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{{#Wiki_filter:1 | {{#Wiki_filter:1 Osmmonwealth Edison 0,mpany Quad Citics Generating Station 22710 206th Avenue North Girdova, 11.61242-9740 Tcl MFM5 4-22 41 i | ||
ESK-97-023 February 24,1997 | |||
ESK-97-023 | ) | ||
February 24,1997 | |||
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk | U. S. Nuclear Regulatory Commission ATTN: Document Control Desk | ||
{ | { | ||
Washington, DC 20555 | Washington, DC 20555 | ||
==Subject:== | ==Subject:== | ||
Quad Cities Nuclear Power Stations Units 1 and 2 Notification of Changes to Bases of Facility | Quad Cities Nuclear Power Stations Units 1 and 2 Notification of Changes to Bases of Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical Specification, Bases for Section 3/4.8.D Control Room Emergency Ventilation System NRC Docket Nos. 50-254/265 i | ||
Pursuant to 10 CFR 50.59, Comed has changed the Bases of Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical Specifications, Bases for Section 3/4.8.D. | Pursuant to 10 CFR 50.59, Comed has changed the Bases of Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical Specifications, Bases for Section 3/4.8.D. | ||
The following information will be added to clarify the bases for Technical Specification Surveillance 4.8.D.5.c. | The following information will be added to clarify the bases for Technical Specification Surveillance 4.8.D.5.c. | ||
Testing of the Control Room Emergency Ventilation system during the pressurization mode of operation verifies the integrity of the Control Room and the assumed inleakage rates of potentially contaminated air. | Testing of the Control Room Emergency Ventilation system during the pressurization mode of operation verifies the integrity of the Control Room and the assumed inleakage rates of potentially contaminated air. | ||
During the pressurization mode of operation the Control Room Emergency Ventilation system is designed to slightly pressurize the Control Room to a positive pressure greater than or equal to 0.125" w.g. | During the pressurization mode of operation the Control Room Emergency Ventilation system is designed to slightly pressurize the Control Room to a positive pressure greater than or equal to 0.125" w.g. | ||
with respect to potentially contaminated areas. Potentially contaminated areas adjacent to the Control Room include the outside air, Turbine Building, Battery Room, Shift Engineers Office, the west stairwell and the adjacent hallway. Although the Cable Spreading Room is adjacent, it is not a potentially contaminated area because it is part of the Control Room | with respect to potentially contaminated areas. Potentially contaminated areas adjacent to the Control Room include the outside air, Turbine Building, Battery Room, Shift Engineers Office, the west stairwell and the adjacent hallway. Although the Cable Spreading Room is adjacent, it is not a potentially contaminated area because it is part of the Control Room Emergency Zone. The Cable Spreading Room is therefore not considered an adjacent area for the purposes of periodic testing. | ||
Emergency Zone. The Cable Spreading Room is therefore not considered | |||
This change agrees with NUREG 1433, Rev.1 (Improved Standard Technical Specifications for GE BWR/4 plants), which states, "The control room positive pressure with respect to potentially contaminated adjacent areas (the turbine building), is periodically tested to verify proper function of the [MCREC] | This change agrees with NUREG 1433, Rev.1 (Improved Standard Technical Specifications for GE BWR/4 plants), which states, "The control room positive pressure with respect to potentially contaminated adjacent areas (the turbine building), is periodically tested to verify proper function of the [MCREC] | ||
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e | e U. S. NRC ESK-97-024 2 | ||
February 24,1997 In support of the proposed changes to the Technical Specification Bases, Comed has performed an evaluation pursuant to 10 CFR 50.59, and determined that an Unreviewed i | |||
performed an evaluation pursuant to 10 CFR 50.59, and determined that an Unreviewed | Safety Question does not exist. This Bases change has been reviewed in accordance with Quad Cities procedures. The marked up and revised Technical Specification Bases pages are attached. | ||
s If there are any questions regarding this issue, please contact Mr. Charles Peterson, l Quad Cities Regulatory Affairs Manager at (309) 654-2241., extension 3609. | s If there are any questions regarding this issue, please contact Mr. Charles Peterson, l | ||
