ML14220A213: Difference between revisions
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| number = ML14220A213 | | number = ML14220A213 | ||
| issue date = 08/08/2014 | | issue date = 08/08/2014 | ||
| title = | | title = E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 | ||
| author name = Hon A | | author name = Hon A | ||
| author affiliation = NRC/NRR/DORL/LPLII-2 | | author affiliation = NRC/NRR/DORL/LPLII-2 | ||
| addressee name = Hamrick G | | addressee name = Hamrick G, Murray W | ||
| addressee affiliation = Duke Energy Progress, Inc | | addressee affiliation = Duke Energy Progress, Inc | ||
| docket = 05000324, 05000325, 05000327, 05000328 | | docket = 05000324, 05000325, 05000327, 05000328 | ||
Line 13: | Line 13: | ||
| document type = E-Mail, Request for Additional Information (RAI) | | document type = E-Mail, Request for Additional Information (RAI) | ||
| page count = 2 | | page count = 2 | ||
| project = TAC:ME9623, TAC:ME9624 | |||
| stage = RAI | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:Hon, Andrew From: Han, Andrew Sent: Friday, August 08, 2014 11:11 AM To: Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com) | |||
Cc: Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Jimenez, Manuel | |||
==Subject:== | |||
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION REGARDING VOLUNTARY RISK INITIATIVE NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME9623 AND ME9624) | |||
Mr. George T. Hamrick, Vice President Brunswick Steam Electric Plant Duke Energy Progress, Inc. | |||
Post Office Box 10429 Southport, North Carolina 28461 | |||
==Dear Mr. Hamrick:== | |||
By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) | |||
Accession No. ML12285A428), Duke Energy Progress, Inc. (the licensee) proposed to amend the operating license for the Brunswick Steam Electric Plant, Units 1 and 2, by adopting a new risk-informed performance-based fire protection licensing basis in accordance with National Fire Protection Association Standard 805. | |||
The NRC staff has reviewed your application and determined that further information is needed to complete our evaluation of the proposed change. | |||
On July 16, 2014, the NRC staff and your representatives held a conference call to provide you with an opportunity to clarify the proposed RAI related to probabilistic risk assessment. The NRC staff's finalized this set of RAis is shown below which were discussed with Mr. Bill Murray of your representatives on August 6, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 29, 2014. | |||
The NRC staff considers that timely responses to RAis help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08. Please also note that review efforts on this task are continuing and additional RAis may be forthcoming. | |||
1 | |||
If you have any questions regarding this letter, please contact me. | |||
Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2) | |||
Plant Licensing Branch /1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN08E5 Mail Stop 08G-9a andrew. hon@nrc. gov cc: Distribution via ListServ ADAMS Accession No.: ML14220A213 REQUEST FOR ADDITIONAL INFORMATON VOLUNTARY FIRE PROTECTION RISK INITIATIVE DUKE ENERGY PROGRESS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 Radiation Release RAI 02.01 For the outside areas listed in Attachment E where radioactive materials may be stored, please provide the following information: | |||
: a. Identify the type of container used (e.g., sea land type containers) to store the radioactive material. | |||
: b. Describe the administrative controls that limit the amount of activity which may be present in these containers. | |||
: c. Provide a bounding calculation that demonstrates that the radioactive releases from a fire in a container stored in outside areas will not exceed the applicable 10 CFR Part 20 limits. The analysis should include the assumptions, a summary of the methodology and calculations, and resulting doses. | |||
: d. Provide any administrative controls that will be used to control the release of liquids which may become contaminated from fire-fighting activities. | |||
2}} |
Latest revision as of 19:02, 19 March 2020
ML14220A213 | |
Person / Time | |
---|---|
Site: | Sequoyah, Brunswick |
Issue date: | 08/08/2014 |
From: | Andrew Hon Plant Licensing Branch II |
To: | Hamrick G, Murray W Duke Energy Progress |
Hon A | |
References | |
TAC ME9623, TAC ME9624 | |
Download: ML14220A213 (2) | |
Text
Hon, Andrew From: Han, Andrew Sent: Friday, August 08, 2014 11:11 AM To: Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com)
Cc: Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Jimenez, Manuel
Subject:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION REGARDING VOLUNTARY RISK INITIATIVE NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME9623 AND ME9624)
Mr. George T. Hamrick, Vice President Brunswick Steam Electric Plant Duke Energy Progress, Inc.
Post Office Box 10429 Southport, North Carolina 28461
Dear Mr. Hamrick:
By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML12285A428), Duke Energy Progress, Inc. (the licensee) proposed to amend the operating license for the Brunswick Steam Electric Plant, Units 1 and 2, by adopting a new risk-informed performance-based fire protection licensing basis in accordance with National Fire Protection Association Standard 805.
The NRC staff has reviewed your application and determined that further information is needed to complete our evaluation of the proposed change.
On July 16, 2014, the NRC staff and your representatives held a conference call to provide you with an opportunity to clarify the proposed RAI related to probabilistic risk assessment. The NRC staff's finalized this set of RAis is shown below which were discussed with Mr. Bill Murray of your representatives on August 6, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 29, 2014.
The NRC staff considers that timely responses to RAis help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08. Please also note that review efforts on this task are continuing and additional RAis may be forthcoming.
1
If you have any questions regarding this letter, please contact me.
Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2)
Plant Licensing Branch /1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN08E5 Mail Stop 08G-9a andrew. hon@nrc. gov cc: Distribution via ListServ ADAMS Accession No.: ML14220A213 REQUEST FOR ADDITIONAL INFORMATON VOLUNTARY FIRE PROTECTION RISK INITIATIVE DUKE ENERGY PROGRESS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 Radiation Release RAI 02.01 For the outside areas listed in Attachment E where radioactive materials may be stored, please provide the following information:
- a. Identify the type of container used (e.g., sea land type containers) to store the radioactive material.
- b. Describe the administrative controls that limit the amount of activity which may be present in these containers.
- c. Provide a bounding calculation that demonstrates that the radioactive releases from a fire in a container stored in outside areas will not exceed the applicable 10 CFR Part 20 limits. The analysis should include the assumptions, a summary of the methodology and calculations, and resulting doses.
- d. Provide any administrative controls that will be used to control the release of liquids which may become contaminated from fire-fighting activities.
2