IR 05000416/1987003
| ML20207T592 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/26/1987 |
| From: | Butcher R, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207T584 | List: |
| References | |
| 50-416-87-03-EC, 50-416-87-3-EC, IEIN-86-096, IEIN-86-96, NUDOCS 8703240163 | |
| Download: ML20207T592 (32) | |
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An nee UNITED STATES ng'g
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NUCLEAR RECULATORY COMMIS$10N
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REGION 11
g 101 MARIETTA STREET,N.W.
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ATLANTA, GEORGI A 30323
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Report No.: 50-416/87-03
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Licensee:
System Energy Resources, Inc.,. /
ATTN: Mr. O. D. Kingsley, Jrg. '
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Vice President, Nuclear Operations P. O. Box 23054 Jackson, MS 39205 s
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Docket No.: 50-416 License No.:,NPF-29
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Facility,Name: Grand Gulf
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Enforcement Conf ence C nducted: - ebruary 4,'1987
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In ectors:
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R.~ C Butchep,U5eniorResident. Inspector fate Signed
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Approved by:
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H. C. Dance, Section Chief (Tate S'igned Division of Reactor Projects
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l SUMMARY Scope:
An Enforcement Conference was held in the NRC Region II office on
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February 4,1987, in regards to problems associated with the Standby Service
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Water System. No violations will be issued on this subject.
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REPORT DETAILS
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Licensee Employees at Enforcement Conference 0. D. Kingsley, Jr., Vice President, Nuclear Operations T. H. Cloninger, Vice President, Nuclear Engineering Support F. W. Titus, Director Nuclear Plant Engineering J. C. Cesare, Director (Acting) Licensing and Safety J. W. Yelvertor, Technical Assistant Plant Operations Other licensee employees contacted included construction craftsmen, engineers, technicians,' operators, mechanics, security force members, and office personnel.
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NRC Attendees at Enforcement Conference
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M. L. Ernst, Deputy Regional Administrator
?C L. A. Reyes, Acting Director, of Division of Reactor Projects (DRP)
D. M. Verrelli, Chief, Reactor Projects Branch 1, DRP H. C. Dance, Chief, Reactor Projects Section 1B, DRP A. R. Herdt, Chief, Engineering Branch, Division of Reactor Safety (DRS)
L. L. Kintner, Project Manager, NRR G. R. Jenkins, Director, EICS F. Jape, Chief, Test Program Section,< DRS R. C. Butcher, Senior Resident Inspector, Grand Gulf W. F. Smith, Resident Inspector, Grand Gulf
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L. P. Modenos, Project Enginear, DRP M. Thomas, Reactor Inspector, DRS R. Bernhard, Reactor Inspector, DRS L. Trocine, Enforcement Specialist B. Uryc, Enforcement Speciali,st 2.
Enforcement Conference Meeting' Summary Due to the number of problems associated with the Standby Service Water (SSW) system and their potential safety impact, an enforcement conference was held in the NRC Region II office on February 4, 1987. The licensee had
' documented the SSW system and related problems in Licensee Event Report (LER)86-029.- In addition to the original design deficiencies identified, there were personnel errors which also contributed to the overall problem.
The meeting agenda and the licensee's presentation defining each problem, cause and corrective action are included as Attachment 1 to this Inspection Report. The inspector's coverage of this subject is documented in Inspection
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Reports 416/85-45, 416/86-04, 416/86-08, 416/86-26, 416/86-32, 416/86-37 and 416/86-39 and has been tracked as Unresolved Item 416/86-32-05.
The licensee's evaluation of the effect of the design deficiencies and personnel errors showed that in each case, although design and/or FSAR requirements would have been exceeded in the event of a design basis
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accident, the margins were such that all safety-related equipment would have performed their safety functions.
The licensee's corrective actions have
.been extensive and timely.
Also, the licensee has initiated an independent design review of the SSW system to evaluate overall original design adequacy.
All the noted-problems have been licensee-identified. Using the guidance of the general statement of policy and procedure for NRC enforcement actions' for licensee-identified violations, as defined in 10 CFR 2, Appendix C, no notice of violation will be issued.
Unresolved Item 416/86-32-05 is closed.
The NRC staff had one comment regarding the Engineered Safety Features (ESF) switchgear room coolers flow monitoring program as described on page 17 of Attachment 1.
The NRC does not endorse the action statement as noted in Equipment Performance Instruction 04-1-03-T46-1 and 04-1-03-T46-2.
The NRC's position is that anytime a system component fails to meet its design safety function, that system must be declared inoperable unless analysis shows that the system can still perform its safety function.
Therefore, if an ESF equipment room cooler, or any other cooling component, fails tc have the _ minimum required flow in order for the SSW system to perform its intended design safety function, then the applicable Technical Specification action statement (s) must be entered. The resolution of the action statement wording will be Inspector Followup Item 416/87-03-01.
