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{{#Wiki_filter:*         ', r VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,. VIRGINIA 23261 R. H. LEasBuRo VxcE PRESIDENT NUCl,EAR 0PERATXONS                     September 23, 1982 Mr. Harold R. Denton, Director                               Serial No. 543 Office of Nuclear Reactor Regulation                       NO/GSS:acm Attn: Mr. Steven A. Varga, Chief                           Docket Nos. 50-280 Operating Reactors Branch No. 1                                 50-281 Division of Licensing                             License Nos. DPR-32 U.S. Nuclear Regulatory Commission                                       DPR-37 Washington, D. C. 20555 Gentlemen:
* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,.
AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes are enclosed.
VIRGINIA 23261 R. H. LEasBuRo VxcE PRESIDENT NUCl,EAR 0PERATXONS September 23, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
The proposed changes to Technical Specification 3.lOA for Surry Unit Nos. 1 and 2 are included as Attachment 1.       The changes are a result of safety analyses which have been performed in support of the handling of spent fuel casks in the Fuel Building area. The proposed changes would eliminate the present restriction on the handling of spent fuel casks in the spent fuel storage pool and would require the Cask Impact Pads to be in place on the floor of the spent fuel pool whenever a spent fuel cask is being handled in the spent fuel pool.
Serial No. 543 NO/GSS:acm Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes are enclosed.
The safety analyses in support of these Technical Specification changes are included in Attachment 2,       "A Summary of Information in Support of the Handling of Spent Fuel Casks in the Surry Power Station Unit Nos. 1 and 2 Fuel Building."
The proposed changes to Technical Specification 3.lOA for Surry Unit Nos. 1 and 2 are included as Attachment
This document summarizes the safety analyses associated with a postulated cask drop to assure that the consequences are within acceptable limits. This is in accordance with Alternative 3 provided in NUREG-0612 (Section 5.1.2). As a result of these analyses it was found that Cask Impact Pads will be necessary in order to assure that the consequences of a postulated cask drop are within acceptable limits.
: 1. The changes are a result of safety analyses which have been performed in support of the handling of spent fuel casks in the Fuel Building area. The proposed changes would eliminate the present restriction on the handling of spent fuel casks in the spent fuel storage pool and would require the Cask Impact Pads to be in place on the floor of the spent fuel pool whenever a spent fuel cask is being handled in the spent fuel pool. The safety analyses in support of these Technical Specification changes are included in Attachment 2, "A Summary of Information in Support of the Handling of Spent Fuel Casks in the Surry Power Station Unit Nos. 1 and 2 Fuel Building." This document summarizes the safety analyses associated with a postulated cask drop to assure that the consequences are within acceptable limits. This is in accordance with Alternative 3 provided in NUREG-0612 (Section 5.1.2). As a result of these analyses it was found that Cask Impact Pads will be necessary in order to assure that the consequences of a postulated cask drop are within acceptable limits. This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not involve an unreviewed safety question.
This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not involve an unreviewed safety question.
8209270352 820923 PDR ADDCK 05000280 P PDR
8209270352 820923 PDR ADDCK 05000280 P                     PDR
" .,. ', r e
 
* VrnoINIA ELECTRIC AND PowER CoMPANY To Harold R. Denton Vepco is participating in a demonstration program with the Department of Energy on fuel performance at extended fuel burnup. As part of this program, a removable rod demonstration fuel assembly has been irradiated to extended ~urnup at the Surry Power Station. We have scheduled to ship irradiated fuel rods from this assembly from Surry to be examined under the DOE program in December, 1982. Therefore, we request that this proposed Technical Specification change for Surry be approved by November 15, 1982 to allow shipment of these rods from Surry to the DOE testing facilities.
        ', r e
We have evaluated this request in accordance with the criteria in 10 CFR 170. 22. It has been determined that a Class III and a Class I license amendment fee is required for Unit 1 and Unit 2, respectively.
VrnoINIA ELECTRIC AND PowER CoMPANY To Harold R. Denton Vepco is participating in a demonstration program with the Department of Energy on fuel performance at extended fuel burnup. As part of this program, a removable rod demonstration fuel assembly has been irradiated to extended
Accordingly, a voucher check in the amount of $4,400 is enclosed in payment. Very truly yours, Attachments
          ~urnup at the Surry Power Station. We have scheduled to ship irradiated fuel rods from this assembly from Surry to be examined under the DOE program in December,     1982.     Therefore, we   request that this proposed Technical Specification change for Surry be approved by November 15, 1982 to allow shipment of these rods from Surry to the DOE testing facilities.
: 1. Proposed Technical Specification Changes 2. Safety Analyses Summary 3. Voucher Check No. 81060 for $4,400' cc: Mr. James P. O'Reilly Regional Administrator Region II
We have   evaluated this request in accordance with the criteria in 10 CFR 170. 22. It has been determined that a Class III and a Class I license amendment fee is required for Unit 1 and Unit 2, respectively. Accordingly, a voucher check in the amount of $4,400 is enclosed in payment.
... ' ( l I
Very truly yours, Attachments
* COMMONWEALTH OF VIRGINIA) ) CITY OF RICHMOND ) *
: 1. Proposed Technical Specification Changes
* The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart, who is Manager-Nuclear Operations and Maintenance, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. ..,.J.. Acknowledged before me this 3 day of ~~*I'"", My Commission expires: -.;t. " , 19 a ---------Notary Public (SEAL) M004}}
: 2. Safety Analyses Summary
: 3. Voucher Check No. 81060 for $4,400' cc:   Mr. James P. O'Reilly Regional Administrator Region II
 
