ML20245C928
| ML20245C928 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/02/1987 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8711040232 | |
| Download: ML20245C928 (16) | |
Text
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Docket lNo. 50-395 :V/t ' DISTRIBUTION.
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5 FACILITY:.:V.jC.; Summer NucleaE. Station. a r
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SUBJECT:
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SUMMARY
0F AUGUST 5, 198 MEETING'WITH'SOUTHCARblINAELECTRIC
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- l0n August'5,-1987, thE NRCLstaff met With the South CarolintpElectric and' Gas -
Com The meeting. . v. 4 w &panyc(SCE&G)ltortour heldat'the"V.!C. Summe,r the Nuclear site Station'. and~toAdiscuss 1,ist:of'tpose technical persons issues.
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,; DISCUSSION.C
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1 ., a, mThe agenda:.;forjthe meetingfis [inci ded'as. EndkAare 2 Vu-graph _s used'at the r 4 . meeting are . included.asLEnclosure 3.- Discussion was focused on the - # ~ f' 1 !:information'in.the vu-gfaphs.. .,.
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Enclosures:
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MEETING WITH SCE&G j , , - ', AUGU,ST 5,'1987 ,
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J.'Hopkins- 1, J. Connelly E. Adensam ! A. Paglia B. Mozafari. M. Williams t, ;
, R.JPrevatte J. Skolds -
P. Hopkins P. Troy . G. Soult ! ' A r M. Quinton .,
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South Carolina Public Servire 40.'driq 'rB Beer
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Enclosure'2-3 ;!.3 [1 ' ;/ ^
!s 1 V' lNRC PROJECT DIRECTORATE AND PROJECT MANAGER VISIT -
i q- . L j. AGENDA' p;[' e. ' AUGUST 5,1987 ll
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'0830 introductions Ollie Bradham:
' Third Refueling Outage Accomplishments Jack Skolds Steam Generator Program Phil Troy l.l; ,
Generic Letter 87-02, RHR 1/2 Pipe Gene' Soult ? Operations !
. McGuire Reactor Trip Breaker Incident Mike Quinton
* . Impact on V. C. Summer Nuclear Station 7 l 1000 Plant Tour R. L. Prevatte i y
1200; Lunch Nuclear Training 3 Center l A 1330l ' Nticlear Training Center and Randy Ruff 1 Simulator Tour. i Nx , Environmental and Dosimetry Lab Tour Bill Baehr
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'- dAction Item List John Connelly Mike Williams AlPagha )
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k i Enclosure 3' CAUSE OF OUTAGE DELAYS 9
- 1. Overall Activity Levels in systems higher than :
anticipated. i i
- 2. Thermocouple conoseal leak required partial draining of the RCS. !
- 3. 1000 Lugs in the ESF Load Sequencer cabinets i required relugging and a complete retest of '
the Sequencer. l
- 4. Sheared stem on RCS RTD Bypass Manifold required )
a second cooldown and depressurization. S. Seal Injection Line leak required a third cooldown 3 and depressurization. )
- 6. Scope of outage increased significantly once it started.
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MAJOR THIRD' REFUELING ACCOMPLISHMENTS 1.' 76 Plant Modifications Completed
- 16: Appendix "R"
- 8 Reg Guide 1.97
- 16 Reliability and Performance improvements
- 36 ALARA, Safety and Other Improvements
- 2. Improved Reliability of Steam Generators
- 3. Performed Ultrasonic inspection (UT) of Two Phase Flow Piping i
- 4. Performed Feedwater Piping Inspection (Surry)
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- 5. Inspected Fuel and Core Barrel for Baffle Jet Impingement
- 6. Cleaned Feedwater and Condensate Systems (Oil) l l
- 7. Detailed Inspection of Main Condenser for Signs of Wear and Erosion
- 8. Installed Live Load Packing in Critical Valves
- 9. Upgraded Steam Generator Hydraulic Snubbers I4 l
- 10. Overhauled One RC Pump Motor l
- 11. Rebuilt Seals in Two RC Pumps
- 12. Chemically Cleaned and Inspected Reactor Building Coolers j l l
- 13. Cleanup and Painting Effort l l
. _ _ - _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
9 THIRD REFUELING ACTIVITY AND MANHOUR I
SUMMARY
! 4 The following is a summary of work activities tracked by CHAMPS.
TYPE OF NUMBER OF MANHOURS % OF TOTAL ACTIVITY ACTIVITIES EXPENDED MANHOURS STPs 2832 20,324 11.3 PMs 3677 19,231 10.7 MWRs 1935 69,418 38.5 MRF/MWRs 1016 71,343 39.5 i TOTAL 9460 180,316 100 l 1 1 I Total Estimated Manhours = 111,000 l l l l I
1 l CONCLUSIONS: e All known preventative measures for PWSCC have been implemented in Hot leg Tube Sheet
- SCE&G understands and can predict corrosion rate.