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ATTACHMENT 1 MEETING AGENDA SYSTEMS ENER.GY RESOURCES, INC.
FEBRUARY 4, 1987, 1:00 P.M.
Atlanta, GA I. OPENING REMARKS J. N. GRACE II. STANDBY SERVICE WATER SYSTEM (SSWS) PROBLEMS L. A. REYES
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o Flow Measuring Instrument Coefficient o
Seismic Design Consideration of Room Cooler Nozzles o
Design Assumption of System Heat Loads o-License Condition 2.C.(21) Application o-Inadequate SSWS Flows III. DISCUSSION OF SSWS PROBLEMS o
Introduction 0. D. KINGSLEY, JR.
o SSWS Design Overview J. G. CESARE o
SSWS Design ~ Problems F. W. TITUS o
Flow Monitoring Program J. W. YELVERTON o
Design Revi_2 T. H. CLONINGER o
Summary /Corc'usion Remarks 0. D. KINGSLEY, JR.
IV. CLOSING COMMENTS J. N. GRACE l
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SSW DESIGN PROBLEMS
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v-LOW FLOW TO COMPONENTS
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UNDERSIZED ESF-SWITCHGEAR. ROOM COOLER ESF SWITCHGEAR ROOM COOLER N0ZZLE DESIGNS
INCORRECT POST-LOCA AUXILIARY BUILDING CORRIDOR TEMPERATURE
SSW CORROSION
f J16 NMAUNC 0017 SSW DESIGN - 1
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t LOW FLOW TO COMPONENTS
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U" PROBLEM:
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LOW SSW FLOWS TO ESF SWITCHGEAR ROOM COOLERS, CONTROL ROOM A/C AND RCIC ROOM COOLERS.
CAUSE:
MICROBIOLOGICAL BIOFOULING AND CORROSION HAS IMPACTED SSW SYSTEM RESISTANCE IN TWO WAYS:
SYSTEM WIDE ROUGHNESS EFFECT
BLOCKAGE / DIAMETER REDUCTION IN PSW SUPPLIED COMPONENTS
CORP.ECTIVE ACTIONS:
SHORT-TERM:
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HYDROLAZED/ FLUSHED PIPING
FLOW MONITORING PROGRAM
REASSESSMENT OF DESIGN FLOWS
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LONG-TERM:
DESIGN CHANGES IMPLEMENTED TO ALLOW ON-LINE FLUSHING.
- CHEMICAL TREATMENT PROGRAM
CORROSION MONITORING
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LOW FLOW T0 COMPONENTS
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DESIGN-BASIS CONSIDERATIONS:
ROOM DESIGN TEMPERATURES WOULD HAVE BEEN EXCEEDED POST-LOCA
UNDER WORST CASE CONDITIONS.
SAFETY SIGNIFICANCE:
EVALUATION APPROACH
CONSERVATIVE DETERMINATION OF PEAK ROOM TEMPERATURE.
PEAK DESIGN OUTSIDE AIR TEMPERATURE PEAK DESIGN SSW TEMPERATURE
REVIEW 0F SAFETY RELATED ROOM COMPONENTS.
- RESULTS
ESF SWITCHGEAR ROOM COOLERS
PEAK ROOM TEMPERATURE:
144*F
7.2 KV POWER BREAKERS - MOST LIMITING
COMPONENT OTHER SAFETY RELATED COMPONENTS UNAFFECTED
CONTROL ROOM AIR CONDITIONING
PEAK ROOM TEMPERATURE 72*F (RECIRCULATION
MODE)
APPROXIMATELY 77'F (OUTSIDE AIR MODE)
NO IMPACT ON EQUIPMENT OR HABITABILITY
RCIC ROOM
ZERO FLOW EVALUATED
PEAK ROOM TEMPERATURE 154*F
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ASCO SOLEN 0 IDS - MOST LIMITING COMPONENT
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NO IMPACT ON RCIC SYSTEM OPERABILITY
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CONCLUSION:
NO IMPACT ON ROOM COMPONENT SAFETY FUNCTIONS.
- J16 NMAUNC 0017 SSW DESIGN - 6
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UNDERSIZED ESF SWITCHGEAR ROOM COOLER
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PROBLEM:
ESFSWIhCHGEARROOMCOOLEREL.119EASTWASFOUNDTOHAVEINADEQUATE
. CAPACITY'. POST-LOCA.
CAUSE:.
NON-CONSERVATIVE ASSUMPTION BY BECHTEL RELATED TO POST-LOCA HEAT TRANSMISSION FROM THE CONTAINMENT.
CORRECTIVE ACTIONS:
DESIGN CHANGE IMPLEMENTED TO INCREASE COOLER CAPACITY.
REEVALUATION OF OTHER SSW SYSTEM HEAT LOADS.
- STATUS:
COMPLETE.
