ML14176A549
| ML14176A549 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/27/1991 |
| From: | Lo R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9107020243 | |
| Download: ML14176A549 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 June 27, 1991 Docket No. 50-261 LICENSEE:
CAROLINA POWER & LIGHT COMPANY FACILITY:
H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2
SUBJECT:
SUMMARY
OF MAY 30, 1991, MEETING REGARDING ECCS OPERATION This refers to the meeting conducted at NRC Headquarters on May 30, 1991, concerning the H.B. Robinson Steam Electric Plant, Unit No. 2 (HBR-2). The purpose of the meeting was to discuss the recovery of the third Safety Injection (SI) pump and the analysis to support the return of HBR-2 to 100%
power following the discovery of a calculational error related to the modeling of a LOCA. A list of attendees, a copy of the agenda, and a copy of your viewgraphs are enclosed.
The following are the salient points of discussion:
(1) The plant modification (R012) in January 1989, resulted in a configuration that two SI pumps could not be run on one emergency bus. This modification is consistent with the Technical Specification amendment issued in June 1988, permitting plant operation with two operable SI pumps. Another basis for the modification is the evaluation of the emergency diesel generator (EDG) capacity. Analysis indicated that the design basis of the EDG would not support the loading of two SI pumps along with other safety loads. The modification changed the SI capability of the plant from three SI pumps to two SI pumps.
(2) CP&L commits to the return of availability of the third SI pump as a spare replacement pump for the other two SI pumps. CP&L will keep the staff informed of the progress of this effort.
9107020243 910627 PDR ADOCK 050002 1
__0
"._0 2
-2 (3) New CP&L calculations with the corrected ECCS model demonstrated that for 100% power operation, 10 CFR 50.46 limits can still be met with the existing emergency procedures for switch-over to ECCS operations on recirculation. The staff discussed with CP&L the operators actions that have to take place to implement these procedures. CP&L stated that the operators are well trained on those procedures and expressed confidence that the action could be taken well within the time assumed in the calculation. The staff's review of these LOCA calculations are being continued.
Original Signed By:
Ronnie Lo, Senior Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
Licensee & Service List DISTRIBUTION Docket File' NRC & Local PDRs F. Miraglia (1218)
J. Partlow (12G18)
S. Varga (14E4)
G. Lainas PD21 Reading A. Mendiola R. Lo OGC E. Jordan (MNBB 3701)
NRC Participants ACRS (10)
J. Wechselberger, Region II OFC
- PM:PD;Y1DRPE
- DPD21:DRPE NAME
- RL
- AMe -
DATE
- 6/1f/91
/91 OFFIIAL RECORD PY Document Name:
BROBINSON MTG
SUMMARY
Mr. L. W. Eury H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr. H. Ray Starling Mr. Dayne H. Brown, Director Manager - Legal Department Department of Environmental, Carolina Power & Ligth Company Health and Natural Resources P. 0. Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Mr. H. A. Cole Special Deputy Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director P. 0. Box 629 Public Staff -
NCUC Raleigh, North Carolina 27602 P. 0. Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Mr. C. R. Dietz Resident Inspector's Office Manager, Robinson Nuclear Project H. B. Robinson Steam Electric Plant Department Route 5, Box 413 H. B. Robinson Steam Electric Plant Hartsville, South Carolina 29550 P. 0. Box 790 Hartsville, South Carolina 29550 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Mr. Heyward G. Shealy, Chief 101 Marietta Street Bureau of Radiological Health Suite 2900 South Carolina Department of Health Atlanta, Georgia 30323 and Environmental Control 2600 Bull Street Mr. R. Morgan Columbia, South Carolina 29201 General Manager H. B. Robinson Steam Electric Plant P. 0. Box 790 Hartsville, South Carolina 29550
May-39--1991-Meeting AtteRdees--Li-st NC CPWe-st-inghey se Ronnie Lo Bob Prunty M. Young Gus Lainas T. B. Clements Tony Mediola Joe Sheppard Bob Jones Charley Dietz Ping Huang Glen Chappell Peter Kang Chris Christensen
CAROLINA POWER & LIGHT COMPANY GE* Tusy.,
00tsc nMAI ROBINSON NUCLEAR PROJECT NRC MEETING SAFETY INJECTION PUMP RECOVERY MAY 30, 1991 91-1318(1)
ROBINSON NUCLEAR PROJECT CAROLINA POWER AND LIGHT COMPANY SI PUMP RECOVERY MEETING WITH USNRC MAY 30, 1991 I. OBJECTIVES
- 1. TO REVIEW CP&L ACTIONS RELATED TO THE RESTORATION OF "C" SAFETY INJECTION PUMP AS A STANDBY, MAINTENANCE PUMP.
