ML20154D341

Summary of 880714 Meeting W/Licensee in Rockville,Md Re Specifics of Recently Submitted Justification for Continued Operation Concerning Hpci/Rcic Valve Operability & Safety Sys Reliability.List of Attendees,Agenda & Viewgraphs Encl

ML20154D341
Person / Time
Site:	Brunswick
Issue date:	09/12/1988
From:	Mozafari B Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-68674, NUDOCS 8809150247
Download: ML20154D341 (39)

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, , , Sentember 12, 1988 DISTR BUTION:

Docket Nos. 50-325 3ee next page and 50-324 LICENSEE: Carolina Power & Light Company (Ci rA )

FACILITY: Brunswick Steam Electric Plant, Units 1 and 2

SUMMARY

OF M:ETING HELD ON JULY 14, 1988 - HPC!/RCIC VALVE OPERABILITY AND SAFETY SYSTEM RELIABILIVY (TAC NO. 68674)

Background

A meeting was held in Rockville, Mary 1cnd on Thursday, July 14, 1988, to discuss the specifics of CP&L's recently submitted Justification for Continued Operation (JC0) with respect to Brunswick Steam Electric Plant, Units 1 and

2. The mezting also was to address safety system reliability in light of a recent trend invciving an increased nurrber of reportable ever's. Participants in the meeting included representatives of the NRC and CP&L. The list of attendees is provided as Enclosure 1.

The specific events which focused attention on Brunswick's HPCI system were:

1. A turbine steam supply valve (F001) failed to open and the HPCI systers was declared inoperable on June 30, putting Unit 1 in a 14 day LCO.

2. On July 5, upon determining that an undersized motor coerator was used in the design for valve FOC6 (M0V injection valve), Unit 2 entered a 14 day LCO.

Tne licensee developed a JC0 to support operation until the next refueling outages without making any physical changes to the injecticn valves. Subse-quently, CP6L decided to shut down Unit 1 to replace the defic 12nt motor operator on injection valve F006. Then, af ter Unit I was restarted and reached 607, Unit 2 would be shut down for similar repair work. The NRC had concr.rns about che JC0 and safety system reliability, whicn the meeting was organized to addre7s. The agenda communicated to the licensee in a teleconference is shown in Enclosure 2.

Suuna ry 1 in response to the questions reflected in the agenda, the licensee made a slide presentation addressing NRC concerns on technical issues, and discussing f ailure modes, corrective acticas and the bases for projected future performance. The slides presented and clarifying information are provided in Enclosure 3.

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8809150247 080912 4 ADOCK 050 gDR l3 i

2 At the close of the meeting, CP&L summarized the following cction items:

Complete short term rep 31rs.

1. Remove starting resistors en F013 valves.

2. Investigate whether removal of starting resistors from other similar valves is appropriate.

3. Reverify findings of INPO 50ER 84-7.

4. Evaluate temperature effects r. motor heater and shunt field.

Lo,.9 term program to be oeveloped o include the complete analysis of safety related valves with resper to design basis requirements.

Schedule 08/15/88 - Prepare a plan and schedule that will establish milestones and completion dates for the analysis phase.

12/31/88 - Complete the design analysis of safety related valves.

02/28/89 - Complete development of a corrective action tmplementation plan to address problems identified.

Along with these CP&L propusals, the NRC requested Intermediate briefings on the progress relative to the above-mentioned actions.

The licensee was instructed to prepare a confirmation of corrective actions letter specifically addressing the very near term actions to support re; tart.

Also, a commitment was made by CP&L to ubtain NRC approval prior to restarting Unit 1 after the valve repair outage.

A followup letter is expected in a couple of weeks af ter this meeting focusing on near term and long term actions, it is expected that the licensee's program will be somewhat evolutionary.

.6 Brenda Mozafari, Project Engineer Project Directorate 11-1 Division of Reactor Projects I/II

Enclosure:

As stated cc w/encis:

See next pape OFC :PE:PDE1:URFR:W.P021 URPR :

. . . . . : . . . . . . . . . . . . : bf ......:............:..................................................

sam  :

NAME

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DATE :9/ /88: :9/ 'V88  :

l OISTRIBUTION FOR MEETING SUMARY DATED: September 12, 1988 Facility: Brunswick Steam Electric Plant, Units 1 and 2

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"Docket Filei : MC Participants NRC~PDR Local PDR B. Buckley PDII-1 Reading N. Grace, RII E. Adensam L. Reyes, RII P. Anderson J. Sniezek (12G18)

8. Mozafari C. Lainas B. Buckley T. Marguiles (12020)

OGC F. Rosa (8020)

