ML18150A124: Difference between revisions

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{{#Wiki_filter:Idaho Nat/a~/ EnglnHdng Labon,tory Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 . ..-..* .. ,.,' .* March 23, 1987
{{#Wiki_filter:.              .
* fJ)fl. TRANSMITTAL OF TECHNICAL EVALUATION REPORT, 11 TMI ACTION--NUREG-0737 (II.D.1) RELIEF AND SAFETY VALVE TESTING, SURRY UNITS 1 AND 2, 11 DOCKET NOs. 50-280 AND -281, EGG-NTA-7633, March 1987 -EWR-57-87 Ref: INEL Technical Assistance To The Office of Nuclear Reactor Regulation, "Evaluation of OR Licensing.Actions  
                                                                                        ..-..*                          fJ)fl.
-NUREG 0737, II.D.1 11 (FIN A6492)  
Idaho Nat/a~/ EnglnHdng Labon,tory March 23, 1987 Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 TRANSMITTAL OF TECHNICAL EVALUATION REPORT, 11 TMI ACTION--NUREG-0737 (II.D.1) RELIEF AND SAFETY VALVE TESTING, SURRY UNITS 1 AND 2, 11 DOCKET NOs. 50-280 AND -281, EGG-NTA-7633, March 1987 - EWR-57-87 Ref:           INEL Technical Assistance To The Office of Nuclear Reactor Regulation, "Evaluation of OR Licensing.Actions - NUREG 0737, II.D.1 11 (FIN A6492)


==Dear Mr. Carrington:==
==Dear Mr. Carrington:==


In accordance with the above reference, INEL has been providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation for th~ evaluation of plant-specific licensing submittals regarding qualification of safety and relief valves. The enclo~ed report is an evaluation of the Surry Units 1 and 2 (Docket Nos. 50-280 and 50-281) submittal.
In accordance with the above reference, INEL has been providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation for th~ evaluation of plant-specific licensing submittals regarding qualification of safety and relief valves.
This evaluation found that the licensee, Virginia Electric and Power Company, has provided acceptable submittals and responses to requests for additional information, reconfirming that the General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 have been met. CLN,cln  
The enclo~ed report is an evaluation of the Surry Units 1 and 2 (Docket Nos. 50-280 and 50-281) submittal. This evaluation found that the licensee, Virginia Electric and Power Company, has provided acceptable submittals and responses to requests for additional information, reconfirming that the General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 have been met.
Very truly yours,
                                                                              ~ cJJ:. 7ft}s:d, E. Wayne Roberts, Manager NRC Headquarters Support CLN,cln


==Enclosure:==
==Enclosure:==


As Stated cc: G. Bagchi, NRR-PAEB G. L. Jones, DOE-ID A. S. Masciantonio, NRR-PAEB Very truly yours, cJJ:. 7ft}s:d, E. Wayne Roberts, Manager NRC Headquarters Support J. 0. Zane, EG&G Idaho (w/o Encl.) n (;,,~ EGB.G Idaho, Inc. 11428 Roclcvll/e Pike Suite 410 Rockville, MD 20852 (--'--8:__7_0-:6-:::0-=9:-:;;0-:;-l-;;;:0-;:;9:--;;:;87::;0~3~2;;;3;-----
As Stated cc: G.         Bagchi, NRR-PAEB G. L. Jones, DOE-ID A. S. Masciantonio, NRR-PAEB J. 0. Zane, EG&G Idaho (w/o Encl.)
1 PDR ADOCK 05000280 p PD~ ..}}
n EGB.G Idaho, Inc.
(;,,~                                            11428 Roclcvll/e Pike               Suite 410 Rockville, MD 20852
(--'--8:__7_0-:6-:::0-=9:-:;;0-:;-l-;;;:0-;:;9:--;;:;87::;0~3~2;;;3;-----1 PDR         ADOCK 05000280 p                                         PD~..}}

Latest revision as of 23:09, 2 February 2020

Forwards EGG-NTA-7633, Technical Evaluation Rept TMI Action - NUREG-0737 (II.D.1) Relief & Safety Valve Testing, Surry Units 1 & 2. Util Submittals Reconfirm That GDC 14,15 & 30 Met
ML18150A124
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/23/1987
From: Roberts E
EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To: Carrington M
Office of Nuclear Reactor Regulation
Shared Package
ML18150A125 List:
References
CON-FIN-A-6492, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM EWR-57-87, NUDOCS 8706090109
Download: ML18150A124 (1)
v • d • e


Text

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..-..* fJ)fl.

Idaho Nat/a~/ EnglnHdng Labon,tory March 23, 1987 Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 TRANSMITTAL OF TECHNICAL EVALUATION REPORT, 11 TMI ACTION--NUREG-0737 (II.D.1) RELIEF AND SAFETY VALVE TESTING, SURRY UNITS 1 AND 2, 11 DOCKET NOs. 50-280 AND -281, EGG-NTA-7633, March 1987 - EWR-57-87 Ref: INEL Technical Assistance To The Office of Nuclear Reactor Regulation, "Evaluation of OR Licensing.Actions - NUREG 0737, II.D.1 11 (FIN A6492)

Dear Mr. Carrington:

In accordance with the above reference, INEL has been providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation for th~ evaluation of plant-specific licensing submittals regarding qualification of safety and relief valves.

The enclo~ed report is an evaluation of the Surry Units 1 and 2 (Docket Nos. 50-280 and 50-281) submittal. This evaluation found that the licensee, Virginia Electric and Power Company, has provided acceptable submittals and responses to requests for additional information, reconfirming that the General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 have been met.

Very truly yours,

~ cJJ:. 7ft}s:d, E. Wayne Roberts, Manager NRC Headquarters Support CLN,cln

Enclosure:

As Stated cc: G. Bagchi, NRR-PAEB G. L. Jones, DOE-ID A. S. Masciantonio, NRR-PAEB J. 0. Zane, EG&G Idaho (w/o Encl.)

n EGB.G Idaho, Inc.

(;,,~ 11428 Roclcvll/e Pike Suite 410 Rockville, MD 20852

(--'--8:__7_0-:6-:::0-=9:-:;;0-:;-l-;;;:0-;:;9:--;;:;87::;0~3~2;;;3;-----1 PDR ADOCK 05000280 p PD~..

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