ML102220114
| ML102220114 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/09/2010 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Schwartz C Entergy Nuclear Operations |
| References | |
| IR-08-009 | |
| Download: ML102220114 (5) | |
See also: IR 05000255/2008009
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210
LISLE, IL 60532-4352
August 9, 2010
Mr. Christopher J. Schwarz
Vice President, Operations
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant
27780 Blue Star Memorial Highway
Covert, MI 49043-9530
SUBJECT:
PALISADES NUCLEAR PLANT -REQUEST FOR INFORMATION
UNRESOLVED ITEM 05000255/2008009-03(DRS)
Dear Mr. Schwarz:
During the 2008 the Component Design Bases Inspection at Palisades Nuclear Power Plant,
the inspectors identified the station relied on non-safety-related equipment to mitigate the
consequences of a steam generator tube rupture (SGTR) concurrent with a loss of offsite
power event. Specifically, additional inspection and consultation with members of Nuclear
Reactor Regulation (NRR) was needed to determine if the use of the non-safety-related
Atmospheric Dump Valves (ADVs) was acceptable for a Final Safety Analysis Report (FSAR)
Chapter 14 analyses. This issue was identified as Unresolved Item (URI 05000255/2008009-
03).
In Task Interface Agreement Number 2009-03, dated June 29, 2010 (ML101260128), the NRR
staff concluded the use of the non-safety-related ADVs was part of the licensing bases. The
document further stated that the use of non-safety-related ADVs was allowed as long as the
analyses using these non-safety-related systems, comply with regulations, and are approved
by the NRC. In addition it requires a means to cool down the primary coolant system in the
event the non-safety-related components are not available, using an established alternate
method with procedures and evaluated to remain bounded by the worst case dose analysis
using the ADVs.
The purpose of this letter is to request additional documents to facilitate the resolution of URI 05000255/2008009-03. The information requested should be available to the lead inspector at
the Regional Office no later than August 18, 2010.
The lead inspector for this inspection is Jorge J. Corujo-Sandín. If there are questions
about the material requested, or the inspection, please call Jorge J. Corujo-Sandín at
(630) 829- 9741. Please send the information to the following e-mail address jorge.corujo-
sandin@nrc.gov. A hard-copy with the required information is also an acceptable option.
It is important that these documents be as complete as possible, in order to minimize the
number of documents requested during any additional follow up or during the on-site
inspection, if one is determined to be required.
C. Schwarz
-2-
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, control number 3150-
0011. The NRC may not conduct or sponsor, and a person is not required to respond to a
request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget control number.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-255
License No. DPR-20
Enclosure:
UNRESOLVED ITEM 05000255/2008009-03 INSPECTION DOCUMENT
REQUEST
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UNRESOLVED ITEM 05000255/2008009-03 INSPECTION DOCUMENT REQUEST
Enclosure
1
Unresolved Item: 05000255/2008009-03
Inspection Report: 05000255/2010
Lead Inspector:
Jorge J. Corujo-Sandín
(630) 829-9741
jorge.corujo-sandin@nrc.gov
A.
Information Requested By August 18, 2010
With respect to the Palisades design basis Steam Generator Tube Rupture (SGTR)
with a concurrent Loss of Off-site Power (LOOP) event, please provide the following:
1. A brief description of the method used to cool down the plant using only
safety-related equipment, in the event the non-safety-related Atmospheric Dump
Valves (ADVs) are unavailable.
2. A brief explanation describing why the use of ADVs is the preferred method to
mitigate the design bases SGTR coinciding with a LOOP.
3. A copy of the latest FSAR which describes the plants response to a SGTR event.
Include sections which describe the use of the ADVs and the safety-related method.
4. A copy of the assessment or analysis which demonstrates the use of only safety-
related equipment for cooling the plant is bounded by the assessment performed for
the use of ADVs. That is, the use of safety-related equipment is will not exceed
worst case off-site dose assessment determined by the use of the preferred method
to cope with a SGTR (the ADVs).
5. A copy of the analysis or calculation that demonstrates the use of only safety-related
equipment for cooling the plant can remove the decay heat without impacting the
primary systems mass inventory to the point that core damage results.
6. A copy of the analysis or calculation that demonstrates the use of only safety-related
equipment for cooling the plant will not result in an overfill situation. That is, the
margin to overfill the ruptured steam generator is bounded by the use of the ADVs.
7. A list of available safety-related options for supplying coolant, feeding, into the
Primary Coolant System. Include each options coolant injection limitations (rate,
shutoff head, etc).
8. If the use of only safety-related equipment for cooling the plant includes discharge
into the pressurizer relief tank (PRT), please provide the following: the amount or
rate of discharge into the PRT; and a description of the method used to vent, spray,
and drain the PRT. Include a list of equipment needed as well as the safety
classification of the equipment.
UNRESOLVED ITEM 05000255/2008009-03 INSPECTION DOCUMENT REQUEST
Enclosure
2
9. A copy of the lesson plans, task training guide, or training material including Job
Performance Measures and simulator scenarios used to train the operators to use
the safety-related equipment when the nonsafety-related ADVs fail.
10. A copy of Corrective Action Documents generated as a result of this URI. Include
associated evaluations, actions, status of actions, procedure changes, modifications,
etc.
If the information requested above will not be available, please contact Jorge Corujo-Sandín as
soon as possible at (630) 829-9741 or email jorge.corujo-sandin@nrc.gov.
C. Schwartz
-2-
request for information or an information collection requirement unless the requesting document displays
a currently valid Office of Management and Budget control number.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure
will be available electronically for public inspection in the NRC Public Document Room or from the
Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the
NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-255
License No. DPR-20
Enclosure:
UNRESOLVED ITEM 05000255/2008009-03 INSPECTION DOCUMENT REQUEST
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DISTRIBUTION:
Susan Bagley
RidsNrrPMPalisades
RidsNrrDorlLpl3-1 Resource
RidsNrrDirsIrib Resource
Steven Reynolds
DRPIII
DRSIII
Patricia Buckley
ROPreports Resource
DOCUMENT NAME: G:\\DRS\\Work in Progress\\Ltr. 080910 Palisdes URI RFI JSC.docx
9 Publicly Available
9 Non-Publicly Available 9 Sensitive 9 Non-Sensitive
To receive a copy of this document, indicate in the concurrence box C = Copy without attach/encl; E = Copy with attach/encl N = No copy
OFFICE
RIII
RIII
NAME
AMStone for JSCorujo:ls
AMStone
DATE
08/09/10
08/09/10
OFFICIAL RECORD COPY