ML20029E841
| ML20029E841 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/18/1994 |
| From: | Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Beard P FLORIDA POWER CORP. |
| References | |
| NUDOCS 9405230119 | |
| Download: ML20029E841 (23) | |
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@R I 8 09A Florida Power Corporation Mr. Percy M. Beard, Jr. (NA21)
Sr. Vice President, Nuclear Operations ATTN: Manager, Nuclear Licensing 15760 West Power Line Street Crystal River, FL 34428-6708 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- CRYSTAL RIVER UNIT 3 This letter refers to the meeting conducted at your request at the NRC Region II offices in Atlanta, Georgia, on April 5,1994. The purpose of the meeting was to discuss a reduction in the scope of a service water inspection at Crystal River Unit 3.
A list of the attendees and a summary of the presentation are enclosed.
It is our opinion that this meeting was mutually beneficial in that it provided us a better understanding of your plans in the service water area and enhanced your understanding of the established process for requesting a reduction in the scope of NRC inspections.
At the meeting onsite April 13, 1994, to discuss the recent SALP report, your staff indicated a concern with statements made by the NRC staff at a meeting April 8, 1994, regarding your proposed membership of a planned service water assessment.
We have reviewed these statements with the Region 11 staff and have concluded that the temporary instruction covering the service water inspection recommends mechanical design engineers and operations engineers with training in fluid flow in piping systems be utilized for the assessment.
You are certainly free to assign whatever staff you feel appropriate to the l
assessment.
Region II will verify the qualifications of your assessment staff.
Should you have any further questions regarding this matter please contact Mr. Thomas A. Peebles at (404)331-5541.
Sincerely, hAWiuL dl L P
y, #1L-i L
Jon R. Johnson, Acting Director Division of Reactor Projects
Enclosures:
1.
List of Attendees.
2.
Presentation Summary cc w/encls:
See page 2 9405230119 94041B DR ADOCK 0500 2
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cc w/encls:
Gary L. Boldt, Vice President Nuclear Production (SA20) 15760 West Power Line Street Crystal River, FL 34428-6708 B. J. Hickle, Director Nuclear Plant Operations (NA2C) 15760 West Power Line Street Crystal River, FL 34428-6708 R. C. Widell, Director (NA2I)
Nuclear Operations Site Support 15760 West Power Line Street Crystal River, FL 34428-6708 Gerald A. Williams Corporate Counsel MAC - ASA P. O. Box 14042 St. Petersburg, FL 33733 Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304 Bill Passetti Office of Radiation Control Department of flealth and
-1 Rehabilitative Services 1317 Winewood Boulevard Tallahassee, FL 32399-0700 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 f.hairman Board of County Commissioners Citrus County 110 N. Apopka Avenue Inverness, FL 36250 Robert B. Borsum B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852-1631 o
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Florida Power Corporation 3
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K. Landis, RII
.S. Vias, RII A. Long, RII L. Raghavan T. Peebles -
Document Control Desk NRC Resident Inspector U. S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL 32629 A. Gibsca,e3 l
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04/o/94 04/jy,/94 04/ p//94 l
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ENCLOSURE 1 LIST OF ATTENDEES U. 5. Nuclear Regulator _y Commission
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A. Gibson, Director, Division of Reactor Safety (DRS), Region II (RII)
T. Peebles,. Chief, Operations Branch, DRS, RII P. Kellogg, Chief, Operational Programs Section, DRS, RII D. Verrelli, Chief, Branch 2, Division of Reactor Projects (DRP), RII K. Landis, Chief, Section 2B, DRP, RII A. Long, Project Engineer,-DRP, RII H. Berkow, Director, Project Directorate 11-2, Office of Nuclear Reactor Regulation (NRR)
L. Raghavan, Project Manager, Crystal River, NRR Florida Power Corporation P. Tanguay, Director, Nuclear Operations Engineering and Projects J. Maseda, Manager, Nuclear Operations Engineering D. Shook, Nuclear Staff Engineer J. Tunstill, Senior Nuclear Licensing Engineer i
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ENCLOSUN2 FLORIDA POWER CORPORATION NRC MEETING ON SWSOPI APRIL 5,1994 PURPOSE OF FPC MEETING WITH THE NRC Tanguay BACKGROUND Tunstill THE SCOPE OF THE SERVICE WATER Terry /Czufin PREVIOUS RELATED ACTIVITIES 1987 OSTI BY THE NRC.