E. Jordan (MNB8 3302) E. Brown (EWS 207)

8. Grimes (9A2) 0. Rothberg (NS 217A)

ACRS (10) T. Martin (12G18)

8. Troskoski (17019) S. Long (10A2)

R. Barrett (10A2) cc: Licensee / Applicant Service List K. Eccleston (14H3)

W. Ruland, RII B. Troskoski RI!

E. Adensam B. Mozafari J. Huang (9H3)

F. Miraglia (12G18)

A. Thadani (7E4)

D. Tondi (8D20)

P. Kang (8D20)

T. Collins (8E23) l y

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Mr. E. E. Utley Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. P. W. Howe Mr. J. L. Harness Vice Presteent Plant General Manager Brunswick Nuclear Project Brunswick Steam Electric Plant Box 10429 P. O. Box 10429 Southport, North Carolina 28461 Southport, North Carolina 28461 Mr. R. E. Jones, General Counsel Mr. H. A. Cole Carolina Power & Light Company Special Deputy Attorney General P. O. Box 1551 State of North Carolina Raleigh, North Carolina 27602 Post Office Box 629 Raleigh, North Carolina 27602 Mr. Mark S. Calvert Associate General Counsel ltr. Robert P. Gruber Carolina Power & Light Company Executive Director Post Office Box 1551 Public Staff - ilCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Mr. Christopher Chappell, Chairman Board of Comissioners Post Office Box 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Buoget and Management [

116 West Jones Street Raleigh, North Carolina 27603 Resident inspector U. S. Nuclear Regulatory Comission Star Route 1 Post Office Sox 208 Southport, North Carolina 28461 Regional Aoministrator, Region !!

U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. Dwayne H. Brown, Chief Radiation Protection Branch Division of facility Services N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008

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, ENCLO.CRE 1 LIST OF ATTENDEES JULY 14. 1986 Name Organization B. Buckley NRC N. Grace NRC L. Reyes NRC J. Sniezek NRC t G. Lainas hRC E. Utley CP&L l P. Howe CP&L l C. Dietz CP&L R. Helme CP&L '

J. O'Sullivan CP&L T. Marguiles NRC J. Boone CP&L R. Richey CP&L F. Rosa NRC

! E. Brown NRC

0. Rothberg NRC T. Martin NRC

5. Long NRC .

R. Barrett NRC f X. Eccleston NRC W. Ruland NRC SRI S. Troskoski NRC E. Adensam NRC B. Mozafari NRC J. Huang NRC F. Miraglia NRC A. Inadani NRC

0. Tordi hRC P. Kang NRC <

T. Collins NRC i I

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ENCLOSURE 2 AGENDA JULY 14, 1988

!. Specifics on JC0 A. Define problems with each vcive.

B. Identify changes proposed or implemented to resolve the ',et tned problems.

C. Basis for determining that the problems will be solved by the chances and not introduce new problers, j

0. Describe the testing proposed to demonstrate that the enanges have i resolved the identified problem.

l E. Previous operating history for each valve.

F. Testing experience wich MOVATS-type program for these valves.

G. Discuss differences between units on torque requirem2nts for sister valves.

!!. Address Safety System Reliability at Brunswick.

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1 ENCLOSURE 3 )

I PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION JULY 14, 1988 0 OBJECTIVES l

o TO REVIEW SPECIFIC TECHNICAL ISSUES THAT IMPACT THE BASES OF BNP'S JUSTlFICATION FOR CONTINUED OPERATION FOR THE UNIT 1 AND UNIT 2 HIGH PRESSURE COOLANT INJECTION SYSTEMS, JULY 10, 1988.

, o TO REVIEW BNP SAFETY SYSTEM REllABILITY, SPECIFICALLY FOCUSED TO THE HIGH PRESSURE COOLANT INJECTION SYSTEMS, PRESENTATION IS STRUCTURED TO DISCUSS FAILURE MODES, CORRECTIVE ACTIONS, AND THE BASES FOR PROJECTED FUTURE PERFORMANCE.

