ML15244A257
| ML15244A257 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/02/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8706110287 | |
| Download: ML15244A257 (19) | |
Text
REGULATO 4 INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:18706110287 DOC.DAT: 87/06/02 NOTARIZED: NO DOCKET #
FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co.
05000269 50.-270 Oconee Nuclear Station, Uinit 2, Duke Power Co.
05000270 50-287 Oconee Nuclear Station, Unit 3, Duke Power Co.
05000287 AUTH.NAME AUTHOR AFFILIATION GRACEJ.N.
Region 2, Office of Director RECIP.NAME RECIPIENT AFFILIATION TUCKER,H.B.
Duke Power Co.
SUBJECT:
Forwards brief meeting summary including list of attendees
& outline of info presented by util re specific issues discussed.
DISTRIBUTION CODE: IE45D COPIES RECEIVED:LTR _
ENCL L SIZE:
TITLE: Summary of Significant Meeting with Licensee NOTES:AEOD/Ornstein:1cy.
05000269 AEOD/Ornstein:1cy.
05000270 AEOD/Ornstein:icy.
05000287 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENGL PD2-3 LA 1
0 PASTIS,H 1
1 INTERNAL: AEOD/DOA 1
1 AEOD/DSP/TPAB 1
1 DEDRO 1
1 NRR/DLPG/GAB 1
1 NRR/DREP/EPB 1
1 NIR./M -
I LRB 1
1 DOGC/ROED 1
1 REG FILE 02 1
1 RGN2 FILE 01 1
1 EXTERNAL: LPDR 1
1 NRC PDR 1
1 NSIC 1
1 NOTES:
1 1
TOTAL NUMBER OF COPIES REQUIRED: LTiR 15 ENCL 14
JUN 0 2 1987 Docket Nos. 50-269, 50-270, 50-287 License Nos. DPR-38, DPR-47, DPR-55 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- DUKE POWER COMPANY - OCONEE NUCLEAR STATION -DOCKET NOS. 50-269, 50-270, AND 50-287 This letter refers to the meeting conducted at your request in the NRC Region II Office on May 13, 1987. This was a technical meeting held to discuss the history of heat exchanger fouling at the Oconee facility.
Enclosed is a brief meeting summaryincluding a list of attendees, and an outline of the information presented by Duke Power Company regarding the specific issues discussed.
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's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them.
Sincerely, ORIGINAL SIGNED BY M. L. ERNST J. Nelson Grace Regional Administrator Endlosure:
Meeting Summary w/Attachments cc w/encl:
M. S. Tuckman, Station Manager (bcc w/encl:
See page 2) 8706110287 870602 PDR ADOCK 05000269 P
Duke Power Company 2
JUN 0 2 198~7 bcc w/encl:
NRC Resident Inspector H. Pastis, NRR State of South Carolina Document Control Desk RH RII RH BBonse ht TAPeebles Br lee Reys 0$/Z/87
/ V87 v/87 2/87
ENCLOSURE MEETING
SUMMARY
On May 13, 1987, representatives of Duke Power Company (DPC) met with the NRC at DPC's request in the NRC Region II Office in Atlanta, Georgia.
The subject of discussion was fouling of Low Pressure Injection (LPI) system and Reactor Building Cooling Unit (RBCU) system heat exchangers serviced by Low Pressure Service Water (LPSW) at Oconee.
A list of meeting attendees is in.
DPC gave a presentation which consisted of a brief description of the Low Pressure Injection System and the Reactor Building Cooling System, design criteria of the coolers, a chronology of events surrounding testing of the coolers, and future activities planned to assess and enhance the performance of the coolers.
The outline of DPC's presentation is attached as Attachments 2 and 3.
Attachments: (z 43 E---
- 1. List of Attendees
- 2. Oconee Nuclear Station - Reactor Building Cooling Units/Low Pressure Injection Coolers NRC Meeting of May 13, 1987
- 3. Oconee Nuclear Station LPI and Reactor Building Coolers Chronology of Events
ATTACHMENT 1 MEETING ATTENDEES MAY 13, 1987 HEAT EXCHANGER FOULING MEETING Name Organization Title Fred Owens DUKE Regulatory Compliance Richard Sweigart DUKE Superintendent of OPS, ONS Mike Tuckman DUKE Station Manager, ONS Maurice McIntosh -
DUKE General Manager, G.O.
