ML19269C752
| ML19269C752 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 02/07/1979 |
| From: | Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7902120149 | |
| Download: ML19269C752 (1) | |
Text
Vepco February 7,1979 Mr. Jame.< P. O'Reilly Serial No. 025A Office of Inspection & Enforcement PSE&C/RLR:adw:mc U. S. Nuclear Regulatory Connissio#n '
Region II W
Decket No. 50-339 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear fir. O'Reilly:
On January 8,1979, a report was submitted under provisions of 10CFR50.55(e) concerning the High Head Safety Injection Pumps. This was followed by an additional report made on January 12, 1979, under provi-sions of 10CFR21 which further described the inability to obtain the de-sign service water flow rate through the skid-mounted coolers which serve each pump.
Tests have been r.onducted on the skid service water piping. These tests revealed unusually high pressure drops through the skid piping for the flow rates experienced during the tests.
Further examination of the piping disclosed that flow was restricted due to the fouling of several sections of skid piping. This fouled piping was responsible for the un-usually hi;t pressure drops encountered in the tests.
It was apparent that the skid piping had been inadequately cleaned prior to being ploced in service.
The piping and coolers on all the Unit 2 High Head Safety irdection Pump skids will be cleaned and restored to design flow and pressure drop requirements prior to the Unit 2 fuel load date.
This letter is considered to be the final report on this subject under provisions of 10CFR21 and 10CFR50.55(e).
Should you require further information, pl ase contact this office, f) /
Ver rul yours',
j' f Seniorg)C.
C $am rown, Jr.
ice President owe?
Station Engineering a d Construction cc: tir. John G. Davis, Acting Director Office of Inspection & Enforcement dr.HaroldR.Denton, Director Office of Nuclear Reactor Regulation DD 7902126\\M s