- 2.
TO REVIEW THE CURRENT STATUS OF "C" SAFETY INJECTION PUMP REPLACEMENT.
- 3. TO REVIEW THE STATUS OF OPERATIONAL CONCERNS THAT PRECLUDE THREE PUMP OPERATION.
- 4.
TO REVIEW THE SCOPE OF FUTURE COMMITMENTS CONCERNING THE RESTORATION OF THE THIRD STANDBY, MAINTENANCE PUMP.
- 5. TO PRESENT A TECHNICAL REVIEW OF THE ANALYSIS SUPPORTING RESTORATION OF POWER TO RATED ON MAY 29, 1991.
91-1318(2)
ROBINSON NUCLEAR PROJECT CAROLINA POWER AND LIGHT COMPANY SI PUMP RECOVERY AGENDA INTRODUCTION C. R. DIETZ o
HISTORICAL
SUMMARY
PUMP CASING HISTORY CASING PROCUREMENT LICENSING HISTORY OPERATIONAL ISSUES J. J. SHEPPARD 0 ORIGINAL DESIGN BASES 0
SINGLE FAILURE CONCERNS 0
SWAP-OVER ISSUE 0
OPERABILITY CONCERNS PUMP RECOVERY CONCLUSIONS C. R. DIETZ o
CASING STATUS AND FUTURE COMMITMENTS RESTORATION CALCULATIONS T. B. CLEMENTS 0
ANALYTICAL REVIEW AND ASSUMPTIONS 0
QUESTIONS AND ANSWERS 91-1318(3)
ROBINSON NUCLEAR PROJECT CAROLINA POWER AND LIGHT COMPANY II. INTRODUCTION A. HISTORICAL
SUMMARY
OF EVENTS
- 1. PUMP HISTORY 11/87 FLANGE BOLTS HAVE BORIC ACID DEPOSITS. BOLTS ARE REMOVED AND INSPECTED AND AFTER RETORQUING, NO SUBSEQUENT LEAKAGE IS DETECTED.
12/88 LEAKAGE NOTED AT PUMP FLANGE GASKET. AFTER REPLACING GASKET, NO SUBSEQUENT LEAKAGE IS DETECTED.
04/89 PUMP APPEARS TO BE LEAKING AT FLANGE WHILE CONDUCING OST-151.
AFTER RETORQUING FLANGE BOLTS, NO SUBSEQUENT LEAKAGE IS DETECTED.
91-1318(4)
07/89 LEAKAGE IS DETECTED AT FLANGE WHILE PUMP IS RUNNING.
VENDOR ASSISTS IN TROUBLE SHOOTING.
INITIATED ROUTINE PUMP MAINTENANCE AND REFURBISHMENTS LIQUID PENETRANT TESTING SHOWS NO CRACK
- X-RAY TESTING SHOWS NO CRACK INDICATION ULTRASONIC TESTING SHOWS POSSIBLE CRACK 08/89 PUMP MAINTENANCE IS COMPLETED.
DURING POST.
MAINTENANCE TESTING, LEAKAGE AT FLANGE IS DETECTED ONCE AGAIN VENDOR ASSISTANCE UTILIZED TO INVESTIGATE INVESTIGATE FLANGE FLATNESS/ROLL RENEW SEARCH FOR CRACK
- WET FLUORESCENT MAGNETIC PARTICLE TESTING SHOWS FAINT CRACK ACROSS FLANGE FACE 91-1318(5)
09/89 DIAGNOSTICS CONTINUE.
BOAT SAMPLE IS TAKEN FOR MATERIALS FAILURE ANALYSIS REPAIRS HAMPERED BY PRESENCE OF 308SS IN CASING POSING A HEAT TREATMENT PROBLEM.