Paul Guill DUKE Licensing Engineer, G.O.
Paul White DUKE Design Engineer,G.O.
Norman Staurbaugh DUKE Nuclear Production Engineer, G.O.
Gregg B. Swindlehurst DUKE Design Engineer, G.O.
E. M. Weaver DUKE Design Engineer Dpt. - M&N, Divsn.
Ned Edwards DUKE Operations Engineer, ONS T. A Peebles NRC-RII Acting Branch Chief J. C. Bryant NRC-RII Sr. Resident Inspector B. R. Bonser NRC-RII Project Engineer P. K. VanDoorn NRC-RII Sr. Resident Inspector, Catawba Johnny L. Mathis NRC-RII Reactor Inspector Arthur J. Szczepaniec NRC-RII Reactor Inspector McKenzie Thomas NRC-RII Reactor Inspector
ENCLOSURE MEETING
SUMMARY
On May 13, 1987, representatives of Duke Power Company (DPC) met with the NRC at DPC's request in the NRC Region II Office in Atlanta, Georgia.
The subject of discussion was fouling of Low Pressure Injection (LPI) system and Reactor Building Cooling Unit (RBCU) system heat exchangers serviced by Low Pressure Service Water (LPSW) at Oconee.
A list of meeting attendees is in.
DPC gave a presentation which consisted of a brief description of the Low Pressure Injection System and the Reactor Building Cooling System, design criteria of the coolers, a chronology of events surrounding testing of the coolers, and future activities planned to assess and enhance the performance of the coolers.
The outline of DPC's presentation is attached as Attachments 2 and 3.
Attachments:
- 1. List of Attendees
- 2. Oconee Nuclear Station - Reactor Building Cooling Units/Low Pressure Injection Coolers NRC Meeting of May 13, 1987
- 3. Oconee Nuclear Station LPI and Reactor Building Coolers Chronology of Events
ATTACHMENT 1 MEETING ATTENDEES MAY 13, 1987 HEAT EXCHANGER FOULING MEETING Name Organization Title Fred Owens DUKE Regulatory Compliance Richard Sweigart DUKE Superintendent of OPS, ONS Mike Tuckman DUKE Station Manager, ONS Maurice McIntosh DUKE General Manager, G.O.
Paul Guill DUKE Licensing Engineer, G.O.
Paul White DUKE Design Engineer, G.O.
Norman Staurbaugh DUKE Nuclear Production Engineer, G.O.
Gregg B. Swindlehurst DUKE Design Engineer, G.O.
E. M. Weaver DUKE Design Engineer Dpt. - M&N, Divsn.
Ned Edwards DUKE Operations Engineer, ONS T. A Peebles NRC-RII Acting Branch Chief J. C. Bryant NRC-RII Sr. Resident Inspector B. R. Bonser NRC-RII Project Engineer P. K. VanDoorn NRC-RII Sr. Resident Inspector, Catawba Johnny L. Mathis NRC-RII Reactor Inspector Arthur J. Szczepaniec NRC-RII Reactor Inspector McKenzie Thomas NRC-RII Reactor Inspector
ATTACHMENT 2 mR>E~zmsIsulp BUI JZDINGCQG(II-TG CCCI..TIT',,S Mi2-Z 133, 1-987
AGENTDA SYSTEM DESCRIPTIONS LOW PRESSURE INJECTION SYSTEM REACTOR BUILDING COOLING SYSTEM DESIGN CRITERIA FOR COOLERS CHRONOLOGY OF EVENTS FUTURE ACTIVITIES