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PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION JULY 14, 1988 0 SAFETY SYSTEM RELIABILITY R. E. HELME o HISTORICAL PERFORMANCE o FAILURE RESPONSE ,

o CORRECTIVE ACTIONS

, o RESULTS OF CORRECTIVE ACTIONS 3

o CURRENT FAILURE HISTORY o SEQUENCE AND TYPE 0 CONCLUSIONS C. R. DIETZ i

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PRESENTATION TO U.S, NUCLEAR REGULATORY COMMISSION JULY 14, 1988 AGENDA 0 JUSTIFICATION FOR CONTINUED OPERATION RESPONSE J. S, BOONE  :

o PROBLEMS IDENTIFIED PER VALVE o INDIVIDUAL MODIFICATIONS PER VALVE ACCEPTABILITY OF CORRECTIVE ACTIONS o ACCEPTANCE TESTING 0 HPCI VALVE PERFORMANCE J. O'SULLIVAN o MECHANICAL ANALYSIS CHARACTERIZATION (MAC) o TORQUE SETTING VARIANCE l

o CORRECTIVE ACTIONS I o INTERIM o LONG TERM i

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i PRESENTATION TO U.S, NUCLEAR REGULATORY COMMISSION JULY 14, 1988 0 CONCLUSIONS o PREVIOUS CORRECTIVE ACTIONS o NARROWLY FOCUSED o FAILURE TO CHALLENGE DESIGN /AS-INSTALLED VERSUS THE DESIGN BASES / CRITERIA o CURRENT AND PROJECTED CORRECTIVE ACTIONS o CONFIDENT IN THE RESULTS, , , , PROVE IT!!

o ASSESSING SELECTIVE DECREASES IN SURVEILLANCE INTERVALS OR INCREASED FREQUENCY OF TESTING FOR HISTORICAL POOR PERFORMANCE o CONFIDENT IN THE RESULTS, , , , WHY IMPROVE? '

o PLANT MODIFICATIONS ARE DEVELOPED TO IMPROVE OPERATING MARGINS COMPARED TO THE ENTIRE ,

SPECTRUM OF DESIGN BASES REQUIREMENTS o ROOT CAUSE DETERMINATIONS WILL ENABLE ELIMINATION OF CHRONIC FAILURE CONTRIBUTORS o VOLTAGE SURGE PROTECTION

I B PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION JULY 14, 1988 IMPROVE (?). . . . (CONTINUED) .

l o ELIMINATION OF STARTING RESISTORS o VALVE APPLICATIONS TO ELIMINATE THERMAL BINDING o VALVE RELOCATION TO IMPROVE OPERATING ENVIRONMENT / TEMPERATURE IMPACT ON MOTOR CAPACITY o EFFECT OF THE AB0VE ACTIONS IS NOT YET QUANTIFIABLE o OTHER FAILURES SUCH AS THE HIGH STEAM FLOW ISOLATION SETPOINTS ARE CONSIDERED TO BE ISOLATED OCCURRENCES l

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PROBLEMS 0

SUMMARY

o THERMAL BINDING o CHANGES IN VALVE TEMPERATURE INCREASE TORQUE REQUIREMENTS o NO ALLOWANCE IN ORIGINAL MOTOR SIZING BY VENDOR o CAUSED BY CLOSING HOT; OPENING COLD o VALVE BODY CONTRACTION EXCEEDS DISK CONTRACTION o MOTOR TORQUE DEFICIENCY o MOTOR UNABLE TO DEVELOP REQUIRED TORQUE IN SOME CONDITIONS o STARTING RESISTOR l

o REDUCED STARTING VOLTAGE FOR 1-2 SECONDS o FOR OPENING, o MAXIMUM TORQUE NEEDED TO UNSEAT  !

o MOTOR MAY STALL AND NOT RESTART EVEN WITH FULL VOLTAGE l

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o FOR CLOSING, o MINIMAL TORQUE NEEDED TO START o N0 IMPACT o PRESENCE OF STARTING RESISTORS NOT CONSIDERED IN MOTOR SIZING BY VENDOR o CABLE SIZING o UNABLE TO SUPPLY SUFFICIENT CURRENT TO DEVELOP ASSUMED TORQUE FOR ALL CONDITIONS o ACTUAL MOTOR AND CABLE TEMPERATURES REDUCE ASSUMED CURRENT CAPABILITY o CABLE NOT SIZED FOR FULL LOAD REQUIRED TO UNSEAT OR TORQUE SEAT VALVE o TORQUE SWITCH SETTING o MOTOR SIZED FOR MAXIMUM DESIGN LOAD o TORQUE SWITCH SET AB0VE MAXIMUM DESIGN LOAD l

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0 UNIT 1 HPCI STEAM SUPPLY VALVE (1-E41-F001) o THERMAL BINDING o EXISTS UP TO APPROXIMATELY TWO HOURS AFTER HPCI STEAM LINE PRESSURIZED o OCCURS ONLY AFTER STEAM LINE ISOLATED FOR MAINTENANCE OR TESTING  ;

o DISAPPEARS AFTER RETURN TO NORMAL TEMPERATURE :

o MOTOR TORQUE DEFICIENCY o INSUFFICIENT TORQUE TO OPEN VALVE o RESULTS FROM A LOSS OF 0FF-SITE POWER WHICH CAUSES MINIMUM BUS VOLTAGE o EMERGENCY DIESEL GENERATOR OPERATION RESTORES ADEQUATE VOLTAGE IN 10 SECONDS t

