8.)
RHK13 Page 9
~ o.
BNP UNIT 2 STARTUP AND POWER ASCENSION CONTism.amd FIAN
-PROBLEM CONTINCENCY ' RESPONSIBILITY STATUS /ColetENTS
- 6. Main generator manual / auto a. Perform portions of OSPP- a. 'T/S./I&C a. Complete voltage regulator failure. GEN 007, Main Generator Voltage
Reference:
LER-2-91-005 Regulator Board' Replacement and Functional checkout" as directed by' system engineer prior to startup. .
- b. Ops b. Scheduled during,
- b. . Conduct FT-40.2.11. " Main startup Cenerator Voltage Regulator Manual and Automatic Operctional Check" during startup.
~
- 7. Main generator bearings low a. Check bearing ground a. I&C a. In progress meggar readings. readings routinely prior to
Reference:
Operations startup per OPM-BPD002, (Generator-Exciter Bearing Insulation Check."
- 8. EHC controls instability / a. . Train operators on EHC a. Training a. Complete failure. controls and required startup
Reference:
LER 2-92-001 testing.
- b. Conduct PM 89-073, " Unit 2' b. OM&M b. Scheduled during' Partial Arc Conversion" Accep- startup-tance Testing.
- 9. Main turbine rolls off turning a. Implement temporary modifi- a. T/S a. . Complete gear. cation to disable high speed
Reference:
Operations /I&C/ Technical operation of turning gear. ,
Support b. Evaluate use of reduced b. T/S b. l Complete. 2SP-92-012, number of lift pumps, as Revision 1 required.
- 10. Spurious RUCU isolations. a. Review with Control Room a. Ops a. Complete. Warning-
Reference:
LERs.2-91-004, 1-91-028, operators the caution regarding ~
signs posted on-Steam 1-92-014, 1-92-015 operation of switches associated Imak Detection System.
with the Steam Isak Detection system.
- 11. Main Turbine rub or high a. Verify equipment and a. T/S a. Complete vibration during startup. personnel available.
- b. Required procedures. b. T/S b. Complete
- c. Balance weights on site. c. T/S c. Complete-RHK13 Page 10 L - _ _ _ _ _ _ _ .-
BNP UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCY PIAN PROBLEM CONTINCENCY- RESPONSIBILITY STATUS / COMMENTS
- 12. Actuations, isolations and/or a. Review previous MST/PM a. Maint a. Planned prior to scram due to improper MST/PM events with appropriate person- startup.
performance or wrong plant nel.
conditions. b. Verify plant condition b. PATM/UCC
Reference:
LERs 2-90-009, 2-91-001, requirements as part of b. Complete 2-91-005, 2-91-018, 2-91-021, 1 scheduling process.
014, and 1-91-018
- 13. Reactor scram during performance a. Replacc #2 TSV Master / Slave a. I6C a. Complete (VR/JO 91-of MST-RPS35R (Main Turbine Stop Logic Board. AJUB1)
Valve Testing) due to b. Perform 2MST-RPS35R prior to b. I&C b. Complete 1/10/93 malfunction of master / slave startup.
logic for #2 TCV.
Reference:
LER 1-92-005
- 14. Attempts to adjust RPS "A" bus a. Install warning sign on each a. Ops a. To be complete prior by an Auxiliary Operator without RPS MG Set. to Unit 2 startup.
using the VR/JO process resulted in a voltage overshoot and a 1/2 scram, 1/2 Group 1 signals, and Group 1,2,3,5, and 8 iso-lations.
Reference:
LER 1-92-022
- 15. Reactor scram - Transmission a. Establish strict controls a. T/S a. Complete. Customer /
Maintenance Relay technician did for switchyard work. Supplier Agreement PLP-24 not return overcurrent relay and 2SP-93-019.
setting to correct setting b. Develop list of work per- b. T/S b. Complete following calibration. formed on the off-site electri-
Reference:
LER 1-91-007 cal supply system during the outage.
- c. Develop recheck / reinspection c. T/S c. Complete. Transmis-list based on work performed. sion/ Relay crew calibra-tion data sheets now require independent veri-fication of return to service settings.
RHK13 Page 11
BNP UNIT 2 STARTUP AND POWER ASCENSION CONTINGENCY PLAN PROBLEM CONTINCENCY.. RESPONSIBILITY ' STATUS / COMMENTS. ;
- 16. MSR Level Controllers not a. Tune controllers during a. I&C a. Scheduled during controlling at setpoint. startup. (UR/Jos 91-ARHS1, startup
Reference:
I6C/ Technical Support ASAS1, ASBQl, ASCD1, ASCSI, ASDH1, ASFBI, AWAGl)
- 17. Heater drain level controllers a. Conduct functional verifica- a. I6C/ T/S a. Complete not controlling properly. tion of Heater Drain loops per
Reference:
Technical Support 2-SP-93-016 prior to startup.
- 18. Due to improved ventilation in a. Issue EER to allow installa- a. T/S a. . Complete. EER 93-the Main Steam Tunnel, problems tion of air flow shield around 0324 issued could be experien(2d in satis- temperature switches.
factorily performing PT-2.1.22. b. . Install heater as required b. Mechnical
Reference:
Technical Support by EER. 93-ALLX1 Maint. b. Awaiting material.