DESIGN BASIS CONSIDERATIONS:
ROOM DESIGN TEMPERATURE WOULD HAVE BEEN EXCEEDED POST-LOCA
UNDER WORST CASE CONDITIONS.
SAFETY SIGNIFICANCE:
NO IMPACT ON ROOM COMPONENT SAFETY FUNCTIONS.
(LOW FLOW
OPERABILITY ASSESSMENT IS BOUNDING)
DESIGN CHANGE MADE TO RESTORE ORIGINAL CONSERVATIVE DESIGN MARGINS.
J16 NMAUNC 0017 SSW DESIGN - 7
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ESF SWITCHGEAR R0OM COOLER N0ZZLE DESIGNS
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- PROBLEM:
THE ESF SWITCHGEAR' ROOM COOLERS WERE NOT APPROPRIATELY ANALYZED TO CONSIDER VENDOR (AAF) N0ZZLE. ALLOWABLE LOADS.
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CAUSE:-
- INCORRECT USE OF SMALL BORE PIPING ANALYSIS SPECIFICATION BY BECHTEL IN THE ORIGINAL DESIGN.
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CORRECTIVE ACTIONS:
DETAILED RE-REVIEW 0F THE 18 AAF ROOM COOLERS AND APPROPRIATE'
DESIGN MODIFICATIONS.
- REVIEW 0F.0THER SMALL BORE PIPING N0ZZLES.
DIRECTED RE-TRAINING OF BECHTEL STRESS ANALYSTS TO EMPHASIZE
CORRECT USE OF SPECIFICATION.
REVIEWED THIS SUBJECT WITH SERI STRESS ANALYSTS.
- ADVISED BECHTEL OF POTENTIAL 10CFR21 APPLICABILITY.
- STATUS:
COMPLETE.
DESIGN BASIS CONSIDERATIONS:
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NORMAL CONDITION N0ZZLE LOADS WERE ACCEPTABLE AS IS FOR ALL COOLERS.
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UPSET AND FAULTED CODE ALLOWABLES WERE EXCEEDED FOR ONLY ONE (1)
COOLER (FUEL POOL COOLING PUMP ROOM "A"),
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SAFETY SIGNIFICANCE:
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FOR 17 0F THE 18 COOLERS, THERE IS NO OPERABILITY CONCERN.
- FOR ONE COOLER, FULL DESIGN MARGINS MAINTAINED FOR NORMAL
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CONDITIONS.
IN THE EVENT OF A LOCA WITH OBE/SSE, THE OPERABILITY OF THE
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COOLER WAS MAINTAINED.
J16 NMAUNC 0017 SSW DESIGN - 8
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INCORRECT POST-LOCA AUXILIARY BUILDING CORRIDOR TEMPERATURE
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PROBLEM:
POST-LOCA AUXILIARY BUILDING CORRIDOR TEMPERATURE EXCEEDS 104*F STATED IN THE FSAR, CAUSE:
INAPPROPRIATE RELIANCE ON ENGINEERING JUDGMENT IN THE ORIGINAL DESIGN IN LIEU OF A SPECIFIC HEAT LOAD ASSESSMENT.
. CORRECTIVE ACTIONS:
EVALUATION OF DIRECT EFFECT OF INCREASED POST-LOCA TEMPERATURES
ON SAFETY RELATED EQUIPMENT.
EVALUATION OF INDIRECT EFFECTS ON ADJACENT ROOM TEMPERATURES.
- EVALUATION OF OTHER AREAS.
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STATUS:
COMPLETE.
DESIGN BASIS CONSIDERATIONS:
DESIGN TEMPERATURES WOULD BE EXCEEDED IN THE AUXILIARY BUILDING
. POST-LOCA UNDER WORST CASE CONDITIONS.
SAFETY SIGNIFICANCE:
EVALUATION APPROACH
CONSERVATIVE DETERMINATION OF PEAK AREA TEMPERATURES
REVIEW 0F SAFETY RELATED COMPONENTS
LIMITING COMPONENTS:
ROSEMOUNT TRANSMITTERS (FULLY
QUALIFIED).
- ACCESS CONSIDERATIONS
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CONCLUSION:
NO IMPACT ON SAFETY RELATED EQUIPMENT FUNCTIONING.
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RE EVALUATION OF POST LOCA AUXILIARY BUILDING CORRIDOR TEMPERATURES
ESF S/W ROOMS ECCS PUMP ROOMS FPPCU PUMP ROOM HEAT LOAD MEAT LOAD HEAT LOAD RE EVALUATION RE EVALUATION RE EVALUATION
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REVIEW 0F DESIGN CALCULATIONS FOR 0?NER SAFETY RELATED SYSTEMS DIESEL JNERATOR
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'II BUILDING HVAC, x77 CONTROL BUILDING NEAT LOADS RE EVALUATION l CONTROL ROOM l AREAS OUTSIDE TNE EL. 111', SAFEGUARD S/W CONTROL ROOM ENVELOPE AND EMERGENCY BATTERY ROOMS
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SSW CORROSION
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PROBLEM:
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MICROBIOLOGICALLY INFLUENCED CORROSION (MIC) HAS BEEN IDENTIFIED IN l
THE SSW SYSTEM.
