ML103140655: Difference between revisions

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=Text=
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{{#Wiki_filter:1 WBN2Public Resource From: Poole, Justin Sent: Thursday, October 21, 2010 4:55 PM To: Garg, Hukam; Singh, Gursharan Cc: WBN2HearingFile Resource
{{#Wiki_filter:WBN2Public Resource From:                       Poole, Justin Sent:                       Thursday, October 21, 2010 4:55 PM To:                         Garg, Hukam; Singh, Gursharan Cc:                         WBN2HearingFile Resource


==Subject:==
==Subject:==
FW: NRC Information Requests See below JustinC.PooleProjectManagerNRR/DORL/LPWBU.S.NuclearRegulatoryCommission(301)4152048email:Justin.Poole@nrc.gov From: Crouch, William D [mailto:wdcrouch@tva.gov]
FW: NRC Information Requests See below Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Crouch, William D [mailto:wdcrouch@tva.gov]
Sent: Thursday, October 21, 2010 4:42 PM To: Poole, Justin Cc: Hilmes, Steven A; Clark, Mark Steven; Knuettel, Edward Terry  
Sent: Thursday, October 21, 2010 4:42 PM To: Poole, Justin Cc: Hilmes, Steven A; Clark, Mark Steven; Knuettel, Edward Terry


==Subject:==
==Subject:==
FW: NRC Information Requests Seebelowresponsetoyourquestionsentyesterdayviaemail.William D. (Bill) Crouch(423)365 2004WBN(256)777 7676Cell FSAR Table 7.5-2 variable 4 provides the design information specific to the Containment High Range Radiation Monitors as excerpted below. The type/category design requirements are provided in FSAR Section 7.5.1.4.3 excerpted below. Since the highest classification is A1, the design criteria for the C3 and E1 variables is not included. These are the same requirements that are included in WB-DC-30-7, Post Accident Monitoring Instrumentation which was submitted on TVA Letter to NRC dated June 18, 2010, WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - INSTRUMENTATION AND CONTROLS STAFF INFORMATION REQUESTS.  
FW: NRC Information Requests See below response to your question sent yesterday via email.
 
William D. (Bill) Crouch (423) 3652004 WBN (256) 7777676 Cell FSAR Table 7.5-2 variable 4 provides the design information specific to the Containment High Range Radiation Monitors as excerpted below. The type/category design requirements are provided in FSAR Section 7.5.1.4.3 excerpted below. Since the highest classification is A1, the design criteria for the C3 and E1 variables is not included. These are the same requirements that are included in WB-DC-30-7, Post Accident Monitoring Instrumentation which was submitted on TVA Letter to NRC dated June 18, 2010, WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - INSTRUMENTATION AND CONTROLS STAFF INFORMATION REQUESTS.
There is no response time requirement for the Containment High Range Radiation Monitors.
There is no response time requirement for the Containment High Range Radiation Monitors.
 
FSAR Table 7.5-2 Deviation 36 is applicable to Variable 4 and is included in this response.
FSAR Table 7.5-2 Deviation 36 is applicable to Variable 4 and is included in this response.  
Additional information is included in the procurement specifications which are scheduled to be provided on the October 29, 2010 letter. These documents are too large to transmit via e-mail.
Variable Variable Name        Type /      Redundant Minimum        Maximum Range Notes Number                        Category    Channels      Range      Range      Units From      To
: 4.          Containment        A1 C3 E1    P1 P2        1          1.0E7      R/hr      Deviation Radiation                      2 Upper                                        #36 2 Lower 7.5.1.4.3 Design Criteria For Category 1 Variables 1