- SYSTEM DESCR.IPT'IONS LOW PRESSURE INJECTION SYSTEMS LPI SYSTEM PROVIDES BOTH NORMAL AND ACCIDENT FUNCTIONS TWO FULL CAPACITY ENGINEERED SAFEGUARDS ACTUATED TRAINS 1 PUMP AND 1
COOLER PER TRAIN INITIAL PHASES OF ACCIDENT USE WATER FROM BWST LATER PHASES OF ACCIDENT RECIRC WATER FROM REACTOR BUILDING SUMP SYSTEM REJECTS HEAT TO LOW PRESSURE SER VICE WATER SYSTEM LPSW A
THIRD NON-ES PUMP IS PROVIDED NORMAL FLOW IS 3,000 GPM LPSW FOR EACH TRAIN IN ACCIDENT CONDITIONS TWO TRAINS REQUIRED OPERABLE WHEN REACTOR IS ABOVE 250 DEGREES OR 350 PSI COOLERS ARE SHELL AND TUBE TYPE WITH RAW WATER ON SHELL SIDE
R.EACTOQR BUJILDIN~G COOLINTG UNIT SYSTEM RC SYSTEM PROVIDES BOTH NORMAL AND AC CIDENT FUNCTIONS THREE FULL CAPACITY ES INDEPENDENT TRAINS PROVIDED SYSTEM REJECTS REACTOR BUILDING HEAT TO LOW PRESSURE SERVICE WATER SYSTEM NORMAL FLOW IS 1400 GPM LPSW FOR EACH COOLER IN ACCIDENT CONDITIONS TWO COOLERS ARE REQUIRED WHEN REACTOR IS ABOVE 250 DEGREES OR 350 PSI THREE COOLERS ARE REQUIRED WHEN THE REACTOR IS CRITICAL
TIC 40T LEG 1
2 3
LOW PRESSURE INJECTION SYSTEM 0
PLWYPASS T0
-- ~ ~ B - -
CAT HEAT COOLER a
- L 4
IP PtRf B IESI
LOW PRESSURE SERVICE WATER SYSTEM (REACTOR BUILDING & AUXILIARY BUILDING)
LPSW LFSWd LINE 'A' IKE 'H Is:1 22:
DECAY HEAT COOLER 'A' DECAY ((EAT AS_
BUILDING COOLING3 UNIT ROC Rac RMC RB _
18 _
RD_
RI A31 ABB AS AS III A-31 RI A-31
-RI A-31RI-1 fa2:41ESI I
21
(]
24 WIES) il (ESI I(
ES)
(ES) al 82 83J 4'
-6 LPSW-B tLPSV-252 2LPSW-251 2LPSW-252 3LPSW?.-404 3LPS W-406 RETURN TO CCw CROSSOVER OSFfl-1240-I. REV
DESIGN CT RIT'rERI A NOR FMLAL PL ANTI C
OE RATIONTS REACTOR BUILDING COOLING UNITS MAIN TAIN CONTAINMENT ENVIRONMENT RBCU OPERATE UNDER DRY AIR CONDITIONS USING SENSIBLE HEAT TRANSFER COMBINED HEAT REMOVAL OF BOTH TRAINS OF LPI CAN COOL REACTOR FROM 250 DEGREES TO 140 DEGREES IN 14 HOURS EMERGENCY PLJAT OPERAT I ONS COMBINED HEAT REMOVAL CAPABILITY OF RBCU' S
AND LPI CAN MEET ACCIDENT HEAT GENERATION IN CONTAINMENT LOSS OF COOLANT ACCIDENT HEAT REMOVAL AT 30 MINUTE TIME FRAME (AFTER INJECTION PHASE)
LOSS OF COOLANT ACCIDENT HEAT REMOVAL LONG TERM TO ASSURE THAT CONTAINMENT TEMPERATURE PROFILE MATCHES ENVIRONMENTAL QUALIFICA TION REQUIREMENTS REACTOR BUILDING COOLING UNITS OPERATE UNDER SATURATED AIR CONDITIONS USING LATENT AND CONDENSING HEAT TRANSFER ABOVE CRITERIA ASSUMES THE LOSS OF THE BEST LPI COOLER BEST REACTOR BUILDING COOLING'UNIT AS WELL AS OTHER CREDIBLE SINGLE FAILURES
