ML20033G852
| ML20033G852 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/29/1990 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9004120213 | |
| Download: ML20033G852 (7) | |
Text
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. /o* %\\ e UNITE D STATis NUCLE AR REGULATORY COMMISSION
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March 29, 1990 Docket No.
50 416 LICENSEE:
$YSTEM [NERGY RESOURCE $ INC., (fERI)
FACILITY:
GRAND GULF NUCLEAR $TATION, UNIT 1 (GGNS 1)
SUBJECT:
SUM %RY OF FEBRUARY 15, 1990 MEETING REGARDING INCREASED COOLING CAPACITY OF $ PENT FUEL POOL The NRC staf f met with the licensee at the NRC of fices, Rockville, Maryland to hear and discuss the licensee's proposed means for increasing the cooling capacity of the spent fuel pool. is a list of the attendees. is a handout prepared by the licensee.
When the high density spent fuel pool cooling racks were approved (Operating License Amendment No. 17 August 18,1986) en open issue was the need for increased cooling capacity in order to utilize all cells of the racks.
The licensee committed (June 5 and July 25, 1986) to proposed an acceptable engineering solution by the third refueling outage and to implement it by the fitth refueling outage.
Cooling was evaluated as adequate for a maximum of 2324 assemblies out of the total available spaces in the racks (4348).
The licensee proposed (April 27,1989) to supplement the fuel pool cooling and cleanup (FPCC) system with the residual heat removal (RHR) system for the first 35 days after shutdown when fuel is unloaded from the core.
However, the Standard Review Plan ($RP) acceptance criteria are based on the assumption that the spent fuel pool cooling system by itself will perform this safety function.
During this meeting the licensee proposed the use of one FPCC pump and two FPCC heat exchangers in parallel to meet the $RP guidance (Enclosure 2, page 10).
The two pumps and two heat exchangers would be interconnected so that this alignment can be achieved with either pump.
Calculated performance is shown on page 9 of Enclosure 2.
The staff noted that the design maximum standby service water temperature (90*F) was not used in the latest calculation and indicated it should be.
Also staff questioned whether conservative heat exchanger fouling factors and tube plugging factors were considered.
The licensee indicated that the margin between heat removal capability and nominal maximum spent fuel heat load (page 10 of Enclosure 2) is adequate to accommodate a 90'F standby service water temperature and conservative heat exchanager factors.
With the use of one pump and two heat exchangers, it would not be necessary to use the RHR system to assist in spent fuel pool cooling for normal situations.
There may be some abnormal situations which would prevent the use of both heat exchangers but these times are expected to be few.
In this abnormal situation, an RHR pump and heat exchanger would be used, l
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The staff asked whether the licensee had evaluated the worst single failure.
For example, if the service water to a heat exchanger failed because of inadvertent closure of a valve or f ailure of a service water pump, there should be adequate cooling for the normal, maximum heat load using two pumps and one heat exchanger.
Alternatively, valves may be locked to preclude an unacceptable single failure.
The licensee agreed to evaluate potential single f ailures for both the FPCC system and the service water system and justify the worst single failure in its submittal to the staff.
The licensee's analysis will demonstrate conformance with SRP 9.1.3.
The licensee will resubmit its proposed increased cooling capability for the spent fuel pool.
In addition, the licensee will propose a change to the Technical Specifications to increase the fuel storage capacity from 2324 to 4348.
Original Slgned By:
Lester L. Kintner, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/enclosurs:
See next page DISTRIBUTION See attached page OFC : PM:
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(.1 (1-1
...t NAME :LK ner:sy asam
.....:...........j:......................................:............:......................
DATE:3/J.7/90 3/ty /90
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Mr. W. T. Cottle System Energy Resources, Inc.
GrandGulfNuctsarStation(GGNS)
)
cc:
Mr. T. H. Cloninger Mr. C. R. Hutchinson 1
Vice President, Nuclear Engineering GGNS General Manager j
& Support System Energ Resources, Inc.
System inergy Resources, Inc.
P. O. Box 766 i
P. O. Box 31995 Port Gibson, Mississippi 39150 l
Jackson, Mississippi 39280 l
Robert B. McGehee Esquire The Honorable William J. Guste, Jr.
(
Wise, Carter, Child,and Attorney General i
Caraway Department of Justice P. O. Ecx 651 State of Louisiane Jackson, Mississippi 39205 P. O. Box 94005 l
Baton Rouge, LA 70804 9005 l
Nicholas S. Reynolds Esquire Bishop. Cook,Purcell Alton B. Cobb, M.D.
i and Reynolds Statt Health Officer 4
1400 L Street, N.W.
12th Floor State Board of Health Washington 0.C.
20005-3502 P. O. Box 1700 Jackson, Mississippi 39205 l
Mr. Ralph T. Lelly Manager of Quality Assurance Entergy Services, Inc.