Additional information is included in the procurement specifications which are scheduled to be provided on the October 29, 2010 letter. These documents are too large to transmit via e-mail.
(A) Redundant Class 1E qualified continuous indication of these variables has been provided. Qualification applies from the sensor to the display. The variables have been provided with a minimum of two independent channels (PAM 1 and PAM 2) for monitoring each variable. These two redundant channels allow the operator to deduce actual plant conditions.
Variable Number Variable Name Type /
Category Redundant Channels Minimum Range From Maximum Range To Range Units Notes 4. Containment Radiation A1 C3 E1 P1 P2 2 Upper 2 Lower  1  1.0E7  R/hr  Deviation
#36  7.5.1.4.3 Design Criteria For Category 1 Variables 2 (A) Redundant Class 1E qualified continuous indication of these variables has been provided. Qualification applies from the sensor to the display. The variables have been provided with a minimum of two independent channels (PAM 1 and PAM 2) for monitoring each variable. These two redundant channels allow the operator to deduce actual plant conditions.
Where failure of a channel would present ambiguous or confusing information to the operator, preventing the operator from taking action or misleading the operator, an additional redundant (PAM 3) channel has been provided. The PAM 3 channel has been qualified to the same requirements as the first two channels. Table 7.5-2 lists the redundancy requirements for each Category 1 variable.
Where failure of a channel would present ambiguous or confusing information to the operator, preventing the operator from taking action or misleading the operator, an additional redundant (PAM 3) channel has been provided. The PAM 3 channel has been qualified to the same requirements as the first two channels. Table 7.5-2 lists the redundancy requirements for each Category 1 variable.
DEVIATION 36  
DEVIATION 36 VARIABLE 4 Containment Area Radiation, High Range DEVIATION FROM RG 1.97 GUIDANCE Note 7 of RG 1.97, Revision 2 for the subject variable states, "detectors should respond to gamma photons within any energy range from 60 KeV to 3 MeV with an energy response accuracy of 20% at any specific photon energy from 0.1 MeV to 1 MeV. Overall system accuracy should be within a factor of 2 over the entire range. TVA meets the requirements of RG 1.97, Revision 3 Note 7 for the subject variable, which states, "Detectors should respond to gamma radiation photons within any range from 60 KeV to 3 MeV with a dose rate response accuracy within a factor of 2 over the entire range."
 
VARIABLE 4 Containment Area Radiation, High Range DEVIATION FROM RG 1.97 GUIDANCE  
 
Note 7 of RG 1.97, Revision 2 for the subject variable states, "detectors should respond to gamma photons within any energy range from 60 KeV to 3 MeV with an energy response accuracy of 20% at any specific photon energy from 0.1 MeV to 1 MeV. Overall system accuracy should be within a factor of 2 over the entire range. TVA meets the requirements of RG 1.97, Revision 3 Note 7 for the subject variable, which states, "Detectors should respond to gamma radiation photons within any range from 60 KeV to 3 MeV with a dose rate response accuracy within a factor of 2 over the entire range."  
 
JUSTIFICATION It is acceptable to meet the requirements of RG 1.97, Revision 3.
JUSTIFICATION It is acceptable to meet the requirements of RG 1.97, Revision 3.
From: Poole, Justin [mailto:Justin.Poole@nrc.gov]
From: Poole, Justin [mailto:Justin.Poole@nrc.gov]
Sent: Wednesday, October 20, 2010 4:25 PM To: Crouch, William D Cc: WBN2HearingFile Resource  
Sent: Wednesday, October 20, 2010 4:25 PM To: Crouch, William D Cc: WBN2HearingFile Resource


==Subject:==
==Subject:==
FW: NRC Information Requests Please see below.
FW: NRC Information Requests Please see below.
JustinC.PooleProjectManagerNRR/DORL/LPWBU.S.NuclearRegulatoryCommission(301)4152048email:Justin.Poole@nrc.gov From: Singh, Gursharan Sent: Monday, October 18, 2010 1:00 PM To: Poole, Justin Cc: Garg, Hukam  
Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Singh, Gursharan Sent: Monday, October 18, 2010 1:00 PM To: Poole, Justin Cc: Garg, Hukam


