ML20135A844
| ML20135A844 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/21/1997 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | Hadley E AFFILIATION NOT ASSIGNED |
| References | |
| 2.206, NUDOCS 9702270450 | |
| Download: ML20135A844 (14) | |
Text
February 21, 1997 e
Ernest C. Hadley, Esq.
1040 B Main Street P.O. Box 549 West Wareham, MA 02576
Dear Mr. Hadley:
This letter provides an update of the 10 CFR 2.206 Petition you submitted on August 21, 1995, as supplemented August 28, 1995, on behalf of Mr. George Galatis and the group, We the People, Inc.
The staff has not completed its review of the Petitioners' remaining request for enforcement action pursuant to 10 CFR 50.5 and 50.9.
During a February 5, 1997 meeting with the public, two staff members of the NRC's Office for Analysis and Evaluation of Operational Data presented their generic assessment of spent fuel cooling.
Copies of the slides used by the presenters (Enclosure 1) and their September 1996 report (Enclosure 2) are provided for your informat 4n.
Please call me at (301) 415-1455,-if you have any questions concerning this issue.
Sincerely, Stephen Dembek, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-245
Enclosures:
As stated
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NUCLEAR REGULATORY COMMISSION 5
I WASHINGTON, D.C. 30006 4 001
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February 21, 1997 Ernest C. Hadley, Esq.
1040 8 Main Street P.O. Box 549 West Wareham, MA 02576
Dear Mr. Hadley:
This letter provides an update of the 10 CFR 2.206 Petition you submitted on August 21, 1995, as supplemented August 28, 1995, on behalf of Mr. George Galatis and the group, We the People, Inc. The staff has not completed its review of the Petitioners' remaining request for enforcement action pursuant to 10 CFR 50.5 and 50.9.
During a February 5,1997 meeting with the public, two staff members of the NRC's Office for Analysis and Evaluation of Operational Data presented their generic assessment of spent fuel cooling. Copies of the slides used by the presenters (Enclosure 1) and their September 1996 report (Enclosure 2) are provided for your information.
Please call me at (301) 415-1455, if you have any questions concerning this issue.
Sincerely, Stephen Dembek, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-245
Enclosures:
As stated
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ENCLOSURE 1
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ASSESSMENT OF SPENT FUEL COOLING l
Jose G. Ibarra Hal Ornstein l
i Office for Analysis and Evaluation of Operational Data (AEOD) l i
February 5,1997 t
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l SPENT FUEL COOLING ASSESSMENT t
- AEOD study requested by Executive Director for Operations.
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Developed generic configurations to assess loss of spent fuel pool cooling and inventory.
Assessed 12 years of operational experience.
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Performed site visits to gather information on i
physical configuration, practices, and procedures.
j Pedormed assessments of electrical systems, instrumentation, heat loads, and radiation.
l Evaluated risk of losing spent fuel cooling.
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PWR SPENT FUEL COOLING SYSTEMS Containment rAu ry Beg Building Cavity Watt
(
W Gate (s)
== c-2 /*
E y/ju Fuel Transfer
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L Refueti g
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Fuel Racks Maru tion
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Storage Area) 3
L BWR SPENT FUEL COOLING SYSTEMS uu-From RHR Symem An3-SW r'r
/ Mechanism Make up u
Sources Gates
/
n ps
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A!
y Cavig Sea Skimmer
' 3 Discharge l
r Dryer Surg g
Strainer Fuel Pool Refueling Separator Ta l
Seal Pit i r Fuel Racks i
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-> Purification HX ~Q gy i
Reactor N
Vessel hS
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u To RHR System 4
P SPENT FUEL POOL EVENTS TYPE OF EVENT NUMBER OF EVENTS i
i SFP Inventory 4
38 l
Connected Systems 20 Gates & Seals 10 l
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Structure or Liner 8
SFP Cooling 56 i
Cooling Flow 50 Heat Sink 6
5 t
LOSS OF INVENTORY LEVELS NUMBER OF OCCURRENCES 10 -
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4
==
2 2
2 0
<3 3TO 12 12TO 60
> 60 LEVEL DECREASE (INCHES)
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LOSS OF COOLING EVENTS NUMBER OF OCCURRENCES 20 16 15 10 5
3 mN 1
0 0
0TO 20 20TO 40 40TO 60 TEMPERATURE INCREASE (DEG F) l 7
NINE MILE POINT UNIT 2 60 m
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GATES OUT
$O 50-O GATES IN i
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29.4 30-uJ F
24.2 E
20-17.s g
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3 4
l REFUEL OUTAGE NUMBER I
I N
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FINDINGS AND CONCLUSIONS l
I Likelihood and Consequences Consequences of actual events have not j
been severe.
Primary cause of events has been human error.
l Relative risk of fuel damage is low compared with other reactor events.
i Highly dependent on human performance and j
plant design.
Frequency of coolant loss > 1 foot,1/100 reactor j
years.
Frequency of cooling loss > 20 F,2-3/1000 reactor i
years.
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i FINDINGS AND CONCLUSIONS (CONT.)
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Preventiort i
- Configuration control improvements can prevent and/or mitigate SFP events.
Evaluations may be needed at some multiunit sites for potential SFP boiling effects on safe shutdown.
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Response
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- Attention to time to boil with shorter outages.
Improved procedures and training may be needed.
- Improvements to instrumentation and power supplies may be needed.
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ENCLOSURE 2 4
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