Masedaffanguay FPC 1992 OUALITY PROGRAMS DEPARTMENT ON Shook THE SERVICE WATER SYSTEM.
1993 EDSFl(and other Electrical) BY THE NRC Shook SELF ASSESSMENT TO BE PERFORMED BY FPC.
Shook DISCUSSION Tanguay/ALL SCHEDULE and CLOSING Tanguay Those in attendance for Florida Power:
Paul Tanguay Director Nuclear Operations Engineering and Projects Joe Maseda Manager Nuclear Operations Engineering Jim Terry Manager, Nuclear Plant Systems Engineenng Jack Tunstill Senior Nuclear Licensing Engineer Don Shook Nuclear Staff Engineer David Czufin Su ervisor Mechanical Systems En ineering
4 PREPARATIQN FOR A SWSOPI
.0PTIONS AVAILABLE
" FULL-SCOPE" SWSOPI ENCOMPASSING THE ELEMENTS
=
OF TI 2515/118,. REVISION 1.
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" REDUCED-SCOPE" SWSOPI BASED ON LICENSEE
=
PERFORMANCE OF A SELF-ASSESSMENT.
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- - - = _ _. _ - _, _ _ _ _ _, _ _ _ _ _ _
IP 40501 LICENSEE SELF-ASSESSMENTS RELATED TO AREA-0F-EMPHASIS INSPECTIONS INSPECTION PROCEDURE 40501 PURPOSE:
TO PROVIDE GUIDANCE ON THE PILOT PROGRAM TO EVALUATE A LICENSEE'S SELF-ASSESSMENT EFFORT AS AN ALTERNATIVE TO AN EXTENSIVE NRC AREA-OF-EMPHASIS TEAM INSPECTION.
IP 40501 ALLOWS PLANTS WHICH WERE LICENSED BEFORE 1979 TO REQUEST REDUCED-SCOPE INSPECTIONS.
ANY LICENSEE SELF-ASSESSMENT UPON WHICH A REQUEST FOR REDUCED-SCOPE CONSIDERATIONS, SHOULD BE AT A MINIMUM:
(1) VERY RECENT (2) CONSISTENT IN SCOPE WITH TI 2515/118 (3) PERFORMED BY A CREDIBLE TEAM OF PERSONNEL l
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TEMPORARY INSTRUCTION 2515/118, REVISION 1 SERVICE WATER SYSTEM OPERATIONAL PERFORMANCE INSPECTION (SWSOPI)
TI 2515/118 PURPOSE ASSESS THE LICENSEE'S PLANNED OR COMPLETED ACTIONS IN RESPONSE TO GENERIC LETTER 89-13 ISSUED IN JULY 1989 AND VERIFY / ASSESS THE SWS IS CAPABLE OF FULFILLING ITS SAFETY-RELATED FUNCTION.
EXTENSIVE INSPECTION IN ALL AREAS OF PLANT REQUIRING NRC/ LICENSEE RESOURCES FOR 7-11 WEEKS.
TI 2515/118 DOES GIVE NRC THE LATITUDE TO CONSIDER REDUCTIONS OR WAIVERS FOR THE SWSOPI i
BASED UPON "RECENT" INSPECTIONS WHICH WERE SWSOPI IN SCOPE.
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GENERIC LETTER 89-13 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT G.L. 89-13 ISSUED ON JULY 18, 1989 AS AN INFORMATION REQUEST.
FPC'S RESPONSE IS DATED JANUARY 30, 1990.
NRC ISSUED SUPPLEMENT 1 ON APRIL 4, 1990 To DOCUMENT QUESTIONS AND ANSWERS DISCUSSED AT NRC WORKSHOPS ON THE LETTER IN LATE 1989.
FPC HAS A REVISION IN PREPARATION TO OUR GL RESPONSE TO CLARIFY FPC'S COMMITMENTS REGARDING SEVERAL OF THE ACTION ITEMS.