==Subject:==
==Subject:==
RE: NRC Information Requests Justin, 3I do not find design criteria within this document. This document covers all radiation monitors. Have TVA look at the following document to see if it contains criteria for the containment high range area monitors (referenced in the document in your email).
RE: NRC Information Requests
8.3.5 TVA WB-DC-30-7, Post Accident Monitoring Instrumentation
: Justin, 2
 
FSAR Section 7.5.1 contains the general design criteria for all Category 1 radiation monitors. I am looking for a design document that includes containment high range radiation monitor design requirements such as ranges, accuracy, maximum acceptable response time for the system etc.
Gush 


From: Poole, Justin Sent: Friday, October 15, 2010 10:56 AM To: Singh, Gursharan Cc: Garg, Hukam; WBN2HearingFile Resource  
I do not find design criteria within this document. This document covers all radiation monitors. Have TVA look at the following document to see if it contains criteria for the containment high range area monitors (referenced in the document in your email).
8.3.5 TVA WB-DC-30-7, Post Accident Monitoring Instrumentation FSAR Section 7.5.1 contains the general design criteria for all Category 1 radiation monitors. I am looking for a design document that includes containment high range radiation monitor design requirements such as ranges, accuracy, maximum acceptable response time for the system etc.
Gush From: Poole, Justin Sent: Friday, October 15, 2010 10:56 AM To: Singh, Gursharan Cc: Garg, Hukam; WBN2HearingFile Resource


==Subject:==
==Subject:==
FW: NRC Information Requests Gush, Please see below. Please note that if you intend to use any of this information in your safety evaluation, then TVA needs to send this on the docket (this is not official) so let me know. Thanks.  
FW: NRC Information Requests
 
: Gush, Please see below. Please note that if you intend to use any of this information in your safety evaluation, then TVA needs to send this on the docket (this is not official) so let me know. Thanks.
JustinC.PooleProjectManagerNRR/DORL/LPWBU.S.NuclearRegulatoryCommission(301)4152048email:Justin.Poole@nrc.gov From: Knuettel, Edward Terry [mailto:etknuettel@tva.gov]
Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Knuettel, Edward Terry [mailto:etknuettel@tva.gov]
Sent: Friday, October 15, 2010 10:42 AM To: Poole, Justin Cc: Clark, Mark Steven; Hilmes, Steven A; Crouch, William D  
Sent: Friday, October 15, 2010 10:42 AM To: Poole, Justin Cc: Clark, Mark Steven; Hilmes, Steven A; Crouch, William D


==Subject:==
==Subject:==
NRC Information Requests Justin, the attached information was requested by Gursharan Singh. Please contact me or Steve Clark with any questions/comments regarding these responses.  
NRC Information Requests Justin, the attached information was requested by Gursharan Singh. Please contact me or Steve Clark with any questions/comments regarding these responses.
 
Thanks
Thanks  ***************************************************************
***************************************************************
Terry Knuettel WBN Unit 2 Licensing EQB 1B-WBN [Licensing Trailer] 423-365-7750, fax 423-365-3833 From: Clark, Mark Steven Sent: Friday, October 15, 2010 9:48 AM To: Knuettel, Edward Terry Cc: Hilmes, Steven A  
Terry Knuettel WBN Unit 2 Licensing EQB 1B-WBN [Licensing Trailer]
423-365-7750, fax 423-365-3833 From: Clark, Mark Steven Sent: Friday, October 15, 2010 9:48 AM To: Knuettel, Edward Terry Cc: Hilmes, Steven A


==Subject:==
==Subject:==
NRC Information Requests Terry:
NRC Information Requests Terry:
4 Please forward to Justin Poole for Gursharan Singh.
3
: 1. Please send the Radiation Monitoring Design Criteria document.