0 UNIT 1 AND 2 HPCI INJECTION VALVES (E41-F006)

o MOTOR TOROUE DEFICIENCY o INSUFFICIENT TORQUE TO OPEN VALVE V

j o INSUFFICIENT TORQUE TO TORQUE SEAT VALVE CLOSED ,

i o OCCURS ONLY DURING A MAIN STEAM LINE BREAK ACCIDENT IN THE MSIV PIT 0 UNIT 1 AND 2 RCIC INJECTION VALVE (E51-F013)  :

o NO PROBLEMS FOUND .

E RESOLUTIONS 0 THERMAL BINDING o E41-F001 (UNIT 1 AND UNIT 2) o EXTENDED HPCI STEAM LINE PRESSURIZATION / WARM-UP TIME TO FOUR HOURS AFTER UNIS0LATING l o HPCI CONTINUES TO BE CONSIDERED INOPERABLE DURING THIS PERIOD j o NO CREDIT TAKEN FOR HPCI DURING PCRIOD THERMAL l BINDING COULD EXIST o ACCEPTABILITY o HPCI NOT CONSIDERED OPERABLE WHEN POTENTIAL FOR  ;

, THERMAL BINDING EXISTS o SUSCEPTIBLE CONDITION EXISTS ONLY APPROXIMATELY TWO HOURS AFTER HPCI STEAM LINE IS PRESSURIZED  !

I FOLLOWING MAINTENANCE OR TESTING i 0 MOTOR TORQUE DEFICIENCY I o E41-F001 (UNIT 1)

\ l o ELIMINATED REDUCED VOLTAGE STARTIN6 i I o INCREASED POWER CABLE SIZE .

o CHANGED OPERATOR GEAR RATIO TO lilCREASE TORQUE

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o E41-F006 (UNIT 1) o ELIMINATED REDUCED VOLTAGE STARTING o OUTAGE BEGUN TO INSTALL LARGER MOTOR o E41-F006 (UNIT 2)

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I o ELIMINATED REDUCED VOLTAGE STARTING t

q o OUTAGE PLANNED TO BEGIN ABOUT JULY 17 TO INSTALL LARGER MOTOR o E51-F013 (UNIT 1 AND UNIT 2) o ELIMINATING REDUCED VOLTAGE STARTING L

o SUFFICIENT MOTOR TORQUE AVAILABLE u

i o CHANGE PERFORMED TO ACHIEVE ADDED MARGIN p o ACCEPTABILITY o  !

ADEQUATE TORQUE CAPABILITY RESTORED FOR DESIGN CONDITIONS l

o CHANGES REVIEWED WITH VENDORS  :

} o OTHER DESIGN REQUIREMENTS SATISFIED  ;

o DC LOAD STUDY l

o CABLE SIZING l o MCC/ BREAKER / STARTER CAPACITY ,

ACCEPTANCETEST!yG 0 E41-F001 VALVE o MAC TEST AT 0# AND 1000#

o STROKE TIME o CURRENT TRACE o TORQUE o HPCI OPERABillTY SURVEILLANCE o TECHNICAL SPECIFICATION FUNCTIONAL TEST 4

i o ISI PERFORMANCE TESTS ON SYSTEM AND F001 AND F006 VALVES 0 E41-F006 o STROKE TIME i

o CURRENT TRACE

o MAC TEST (FLANNED) o STROKE TIME o CURRENT TRACE 2

I o TORQUE i

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, 0 E51-F013 o STROKE TIME ,

! r o CURRENT TRACE ,

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I VALVE MOTOR FAILURE HISTORY 1-E41-F001 (4 FAILURES) 10/08/86 12/31/87 05/28/87 07/01/88 2-E41-F001 (0 FAILURES) 1-E41-F006 (O FAILURES) .

, 2-E41-F006 (1 FAILURE) 01/05/87 1-E51-F013 (0 FAILURES) 2-E51-F013 (0 FAILURES) I l

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(MOTOR ACTUATOR CHARACTER!ZER) i TOROUE CURRENT (FT LBS) (AMPS) T.S.