METALLURGY FINDS CASTING FLAWS -
CONNECTION OF FLAWS LEADS TO CRACK 10/89 DECONTAMINATION EFFORTS ARE INITIATED.
- ON-SITE DECONTAMINATION UTILIZING D'COMX COMPANY.
EFFORTS ARE ABANDONED DUE TO CHEMICAL DISPOSAL PROBLEMS; ONSITE RADIATION CONTROL CONTINUES WITH DECON EFFORTS.
DETERMINED THAT WESTINGHOUSE COULDN'T REPAIR IN HOT SHOP DUE TO ABSENCE OF EQUIPMENT NEWPORT NEWS WILL NOT REPAIR EITHER HOT OR UNCONTAMINATED/
DRESSER CAN REPAIR ONLY IF DECONTAMINATED 91-1318(6)
DETERMINATION THAT REPAIR CAN BE ACCOMPLISHED ONLY WITH ALL 308SS REMOVED DUE TO HEAT TREATMENT 12/89 PUMP CASING SENT TO BRUNSWICK FOR DECONNING.
01/90 PURCHASE ORDER PREPARED FOR DRESSER TO REPAIR; DETERMINED TO BE THE ONLY REPAIR CHOICE AND ASSUMES THAT DECON CAN BE SUCCESSFULLY COMPLETED.
02/90 HOT CELL CORPORATION BEGINS DECON EFFORTS IN WASHINGTON STATE.
03/90 DECON EFFORTS ARE SUCCESSFUL AND PUMP IS SHIPPED TO DRESSER CORPORATION IN HUNTINGTON PARK, CALIFORNIA.
AWAITING QUOTE FROM DRESSER ON REPAIR PROCEDURE; DELAY BECOMES EXCESSIVE.
05/90 QUOTE RECEIVED FROM DRESSER REFLECTING TIME OF REPAIR COMPARABLE TO DELIVERY TIME FOR NEW CASINGS AT SIMILAR PRICE, QUOTE FOR REPAIR TRIPLED COMPARED TO THE ORIGINAL ESTIMATE.
06/90 DECISION TO ABANDON REPAIR EFFORTS AND PROCEED TO PURCHASE TWO NEW CASINGS.
91-1318(7)
A. PUMP HISTORY
- 2. CASING REPLACEMENT 08/90 PROCUREMENT REQUEST RECEIVED BY NED 09/90 BUDGET INFORMATION PACKAGE SUBMITTED 01/91 FUNDS TRANSFERRED TO SUPPORT PROCUREMENT BUDGET 02/91 SPECIFICATION DEVELOPMENT IN PROGRESS 05/91 SPECIFICATION DEVELOPMENT COMPLETE WITH ISSUANCE TO PURCHASING FOR TWO NEW CASINGS 91-1318(8)
A. PUMP HISTORY
01/29/88 PLANT SHUTDOWN TO RESOLVE DESIGN DEFICIENCY.
02/26/88 RECEIVED SIGNIFICANT HAZARDS ANALYSIS THAT SUPPORTS 60%
OPERATION WITH ONE PUMP AND 100%
OPERATION WITH TWO PUMPS.
03/07/88 RESOLVED ALL SINGLE FAILURE SCENARIOS AND SUBMITTED LICENSE AMENDMENT 115 TO SUPPORT POWER OPERATION AT 60%.
05/09/88 SUBMITTED ANALYSIS TO NRC JUSTIFYING RETURN TO 100% POWER WITH TWO SAFETY INJECTION PUMPS; "B" PUMP IS RECOGNIZED AS A STANDBY, MAINTENANCE PUMP.
06/20/88 NRC APPROVES LICENSE AMENDMENT 119 REQUEST.
91-1318(9)
05/14/91 CP&L DETERMINES CALCULATION ERROR IN LONG TERM ECCS ANALYSIS AS PART OF PRA ANALYSIS; POWER REDUCTION TO 60%
PENDING REANALYSIS; INITIAL CALCULATIONS ASSUMING ANS 1979 DECAY HEAT CODE FACILITATES RETURN TO 95% POWER; PLANT IS RETURNED TO 90% POWER.