Response: Design Criteria WB-DC-40-24 Rev. 21 is attached. 2. Why isn't the Loose Part Monitoring System included in FSAR Section 3.10 when it is designed to withstand an OBE?
Please forward to Justin Poole for Gursharan Singh.
: 1. Please send the Radiation Monitoring Design Criteria document.
Response: Design Criteria WB-DC-40-24 Rev. 21 is attached.
: 2. Why isnt the Loose Part Monitoring System included in FSAR Section 3.10 when it is designed to withstand an OBE?
Response: The FSAR Section 3.10 title is SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT. Since the Loose Part Monitoring System is not a Category 1 system, it is not included in the scope of 3.10. FSAR Section 7.6.7 provides the information the seismic design of the system which is consistent with the requirements of TVA Design Criteria, WB-DC-30-31, LOOSE PARTS MONITORING SYSTEM.
Response: The FSAR Section 3.10 title is SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT. Since the Loose Part Monitoring System is not a Category 1 system, it is not included in the scope of 3.10. FSAR Section 7.6.7 provides the information the seismic design of the system which is consistent with the requirements of TVA Design Criteria, WB-DC-30-31, LOOSE PARTS MONITORING SYSTEM.
: 3. Question on Responses to RAI Matrix Items 54 and 55. What is Reference 3?
: 3. Question on Responses to RAI Matrix Items 54 and 55. What is Reference 3?
Response: Reference 3 is TVA Design Criteria WB-DC-40-54, ENVIRONMENTAL QUALIFICATION TO 10CFR50.49, which provides the definition of mild and harsh environments.
: 4. Question on RAI Matrix item 318. Is 1QR or QR correct for document number 04508905-QR?
Response: 04508905-QR is correct. The response will be revised before it is submitted.
Please let me know if you need either of the referenced design criteria documents submitted on the docket.
: Regards, Steve Steve Clark Bechtel Power Corp.
Control Systems Watts Bar 2 Completion Project Phone: 865.632.6547 Fax: 865.632.2524 e-mail: msclark0@tva.gov 4


Response:
Hearing Identifier:   Watts_Bar_2_Operating_LA_Public Email Number:         176 Mail Envelope Properties   (19D990B45D535548840D1118C451C74D6FD3723A31)
Reference 3 is TVA Design Criteria WB-DC-40-54, ENVIRONMENTAL QUALIFICATION TO 10CFR50.49, which provides the definition of mild and harsh environments. 4. Question on RAI Matrix item 318. Is 1QR or QR correct for document number 04508905-QR?
 
Response: 04508905-QR is correct. The response will be revised before it is submitted. 
 
Please let me know if you need either of the referenced design criteria documents submitted on the docket. 
 
Regards,  Steve  Steve Clark Bechtel Power Corp.Control SystemsWatts Bar 2 Completion ProjectPhone: 865.632.6547Fax: 865.632.2524e-mail: msclark0@tva.gov Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 176   Mail Envelope Properties   (19D990B45D535548840D1118C451C74D6FD3723A31)


==Subject:==
==Subject:==
FW: NRC Information Requests Sent Date:   10/21/2010 4:55:03 PM Received Date: 10/21/2010 4:56:21 PM From:   Poole, Justin Created By:   Justin.Poole@nrc.gov Recipients:     "WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>
FW: NRC Information Requests Sent Date:           10/21/2010 4:55:03 PM Received Date:       10/21/2010 4:56:21 PM From:                 Poole, Justin Created By:           Justin.Poole@nrc.gov Recipients:
Tracking Status: None "Garg, Hukam" <Hukam.Garg@nrc.gov>
"WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>
Tracking Status: None "Singh, Gursharan" <Gursharan.Singh@nrc.gov> Tracking Status: None  
Tracking Status: None "Garg, Hukam" <Hukam.Garg@nrc.gov>
 