Outage scheduled.
- 19. Inadequate on-site personnel to Implement staffing plan as a. All a. Scheduled during rapidly respond to operational required by " Unit 2 Startup and startup requirements. Power Ascerution Performance
Reference:
Operations / Maintenance Objectives and Management Plan."
RHK13 Page 12
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% ...* / APR 2 91993 f
4 Docket Nos. 50 325, 50 324 License Nos. DPR-71, DPR 62 Carolina Power and Light Company ATTN: Mr. W. Cavanaugh, 111 President and C00 P. O. Box 1551 Raleigh, NC 27602 1
Gentlemen:
1
SUBJECT:
COMPLETION OF AC110NS SPECIFIED IN CONFlRHATORY ACTION LETTER (CAL) BRUNSWICK UhlT 2 This letter documents our telephone discussion on April 27, 1993 in which the U.S. Nuclear Regulatory Commission (NRC) concurred with the Carolina Power and Light (CP&L) Company's determination that the Brunswick Nuclear Plant (BNP),
Unit 2, had successfully complied with the commitments made to the NRC as prerequisites to the restart of Unit 2.
In a public meeting held in Southport, North Carolina on April 26, 1993, CP&L affirmed that the commitments had been met and that CP&L was ready to commence the startup of Unit 2. This was also certified by the CP&L letter dated April 26, 1993, that the licensee commitmentf confirmed by NRC Confirmation Action Letter (CAL) of December 18, 1992, have been adequately addressed.
The NRC staff, under the cognizance of the Brunswick Assessment Panel (BAP),
reviewed the preparations for restart, independently verified CP&L activities via inspection, and affirmed that the CP&L commitments had been complied with and that there were no significant regulatory issues open that would preclude the restart of Unit 2. The Chairman of the BAP recommended in a memorandum dated April 27, 1993, that the Regional Administrator concur with restart of Unit 2.
CP&L may proceed with the restart of Unit 2 in accordance with the agreed upon Startup and Power Ascension Plan, observing all hold points in the process.
Should you have any questions concerning this matter, please contact us.
Sincerely, v'Y Stewart D. Ebneter Regional Administrator cc: (See page 2)
/
acnamneu4s @ lf'D
APR 2 91993 Carolina Power and Light Company 2 tc: R. A. Anderson Robert P. Gruber Vice President Executive Director Brunswick Nuclear Project Public Staff NCUC P. O. Box 10429 P. O. Box 29520 Southport, NC 28461 Raleigh, NC 27626 0520 Ms. Gayle B. Nichols Staff Counsel SC Public Service Commission P. O. Box 11649 Columbia, SC 29211 H. Brown Plant Manager Unit 1 Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 C. Warren Plant Manager Unit 2 Brunswick Steam Electric Plant P. C. Box 10429 Southport, NC 28461 Mr. Mark S. Calvert Associate General Counsel Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 Kelly Holden Board of Commissioners P. O. Box 249 Bolivia, NC 28422 Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environment, Health & Natural Resources P. O. Box 27687 Raleigh, NC 27611-7687 H. A. Cole Special Deputy Attorney General State of North Carolina P. O. Box 629 j Raleigh, NC 27602 j 1
w....w..u w.u.- s m.o,,ovL 4, 4
[d,kno Av0 $- h. & L 2 24 Hour MesMa contact Line S 9446818 Camilna Power &IJght Extemat Communications P.O. Box 1551 Raleigh N.C.27002 BRUNSWICK UNIT 2 GETS NRC PFRTART APPROVA!, April 27,1993 Carolina Power & Light has received Nuclear Regulatory Commission appmval to restan Unit 2 of the Brunswick Plant.
NRC appmval to testart Unit 2 was issued at 5:50PM on April 27. Plant personnel LmWJataly began a detailed start-up process that will ensure a safe. controlled and dallberate return to service.
"We are pleased that very soon we will again be pmviding customers electric power generated at the Brunswick plant. Over the next several weeks, we will be going thmugh a very careful, very deliberate startup and power ascension p.ucess that will lead to full power operations in May," said Roy A. Anderson, Brunswick Plant Vice President.
, Anderson uid the pmcess has been designed to assure thu modifications made in 1
operating systems perform pivperly as the plant moves toward full power operations.
I "The fint mission of the plant is to provide a sde, reliable source of electric generation l
for CP&L customen," Anderson said, "The startup and power ascension plan is designed to assure that this mission is met."
Both units of the Brunswick Plant were removed from service on April 21,1992. Unit I remains in a refueling outage and is scheduled to retum to service in the fall.
'Itc restart process includes: 1) a detailed testing plan to ensure that all systems are operating properly; 2) several " hold points" at which the unit's performance will be ast*<tM before moving up to the next step in process; 3) specific points at which management 1
approval will be required to continue the process.
Post it" brand fax transmmalmemo 76n **'>e==* /
w b Nd(Yl5 ~ fLkHi'ld l a u o.,< -,
356- 2563 **"(9I915%-UdS ~
1 INRL