l Respectfully, E. S. Kra Jr | Quad Cities Regulatory Affairs Manager at (309) 654-2241., extension 3609. | ||
l Respectfully, t, | |||
E. S. Kra Jr. | |||
Site Vice President Quad Cities Station i | Site Vice President Quad Cities Station i | ||
Attachments: | Attachments: | ||
1. | |||
R. M. Pulisifer, Project Manager - NRR Office of Nuclear Facility Safety - IDNS R. J. Singer, MidAmerican Energy Company | Marked-Up Technical Specificat'nn Bases Page o | ||
2. | |||
Revised Technical Specification Bases Page cc: | |||
A. B. Beach, Regional Administrator - RIII C. G. Miller, Senior Resident Inspector - Quad Cities R. M. Pulisifer, Project Manager - NRR Office of Nuclear Facility Safety - IDNS R. J. Singer, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company F. A. Spangenberg, Regulatory Affairs Manager - Dresden DCD - License (Both electronic and hard copy) | |||
M. Wagner, Nuclear Licensing Department j | |||
4 | |||
ATTACHMENT I Marked-Up Technical Specification Bases Page (3 pages attached) | ATTACHMENT I Marked-Up Technical Specification Bases Page (3 pages attached)}} | ||
Latest revision as of 02:17, 12 December 2024
| ML20135D935 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 02/24/1997 |
| From: | Kraft E COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135D938 | List: |
| References | |
| RTR-NUREG-1433 ESK-97-023, ESK-97-23, NUDOCS 9703060125 | |
| Download: ML20135D935 (3) | |
Text
1 Osmmonwealth Edison 0,mpany Quad Citics Generating Station 22710 206th Avenue North Girdova, 11.61242-9740 Tcl MFM5 4-22 41 i
ESK-97-023 February 24,1997
)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk
{
Washington, DC 20555
Subject:
Quad Cities Nuclear Power Stations Units 1 and 2 Notification of Changes to Bases of Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical Specification, Bases for Section 3/4.8.D Control Room Emergency Ventilation System NRC Docket Nos. 50-254/265 i
Pursuant to 10 CFR 50.59, Comed has changed the Bases of Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical Specifications, Bases for Section 3/4.8.D.
The following information will be added to clarify the bases for Technical Specification Surveillance 4.8.D.5.c.
Testing of the Control Room Emergency Ventilation system during the pressurization mode of operation verifies the integrity of the Control Room and the assumed inleakage rates of potentially contaminated air.
During the pressurization mode of operation the Control Room Emergency Ventilation system is designed to slightly pressurize the Control Room to a positive pressure greater than or equal to 0.125" w.g.
with respect to potentially contaminated areas. Potentially contaminated areas adjacent to the Control Room include the outside air, Turbine Building, Battery Room, Shift Engineers Office, the west stairwell and the adjacent hallway. Although the Cable Spreading Room is adjacent, it is not a potentially contaminated area because it is part of the Control Room Emergency Zone. The Cable Spreading Room is therefore not considered an adjacent area for the purposes of periodic testing.
This change agrees with NUREG 1433, Rev.1 (Improved Standard Technical Specifications for GE BWR/4 plants), which states, "The control room positive pressure with respect to potentially contaminated adjacent areas (the turbine building), is periodically tested to verify proper function of the [MCREC]
System."
[
9703060125 970224 PDR ADOCK 05000254 lI p
,Q f
y,asspasian
- ~
A l'nicum Osmpan)
{
J
e U. S. NRC ESK-97-024 2
February 24,1997 In support of the proposed changes to the Technical Specification Bases, Comed has performed an evaluation pursuant to 10 CFR 50.59, and determined that an Unreviewed i
Safety Question does not exist. This Bases change has been reviewed in accordance with Quad Cities procedures. The marked up and revised Technical Specification Bases pages are attached.
s If there are any questions regarding this issue, please contact Mr. Charles Peterson, l
Quad Cities Regulatory Affairs Manager at (309) 654-2241., extension 3609.
l Respectfully, t,
E. S. Kra Jr.
Site Vice President Quad Cities Station i
Attachments:
1.
Marked-Up Technical Specificat'nn Bases Page o
2.
Revised Technical Specification Bases Page cc:
A. B. Beach, Regional Administrator - RIII C. G. Miller, Senior Resident Inspector - Quad Cities R. M. Pulisifer, Project Manager - NRR Office of Nuclear Facility Safety - IDNS R. J. Singer, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company F. A. Spangenberg, Regulatory Affairs Manager - Dresden DCD - License (Both electronic and hard copy)
M. Wagner, Nuclear Licensing Department j
4
ATTACHMENT I Marked-Up Technical Specification Bases Page (3 pages attached)