Tracking Status: None "Singh, Gursharan" <Gursharan.Singh@nrc.gov>
Post Office:   HQCLSTR02.nrc.gov Files     Size     Date & Time MESSAGE   7511     10/21/2010 4:56:21 PM Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:}}
Tracking Status: None Post Office:         HQCLSTR02.nrc.gov Files                         Size                 Date & Time MESSAGE                       7511                 10/21/2010 4:56:21 PM Options Priority:                     Standard Return Notification:         No Reply Requested:             No Sensitivity:                 Normal Expiration Date:
Recipients Received:}}

Revision as of 06:19, 13 November 2019

2010/10/21 Watts Bar 2 OL - FW: NRC Information Requests
ML103140655
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 10/21/2010
From:
Office of Nuclear Reactor Regulation
To:
Division of Operating Reactor Licensing
References
Download: ML103140655 (5)


Text

WBN2Public Resource From: Poole, Justin Sent: Thursday, October 21, 2010 4:55 PM To: Garg, Hukam; Singh, Gursharan Cc: WBN2HearingFile Resource

Subject:

FW: NRC Information Requests See below Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Crouch, William D [1]

Sent: Thursday, October 21, 2010 4:42 PM To: Poole, Justin Cc: Hilmes, Steven A; Clark, Mark Steven; Knuettel, Edward Terry

Subject:

FW: NRC Information Requests See below response to your question sent yesterday via email.

William D. (Bill) Crouch (423) 3652004 WBN (256) 7777676 Cell FSAR Table 7.5-2 variable 4 provides the design information specific to the Containment High Range Radiation Monitors as excerpted below. The type/category design requirements are provided in FSAR Section 7.5.1.4.3 excerpted below. Since the highest classification is A1, the design criteria for the C3 and E1 variables is not included. These are the same requirements that are included in WB-DC-30-7, Post Accident Monitoring Instrumentation which was submitted on TVA Letter to NRC dated June 18, 2010, WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - INSTRUMENTATION AND CONTROLS STAFF INFORMATION REQUESTS.

There is no response time requirement for the Containment High Range Radiation Monitors.

FSAR Table 7.5-2 Deviation 36 is applicable to Variable 4 and is included in this response.

Additional information is included in the procurement specifications which are scheduled to be provided on the October 29, 2010 letter. These documents are too large to transmit via e-mail.

Variable Variable Name Type / Redundant Minimum Maximum Range Notes Number Category Channels Range Range Units From To

4. Containment A1 C3 E1 P1 P2 1 1.0E7 R/hr Deviation Radiation 2 Upper #36 2 Lower 7.5.1.4.3 Design Criteria For Category 1 Variables 1

(A) Redundant Class 1E qualified continuous indication of these variables has been provided. Qualification applies from the sensor to the display. The variables have been provided with a minimum of two independent channels (PAM 1 and PAM 2) for monitoring each variable. These two redundant channels allow the operator to deduce actual plant conditions.

Where failure of a channel would present ambiguous or confusing information to the operator, preventing the operator from taking action or misleading the operator, an additional redundant (PAM 3) channel has been provided. The PAM 3 channel has been qualified to the same requirements as the first two channels. Table 7.5-2 lists the redundancy requirements for each Category 1 variable.

DEVIATION 36 VARIABLE 4 Containment Area Radiation, High Range DEVIATION FROM RG 1.97 GUIDANCE Note 7 of RG 1.97, Revision 2 for the subject variable states, "detectors should respond to gamma photons within any energy range from 60 KeV to 3 MeV with an energy response accuracy of 20% at any specific photon energy from 0.1 MeV to 1 MeV. Overall system accuracy should be within a factor of 2 over the entire range. TVA meets the requirements of RG 1.97, Revision 3 Note 7 for the subject variable, which states, "Detectors should respond to gamma radiation photons within any range from 60 KeV to 3 MeV with a dose rate response accuracy within a factor of 2 over the entire range."

JUSTIFICATION It is acceptable to meet the requirements of RG 1.97, Revision 3.