... ' (
l I COMMONWEALTH OF VIRGINIA)
                                )
CITY OF RICHMOND         )
The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart, who is Manager-Nuclear Operations and Maintenance, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
                                            ..,.J..
Acknowledged before me this ~ 3       day of   ~~*I'"",
My Commission expires:       ~ - .;t. "
                                    ---------             , 19  a~
Notary Public (SEAL)
M004}}

Latest revision as of 00:55, 3 February 2020

Application to Amend Licenses DPR-32 & DPR-37,eliminating Restriction on Handling of Spent Fuel Casks in Spent Fuel Storage & Requiring Cask Impact Pads to Be Placed on Floor of Spent Fuel Pool Whenever Cask Is Handled
ML18139C038
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/23/1982
From: Leasburg R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML18139C039 List:
References
543, NUDOCS 8209270352
Download: ML18139C038 (3)


Text

  • ', r VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,. VIRGINIA 23261 R. H. LEasBuRo VxcE PRESIDENT NUCl,EAR 0PERATXONS September 23, 1982 Mr. Harold R. Denton, Director Serial No. 543 Office of Nuclear Reactor Regulation NO/GSS:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U.S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes are enclosed.

The proposed changes to Technical Specification 3.lOA for Surry Unit Nos. 1 and 2 are included as Attachment 1. The changes are a result of safety analyses which have been performed in support of the handling of spent fuel casks in the Fuel Building area. The proposed changes would eliminate the present restriction on the handling of spent fuel casks in the spent fuel storage pool and would require the Cask Impact Pads to be in place on the floor of the spent fuel pool whenever a spent fuel cask is being handled in the spent fuel pool.

The safety analyses in support of these Technical Specification changes are included in Attachment 2, "A Summary of Information in Support of the Handling of Spent Fuel Casks in the Surry Power Station Unit Nos. 1 and 2 Fuel Building."

This document summarizes the safety analyses associated with a postulated cask drop to assure that the consequences are within acceptable limits. This is in accordance with Alternative 3 provided in NUREG-0612 (Section 5.1.2). As a result of these analyses it was found that Cask Impact Pads will be necessary in order to assure that the consequences of a postulated cask drop are within acceptable limits.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not involve an unreviewed safety question.

8209270352 820923 PDR ADDCK 05000280 P PDR

', r e

VrnoINIA ELECTRIC AND PowER CoMPANY To Harold R. Denton Vepco is participating in a demonstration program with the Department of Energy on fuel performance at extended fuel burnup. As part of this program, a removable rod demonstration fuel assembly has been irradiated to extended

~urnup at the Surry Power Station. We have scheduled to ship irradiated fuel rods from this assembly from Surry to be examined under the DOE program in December, 1982. Therefore, we request that this proposed Technical Specification change for Surry be approved by November 15, 1982 to allow shipment of these rods from Surry to the DOE testing facilities.

We have evaluated this request in accordance with the criteria in 10 CFR 170. 22. It has been determined that a Class III and a Class I license amendment fee is required for Unit 1 and Unit 2, respectively. Accordingly, a voucher check in the amount of $4,400 is enclosed in payment.

Very truly yours, Attachments

1. Proposed Technical Specification Changes
2. Safety Analyses Summary
3. Voucher Check No. 81060 for $4,400' cc: Mr. James P. O'Reilly Regional Administrator Region II

... ' (

l I COMMONWEALTH OF VIRGINIA)

)

CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart, who is Manager-Nuclear Operations and Maintenance, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

..,.J..

Acknowledged before me this ~ 3 day of ~~*I'"",

My Commission expires: ~ - .;t. "


, 19 a~

Notary Public (SEAL)

M004