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KAJOR COMPONENTS COOLED BY NUCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM SW NUCLEAR SERVICES CLOSED CYCLE SURGE TANX CONTROL R00 DRIVE MECHANISM COOLERS PUMP & MOTOR COOLERS ONE MOTOR DRIVEN EMERGENCY FEED PUMP KAKEUP AND PURIFICATION PUMPS & MOTORS ONE NORMAL NUCLEAR SERVICES CLOSED CYCLE COOLING PUMP TWO EMERGENCY NUCLEAR SERVICES CLOSED CYCLE COOLING PUMPS ONE NORMAL NUCLEAR SERVICES RAW WATER PUMP TWO EMERGENCY NUCLEAR SERVICES RAW WATER PUMPS REACTOR COOLANT PUMPS AND MOTORS LETDOWN COOLERS RC DRAIN TANK COOLER RB FAN ASSEMBLY & VENTILATION FAN MOTOR COOLERS SAMPLE COOLERS SEAL RETURN COOLERS WASTE GAS COMPRESSORS STEAM GENERATOR COOLERS PRESSURIZER COOLER VENTILATION FAN MOTORS SPENT FUEL COOLERS SPENT FUEL COOLANT PUMPS AIR HANDLING UNITS CONTROL COMPLEX WATER CHILLERS MAJOR COMPONENTS COOLED BY DECAY HEAT CLOSED CYCLE COOLING SYSTEM DC ONE MAKEUP PUMP COOLER ONE RAW VATER PUMP COOLER ONE BUILDING SPRAY PUMP COOLER ONE DECAY HEAT PUMP COOLER ONE AIR HANDLING FAN COOLER
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CRYSTAL RIVER # 3 SYSTEM DESCRIPTIONS This attachment provides a brief description of three plant systems:
Nuclear Services and Decay Heat Raw Water System (RW).
Nuclear Services Closed Cycle Cooling System (SW).
Decay Heat Closed Cycle Cooling System (DC).
RW The RW system is an onen loop water system that provides a heat sink to the SW system which provides cooling to nuclear safety and non-safety related equipment. The RW system also provides a heat sink to the DC system during normal shutdown or following a loss-of-coolant accident. The heat sink function of the RW system is achieved by circulating seawater through the tube side of the SW and DC systems heat exchangers and rejecting the transferred heat to the ultimate heat sink, the Gulf of Mexico.
The RW system takes suction from a pump pit in the seawater room at elevation 95 of the Auxiliary Building. The RW system uses separate sets of pumps to circulate seawater to the SW and DC systems heat exchangers.
RWP-1 is the normal RW pump which circulates seawater to the SW system heat exchangers. During normal power operation, RWP-1 will deliver the required flow to the RW/SW heat exchangers to cool all of the SW system loads. RWP-2A and RWP 2B operate to supply seawater to the SW heat exchangers during emergency modes of operation. Either pump may also be substituted for RWP-1 during refueling operations.
RWP-2A and 2B are each rated at 100% capacity for emergency conditions and are powered from separate 4160 volt Engineered Safeguards (ES) buses which provide the required redundancy in case of a single failure in the emergency power generation and distribution system.
A 24 inch common discharge header from the three RW pumps dedicated to SW system cooling (i.e., RWP-1, RWP-2A and RWP-2B) conveys the seawater to the four RW/SW heat exchangers, RW flow can be diverted to either or both of the two underground,100%
capacity,48 inch discharge conduits for discharge to the Gulf of Mexico.
RWP-3A and RWP-3B are the dedicated RW pumps which circulate seawater to the DC heat exchangers. Both RWP-3A and 3B are each rated at 100% capacity for emergency conditions and are powered from separate 4160 volt ES buses to provide the required redundancy in case of a single failure. Although each pump is capable of supplying the required flow, during emergency conditions both pumps will be actuated simultaneously by an Engineering Safety Actuation System (ESAS) signal and will be operated simultaneously to accelerate the cool down.
While the RW pumps dedicated to SW cooling provide seawater to a common supply header for the SW heat exchangers, the RW pumps dedicated to the DC system cooling, supply their respective RW/DC heat exchanger separately.
RWP-3A supplies heat Page 1
exchanger DCHE-1A while RWP 3B supplies DCHE-1B. The seawater is discharged back to the ultimate heat sink through either or both of the two underground,100% capacity,48 inch concrete discharge conduits.
