ML19289F590
| ML19289F590 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/11/1979 |
| From: | Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| 148-030679, 148-30679, NUDOCS 7906150134 | |
| Download: ML19289F590 (2) | |
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VIRGINI A ELECTRIC AND POWER COMP ANY, RICHMONO. VIRGlHI A 23261 June 11, 1979 Mr. Harold R. Denton, Director Serial No. 148/030679 Office of Nuclear Reactor Regulation PSE&C/LTW:adw:mc Attn: Mr. O. D. Parr, Chief Ligh; Water Reactors Branch No. 3 Docket flos. 50-338 Division of Project Manatament 50-339 U. S. Nuclear Regulatory Conmission License No. NPF-4 Washington, D. C.
20555
Dear Mr. Denton:
The Safety Evaluation Report on the fire protection program for North Anna Power Station, Units 1 and 2, was transmitted by Mr. 0. D. Parr's letter of March 6, 1979. We would appreciate your further investigation of two of the items contained in this Safety Evaluation Report. The two items under question were never required or agreed upon in any discussions on the station fire pro-tection program.
It is our position that.the two requirements are unjustified.
The following paragraphs explain the basis for this position.
Item IV.B.2 states that a sprinkler system will be installed to provide coverage of the component cooling water pumps on elevation 244.5 of the Aux-iliary Building, and to provide coverage of a similar area on the floor level above the pumps, elevation 259.5. Sprinkler coverage on elevation 259.5 is not necessary since that portion of the floor directly above the pumps and ex-tending at least seven-feet beyond the base of each pump and motor is solid concrete. Therefore, a fire on elevation 259.5 would not spread downward to the component cooling water pumps. The power feeds to these punps are routed on elevation.259.5, but the Unit 1 power feeds are separated from the Unit 2 power feeds by a minimum distance of 25 feet. Therefore, a fire would not disable more than two of the four pumps, thus ensuring the ability to bring either or both Units from a hot standby to a cold shutdown condition.
Table 1 states that the present Ib hour fire damper in the wall separat-ing the Control Room from the Turbine Building should be replaced with a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire damper. The referenced ventilation duct is a 12 inch diameter, schedule 40 pipe with two seismically-qualified butterfly valves in series located directly inside the Control Room. These valves are normally closed except during. conditions of emergency air supply to the Control Room. Add-ing a 3 hcur fire damper is not necessary since the existing valves provide the equivalent or better than a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> damper.
2229 047 7906150III b
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Mr. Harold R. Denton, Director 2
Thank you for your review of these two items. Please contact us if there are any questions.
.rjtrulyyours,,
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(,'5enior/Vice President-By n wer tation Engi,neering and Cons ctio Mr.JamesP.O'Reilly, Director.!
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Office of Inspection &-Enforcement Region II 2229 048
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