1-E41-F001 5/17/87 CLOSING 584.5 26.25 2 1/4 OPENING 245.9 11.11 7/10/88 CLOSING 569.0 45.66 2 1/8 OPENING 379.1 18.8 2-E41-F001 1/15/88 CLOSING 606.3 33.43A 2 3/8 OPENING 305.1 10.13A 7/12/88(1) CLOSING 601.9 31.77A 2 3/8 OPENING 257.5 12.72A 1-E41-F006 1 5/31/87 CLOSING 1,771.3 64.2 1.5 OPENING 413 35.8 7/10/88(1,2) CLOSING NA 66.18 NA OPENING NA 82.78 2-E41-F006 3/31/88 CLOSING 1,871.3 61.78 1 3/4 OPENING 1,211.1 28.08 7/11/88(1,2) CLOSING NA 78.39A NA OPENING NA 55.92A i

M (1) WITHOUT STARTING RESISTORS.

(2) AT 1000 PSI DIFFERENTIAL PRESSURE-CURRENT TRACE ONLY. ,

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(CONT'D)

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3/2/88 CLOSING 76.2 4.4 1 -

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VALVE MOTOR OPERATOR DATA E41-F001:

4 SIZE: SMB-1 (60'#) MOTOR: 1900 DIFF PRESS: 1118 PSI MOTOR HP: 4.35 STROKE I!ME: 20 SEc FULL LOAD AMPS: 17 POWER SUPPLY: DC LOCKED ROTOR AMPS: 105  :

VOLTAGE: 240 i

E41-F006:

i SIZE: SMB-3 (100'#) MOTOR: 1900 DIFF PRESS: 1550 PSI MOTOR HP: 7.25 STROKE IIME: 20 SEc Futt LOAD AMPS 30  !

POWER SUPPLY: DC LOCKED ROTOR AMPS: 146  !

VOLTAGE: 240 J

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l NEAR TERM ENHANCEMENTS 1

1-E51-F013 REMOVE STARTING RESISTORS TO INCREASE

PERATING MARGINS.

2-E51-F013 1-E41-F012 REMOVE STARTING RESISTORS.

l 1-E41-F041  :

1 1-E41-F042

, 1-E41-F059  ;

1-E51-F019 REMOVE STARTING RESISTORS. .

1-E51-F029  ;

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i 1-E51-F031 i

} I l REVERIFY INP0 SOER 84-7 FINDINGS.

EVALUATE THE EFFECTS OF TEMPERATURE CONTRIBUTED BY MOTOR HEATERS j

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.' i MISSION STATEMENT i

t IHROUGH SYSTEMATIC ANALYSIS DETERMINE THAT THE BRUNSWICK PLANT'S  !

4 SAFETY RELATED MOTOR-OPERATED YALVES WILL FUNCTION PROPERLY j WHEN SUBJECTED TO DESIGN BAS!$ OPERATING, ENVIRONMENTAL AND DEGRADED VOLTAGE SCENARIOS. VALVES AND OPERATORS WHOSE DESIGN !

j OR APPLICATION DOES NOT OFFER ADEQUATE DESIGN OPERATING MARGIN I WILL BE IDENTIFIED FOR REPLACEMENT OR MODIFICATION AS APPROPRIATE.  !

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VALVE ANALYSIS OVERVIEW CONSISTENT WITH DEVELOPED PRA TECHN! QUES, ESTABLISH A PRIORITIZATION SCHEME DFSIGNED TO SELECT VALVES FOR EXAMINATION BASED ON THE FOLLOWINGi

- CRITICALITY OF SERVICE

- OPERATING HISTORY IN-PLANT

- INDUSTRY OPERATING HISTORY j ESTABLISH EFFECT!YE LIA! SON WITH VALVE AND OPERATOR VENDORS.

OBTAIN UPDATED VALVE AND OPERATOR DATA FROM YENDORS.

DEVELOP CRITERIA FOR EVALUATING EXISTING VALVE INSTALLATIONS TO UPDATED DESIGN INFORMATION.

DEVELOP A PROJECT PLAN AND SCHEDULE TO IDENTIFY NEAR-TERM AND LONG rRM OBJECTIVES BASED ON PRIORITIZATION SCHEME.

S[BEDULE l AUGUST 15, 1988: PROMULGATE A PLAN AND SCHEDULE THAT WILL l ESTABLISH MILESTONES AND COMPLETION DATES FOR THE ANALYSIS PHASE.

DECEMBER 31, 1988: COMPLETE THE DESIGN ANALYSIS OF SAFETY l RELATED YALVES. .

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! FEBRUARY 28, 1989: COMPLETE DEVELOPMENT OF A CORRECTIVE  ;

ACTION IMPLEMENTATION PLAN TO ADDRESS PROBLEMS IDENTIFIED.

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