BASED UPON CONCERNS TO DECAY HEAT
- LOADING, ANALYSIS IS REDONE ASSUMING ANS 1971 + 20% DECAY HEAT LOADING; NEW ANALYSIS SUPPORTS 92.5% POWER OPERATION; PLANT IS RESTRICTED TO THIS POWER LEVEL PENDING RESOLUTION BY ENGINEERING.
91-1318(10)
III.
OPERATIONAL ISSUES A. ORIGINAL LICENSING BASES START 3 PUMPS B. 1/88 SINGLE FAILURE CONCERN START 2 PUMPS
- 1. PUMP OPERATION OPTIONAL (3/88 -
9/88)
- 2. PUMP OPERATION NOT AVAILABLE (1/89 (PosT R012) TO PRESENT)
A. REANALYSIS OF ELECTRICAL CAPABILITY (1987 SSFI) WILL NOT SUPPORT 2 SI PUMPS ON ONE BUS B. LONG TERM RECIRC LOADS WILL EXCEED EDG 2 HR CAPABILITY C. FINAL CONFIGURATION AS OF RFO 12 91-1318(11)
C. SWAPOVER ISSUE
- 1. EPP-9 WRITTEN TO COVER BROAD SPECTRUM OF LOCAs.
- 2. ONE SI PUMP RUN TO MAXIMIZE TIME FOR MANUAL ACTIONS TO BE TAKEN.
- 3. PER ABOVE TWO PUMPS COULD NOT BE RUN ON THE SAME EMERGENCY BUS WITHOUT SECURING RHR OR AFW PUMP. THIS WOULD ALSO CREATE A TIME CRUNCH.
- 3. SPLIT FLOW WITH RHR ADDS COMPLEXITY FROM A PROCEDURE AND OPERATIONAL STANDPOINT.
D. CONCLUSION OF OPERATIONAL ISSUES
- 1. ONE PUMP IS ADEQUATE. EPP-9 IS DESIGNED TO HANDLE BROAD SPECTRUM OF EVENTS AND PRODUCE REQUIRED RESULTS.
A)
LIMITED TIME AVAILABLE B)
SIMPLE REPETITIVE TASKS TO MINIMIZE PROBABILITY OF ERROR
- 2. THIRD PUMP IS MAINTENANCE ONLY.
- 3. CONTINUING TO PURSUE METHODS TO INCREASE ECCS MARGINS.
91-1318(12)
T-ZI Tz/1 FIGUR 2
0 NOTE:
The "B" SI pump will align to start on one of the emergency buses only when it is replacing the "A" or "C" SI pumps.
Alignment to El or E2 buses will be accomplished by racking out one E1-E2 breaker and racking in the ocher E1-E2 breaker.
Under normal conditions, both breakers will be racked out and the "B" SI pump will stand by as a maint enance onmp only.
INITIAL RECIRCULATION 51MPLIFIEU UIAGKAM 81-S87478B 8174 SA6I 81N67 1".col PFmp Il S70 86781 R IRS 84 W
83 t86 RN3 8H86aNIaOE 61-83*
/
81-866 920~~0 32 2
2 I
866A I 865 8
63 iti 70 iR74 fil
-63AO SI8666 A~~
Ri 876CGK RI rr*
00Inretsion-Pumps 027S 864A
(
'921) 23 1
96R'llR 811-862A 1.8 cRI RS 863A SI-85A
%1 -- 1158 8 4A81-862A c:01Ril 759B75 Sil-8TE JRIIKR8ith4biA 111lR-744B 1-as0A 81-881A 81-841
LONG TERM RECIRCULATION SIMPLIFIED DIAGRAM loop 3 lie6 Le tB-74A m
SI_84BL m
WST I.
81--7087BI 8J S M-43 1A 81-870Ai ATr rr mm. p 9IH.2A(
92 92ft3Cj 'IN~:i~
LT-87 AIST1*
I.".
"I M~i s i n PunN 1:-1111 3
(St mgg ti imS 1,1163A 929:1 81-28 9212 SI A7N ITnBLT 92 gi 4926 921 C
t 81-863B S1-862A
.- I thR!IIR 7598 4
S-86A 1-4,1itS E -
1114t1176iA Illfit 744A A) asac SI 881281 I11til 7119A11-01
'lilt 71I1I1 0-860A S186t A 81-861 Cstsaseen