e Unclear if PWSCC has been cured, but clearly improved SG status. i e Need to continue F* like effort on Leak before break technology Moisture carryover
i i CORROSION RATE l e SCE&G has developed statistical models to predict corrosion rate. e Last Outage Results BEST BEST WORST SG ACTUAL CASE EST. CASE A 9 19 64 71 B 42 66 152 118 C 19 33 91 71 l l
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OBSERVATIONS - l l e Scope For B&W To Date e Successfully Worked 3 SG's in Parellel, Sometimes.Both Channel Heads On Each SG e Scheduled Processes Such That Set-up Tear-Down i Minimized, Optimum Flexibility e Outage Successful Based Upon Coordinated Planning and SCE&G Management Commitment
'To Complete Tasks on Schedule ,
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.I PLUG REMOVAL i
e Returned 24 Tubes To Service o Plugs Removed By TIG Relaxation , e 10 W Ribbed 38 B&W Rolled U-Bend Stress Relief i e All Row-1 and Row-2 In A/C SG's n e Row-2 B SG i e 5 Row-1's in B SG '
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1 PLUGGING MARGIN l o Broad Front Effort F* l Fo l Flow Margin 1 LOCA Reanalysis e Future New LOCA Codes (BASH) Leak Before Break i I i l i l 1 4 I _ _ _ _ _ __________--.- _- - - J
- 9.~ Changes as a result of this review may be grouped in categories as i follows:
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. A. Procedural- l l 1 L 1.' Additional guidance will be added to GOP-10 and SOP-115 to:
- a. proce'duralize the methodology of initially reducing flow and . <
monitor running pump amps to prevent vortexing.
- b. if vortexing is evident, align the idle train of l RHR to the RWST and commence filling the RCS to recover t Reactor Vessellevel 1
2.' Review ARP's to add precaution if RHR pump trip is due to vortexing;
. then do not start the standby pump, proceed by aligning the standby l
pump to the RWST per SOP-115.
- 3. Proceduralize, using the mass balance inventory of the RCS when plant conditions allow.
- 4. Perform testing of RVLIS versus standpipe levelincluding the phenomenon of " moving air around' affecting level and adding RVLIS to i operator's shutdown shift logs.
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- 5. Revise EOP 2.4 to address setting containmentintegrity on loss of RHR and the RCS is open to the Reactor Building. ;
- 6. Update RHR or RCS DBD to include half pipe operations.
- 7. Provide a Technical Specification interpretation on Mode 5 RHR Flow Rate.
B. Hardware changes (Modifications)- 1
- 1. Hard piping the tygon levelindicators at horizontal runs to prevent inadvertent level indication spikes due to obstructions. ;
- 2. Temporarily install remote monitoring device for Reactor Vessel standpipe level indication.
C. Training - Provide training to operators prior to scheduled half-discussing industry problems and corrective actions. pipe operations l 1
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- 2. CONTROL AND INDICATION AVAILABLE TO THE OPERATOR MCB INDICATION '
RHR Pump Amps 0 500/330/10 amp increments
.RHR Flow 0-5000 gpm/100 gpm RHR Heat Exchanger inlet - 50-400 *F/10'F q i
RHR Heat Exchanger Outlet 50 400*F/10'F .l i RHR Pump _ Discharge Press 0-700 psig/10 psig - I RCS WR Press 0 3000 p,sig/50 p,sig 0 600 psig/10 psi RVL15 NR 0-120 %/2 % UP 64-120 %/109.3 %/2 % l MCB ALARMS ( XCP-610): Pump Trip SW/ Breaker Mismatch RHR Loop Flow Low 2200 gpm with Breaker Closed Dish Press High - 550 psig l j COMPUTER POINT ALARMS: Parameter High Alarm Low Alarm RHR Flow 4500 gpm 2400 gpm RHR Pump Breaker Open RHR Hx Outlet Temp 345*F 55'F RHR Pump Outlet Temp 345 F 55*F RCS Wide Range Pressure 2300 psig 325 psig PRT Pressure 7 psig 2.6 psig i incore TC's 635 522.5 . l Tygon Tube B Loo] Intermediate Leg to Pzr Steam I Samp e Line, Markings are permanently on the wallin the RB. t
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V. C. SU M M ER o REACTOR TRIP BREAKERS (RTBs) l.D. LOCATION CYCLES ' q 1
; i RT-1 Shop 02140. i:8L3) l RT-2 RT-A 02153 (4/87) l RT-3 RT-B 01354 ll4/87)
RT-4 BY-B 01338 ll4/87) ) RT-5 BY-A 00239I:8-3) l
..e McGuire and Catawba RTBs at Westinghouse for inspection / evaluation ie . Inspected RT-17/87; no visible deficiencies e Last inspected RT-2,-3,-4 and -5 4/87; due 10/87 e Electrical Supervisor to observe l Catawba RTB inspection i e WOG previouslyidentified potential problem with RTBs due to excessive cycling
- Current semi-annual surveillance test cycles the RTB 30 to 40 times e Furtherinvestigation pending Westinghouse Evaluation / inspection results
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MEETING
SUMMARY
DISTRIBUTION ; i;
- 1Doicket?No(s)A50-395?mt ,
NRC PDR l Local PDR PD II .1 r/f. E. Adensam.
-Attorney, 000 P. Andersott E. Jordan-
'J. Partlow-ACRS (10) ~t Project Manager Jon B. Hopkins l )
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-NRC' PARTICIPANTS J. Hopkins E..Adensam' !
[ B. Mozafari .1 l
.R. Prevatte
.P. Hopkins I
l I l l cc: Applicant & Service List l i l ___}}