ML19209B730: Difference between revisions

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=Text=
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{{#Wiki_filter:Vepco_ _ . . . . _ _ . _ _ . _ . _ _ . _ _ _
{{#Wiki_filter:Vepco                              _ _ . . . . _ _ . _ _ . _ . _ _ . _ _ _
.October 4,1979
                                            .
, Mr. James P. O'Reilly. Director Serial No. 657A Office of Inspection & Enforcement PSELC/CES:mac: wang U.S. Nuclear Regulatory Commission Region II Docket Nos. 50-404 101 Marietta Street 50-405-Suite 3100 Atlanta, Georgia 30303 Control No. F20097H1
                                      ,
October 4,1979 Mr. James P. O'Reilly. Director                               Serial No. 657A Office of Inspection & Enforcement                           PSELC/CES:mac: wang U.S. Nuclear Regulatory Commission Region II                                                     Docket Nos. 50-404
- 101 Marietta Street                                                       50-405 Suite 3100 Atlanta, Georgia 30303                                       Control No. F20097H1


==Dear Sir:==
==Dear Sir:==
The purpose of this letter is to clarify a particular point of information provided in our letter to the Nuclear Regulatory Consnission (NRC), Serial No.
The purpose of this letter is to clarify a particular point of information provided in our letter to the Nuclear Regulatory Consnission (NRC), Serial No.
657, dated August ?l, 1979 regarding maximum predicted groundwater elevations for safety-related structures for North Anna Power Station Units 3 and 4 The table, included in the body of the letter, indicated that the presently predicted maximum groundwater level at the Units 3 and 4 service water pump house (SWPH) is elevation 315.
657, dated August ?l, 1979 regarding maximum predicted groundwater elevations for safety-related structures for North Anna Power Station Units 3 and 4 The table, included in the body of the letter, indicated that the presently predicted maximum groundwater level at the Units 3 and 4 service water pump house (SWPH) is elevation 315. Inclusion of tMs figure for the SWPH in the table m'ay be somewhat misleading. Elevatica 315 corresponds to the maximum normal reservoir level and is used in the conservative design of the structure. It should be pointed out that the groundwater level in the area of the SWPH is significantly lower than the reservoir level due to the effectiveness of the liner along the reservoir sides and bottom. No predictions have been made as to the maxi wm ant-icioated groundwater level in the area of the SWPH since the maximum normal elevation of the reservoir (elevation 315) will control the structural design.
Inclusion of tMs figure for the SWPH in the table m'ay be somewhat misleading. Elevatica 315 corresponds to the maximum normal reservoir level and is used in the conservative design of the structure.
                                    , Wy-   uly ypur ,
It should be pointed out that the groundwater level in the area of the SWPH is significantly lower than the reservoir level due to the effectiveness of the liner along the reservoir sides and bottom. No predictions have been made as to the maxi wm ant-icioated groundwater level in the area of the SWPH since the maximum normal elevation of the reservoir (elevation 315) will control the structural design., Wy-uly ypur ,//f a ? Nc c//" S m C. Brown, Jr.
                                          //f     a ? Nc c//
9 SeniorVicePresident.9 Power Station Engineering
                                    " S m C. Brown, Jr. 9 SeniorVicePresident.9 Power Station Engineering
' and Construction ec: Mr. Victor Stello, Director Office of Insoection and Enforcement vMr. Harold R. Denton, Director Office of Nuclear Reactor Regulation
                                    ' and Construction ec: Mr. Victor Stello, Director Office of Insoection and Enforcement vMr. Harold R. Denton, Director Office of Nuclear Reactor Regulation
%101@O 5'o-n 79101 00 B}}
                                                                            %   101
                                                                              @O5'no -
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Revision as of 14:42, 19 October 2019

Clarifies Info in Util 790821 Ltr Re Max Predicted Groundwater Elevations for safety-related Structures. Elevation 315 Corresponds to Max Reservoir Level & Is Used in Conservative Structure Design
ML19209B730
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 10/04/1979
From: Brown S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7910100364
Download: ML19209B730 (1)
v • d • e


Text

Vepco _ _ . . . . _ _ . _ _ . _ . _ _ . _ _ _

.

,

October 4,1979 Mr. James P. O'Reilly. Director Serial No. 657A Office of Inspection & Enforcement PSELC/CES:mac: wang U.S. Nuclear Regulatory Commission Region II Docket Nos. 50-404

- 101 Marietta Street 50-405 Suite 3100 Atlanta, Georgia 30303 Control No. F20097H1

Dear Sir:

The purpose of this letter is to clarify a particular point of information provided in our letter to the Nuclear Regulatory Consnission (NRC), Serial No.

657, dated August ?l, 1979 regarding maximum predicted groundwater elevations for safety-related structures for North Anna Power Station Units 3 and 4 The table, included in the body of the letter, indicated that the presently predicted maximum groundwater level at the Units 3 and 4 service water pump house (SWPH) is elevation 315. Inclusion of tMs figure for the SWPH in the table m'ay be somewhat misleading. Elevatica 315 corresponds to the maximum normal reservoir level and is used in the conservative design of the structure. It should be pointed out that the groundwater level in the area of the SWPH is significantly lower than the reservoir level due to the effectiveness of the liner along the reservoir sides and bottom. No predictions have been made as to the maxi wm ant-icioated groundwater level in the area of the SWPH since the maximum normal elevation of the reservoir (elevation 315) will control the structural design.

, Wy- uly ypur ,

//f a ? Nc c//

" S m C. Brown, Jr. 9 SeniorVicePresident.9 Power Station Engineering

' and Construction ec: Mr. Victor Stello, Director Office of Insoection and Enforcement vMr. Harold R. Denton, Director Office of Nuclear Reactor Regulation

% 101

@O5'no -

79101 00 B

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