S_W The SW system is a closed cycle cooling water systsm which provides cooling to nuclear safety and non-nuclear safety related equipment. Treated demineralized water is the cooling medium used in the SW system. The SW rejects heat to the RW system through the RW/SW heat exchangers. In addition to its equipment cooling function, the SW system serves as an intermediate barrier to prevent radioactive releases to the environment form potential leaks in interfacing systems that it cools.
During power operation, SWP-1C is the normal duty pump and provides all the required SW cooling water flow. During emergency conditions, the two emergency pump sets, SWP-1A and SWP-1B, will start on an ESAS signal to supply the cooling flow requirements to the essential equipment. Each of the two emergency pumps sets is capable of supply 100 %
of the flow required during emergency conditions so that single failure on one pump set will not affect the safety of the plant. Each emergency pump set is comprised of two pumps powered by one motor. Each pump set motor is powered from a separate ES bus to protect against single failure on the emergency power generation and distribution system.
During normal power operations, the SW system will provide cooling to essential pump motor coolers, letdown coolers and reactor drain tank cooler, Reactor Building fan assemblies and ventilation fan motor coolers, control rod drive mechanism coolers, essential pump seal return coolers, waste gas compressors and waste and reactor coolant evaporator packages, reactor pump coolers, spent fuel coolers, spent fuel coolant pumps air handling units, and Control Complex water chillers. During emergency conditions, the non-essential loads in the above list (i.e., waste gas compressors, waste and reactor coolant evaporators packages, make-up seal return coolers) are automatically isolated so that essential equipment can be provided with the cooling flow that is required.
DC The DC system is closed cycle cooling water system which removes decay heat generated by the reactor core after a normal shutdown, or following a loss of coolant accident. Like the SW system, the DC system uses treated demineralized water as the cooling medium.
The other function of the DC system is to provide an intermediate barrier between the reactor coolant system and the RW system to prevent release of radioactivity to the environment.
l The DC system is comprised of two redundant and independent cooling loops, each capable l
of transporting the decay heat during shutdown or emergency conditions to the RW system through the RW/DC heat exchangers (DCHE-1A and DCHE-1B).
here is one pump in each DC system cooling loop. DCP-1A and DC-1B are powered by t
separate 4160 volts ES buses to protect against single failure in the emergency power generation and distribution system.
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Each DC system will provide cooling flow to its respective decay heat removal heat exchanger (i.e., DHHE-1A and DHHE-1B) and to other essential equipment such as RWP-3A and RWP-3B pump motors, the decay heat removal (DHR) system pumps and motors, the Reactor Building spray pumps and motors, the DC pump motor air handling units, and the make up and purification (MU) pumps and motors 1A and IC.
The decay heat transferred from the DHR system and the heat loads transferred from the various other essential equipment listed above is transported by the DC system and transferred to the RW system via DCHE-1A and DCHE-1B heat exchangers.
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PREVIOUS RELATED ACTIVITIES OSTI Operational Safety Team inspection (OSTI) in 1987 insufficient technical justification for Ultimate Heat Sink (UHS) design temperature of 85 F (UHS is the RW system)
FPC completed all required re-analyses / testing to justify raising UHS design temperature to 95*F Systems included:
SW DC RW Analyses / testing included:
Transient and Steady State Thermal Analysis Hydraulic Analysis Flow Balance Testing (SW System, PT-136)
Vendor verification of component operability at elevated temperatures Heat Exchanger Performance Testing (SWHE's)
AUDIT REPORT 92-11-RWSW THE AUDIT TEAM WAS COMPRISED OF:
Two Mechanical Engineers Three Quality Auditors THE AUDIT TOOK PLACE OVER A THREE WEEK PERIOD OVER 1000 AUDIT HOURS WERE USED.
AUDIT WAS BASED ON :
Generic Letter 89-13 Preliminary Tl 2515/118 COMPLIANCE AUDIT, NOT AN ENGINEERING AUDIT RESULTS OF THE AUDIT:
The Problem neport System is Crystal River's Corrective action system.