From: Poole, Justin tin.Poole@nrc.gov

Sent: Wednesday, October 20, 2010 4:25 PM To: Crouch, William D Cc: WBN2HearingFile Resource

Subject:

FW: NRC Information Requests Please see below.

Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Singh, Gursharan Sent: Monday, October 18, 2010 1:00 PM To: Poole, Justin Cc: Garg, Hukam

Subject:

RE: NRC Information Requests

Justin, 2

I do not find design criteria within this document. This document covers all radiation monitors. Have TVA look at the following document to see if it contains criteria for the containment high range area monitors (referenced in the document in your email).

8.3.5 TVA WB-DC-30-7, Post Accident Monitoring Instrumentation FSAR Section 7.5.1 contains the general design criteria for all Category 1 radiation monitors. I am looking for a design document that includes containment high range radiation monitor design requirements such as ranges, accuracy, maximum acceptable response time for the system etc.

Gush From: Poole, Justin Sent: Friday, October 15, 2010 10:56 AM To: Singh, Gursharan Cc: Garg, Hukam; WBN2HearingFile Resource

Subject:

FW: NRC Information Requests

Gush, Please see below. Please note that if you intend to use any of this information in your safety evaluation, then TVA needs to send this on the docket (this is not official) so let me know. Thanks.

Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Knuettel, Edward Terry [2]

Sent: Friday, October 15, 2010 10:42 AM To: Poole, Justin Cc: Clark, Mark Steven; Hilmes, Steven A; Crouch, William D

Subject:

NRC Information Requests Justin, the attached information was requested by Gursharan Singh. Please contact me or Steve Clark with any questions/comments regarding these responses.

Thanks

Terry Knuettel WBN Unit 2 Licensing EQB 1B-WBN [Licensing Trailer]

423-365-7750, fax 423-365-3833 From: Clark, Mark Steven Sent: Friday, October 15, 2010 9:48 AM To: Knuettel, Edward Terry Cc: Hilmes, Steven A

Subject:

NRC Information Requests Terry:

3

Please forward to Justin Poole for Gursharan Singh.

1. Please send the Radiation Monitoring Design Criteria document.

Response: Design Criteria WB-DC-40-24 Rev. 21 is attached.

2. Why isnt the Loose Part Monitoring System included in FSAR Section 3.10 when it is designed to withstand an OBE?

Response: The FSAR Section 3.10 title is SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT. Since the Loose Part Monitoring System is not a Category 1 system, it is not included in the scope of 3.10. FSAR Section 7.6.7 provides the information the seismic design of the system which is consistent with the requirements of TVA Design Criteria, WB-DC-30-31, LOOSE PARTS MONITORING SYSTEM.

3. Question on Responses to RAI Matrix Items 54 and 55. What is Reference 3?

Response: Reference 3 is TVA Design Criteria WB-DC-40-54, ENVIRONMENTAL QUALIFICATION TO 10CFR50.49, which provides the definition of mild and harsh environments.

4. Question on RAI Matrix item 318. Is 1QR or QR correct for document number 04508905-QR?

Response: 04508905-QR is correct. The response will be revised before it is submitted.

Please let me know if you need either of the referenced design criteria documents submitted on the docket.

Regards, Steve Steve Clark Bechtel Power Corp.

Control Systems Watts Bar 2 Completion Project Phone: 865.632.6547 Fax: 865.632.2524 e-mail: msclark0@tva.gov 4

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 176 Mail Envelope Properties (19D990B45D535548840D1118C451C74D6FD3723A31)

Subject:

FW: NRC Information Requests Sent Date: 10/21/2010 4:55:03 PM Received Date: 10/21/2010 4:56:21 PM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:

"WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>

Tracking Status: None "Garg, Hukam" <Hukam.Garg@nrc.gov>

Tracking Status: None "Singh, Gursharan" <Gursharan.Singh@nrc.gov>

Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 7511 10/21/2010 4:56:21 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: