ML20043E145

Forwards Summary of 900524 Meeting in Region II Ofc Re Results & Corrective Actions on Operational Evaluations. List of Attendees & Handouts Also Encl

ML20043E145
Person / Time
Site:	Brunswick
Issue date:	06/01/1990
From:	Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Eury L CAROLINA POWER & LIGHT CO.
References
NUDOCS 9006120114
Download: ML20043E145 (14)

Text

{{#Wiki_filter:. e o-l f June 1, 1990 Docket Nos. 50-325, 50-324 License No. DPR-71 DPR-62 t Carolina Power and Light Company i ATTN: Mr. Lynn N. Eury Executive lice President Power Suppl.y P. 0. Box 1551 Raleigh, NC 27602 Gentlemen:

SUBJECT:

MEETING

SUMMARY

- OPERATIONAL EVALUATIONS Representatives of Carolina Power and Light Company (CP&L) met on May 24, 1990, at the NRC's Region 11 office to discuss the results and corrective actions related to 'the recent Operational Evaluations at the Brunswick site.

A list of attendees, e meeting summary, and a copy of the handouts are enclosed. In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room. Should you have any questions concerning this matter, please contact us. Sincerely. (ORIGINALSIGNEDBYJ.E.ROSENTHALFOR) Ellis W. Merschoff, Acting Director Division of Reactor Safety

Enclosures:

1. List-of Attendees 2. Meeting Summary 3. CP&L Handout 4. NRC Handout ec w/encis: R. B. Starkey, Jr. Vice President Brunswick Nuclear Project Box 10429 Southport, NC 28461 (cc w/encls cont'd - See page 2) 9006120114 900601 DR ADOCK 05000329 ft.@f s / g

I ~ O Carolina Power and Light Company 2 June 1, 1990 (cc w/encls cont'd) J. L. Harness Plant General Manager Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 R. E. Jones, General Counsel Carolina Power & Light Company H P. O. Box 1551 Raleigh, NC 27602 Ms. Frankie Rabon Board of Commissioners P. O. Box 249 Bolivia, NC 28422 Chrys Bagget State Clearinghouse Budget and Management 116 West Jones Street Raleigh, NC 27603 Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environment, Health & Natural Resources P. O. Box 27687 Raleigh, NC 27611-7687 i H. A. Cole Special Deputy Attorney General State of North Carolina P. O. Box 629 Raleigh, NC 27602 Robert P. Gruber i Executive Director Public Staff - NCUC P. O. Box 29520 Raleigh, NC 27626-0520 - b c w/ encl: ocument Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission Star Rte. 1 Box 208 Southport NC' 28461 ~ l Ril:DRS RII:DRS RI:08S R 1 (v

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jj-ENCLOSURE 1 a LIST OF ATTENDEES ' U. S. Nuclear Regulatory Commission C. W. Hehl, Deputy Director DRP ,,i< E. W. Merschoff, Acting Director, DRS p L. A. Reyes, Director, DRP S. D. Ebneter, Regional Administrator J. Milhoan Deputy Regional Administrator R. E. Carroll, Jr., Project Engineer /RII-J. E. Rosenthal, Acting Deputy Director, DRS 'C. A. Casto, Chief, Operator Licensing Section 2, DRS, RII T. A. Peebles, Chief Operations Branch, DRS, RII E. G. Adensam, Projects Director /PDII-1/NRR D. J. Lange, Chief, Examination Development Section, NRR W. Levis, Resident Inspectcr, BSEP H. C; Dance, Section Chief. DRP G. Lainas, NRR/DRP Carolina Power Company R. Starkey, Vice President, Nuclear Operations A. B. Cutter, Vice President, Nuclear Services R. W. Watson, Senior Vice President, CP&L L.fl. Loflin, Manager, Nuclear Licensing, CP&L L. W. Eury, Executive Vice President, CP&L L. H. Martin, Manager, Nuclear Training i l ] I l a

i ENCLOSURE 2 MANAGEMENT MEETING

SUMMARY

A meeting was held at the NRC's Region 11 office with Carolina Power and Light Company (CP&L) on May 24, 1990, to discuss the results and corrective actions related to the recent Operational Evaluations conducted at the Brunswick site. Following openino remarks by the NRC Regional Administrator on the specific NRC concerns, ChaL's Senior Vice President commented on their desire to determine the root cause of the evaluation results, and outlined the objectives for the short term recovery plan. The Nuclear Training Manager described the licensed operator upgrade training plans, followed by a synopsis of the root cause assessment process by the Vice President for Nuclear Services (Enclosure 3). The CP&L formal presentation was closed by remarks from the Vice President Brunswick site and the Senior Vice President. They stated their conclusions of the evaluation results, and their expectations for future performance, following the CP&L formal presentation, the NRC and CP&L discussed the logistics for future Operational Evaluations. Additionally, the NRC provided CP&L with some conclusions from the NRC assessment of the Operational Evaluation (Enclosure 4). The Deputy Regional Administrator closed the meeting by thanking Carolina Power and Light Company representatives for the presentation. L l-l

s 4 ' ENCLOSURE 3 3.,. a. j CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAN ELECTRIC PLANT i t LICENSED OPERATOR UPGRADE TRAINING PLANS AND ROOT CAUSE ASSESSMENT l l-MAY 24, 1990 (SLIDES) l

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i AGENDA i INTRODUCTION R. A. WATSON PRINCIPAL ISSUES L. H. MARTIN l l SHORT TERM TRAINING PLANS L. H. MARTIN l l l l . ROOT CAUSE ASSESSMENT A. B. CUTTER CONCLUSION / EXPECTATIONS R. B. STARKEY R. A. WATSON 3 (SLIDES)

_ - _ _ ____. _._ _ _.. y

7. -

f PRINCIPAL ISSUES o COMAND AND CONTROL THE' ROLES OF THE KEY CONTROL ROOM PERSONNEL 1 HAVE BEEN CLARIFIED THE SOS IS IN CHARGE e f i L o COMUNICATIONS PLANT MANAGEMENT REVIEWING EXPECTATIONS WITH EACH SHIFT FOR CLEAR CONCISE COMMUNICATION l 5 l REINFORCE DURING SIMULATOR EXERCISES 1 l L I (SLIDES) .y -..e-s-, - ,e-n w.--y.,,......ser, g-w ,n,..,.,,,,.,,,,--e.... ,.--m- ... ~,-,---,..

1 j n.- I* e. PRINCIPAL ISSUES (Courzuuto) 1 o IMPLEMENTATION 0F EMERGENCY OPERATING PROCEDURES E0P REVIEW EXERCISES INCLUDE LEVEL CONTROL PRESSURE CONTROL EMERGENCY DEPRESSURIZATION PRIORITIZATION AND REC 0VERY ACTIVITIES o CLASSROOM PNILOSOPNY/ INTENT OF E0P'S (SLIDES)

a; REMEDIAL TRAINING RECONSTITUTED SHIFTS SIX HOURS CLASSROOM (MINIMUM) TWENTY-FOUR HOURS SIMULATOR (MINIMUM) AT LEAST THREE SESSIONS EVALUATION AT END OF EACH SESSION l FULL SCALE EVALUATION (CP&L & GE) l GO-NO GO DECISION - 5/30/90 SHIFT E (LQR1 EIGHTEEN HOURS CLASSROOM-(MINIMUM) FORTY-EIGHT HOURS SIMULATOR (MINIMUM) AT LEAST NINE SESSIONS MULTIPLE EVALUATIONS FULL SCALE EVALUATION (CP&L & GE) g GO-NO GO DECISION - 5/30/90 l l (SLIDES) L

i ROOT CAUSE ASSESSMENT PROCESS i 0 TEAM MEMBERS CHUCK OLExIK HNP OPERATIONS SUPERVISOR l (TEAM LEADER) (SR0) CHARLES BETHEA RNP TRAINING MANAGER (HAS HELD SR0) JOHN TITRINGTON BNP MANAGER OPERATIONS SUPPORT (SRO) l FRED LOWERY CP&L LOANEE TO INP0 (HAS HELD SRO) i RNP OPERATIONS MANAGER UNTIL 1988 JIM BOONE BNP HPES COORDINATOR (TEAM (HAS HELD SR0) FACILITATOR) l ( (SLIDES) l l

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./ R00T CAUSE ASSESSMENT PROCESS (CONTINUED) x I o TEAM WILL USE HUMAN PERFORMANCE EVALUATION SYSTEM (HPES) c . WILL FOLLOW INP0 METHODOLOGY - Roor CAUSE ANALYSIS INP0 Go0D PRACTICE 0E-907

• PROCESS 1

p - START WITH "WHAT HAPPENED" L i - COLLECT DATA (FACT FINDING NOT FAULT FINDING) - ASSESSMENT USING HPES METHODOLOGY l

• HoW
• WHY(5)

- INPUT TO CORRECTIVE ACTION DETERMINATION u o SCHEDULE i L 5/29 START 6/30 CORRECTIVE ACTION TO NRC L L (SLIDES) .2

y )f 4,, u+ y N ENCLOSURE 4 ,, y a E ^ LEVEL'OF. DIFFICULTY COMPARSION FOR SIMULATOR' SCENARIOS m_ ..m ~o i .I io .l BSEP' <a a h' a SRV-stuck FW.line'Brk, l 4.: loss of CSW, normal FW and .ATWS, Loss of Loss of HP, p ATWS 1 CRD and.1 RHR Loss of I vl.. j p-pump E-Depress p i k

16. Loss of E-busi-Trip RFP, STM DG fall, LOOP LOCA, with one leak, MSIV lsol ATWS, MSIV?! sol, F-

Core Spray-Pump ATWS, HPCl_. f ail Loss of 3'SLCP

.out of sarvice U. 9. DG f ailure, LOOP, ATWS, STM leak, Stm Leak, no HP. RCIC trip,.HPCI LVL INST fail, inj, LOP /LOCA, O L AUTO control fail LOSS of RPS-A, 1-DG f ail Loss of.480bd, HPCI auto start p

12. AUTO. Scram Fall, Loss of HP inj.,

HPCI fall,; Load: LOCA,Jand Loss of-RRP overspeed, reject w/o BPV, .E-bus . Fuel Fall, MSIV .STM leak (D/W), !/ Isol DIV I fails 1.i<, Loss-of vacuum,

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Stuck open.SRV, ATWS, noiFW, ATWS MSIV 1s01, 1 SLCP p' ~ .OOS, >HCTL DG;OOS, LOOP /LOCA,. E

13. Loss - of. vacuum,

.MSL-break LVL L Press inst: h fall, Loss of RHR loop 1, RCIC STM f6[ ATWS, Loss of HP Leak - i nj ec t i on c Y.. k i r i i g., s .I,' fj

TABULATION OF CREW AND INDIVIDUAL FAILURES BY SCENARIO I SCENARIO No.3 INDIVIDUAL CREW I 4. I6. X X 9. X X i.- 12. X X 7. 13. X X 6. X X I i e

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