Office of the Governor P. O. Box 31995 State of Mississippi l
Jackson, Mississippi 39266 Jackson, Mississippi 39201
(
Mr. Jack McMillan, Director President, Division of Solid Waste Management Claiborne County Board of Supervisors i
Mississippi Department of Natural Port Gibson, Mississippi 39150 l
Resources t
P. O. Box 10385 Jackson, Mississippi 39209 Regional Administrator, Region !!
U.S. huclear Regulatory Comission Mr. John G. Cesare 101 Marietta St., Suite 2900 Director, Nuclear Licensing Atlanta, Georgia 30323 System Energy Resources, Inc.
P. O. Box 469 Port Gibson, Mississippi 39150 Mike Moore, Attorney General Frank Spencer, Assist. Attorney General Mr. C. B. Hogg, Pro, ject Manager State of Mississippi Bechtel Power Corporation Post Office Box 22947 P. O. Box 2166 Jackson, Mississippi 39225 Houston, Texas 77252 2166 i
Mr. H. O. Christensen Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 399 Port Gibson, Mississippi 39150 1
I
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.N DISTRIBUTION FOR MEETlWG 5tMMARY DAffD: March 29, 1990 facility: Grand Gulf W441e_
NRC POR Local l'DR T. Murley 12-6 18 E. Adensam 14 B 20 P. Anderson 14020 L. Kintner 14 B 20 H. Walker R. Architzel N. Wagrer G. Thomas OGC 15-B-18 E. Jordan MNBB-3302 ACRS(10)
P 315 D. Borchardt 17-G-21 a
I ATTENDANCE AT NRC-5ERI MEETING February 15, 1990 System Engergy Resources. Inc.. (SERI)
J. Cesare Director, Nuclear Licensing J. Wright Engineer, Nuclear Plant Engineering M. Crawford Manager, N.uclear Licensing G. Zinke Superintendent, Plant Licensing Nuclear Regulatory Commission (NRC)
R. Architzel section Chief, Plant Systems Branch H. Walker Engineer, Plant Systems Branch N. Wagner Engineer, Plant Systems Branch
- G, Thomas Engineer, Reactor Systems Branch L. Kintner Project Manager, Project Directorate !! 1
- Part time I
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I SERI/NRC MEETING SPENT FUEL COOLING CAPABILITY 4
FEBRUARY 15, 1990
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NRC/SERI MEETING SPENT FUEL COOLING FEBRUARY 15, 1990
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AGENDA I.
INTRODUCTION AND PURPOSE OF MEETING J. G. CESARE 1
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II.
BACKGROUND M. L. CRAWFORD A.
GENERAL BACKGROUND
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B.
CURRENT ISSUES I
III. OVERVIEW OF PLANT DESIGN /0PERATIONS FOR G. A. ZINME SPENT FUEL COOLING l
A.
GENERAL DESCRIPTION OF PLANT DESIGN FOR SPENT FUEL COOLING B.
CONDUCT OF OPERATIONS FOR SPENT FUEL COOLING IV.
OVERVIEW 0F SPENT FUEL COOLING ANALYSIS R. J. WRIGHT i
A.
SPENT FUEL DECAY HEAT LOADS B.
SPENT FUEL COOLING CAPABILITY V.
SUMMARY
J. G. CESARE 1
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j GRAND GULF NUCLEAR STATION SPENT FUEL COOLING FEBRl'ARY 15, 1990 INTR 000t? ION I
PURPOSE OF MEETING i
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TO PROPOSE A SPENT FUEL COOLING SOLUTION WHICH WILL ALLOW REMOVAL OF THE HIGH DENSITY SPENT FUEL STORAGE RACK TECH SPEC RESTRICTION a
I o
TO DISCUSS THE ROLE OF RHR ASSIST TO SPENT FUEL COOLING I
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4 3
l GRAND GULF NUCLEAR STATION SPENT FUEL COOLING (CONTINUED)
BACKGROUND o
GENERAL BACKGROUND j
HISTORY PCOL SUBMITTED ON HIGH DENSITY SPENT FUEL STORAGE RACKS MAY 6, 1985 OL AMENDMENT 17 ISSUED AUGUST 18,
- 1986, LICENSING HIGH DENSITY SPENT FUEL STORAGE TECH SPEC 3/4.7.9 - SPENT FUEL STORAGE j
P0OL TEMPERATURE (140'F)
TECH SPEC 5.6.3 - FUEL STORAGE CAPACITY (SFP RESTRICTED TO 2324 0F 4348 l
ASSEMBLIES)
