ML20041C528
| ML20041C528 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 02/11/1982 |
| From: | Mazur D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, GO1-82-0048, GO1-82-48, NUDOCS 8203020189 | |
| Download: ML20041C528 (3) | |
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 February 11, 1982 G01-82-0048 f
0 Nuclear Regulatory Commission gg I
Region V 1450 Maria Lane, Suite 210 i
"R.R () { #
Walnut Creek, California 94596 14 "f
Attention:
Mr. B. H. Faulkenberry, Chief Reactor Construction, Projects Branch j
Subject:
NUCLEAR PROJECT N05. 1 & 4
.00CKET NOS. 50-460 AND 50-513 REPORTABLE CONDITION 10CFR50.55(e) (P0TENTIAL)
GSB FLOODING
Reference:
- 1) Telecon, M. E. Rodin, Supply System to P. P. Narbut, Region V, Nuclear Regulatory Commission, dated January 11, 1982.
In Reference 1), the Supply System informed your office of a potentially reportable deficiency under 10CFR50.55(e).
Attachment "A" to this letter, provides the Supply System's report on the subject condition. Because the Project has opted not to energize and test the motors / pumps prior to cleanup and restoration, we are unable to accurately determine the safety significance of the flood.
Therefore, we are identifying this situation in a manner commensurate with a reportable 10CFR50.55(e) report.
If for some reason, the facts as we know them change significantly, we will so inform your office; otherwise this will be our final report on the subject condition.
If you have any questions or desire further information, please advise.
If e
D. W.
WNP-1/4 Program Director
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ATTACHMENT A Docket Nos. 50-460 and 50-513 Reportable Condition 10CFR50.55(e) (Potential)
Flooding of the General Services Building Final Report
Background
On January 9,1982, a 6" temporary water line adjacent to the Unit I General Services Building (GSB) ruptured and flooded the 395' elevation.
From the water marks which remained on the building walls, it appears that the water level varied from 1" to approximately 3' in depth depending on location. The flooding problem was discovered by site security personnel at approximately 10:30.p.m.; from which time it took approximate-ly another 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to isolate the temporary line and stop the flow of water.
Description of Potential Deficiency During the flooding, numerous items, i.e., valves, pipe spools, motors, pumps, etc., were completely or partially submerged in water of unknown quality. A major concern at this juncture was the effect of the water chemistry on the submerged items. Water samples were taken from sumps at the 395' elevation and a chemical analyses was performed. However, because the samples were taken from sumps after the flooding had been stopped and the area dewatered, there is some question as to the reliabil-ity of the results. Therefore, a halogen survey (swipe tests) will be conducted upon completion of decontamination of the metal surfaces which were exposed to the flood water.
What effect the water has had on the electrical motors for the motor-opera-ted gate valves and pumps has yet to be determined. All such items have been identified and appropriately tagged with red hold tags. To date no electrical panels have been identified as being affected by the flood waters.
Safety Implications For the nonelectrical items, the concern is whether or not we have a halogen problem which could cause intergranular stress corrosion or other such types of conditions at some future date. However, the most significant concern is the submersion of the following safety-related equipment: Decay Heat Removal pumps and motors, boron recovery pum:s, Decay Heat Removal motor operated valve, Containment Cooling Water pumps and motors, and a Containment Spray pump and motor. Because these items were exposed to an environment other than for what they were originally designed, the quality of the items has been rendered indeterminate.
Due to the possible adverse effect of the water on the electric motors, the Project made a conscious decision not to energize and test any of the motors. The question of whether or not the motors would have performed as designed cannot be answered, therefore, the impact on plant safety is indeterminate.
Corrective Action Planned A walkdown inspection of the flood area was performed by Bechtel QC and contract coordinators to identify damage and/or contamination.
From this inspection, a total of seventeen (17' Bechtel NCRs, documenting multiple items, were written and dispositioned by UE&C Engineering.
The following is a general summary of the dispositions:
1)
Pumas and Valves--Wash and wipe with clean water, water quality to 3e in accordance with Table III, (Class D) reference Spec. 9779-257, Section 52-B, " Cleaning and Cleanliness Requirements for Nuclear Power Plant Components."
- 2) Electric Motors--All r.otors are to be dried out and subjected to a polarity test in accordance with IEEE-43.
- 3) The Decay Heat Removal pump motor will be removed from the pump assembly and returned to Westinghouse Electric for rework.
- 4) The Decay Heat Removal pump will be cleaned and properly restored at the site with the assistance of a Bingham Pump representative.
- 5) The Containment Spray pump will be cleaned and properly restored at the site with the assistance of a Gould Pump representative.
In addition to the above, a random sample of metal surfaces exposed to the flood water will be swipe tested (halogen survey) after decontamina-tion as part of the aforementioned halogen survey.
Current Status j
Not all of the material, i.e., pumps, motors, valves, etc., have been cleaned and reinspected as of the date of this report.
It is anticipated that all actions will be complete by April 1982.
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