1 There were Nine Problem reports issued.
There were twenty recommendations made 1
DAS SLIDE # 1
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AUDIT REPORT 92-11-RWSW PROBLEM REPORTS THERE WERE NINE PROBLEM REPORTS ISSUED AS PART OF THIS AUDIT. THE FOLLOWING AREAS WERE COVERED:
1 Corrosion problems Pipe hanger problem Documentation procedures problems Paint covering valve position indication Several thread engagement problems Several tagging problems Different lock used then in the procedure Valve checklist problems in SP-381 A drawing in the control room was the wrong revision j
5 ALL OF THE PROBLEM REPORTS HAVE DEEN CLOSED.
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I AUDIT REPORT 92-11-RWSW RECOMMENDATIONS THERE WERE TWENTY RECOMMENDATIONS ISSUED AS PART OF THE AUDIT. THE FOLLOWING AREAS WERE COVERED:
Review procedures Evaluate corrective action plans Review the status of material deficiencies Evaluate the priority of SW material deficiencies Remind the reviewer of completed procedures to look for discrepancies Have an independent self-assessment Prepare a specific thermal performance calculation Verify an upper temperature limit Revise sections of the FSAR Perform an engineering review of SP-456 Assess the understanding of an acceptance criteria Perform more frequent flushing of heat exchangers Review a corrective action plan Maintain SW performance data Determine heat transfer coefficients Provide heat exchanger testing instrumentation Accelerate the installation of new RW spools Expedite the heat exchanger monitoring program Enhance information available to the system engineer.
1 Ensure audit findings must be accepted and responded to.
THE ABOVE RECOMMENDATIONS WILL BE INCLUDED IN THE SELF-ASSESSMENT TO BE PERFORMED BY FPC u
l DAS SLIDE # 3
2 PROBLEM REPORT PR92-0122 9/18/92 HEAT EXCHANGER DCHE-1B FOULED / CLOGGED WITH OYSTER SHELLS CORRECTIVE ACTION COMPLETED Obtained performance data on both heat exchangers Requested information from other Utilities Review work history on the heat exchangers Made long term recommendations 1
THE PROBLEM WAS DETERMINED TO BE THE DEBRIS FROM j
THE PITS AND FLUMES VS MARINE GROWTH OF THE HEAT EXCHANGERS.
LONG TERM RECOMMENDATIONS Have the fiumes, pits, and intake structure cleaned during 9R outage (presently scheduled)
Begin a regular program of RW fiume/ pit cleaning and visualinspections Continue to investigate the use of non-toxic coating and " Clam-trol" type
- blocide, DAS SLIOE # 4
1993 EDSFl(and other Electrical) BY THE NRC.
ELECTRICAL CALCULATIONS DIESEL GENERATOR LOADING l
DAS SLIDE #.5
P l
SELF-ASSESSMENT l
THE SELF-ASSESSMENT WILL INCLUDE (Ref. Tl 2515/118, Rev 1).
j Mechanical Systems Engineering Design Review and Configuration Control Operations Maintenance Surveillance and Testing Quality Assurance and Corrective Action J
f TEAM COMPOSITION.
Team leader Mechanical engineer, design (senior level)
Mechanical engineer, maintenance, training Audit background, operations Audit background, testing FPC WILL NOT DUPLICATE ITEMS ALREADY COVERED.
EDSFI (ex. EDG loading)
OSTI(Ultimateheatsink) i DURATION MAY BE GREATER THAN SIX WEEKS TO MINIMl2E THE IMPACT OF THE SELF ASSESSMENT ON-THE VARIOUS DEPARTMENTS.
October 2, 1994 through November ~18, 1994 FPC REOUEST THAT THE NRC PARTICIPATION DURING THE l-SELF ASSESSMENT NOT INHIBIT THE ACTIVITY.
1.
L I-i FPC EXPECTATIONS ARE THE NRC WILL PERFORM A REDUCED l
SCOPE INSPECTION AND IT WILL BE TO FPC'S AND THE NRC'S
' ECONOMICAL BENEFIT.
DAS-SLIDE # 6
SWSOPI REDUCED SCOPE INSPECTION SCHEDULE FPC LETTER TO REQUEST REDUCED-SCOPE SWSOPI INSPECTION MAY 1994 NRC CONCURRENCE WITH FPC REQUEST JUNE 1994 FPC SELF-ASSESSMENT BEGINS 4TH QUARTER 1994 SUBMIT REPORT ON SELF-ASSESSMENT TO NRC 1ST QUARTER 1995 NRC REDUCED-SCOPE SWSOPI INSPECTION
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