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i CAUSE:-
ORIGINAL DESIGN MATERIAL SELECTION, RAW WATER QUALITY AND SYSTEM OPERATING CHARACTERISTICS WERE CONDUCIVE TO THE DEVELOPMENT OF MIC.
CORRECTIVE ACTION:
SHORT-TERM:
DETAILED SYSTEM INSPECTIONS (RF01).
}
INITIATE CHEMICAL TREATMENT PROGRAM.
- I LONG-TERM:
CORROSION MONITORING PROGRAM
SELECTED REINSPECTION DURING RF02
DESIGN BASIS CONSIDERATIONS:
IN SOME CASES CODE DESIGN MARGINS WERE NOT MAINTAINED AND REPAIRS
WERE MADE.
SAFETY SIGNIFICANCE:
ANALYSIS OF REPAIRED AREAS DETERMINED THERE WERE NO OPERABILITY
CONCERNS.
J16 NMAUNC 0017 SSW DESIGN - 10
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SSW CORROSION INSPECTION PROGRAM
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SSW BASINS A 8 B
'1)
SMALL BORE CARBON STEEL PIPING (APPROX. 220 FT.):
VISUAL INSPECTION OF EXTERNAL SURFACES (100%)
SECTIONS CUT OUT FOR MORE DETAILED EXAMINATION
(8 CASES)
2)
SMALL BORE STAINLESS STEEL-PIPING (APPROX. 300 FT.):
VISUAL INSPECTION OF. EXTERNAL SURFACES (10%)
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VISUAL INSPECTION OF SOCKET WELDS (15%)
3)
LARGE BORE PIPING:
VISUAL INSPECTION OF EXTERNAL SURFACES
(VISIBLE PORTIONS - OVER 90%)
UT-EXAMINATION OF MOST AFFECTED AREAS
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(APPROX. 150 INSPECTIONS)
!
ONE SECTION OF 20 IN. PIPING CUT OUT FOR-
EXAMINATION 4)
PIPE SUPPORTS:
i 22 REPRESENTATIVE SUPPORTS EXAMINED
5)
COLUMN SECTIONS
INTERNAL INSPECTION II.
SSW LOOP A & B & C COMPONENTS 1)
HEAT EXCHANGERS:
ALL FOUR RHR HEAT EXCHANGERS VISUALLY INSPECTED
ALL THREE DIESEL JACKET WATER HEAT EXCHANGERS
VISUALLY INSPECTED RHR PUMP SEAL COOLER
TEN ESF SWITCHGEAR ROOM COOLERS
ONE FUEL POOL HEAT EXCHANGER ROOM COOLER
J16 NMAUNC 0020 SSW INSPECTION - 1 lL
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SSW CORROSION INSPECTION PROGRAM
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2)
VALVES:
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FOUR BUTTERFLY VALVES PULLED FOR INSPECTION TWO RELIEF VALVES INSPECTED
3)
PIPING:
INTERNAL PIPING FOR HEAT EXCHANGERS INSPECTED
INTERNAL PIPING FOR THE INSPECTED VALVES INTERNAL PIPING IN ESF SWITCHGEAR ROOM AREAS
IN PLACE VISUAL INSPECTIONS (15)
CUT-0UT SECTIONS (20)
IN PLACE RT EXAMINATIONS (15)
4)
INSTRUMENTATION:
ONE SSW RADIATION MONITOR
111.
DESIGN BASIS CONSIDERATIONS CODE DESIGN MARGINS WERE NOT MAINTAINED FOR THE
FOLLOWING LOCATIONS:
SSW BASINS
BASIN A, B LARGE BORE PIPING EXTERNAL
SURFACES (21 LOCATIONS)
SMALL BORE CARBON STEEL PIPING (ONE
LOCATION)
OUTSIDE THE SSW BASINS
DIVISION I DIESEL JACKET WATER HEAT
EXCHANGER SHELL IV.
SAFETY SIGNIFICANCE ANALYSIS OF REPAIRED AREAS DETERMINED THERE WERE NO
OPERABILITY CONCERNS.
ALL COMPONENTS WOULD HAVE PERFORMED THEIR SAFETY FUNCTIONS.
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J16 NMAUNC 0020 SSW INSPECTION - 2 la
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FUEL P0OL PUMP ROOM COOLERS OL CONDITION 2.C(21)
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A.
