ML20137F609
| ML20137F609 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/27/1997 |
| From: | Jabbour K NRC (Affiliation Not Assigned) |
| To: | Nerkow H NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9704010161 | |
| Download: ML20137F609 (8) | |
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March 27,1997 l
l Meetina Notice E-Mail Hard Cooy S. Collins /F. Miraglia Docket File R. Zimmerman (RPZ)
PUBLIC S. Varga PD II-2 Rdg.
J. Zwolinski OGC H. Berkow ACRS K. Jabbour Receptionist (Hatch)
L. Berry D. Ross (e-mail to SAM)
Licensee & Service List C. Gratton S. Lee J. Johnson, RII P. Skinner, RII G. Tracy (GMT)
K. Clark (KMC2)
PMNS (Meeting Announcement Coordinator) l l
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gol' 9704010161 970327 PDR ADOCK 05000321 3
P pyy 4
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March 27, 1997 MEMORANDUM T0:
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II FROM:
Kahtan N. Jabbour, Senior Project Manager Original signed by:
Project Directorate 11-2 Division of Reactor Projects - I/II
SUBJECT:
FORTHCOMING MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY (SNC) AND SITE VISIT REGARDING THE SPENT FUEL j
POOL ANALYSIS AND DESIGN FEATURES i
DATE & TIME:
April 9, 1997 April 10, 1997 4
9:15 a.m. - 4:00 p.m.
7:30 a.m. - 4:00 p.m.
LOCATION:
Edwin I. Hatch Nuclear Plant Room 234, Simulator Building Edwin I. Hatch Nuclear Plant i
Baxley, Georgia PURPOSE:
To audit the analysis and design features of the spent fuel pool at Hatch Units 1 and 2, and to visit site.
(See Agenda, Enclosure 1; and Questions, Enclosure 2).
PARTICIPANTS *:
EC
}Jiq K. Jabbour, NRR
- 0. Vidal, et al.
C. Gratton, NRR S. Lee, NRR INEL (NRC Contractor)
S. Khericha Docket No(s). 50-321 and 50-366 cc: See next page CONTACT:
K. Jabbour (301) 415-1496 i
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meetings Open to the Public" 59 Federal Reaister 48340, 9/20/94.
For the tour of the spent fuel pool area, permission to enter the plant must be obtained from Southern Nuclear Operating Company, Inc.
To receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDII-2 6 LA:PDII-2l6 DrPDR-U l l
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NAME KJABBOUR:cn M LBERRY & n HBERKDW DATE 3 / 2 7 /97 ' / " 3 /J7 /97 Q17 /97
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i UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D.C. 2006tH1001
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March 27, 1997 MEMORANDUM TO:
Herbert N. Berkow, Director Project Directorate II-2 Di ion of Re ects - I/II FROM:
Kahtan N. Jabbour, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II
SUBJECT:
FORTHCOMING MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY (SNC) AND SITE VISIT REGARDING THE SPENT FUEL POOL ANALYSIS AND DESIGN FEATURES DATE & TIME:
April 9, 1997 April 10, 1997 9:15 a.m. - 4:00 p.m.
7:30 a.m. - 4:00 p.m.
LOCATION:
Edwin I. Hatch Nuclear Plant Room 234, Simulator Building Edwin I. Hatch Nuclear Plant Baxley, Georgia PURPOSE:
To audit the analysis and design features of the spent l
fuel pool at Hatch Units I and 2, and to visit site.
(See Agenda, Enclosure 1; and Questions, Enclosure 2).
PARTICIPANTS *:
- 0. Vidal, et al.
C. Gratton, NRR S. Lee, NRR INEL (NRC Contractor)
S. Khericha Docket No(s). 50-321 and 50-366 cc: See next page CONTACT:
K. Jabbour (301) 415-1496
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners,'intervenors,~ or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meetings Open to the Public" 59 Federal Reaister 48340, 9/20/94.
For the tour of the spent fuel pool area, permission to enter the plant must be obtained from Southern Nuclear Operating Company, Inc.
Georgia Power Company Edwin I. Hatch Nuclear Plant cc:
Mr. Thomas P. Mozingo Mr. Ernest L. Blake, Jr.
Program Manager Shaw, Pittman, Potts and Trowbridge Nuclear Operations 2300 N Street, NW.
Oglethorpe Power Corporation Washington, DC 20037 2100 East Exchange Place P. O. Box 1349 Mr. D. M. Crowe Tucker, Georgia 30085-1349 Manager Licensing - Hatch Georgia Power Company Charles A. Patrizia, Esquire P. O. Box 1295 Paul, Hastings, Janofsky & Walker Birmingham, Alabama 35201 12th Floor 1050 Connecticut Avenue, NW.
Mr. L. Sumner Washington, DC 20036 General Manager, Nuclear Plant Georgia Power Company Mr. Jack D. Woodard P. O. Box 439 Senior Vice President -
Baxley, Georgia 31513 Nuclear Operations Georgia Power Company Resident Inspector P. O. Box 1295 U.S. Nuclear Regulatory Commission Birmingham, Alabama 35201 11030 Match Parkway North B2xley, Georgia 31513 Chairman Appling County Commissioners Regional Administrator, Region II County Courthouse U.S. Nuclear Regulatory Commission Baxley, Georgia 31513 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Mr. J. T. Beckham, Jr.