COMMITTED TO PROPOSE ENGINEERING SOLUTION PRIOR TO STARTUP FROM RF03 TO BRING SPENT FUEL POOL l
COOLING CAPABILITY INTO CONFORMANCE WITH SRP REQUIREMENTS FOR THE PHYSICAL LIMIT OF HIGH DENSITY SPENT FUEL RACKS (4348 ASSEMBLIES)
COMMITTED TO IMPLEMENT ' SOLUTION PRIOR TO STARTUP FROM FIFTH REFUELING OUTAGE PROPOSED SOLUTION SERI PROPOSED SOLUTION AT RF03 (AECM-89/0029, APRIL 29, 1989)
ONE FPC' TRAIN /SSW PROVIDES ADEQUATE COOLING AFTER OUTAGE DAY 35 COMMITMENT TO RHR ASSIST TO FUEL P00L' COOLING WHEN NEEDED THROUGH OUTAGE DAY 35
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j GRAND GULF NUCLEAR STATION SPENT FUEL COOLING (CONTINUED) o GENERAL BACKGROUND (CONTINUED)
NRC FEEDBACK RECEIVED FROM LPM DISCUSSED ROLE OF RHR ASSIST TO FUEL POOL COOLING i
REQUESTED
- DEDICATION" 0F RHR ASSIST DURING FIRST 35 DAYS OF OUTAGE o
CURRENT ISSUES PROVISION OF SPENT FUEL COOLING CAPACITY FOR HIGH DENSITY SPENT FUEL STORAGE REMOVAL OF TECH SPEC RESTRICTION ON USE OF HIGH DENSITY SPENT FUEL STORAGE CAPACITY l
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GRAND GULF NUCLEAR STATION SPENT FUEL COOLING (CONTINUED)
OVERVIEW 0F PLANT DESIGN /0PERATIONS FOR SPENT FUEL COOLING 1
o GENERAL DESCRIPTION OF PLANT DESIGN FOR SPENT FUEL COOLING t
FUEL LOCATIONS FUEL POOL COOLING t
CCW/SSW TO FPC HEAT EXCHANGER RHR o
CONDUCT OF OPERATIONS FOR SPENT FUEL COOLING i
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i GRAND GULF NUCLEAR STATION SPENT FUEL COOLING (CONTINUED) l OVERVIEW 0F SPENT FUEL COOLING ANALYSIS o
SPENT FUEL DECAY HEAT LOADS HEAT LOAD PER BTP ASB 9-2 l
BOUNDING BATCH SIZE 284 FUEL ASSEMBLIES I
SRP 9.1.3 HEAT LOAD-17.62 MBTU/HR NORMAL DISCHARGE (REFUEL LOAD AFTER 150 l
HOURS),PLUS REFUEL LOAD AFTER 1 YEAR, PLUS
]
REFUEL LOAD AFTER 400 DAYS GGNS DESIGN HEAT LOAD 21.4 MBTV/HR HIGH DENSITY SPENT FUEL STORAGE RACKS FILLED TO CAPACITY 4348 ASSEMBLIES UNCERTAINTY FACTOR (10%) ADDED PER BTP i
APPROACH CONSISTENT W/HDSFR LICENSING HEAT LOAD CALCULATIONS METHODOLOGY CONSISTENT WITH BTP AND CONSERVATIVE REGARDING TOTAL AMOUNT OF DISCHARGED FUEL i
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GRAND GULF NUCLEAR STATION SPENT FUEL COOLING (CONTINUED)
OVERVIEW 0F SPENT FUEL COOLING ANALYSIS (CONTINUED)
I o
SPENT FUEL COOLING CAPABILITY FOCUS IS ON CAPABILITY TO REMOVE DECAY HEAT LOAD DURING OUTAGE DAYS 6-37 4
COOLING CAPABILITY 1
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PREVIOUS ANALYSIS UTILIZED ONE FPC PUMP /1 HX CONFIGURATION i
VALUES USED IN PREVIOUS ANALYSIS FPC FLOW / TEMP 1100 GPM/140*F CCW FLOW / TEMP 1000 GPM/95'F SSW FLOW / TEMP 1065 GPM/90*F 4
APPROACH TO ACHIEVE INCREASED SYSTEM CAPACITY UTILIZE 0NE FPC PUMP /2 HX CONFIGURATION FPC FLOW / TEMP 1600 GPM/140*F (800 GPM/HX)
SSW FLOW / TEMP 1255 GPM/85.8'F ASSESS SSW TEMP FOR OUTAGE CONDITION 4/5 MAXIMUM SSW TEMP 85.5'F FOR OPERATIONAL CONDITIONS 4 AND 5 HEAT REJECTION > 26 MBTV/HR
FPCC HEAT REMOVAL CAPABILITY 30 26.4 25 One Pump /Two HX (SSW) 21.4
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GRAND GULF NUCLEAR STATION SPENT FUEL COOLING j
(CONTINUED) j
SUMMARY
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ANALYSIS SHOWS THE 1 FPC PUMP /2HX/SSW SPENT FUEL COOLING CONFIGURATION WILL REMOVE EXPECTED DECAY HEAT LOADS FOR HIGH DENSITY SPENT FUEL RACK STORAGE AFTER THE CYCLE 16 DISCHARGE o
RHR ASSIST TO SPENT FUEL COOLING NEED NOT BE " DEDICATED" i
o ANALYSIS PROVIDES THE BASIS FOR REMOVAL OF THE HIGH DENSITY SPENT FUEL STORAGE CAPACITY RESTRICTION o
SERI PLANS A
PCOL SUBMITTAL TO REMOVE THE TECH SPEC l
RESTRICTION (TECH SPEC 5.6.3) l 1
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