BACKGROUND o
DELAYS IN PUMP ROOM VENTILATION SYSTEM CONSTRUCTION o
EXPERIENCED
PUMP ROOM SAFETY RELATED, SEISMIC COOLER NOT AVAILABLE (MP8L LETTER 12/21/81)
SER 9.4.2 - NRC STAFF REVIEW (SUPPLEMENT 2 SER, 6/82)
DELAY APPROVED
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0FFLOAD OF SPENT FUEL INTO POOL CONSTRAINED
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NOT ALLOWED UNTIL SAFETY COOLER INSTALLED AND
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FULLY OPERATIONAL PROVISION ALLOWED FOR SPECIAL ALIGNMENT OF RHR FOR
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EARLY OFFLOAD
OL CONDITIONED CONSISTENT WITH SER 9.4.2 - 2.C(21)
IF SPENT IRRADIATED FUEL IS PLACED IN THE SPENT FUEL POOL PRIOR TO INSTALLATION AND OPERABILITY OF THE SAFETY RELATED BACKUP FUEL POOL COOLING PUMP ROOM COOLERS, THE PLANT SHALL BE PLACED IN SHUTDOWN CONDITION AND REMAIN SHUTDOWN WITH THE RHR SYSTEM DEDICATED TO THE FUEL POOL COOLING MODE.
J16 SLIDES 87020301 - 1
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B.
KEY EVENTS
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"B" TRAIN SAFETY RELATED
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FPCC PUMP ROOM COOLER WORK COMPLETED.
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RF01 COMMENCED.
O SEPT. 5, 1986
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RELIANCE OF SSW "B" TRAIN
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(0LC 2.C(21) SATISFIED FOR "B" TRAIN FPCC).
INSPECTION / CLEANING OF'
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SSW "A".
WORK COMPLETED'ON FPCC
OCT 10, APPROX
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PUMP ROOM "A" SAFETY RELATED COOLER.
COOLER RETURNED TO
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OPERATION.
OLC 2.C(21) INTENT MET
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AND SATISFIED.
NPE IDENTIFIED CONCERN
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REGARDING COOLER N0ZZLE LOADING.
TRANSITION TO 2ND HALF 0F
0CT. 13, APPROX
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RF01.
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SSW BASIN "B" DRAIN DOWN.
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RELIANCE ON SSW "A".
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CONSERVATIVE DETERMINATION
OCT
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MADE THAT CERTAIN COOLER N0ZZLES WERE OVERLOADED.
INCIDENT REPORT
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GENERATEDJ REPORTED TO NRC.
QA IDENTIFIED POTENTIAL
OCT 16-20
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NONCOMPLIANCE WITH OLC 2.C(21).
MATTER DISCUSSED IN
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CONFERENCE CALL WITH NRC NRR, REGION 11, AND RESIDENT INSPECTOR.
J16 SLIDES 87020301 - 2 hr
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C.
EVALUATION
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(1 OL CONDITIONED TO INSURE ADEQUATE DECAY HEAT REMOVAL CAPABILITY
OL CONDITION INTENT TO CONSTRAIN SPENT FUEL MOVEMENT UNTIL NEW COOLERS WERE OPERATIONAL OR ACCEPTABLE MEANS PROVIDED FOR DECAY HEAT REMOVAL
SAFETY RELATED COOLERS WERE INSTALLED, TESTED, AND RETURNED TO OPERATIONS
FURTHER DECAY HEAT LOAD (10/86) WELL WITHIN SINGLE RHR TRAIN CAPABILITY
OL CONDITION SATISFIED.
DISCOVERY OF DEFICIENCY AND COMPONENT OPERABILITY SHOULD BE GOVERNED BY TECH SPECS
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O CORRECTIVE ACTIONS STANDING ORDERS, RHR AVAILABILITY
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OPERATORS BRIEFED ON ISSUE, EMPHASIZED
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CONSIDERATIONS OF OL CONDITIONS IN REPORTABILITY DETERMINATIONS MNCR AND INCIDENT REPORT SCREENING, SPECIFIC
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REFERENCE TO OL CONDITIONS
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PROPOSED DELETIONS OF OL CONDITION 2.C(21),
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DISCUSSED WITH NRC NRR AND REGION II - NO LONGER APPLICABLE J16 SLIDES 87020301 - 3
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FLOW MONITORING PROGRAM ESF SWITCHGEAR ROOM COOLERS
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0-SCOPE SAME PROGRAM FOR DIVISION I AND DIVISION II
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COOLERS
PROCEDURES ESTABLISHED EQUIPMENT PERFORMANCE INSTRUCTION 04-1-03-T46-1/2
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SCHEDULED BY SURVEILLANCE PROGRAM (GREEN TASK CARD
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TO INDICATE NRC COMMITMENT)
PERMANENT ANNUBARS INSTALLED
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FLOW DATA TAKEN IN LOCA LINEUP (SAME AS ORIGINAL
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FLOW BALANCE)
ACCEPTANCE CRITERIA ADDRESSED IN PROCEDURE
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O DEGRADED FLOW AND MINIMUM FLOW RATES IN PROCEDURE O
ACTION STATEMENT PROCEDURE STATES "IF ANY FLOWS ARE LESS
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THAN SPECIFIED UNDER THE DEGRADED FLOW COLUMN, THE DUTY MANAGER SHALL BE NOTIFIED S0 THAT HE CAN HAVE AN EVALUATION STARTED.