ATTACHMENT 3 2/6/86 MEETING HELD WITH OCONEE AND CATAWBA TO SHARE INFO ON MCGUIRES RAW WATER FOULING RECOMMENDATIONS MADE ON TESTING AND PM 2/15/86 UNIT 1 LPI COOLERS TESTED DUR ING SHUTDOWN FOR REFUELING COOLERS DEEMED ACCEPTABLE COOLER 1A CLEANED TO IN CREASE MARGIN VISUAL INSPECTION PERFORM ED ON BOTH 1A AND 1B OTHER UNITS NOT DEEMED AFFECTED BY OBSERVATION UNIT 1
ACCEPTABLE UNIT 1
THE OLDEST NO OBSERVED PROBLEMS ON OTHER UNITS 8/12/86 UNIT 2 RBCU TESTING CAPABI LITY DEVELOPED AND PERFORMED IMMRIEDIATELY PRIOR TO OUTAGE PRELIMINARY CALCULATIONS SHOWED DEGRADATION VISUAL INSPECTIONS CON DUCTED AND SHOWED CLEAN CALCULATIONAL ERROR FOUND WHICH AGREED WITH VISUAL LPI VISUAL INSPECTIONS PER FORMED AND SHOWED RESULTS SIMILAR TO UNIT 1 LPI COOLERS
CHRONOLODGY
( Conitinuec<it
)
9/3-8/86 RBCU VENDOR NOT ABLE TO ASSIST IN ANALYZING TEST DATA ASSUMPTION MADE THAT IM PACT OF FOULING NORIAL WAS EQUAL TO EMERGENCY CALCULATIONS WERE SUS PECT DUE TO APPEARANCE OF UNIT 2
COOLERS 9/22/86 DUKE ENGAGES A
CONSULTANT TO DEVELOP ANALYSIS CAPABILITY 10/10/86 RBCU AIR SIDE FOULING FOUND ON UNIT 3
UNIT 3
HAD THE WORST TEST DATA AIR SIDE CLEANING WAS ACCOMPLISHED IN PLACE 12/17/86 TESTING CONDUCTED ON UNIT 3
LPI DURING SHUTDOWN FOR REFUEL ING 1/23/87 DECISION MADE TO NOT CLEAN UNIT 3 LPI COOLERS ANALYSIS SHOWED THEM TO BE ACCEPTABLE A
BETTER TECHNIQUE WAS TO BE USED STARTING WITH UNIT 1'S NEXT OUTAGE VISUAL INSPECTIONS HAD BEEN PERFORMED WITH RE SULTS SIMILAR TO UNIT 1
AND 2
C=
0-
)D,C =*"
- i-i-CHR.ONOLOQGY
( Coni rtnued )
2/25/87 UNIT 1.RBCU AIRSIDE CLEANED NOT REQUIRED BY TEST RESULTS FORCED OUTAGE WHICH PROVIDED OPPORTUNITY LITTLE MATERIAL FOUND 3/30/87 DUKE'S CONSULTANT ISSUED CODE WHICH SHOWED SIGNIFI CANT DEGRADATION OF RBCU'S FOR EMERGENCY DECISION MADE NOT TO PROCEED WITH UNIT 3
STARTUP UNTIL COOLERS CLEANED AND DATA RE ANALYZED 4/1/87 OPERABILITY DETERMINATIONS MADE ON ALL UNITS UNIT 1 WAS AT REDUCED POWER AND WAS DEEMED ACCEPTABLE AT THAT POWER UNIT 2
WAS REDUCED IN POWER TO LEVEL JUSTIFIED BY ANALYS I S DECISION MADE TO CLEAN UNIT 3 RBCU'S AND LPI COOLERS
U 0
CHR.ONOLOGY
( Cot-i riLiued 4/6-12/87 THE FOLLOWING COOLERS WERE CLEANED AND TESTED UNIT 1A LPI COOLER CLEANED BUT UNIT CON DITIONS DID NOT ALLOW TESTING UNIT 2A LPI COOLER
- CLEANED, UNIT SHUTDOWN FOR TESTING UNIT 3
A AND B LPI COOLERS CLEANED AND
- TESTED, A,
B AND C
REACTOR BUILDING COOLERS CLEANED AND TESTED
FUTUR.E ACTIVZITI ES HEAT LOAD REMOVAL TESTING WILL BE CONDUCT ED ON LOW PRESSURE INJECTION COOLERS AND REACTOR BUILDING COOLING UNITS ON A
REFUELING CYCLE CRITERIA FOR CLEANING WILL BE ESTABLISH ED BASED UPON TEST RESULTS DATA TRENDING WILL DICTATE ADJUSTMENT OF THE CRITERIA FOR CLEANING IN THE FUTURE TO ASSURE OPERABILITY CALCULATIONS
.WILL BE PERFORMED TO ASSESS THE PERFORMANCE OF THE COOLERS WITH LAKE TEMPERATURES ABOVE THE DESIGN VALUE