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{{#Wiki_filter:i'_ -------. e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR 0PEllATIONS February 9, 1984 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:
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Serial No. 662B NO/ JDH:jab 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 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated June 16, 1983 (Serial No. 330), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes pertained to NUREG-0737, item 1 rr. F .1 except item II. F .1. 2. A supplement to the proposed changes to include NUREG-0737 items II.F.1.2 and ~I.B.3 is enclosed.
                            ------.                                 e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR 0PEllATIONS February 9, 1984 Mr. Harold R. Denton, Director                                 Serial No. 662B Office of Nuclear Reactor Regulation                           NO/ JDH:jab 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:
The proposed change adds a description of the post-accident sampling program to Section 6, Administrative Controls, in fulfillment of the requirements of NUREG-0737, item II.F.1.2, Sampling and Analysis of Plant Effluents and item II. B. 3, Post-Accident Sampling.
AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated June 16, 1983 (Serial No. 330), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes pertained to NUREG-0737, item 1rr. F .1 except item II. F .1. 2. A supplement to the proposed changes to include NUREG-0737 items II.F.1.2 and ~I.B.3 is enclosed.
The proposed specifications are consistent with the guidance provided in NRG Generic Letter 83-37 and fulfill our commitment in our December 9, 1983 (Serial No. 662) letter. Based on a February 6, 1984 discussion with the NRG Surry Project Manager, the proposed item/III.D.3.4, Control Room Habitability, technical specifications which we had also committed to provide will be forwarded separately.
The proposed change adds a description of the post-accident sampling program to Section 6, Administrative Controls, in fulfillment of the requirements of NUREG-0737, item II.F.1.2, Sampling and Analysis of Plant Effluents and item II. B. 3, Post-Accident Sampling.     The proposed specifications are consistent with the guidance provided in NRG Generic Letter 83-37 and fulfill our commitment in our December 9, 1983 (Serial No. 662) letter.             Based on a February 6, 1984 discussion with the NRG Surry Project Manager, the proposed item/III.D.3.4, Control Room Habitability, technical specifications which we had also committed to provide will be forwarded separately.           The proposed Technical Specification change is provided in Attachment 1 with a discussion of the proposed change in Attachment 2.
The proposed Technical Specification change is provided in Attachment 1 with a discussion of the proposed change in Attachment
This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
: 2. This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not pose an unreviewed safety question as defined in 10CFR50.59 nor a significant hazards consideration as defined in 10CFR50.92.  
It has been determined that this request does not pose an unreviewed safety question as defined in 10CFR50.59 nor a significant hazards consideration as defined in 10CFR50.92.
/i8402150020 840209 PDR ADOCK 05000280 p PDR Attachments:
Very truly yours, i8402150020 840209
: 1. Proposed Technical Specification Changes. 2. Discussion of Proposed Change. Very truly yours, Jl,I~ W. L. Stewart 
    /        PDR ADOCK 05000280 p                 PDR                             Jl,I~
--~---~---
W. L. Stewart Attachments:
--------VIRGINIA.
: 1. Proposed Technical Specification Changes.
ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager -Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 e e ATTACHMENT 1}}
: 2. Discussion of Proposed Change.
 
                                                          --~---~---
                                              --------
VIRGINIA. ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton cc:     Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219
 
e             e ATTACHMENT 1}}

Revision as of 02:52, 21 October 2019

Suppl 1 to Application for Amend to Licenses DPR-32 & DPR-37,adding Description of post-accident Sampling Program to Section 6 Re Administrative Controls,In Fullfillment of Requirements of NUREG-0737,Items II.F.1.2 & II.B.3
ML18141A496
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/09/1984
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML18141A497 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-3.D.3.4, TASK-TM 6628, 662B, GL-83-37, NUDOCS 8402150020
Download: ML18141A496 (3)
v • d • e


Text

i'_ -

. e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR 0PEllATIONS February 9, 1984 Mr. Harold R. Denton, Director Serial No. 662B Office of Nuclear Reactor Regulation NO/ JDH:jab 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 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated June 16, 1983 (Serial No. 330), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2. The proposed changes pertained to NUREG-0737, item 1rr. F .1 except item II. F .1. 2. A supplement to the proposed changes to include NUREG-0737 items II.F.1.2 and ~I.B.3 is enclosed.

The proposed change adds a description of the post-accident sampling program to Section 6, Administrative Controls, in fulfillment of the requirements of NUREG-0737, item II.F.1.2, Sampling and Analysis of Plant Effluents and item II. B. 3, Post-Accident Sampling. The proposed specifications are consistent with the guidance provided in NRG Generic Letter 83-37 and fulfill our commitment in our December 9, 1983 (Serial No. 662) letter. Based on a February 6, 1984 discussion with the NRG Surry Project Manager, the proposed item/III.D.3.4, Control Room Habitability, technical specifications which we had also committed to provide will be forwarded separately. The proposed Technical Specification change is provided in Attachment 1 with a discussion of the proposed change in Attachment 2.

This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.

It has been determined that this request does not pose an unreviewed safety question as defined in 10CFR50.59 nor a significant hazards consideration as defined in 10CFR50.92.

Very truly yours, i8402150020 840209

/ PDR ADOCK 05000280 p PDR Jl,I~

W. L. Stewart Attachments:

1. Proposed Technical Specification Changes.
2. Discussion of Proposed Change.

--~---~---

VIRGINIA. ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219

e e ATTACHMENT 1

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