IF FLOWS ARE LESS THAN FLOWS LISTED UNDER MINIMUM FLOW THE COOLER MUST BE DECLARED INOPERABLE."
"IF A COOLER IS DECLARED INOPERABLE DUE TO LOW FLOWS, AN "INFORMATION ONLY LC0" IS TO BE WRITTEN.
THE FLOW TO THE COOLER MUST BE RESTORED ABOVE THE MINIMUM DESIGN FLOW WITHIN 72 HOURS OR THE ASSOCIATED SSW SYSTEM'MUST BE DECLARED INOPERABLE AND ACTIONS TAKEN AS SPECIFIED BY THE APPLICABLE TECH SPECS."
J16 3 FLOW MONT PROG - 1 M
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FLOW MONITORING PROGRAM ESF SWITCHGEAR ROOM COOLERS BASIS
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72 HOURS IS ACCEPTED TIME FRAME TO RESTORE EQUIPMENT OPERABILITY
FLOWS ARE TAKEN ON FREQUENT BASIS r
THUS SUBSTANTIAL DEGRADATION SHOULD NOT OCCUR
ANALYSIS HAS SHOWN THAT SUBSTANTIAL DEGRADATION DOES NOT EFFECT SAFETY FUNCTION O
MINIMUM FLOWS BASED ON TEMPERATURES NOT EXCEEDING 104*F DURING ACCIDENT CONDITIONS.
TECH SPEC'S DO NOT
' REQUIRE ASSOCIATED EQUIPMENT TO BE DECLARED INOPERABLE UNLESS TEMPERATURES IN ROOMS EXCEED 134*
FOR 4 HOURS.
O SINCE DUTY MANAGER IS INFORMED OF CONDITION HE MAY TAKE MORE CONSERVATIVE ACTION BASED ON MEASURED FLOWS.
O SHIFT SUPERVISOR SIGN OFF ON DATA SHEET AFTER ASSURING FLOW RATES ARE ACCEPTABLE O
FREQUENCY COMMITMENT WAS WEEKLY FOR 4 WEEKS, THEN MONTHLY
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PERFORMED ON WEEKLY BASIS SINCE PLANT RESTART FROM
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RF01 WILL MAINTAIN ON MINIMUM OF WEEKLY BASIS UNTIL
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CONFIDENCE IS REACHED THAT FLOWS ARE STABLE J16 3 FLOW MONT PROG - 2
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FLOW MONITORING PROGRAM ESF SWITCHGEAR ROOM COOLERS
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O DATA TRENDING TREND FOR INCREASE / DECREASE IN FLOW
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DATA UTILIZED TO DETERMINE CONDITIONS OF COOLERS
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AND TO ESTABLISH LONG TERM MONITORING FREQUENCY DIv!SION I
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O FLUCTUATION ON COOLERS PRIOR TO PLANT RESTART
OPENED ALL THROTTLE VALVES FULL OPEN O
FLOWS HAVE SINCE BEEN CONSISTENT (EXCEPTION OF 3A COOLER ON 2/1/87)
DIVISION II
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O FLUCTUATION ON COOLER FLOWS DURING PLANT STARTUP
FLUCTUATIONS COINCIDE WITH SAND INTRUSION INTO PLANT FROM PSW (STARTUP OF ADDITIONAL
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PSW PUMPS)
DUE TO DEGRADED FLOWS OF RECENT WEEKS PERFORMING DIVISION II MONITORING TWICE THIS WEEK AND UNTIL FLOWS STABLIZE J16 3 FLOW MONT PROG - 3
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FLOW MONITORING PROGRAM ESF SWITCHGEAR ROOM COOLERS METHODS AVAILABLE TO CORRECT LOW FLOWS V
VALVE MANIPULATION MOST USEFUL TO DATE
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CLOSING AND RAPIDLY OPENING INDIVIDUAL COOLER
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SUPPLY VALVE REMOVES LOOSE MATERIAL IN COOLER
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FLUSH WITH SSW HIGHER PRESSURE THAN PSW
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REMOVES LOOSE MATERIAL
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FLUSH WITH FIRE PROTECTION SYSTEM HIGHER PRESSURE AND FLOW
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SYSTEM MODIFICATIONS DURING RF01 TO ALLOW FLUSHING
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OF INDIVIDUAL COOLERS
HYDROLAZING PIPING MODIFICATIONS DURING RF01 TO ENHANCE
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HYDROLAZING CAPABILITY FITTINGS INSTALLED TO ALLOW HYDROLAZING WITHOUT
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CUTTING PIPE O
CHEMICAL CLEANING ABILITY TO CLEAN INDIVIDUAL COOLERS OR DIVISION AT
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A TIME UTILIZE CITRIC ACID
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AVAILABLE ON SITE
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SHORT DURATION TO CLEAN
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J16 3 FLOW MONT PROG - 4 zo
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FLOW MONITORING PROGRAM
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CONTROL ROOM AIR CONDITION O
PROCEDURE ESTABLISHED INCLUDES ACCEPTANCE CRITERIA
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MONITORING DIVISION I ONLY HISTORICALLY LOWER FLOWS ON DIVISION I THAN
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DIVISION II 148 GPM DIVISION I
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181 GPM DIVISION II
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DIVISION !! FLOWS WELL ABOVE ACCEPTABLE LIMITS
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PRIOR TO CLEANING PIPING CONFIGURATION-DIVISION I HAS APPROXIMATELY
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600 MORE FEET OF 4"/3" PIPE THAN DIVISION II O
FREQUENCY PERFORMED MONTHLY
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DUE TO HIGH FLOW RATES THERE HAS BEEN MINIMAL BUILDUP OF SILT.