Vice President - Plant Hatch Mr. Charles H. Badger Georgia Power Company Office of Planning and Budget P. O. Box 1295 Room 610 Birmingham, Alabama 35201 270 Washington Street, SW.
Atlanta, Georgia 30334 Steven M. Jackson Senior Engineer - Power Supply Harold Reheis, Director Municipal Electric Authority Department of Natural Resources of Georgia 205 Butler Street, SE., Suite 1252 1470 Riveredge Parkway, NW Atlanta, Georgia 30334 Atlanta, Georgia 30328-4684 j
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J AGENDA i
NRC/GPC Meetina and Site Visit April 9-10. 1997 4
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Soent Fuel Pool (SFP) Reaulatory Analvasis t
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Introduction - Scope and purpose i
Tour of Hatch SFP cooling system, decay heat removal system,
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i steam propagation paths l
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Discussion of Hatch SFP analysis, design, and~ operation (See Hatch SFP Regulatory Analysis, Enclosure 2)
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Closing remarks
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Hatch SFP Reaulatory Analysis During the meeting, NRC will gather information to clarify the following issues'as they relate te probabilistic analyses regarding the ' operation of the spent fuel pool.
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[ Assume Units 1 and 2 are at power (or non-refueling mode) for questions 1 through 12.)
1.
Can the gate between the Unit I and Unit 2 SFPs be operated (opened or 1
i closed) at any time?_ What is the normal position (condition) of the gate (removed or installed)? If the normal position is open (removed),
how often is it installed and for how long? What administrative procedure (s) control whether the canal gate is installed or. removed?
l What operator actions are required? What assistance is available to the operators to manipulate the gate?
i 2.
What type of information (or mode of information display) is available to the operators to recognize a loss of SFP cooling event?
3.
What is the success criteria for restoring SFP cooling?
i 4.
What backup system is available for SFP cooling? Given a loss of the normal cooling system, how soon can this system be available to provide SFP cooling function? What operator actions are required to cool the SFP via the backup system? What assistance is available to the operators?
5.
Are there alternate cooling capabilities for the SFP7 If yes, what are they and what operator actions are required? -What assistance is available to the operators?
6.
What is the site-specific loss-of-offsite power (LOOP) initiating event frequency? What LOOP recovery probabilities are assumed in the plant PRA? How many EDGs are available to be used for SFP cooling, if any?
How long would it take to establish power to SFP cooling from the EDGs?
Are any SFP recovery actions covered by the plant Emergency Operating Procedures?
1 7.
Upon loss of SFP cooling, and assuming cooling is not restored, how long would it take for the SFP to begin boiling? Assume the SFP decay heat load is based on a full SFP (one third core recently discharged from a 30-day outage), ultimate heat sink at its design condition, and the loss of SFP cooling occurs one week after restart.
8.
From the time boiling begins in the SFP, how long would it take for the steam generated from the SFP to start affecting operability of the equipment in the vicinity, if any? In general, what it the enacted communication path for the steam should the SFP boil? Can steam be isolated or diverted? Are any of the safety systems for either of the units vulnerable to steam propagation? If yes, are they recoverable --
if yes, how? Provide any plant analyses or procedures that support this conclusion.
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What initiating event frequency is assumed for loss of inventory event (e.g., due to seal failure, piping failure, siphoning event) for the SFP? What isolation mechanisms -(active or passive) are available?
10.
What indications / indicators are available to the operators to recognize a loss of SFP inventory event? Where are they located? Where do they i
provide indication / alarm? Are they safety-related?
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11.
List the makeup sources to the SFP in order of priority (for use). What operator. actions are required to operate the systems? What operator assistance is available, if any?
i 12.
What is the plant-specific LOCA initiating event frequency assumed in j
the plant PRA? Assuming a LOCA occurs, is the SFP cooling system load-shed?
i 13.-
Provide responses to questions I through 12 given the following 4
conditions: one unit is shut down with one-third core off-loaded to the spent fuel pool, the other unit is operating.
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14.
Provide responses to questions I through 12 given the following i
conditions: one unit is shut down with a full core off-loaded to the spent fuel pool, the other unit is operating.
To assist the NRC staff in their audit of spent fuel pool issues, please have the following material available:
Training material regarding the design and operation of the spent fuel i
pool, spent fuel pool cooling system, decay heat removal system, and residual heat removal system, including normal and emergency operations.
P& ids.for these systems, and elevation drawings of the secondary j
containment (specifically, the spent fuel pool area).
3 Administrative controls regarding refueling operations, particularly those that control available decay heat removal methods.
e Average outage times for your refueling outages. Types of outages performed (full core, partial core) and planned for the future.
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Description / drawing / analysis for the steam transport path should the j
spent fuel pool boil.
Success criteria (PRA} for normal operations, partial core offloads, and full core offloads (number of pumps in each system).
Operational data regarding the operation of the RHR system in the fuel pool cooling assist mode, i.e., has it ever been used? How many times?
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How long did it take to align? Is there pre-operational test data available for review?
Operational data regarding the operation of the decay heat removal system, i.e., how many times was it used? How long does it take to i
3-4 align? Is there pre-operational test data available for review? What quality requirements pertain to the DHR system?
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