O LOW FLOWS WERE DUE TO ROUGHNESS OF PIPE FROM TUBERCULIN GROWTH - CHEMICAL TREATMENT OF SSW SHOULD PREVENT.
O RESULTS SLIGHT REDUCTION FROM FLOW BALANCE TO IST MONTH
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READINGS SINCE STABILIZED
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REDUCTION THOUGHT TO BE RESULT OF TEMPERATURE
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CONTROL VALVE IN SLIGHTLY DIFFERENT POSITION FROM FLOW BALANCE J16 3 FLOW MONT PROG - 5
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FLOW MONITORING PROGRAM SSW SYSTEM FLOWS
BOTH DIVISIONS FLOW BALANCED DURING RF01
ONE DIVISIONS TO BE FLOW BALANCED DURING RF02 MONITORING PROGRAMS AND PAST FLOW BALANCE TO BE
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UTILIZED TO SELECT WHICH DIVISION TO FLOW BALANCE FLOW BALANCE TO BE PERFORMED AT FULL BASIN LEVEL
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UTILIZE NEW ESTABLISHED DATA AS BASELINE
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ANALYZE RESULTS TO DETERMINE EFFECTIVENESS OF
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CHEMICAL TREATMENT PROGRAM RESULTS WILL DETERMINE IF OTHER DIVISION WILL
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REQUIRE FLOW BALANCING
DIVISIONS WILL BE ALTERNATED DURING FUTURE OUTAGES FREQUENCY WILL CONTINUE UNTIL DATA JUSTIFIES
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MODIFICATION J16 3 FLOW MONT PROG - 6 2.
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I E NOTICE 86-96
SUBJECT HEAT EXCHANGER FOULING CAN CAUSE INADEQUATE
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OPERABILITY OF SERVICE WATER SYSTEM
SALIENT POINTS 1)
SYSTEM EVALUATION FOR SURVEILLANCE AND CONTROL EFFORTS TO IMPROVE SAFETY AND RELIABILITY SSW IS CLOSED CYCLE SYSTEM
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CHEMICALLY TREATING SSW BASIN
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FLOW MAXIMIZED THRU ESF SWITCHGEAR ROOM
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COOLERS DESIGN FLOWS ANALYZED
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FLOW MONITORING PROGRAM IMPLEMENTED
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2)
REVISION OF PLANT TECHNICAL SPECIFICATIONS TO REFLECT IMPROVED PROCEDURES ESF SWITCHGEAR ROOM COOLERS / CONTROL ROOM AIR
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CONDITIONER O
ROOM TEMPERATURES ADDRESSED IN TECH-SPECS
EQUIPMENT PERFORMANCE INSTRUCTIONS ADDRESS ACTION FOR LOW FLOWS NO TECH SPEC CHANGES AT PRESENT.
ANALYZE
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EFFECT OF PRESENT PROGRAMS FOR FUTURE CHANGES.
J16 3 FLOW MONT PROG - 7
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I E NOTICE 86-96
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3)
MONITORING THE EFFECTIVENESS OF CONTROL PROCEDURES
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AS PART OF THE SURVEILLANCE PROGRAM
THE FLOW MONITORING PROGRAM PROVIDES FLOW PERFORMANCE AND TRENDING INFORMATION WHICH WILL ASSESS EFFECTIVENESS OF BIOFOULING CONTROL PRACTICES
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O A COMPREHENSIVE EVALUATION OF-SSW SYSTEM FLOWS TO BE PERFORMED DURING RF02 4)
BI0 FOULING SURVEILLANCE IN THE ROUTINE MAINTENANCE PROGRAM
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O SSW PIPING AND HEAT EXCHANGERS INSPECTED DURING RF01
ADDITIONAL INSPECTIONS WILL BE PERFORMED DURING RF02 WHICH WILL INCLUDE DIESEL GENERATOR JACKET WATER COOLER
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RHR HEAT EXCHANGER v
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SELECTED PIPING IN SSW BASIN
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OTHER COMPONENTS SELECTED BY ENGINEERING
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CORROSION COUPONS IN SSW BASIN - ANALYZED FOR EFFECTIVENESS OF CHEMICAL TREATMENT PROGRAM
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J16 3 FLOW MONT PROG - 8
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INCORRECT USE OF ANNUBAR FLOW COEFFICIENTS
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DESCRIPTION OF PROBLEM
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SPECIAL TEST PROCEDURE UTILIZED TO FLOW
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BALANCE SSW A AND SSW B FOLLOWING SSW B PUMP
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REPLACEMENT DURING 1985 FALL OUTAGE UTILIZED WRONG FLOW COEFFICIENTS g
>o c
RESULTED IN CALCULATED (MEASURED) FLOW BEING L
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'1 GREATER THAN ACTUAL j
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METHOD OF IDENTIFICATION L
IN AUGUST 1986, DURING DEVELOPMENT OF TEST
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PROCEDURE TO PERFORM BALANCE OF SSW A FOR
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UPCOMING PUMP REPLACEMENT, ERROR WAS FOUND b'b
CAUSE OF PROBLEM
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ANNUBAR THOUGHT TO BE ANNUBAR TYPE 73
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PROCEDURE WRITER COULD NOT FIND FLOW
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COEFFICIENT FOR TYPE 73 ANNUBAR FOR li"
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DIAMETER PIPE IN ANNUBAR FLOW HANDBOOK TYPE 61 WAS IN HANDBOOK WITH COEFFICIENT FOR
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li" PIPE
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CONCLUDED ANNUBAR WAS TYPE 61 THAT WAS LISTED
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jf FOR 14" PIPE
.w 4.
DURING INITIAL TEST PROCEDURE PREPARATION
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(FALL 1985) INDEPENDENT REVIEWER QUESTIONED s
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THIS SELECTION AND DISCUSSED WITH THE WRITER.
REPEATED SAME ERROR AS THE WRITER AFTER DISCUSSION ANNUBARS WERE SPECIAL ORDER TYPE 73 AND NOT
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INCLUDED IN HANDBOOK ANNUBARS WERE NOT MARKED WITH TYPE OR FLOW
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COEFFICIENT
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INCORRECT USE OF ANNUBAR' FLOW COEFFICIENTS
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O CORRECTIVE ACTION INVESTIGATION OF SCOPE OFsPROBLEM.BY
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TECHNICAL SECTION
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REVIEWED SURVEILLANCES
REVIEWED STARTUP TEST PROCEDURES
INCORRECT FLOW COEFFICIENTS NOT FOUND IN
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OTHER APPLICATIONS
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PERMANENT ANNUBARS INSTALLED IN-ESF ROOM COOLERS REMAINING ANNUBARS CONTROLLED AS M8TE
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FLOW COEFFICIENTS INSCRIBED ON ANNUBAR/0N
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METAL TAG ATTACHED TO ANNUBAR J16 3 FLOW MONT PROG - 10 sh
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DESIGN REVIEW o REASON FOR REVIEW o OBJECTIVES o ASSESS SSW DESIGN ADEGUACY o ASSESS DESIGN ADEGUACY OF AN ADDITIONAL SYSTEM o ASSESS OVERALL ORIGINAL DESIGN ADEGUACY o SCOPE o STANDBY SERVICE WATER SYSTEM o PREVIOUS GRAND GULF PROBLEMS o OTHER PLANT SSW PROBLEMS o CRITICAL DESIGN INTERFACES o INDUSTRY EXPERIENCE INPUT o RELIABILITY / AVAILABILITY o SECOND SYSTEM o DESIGN CRITERIA IMPLEMENTATION & VERIFICATION o EXPAND SCOPE BASED ON SSW REVIEW o APPROACH o INDEPENDENT SAFETY EVALUATION GROUP (ISEG) LEAD o OUTSIDE EXPERTISE TO SUPPLEMENT ISEG
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o DUKE POWER o MULTI DISCIPLINE TEAM o ADDITIONAL SERI SUPPORT AS NEEDED l
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DESIGN REVIEW SCHEDULE o DETERMINE APPROACH COMPLETE o IDENTIFY OUTSIDE RESOURCES COMPLETE o PRELIMINARY SCOPE DEFINITION COMPLETE o COMMENCE REVIEW IN PROGRESS o COMPLETE SYSTEM BACKGROUND REVIEW 02/13 o COMPLETE ASSESSMENT 04/15 o SUMMARY REPORT 04/30 o SPECIFIC RECOMMENDATIONS (BOTH SYSTEM S PROGRAMMATIC)
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o NEED FOR FURTHER ASSESSMENTS
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