ML20055B887

Revised Final Deficiency Rept Re Flooding of General Svcs Bldg,Initially Reported on 820111.Walkdown Insp Performed by Bechtel.Seventeen NCRs Written & Positioned by Ue&C Engineering

ML20055B887
Person / Time
Site:	Washington Public Power Supply System
Issue date:	06/30/1982
From:	Mazur D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Faulkenberry R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, G1-82-409, GO1-82-0409, GO1-82-409, NUDOCS 8207230468
Download: ML20055B887 (7)

Text

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DN 50-460/513 s/^p/

50. 55 (e) Report

• [, ['yg Washington Public Power Supply System

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P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)37'2-y June 30, 1982 h

9, G01-82-0409 f.

N uclear Regulatory Commission Region V

- 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Attention:

Mr. 'R. H. Faulkenberry, Chief Reactor Construction, Projects Branch

Subject:

NUCLEAR PROJECT NOS. 1 AND 4 DOCKET NOS. 50-460 AND 50-513 REPORTABLE CONDITION 10CFR50.55(e) (POTENTIAL)

GSB FLOODING

Reference:

1)

Telecon, ME Rodin, Supply System PP Narbut, Region V, Nuclear Regulatory Commission, dated January 11, 1982.

2)

G01-82-0048, dated February 11, 1982 In Reference 1), the Supply System informed your office of a potentially reportable deficiency under 10CFR50.55(e). Reference 2) provided you with the Supply System report as Attachment A.

During a subsequent inspection conducted by Mr. Narbut of your office on April 5-9, 1982, a request was made for a revised report to include the following:

1).

an evaluation of affected conduit, 2) an evaluaticn of potentially affected electrical panels, 3) an evaluation of the containment spray pump motor, 4) an evaluation of motors not emmersed but exposed to moisture and a description of operational checks prior to use.

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B207230468 820630 PDR ADOCK 05000460 PDR g

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o R. H. Faulkenberry June 30, 1982 GSB Flooding G01-82-0409 Page 2 Attachment "A" to this letter, provides the amended final report of the General Services Building flooding per your request at the exit interview conducted on April 9, 1982.

If you have any questions or desire further information, please advise.

M D. W. Mazur Acting Program Director cc:

CR Bryant, BPA (399)

JP Laspa, Bechtel (860)

V. Mani, UE&C (897)

A. Toth, NRC V. Stello, Director of Inspection, NRC FDCC/899

r ATTACHMENT A DOCKET N05. 50-460 AND 50-513 REPORTABLE CONDITION 10CFR50.55(e) (P0TENTIAL)

FLOODING OF THE GENERAL SERVICES BUILDING AMENDED 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 approxi-mately 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 P0TENTIAL 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 questions as to the reliability 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.

SAFETY IMPLICATIONS For the nonelectrical items, the concern is whether or not a halogen problem exists which could cause intergranular stress corrosion or other such types of conditions at some future date. However, the most significant concern was the possible submersion of the following safety-related equipment: Decay Heat Removal pumps and motors, Boron Recovery pumps, Decay Heat Removal motor operated valve, Containment i

Cooling Water pumps and motors, and a Containment Spray pump and motor.

Because these items were possibly exposed to an environment other l

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.

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CORRECTIVE ACTION 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 list of those items identified as being affected by the flood waters:

1)

Stainless Steel Valves 1-DHR-V-216, 1-DHR-V-217, 1-MUS-V-450, 1-MUS-V-449, 1-MUS-V-675, 1-MUS-V-676, 1-MUS-V-665, 1-MUS-V-663, 1-MUS-V-664, 1-MUS-V-677, 1-MUS-V-678, 1-DHR-V-11A, 1 -DHR-V-I l 9A, 1 -DHR-V-33A, 1 -FWA-V-12A, 1 -DHR-V-13A.

2)

Encapsullation Vessel and Components 1-CSS-VSL-1A, 1-CSS-VSL-EXP-1A 1-CSS-VSL-Coupling lA, 1-DHR-VSL-1A 1-DHR-VSL-EXP-1A, 1-DHR-VSL-Coupling 1A 3)

Carbon Steel Pipe Spools 1-MSS-411701-2, Zone 10A 1-MSS-411701-3 Zone 10A 4) 2" Carbon Steel Gate Valves 1-NSW-V-482A, 1-FWA-V-60B 5)

Boron Recovery Pumps 1-BRS-PMP-7 Serial Number 7801-01-001 1-BRS-PMP-8 Serial Number 7603-01-004 i

6)

Boron Recovery System Control Panels 1-BRS-PNL-RBEP-1, 1-BRS-PNL-RBEP-2 7)

Containment Cooling Water Pumps and Motors I

l-CCW-PMP-3A Serial Number N762798-1 1-CCW-PMP-4B Serial Number N762798-2 8)

Decay Heat Removal Pump Serial Number 230284

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Decay Heat Removal Pump Motor i

Serial Number 15-77/73F63281 l

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The following is a list of respective dispositions for the above items.

1)

Stainless Valves:

Wash and wipe with clean water, water quality to be in accordance with Table III, (Class D) reference spec. 9779-257, Section 52-B,

" Cleaning and Cleanliness Requirements for Nuclear Power Plants".

2)

Encapsullation Vessel and Components:

Disposition same as item I above.

3)

Carbon Steel Pipe Spools:

Disposition same as Item I above.

4) 2" Carbon Steel Gate Valves:

Disposition same as Item I above.

5)

Boron Recovery Pumps:

Clean the pump, motor and surrounding area as per Cleaning and Cleanliness Requirements for Nuclear Power Plants Components.

Megger test the motor to verify acceptability. Notify B&W site representative to witness the megger testing.

6)

Boron Recovery System Control Panels:

Use-As-Is - The flood waters did not rise high enough to affect any of the components of the panel.

7)

Containment Cooling Water Pumps and Motors:

Pumps and motors were not immersed by flooding conditions. Reinspect pumps and motors to verify that no excessive condensation has occurred and restore normal PM program.

8)

Decay Heat Removal Pump:

Have Bingham representative at site to assist with the cleaning and properly restore the pump to its original condition. Coordinate rework activities with B&W Site representative.

9)

Decay Heat Reraval Pump Motor:

Remove the motor from pump assembly and return to Westinghouse Electric for dry-out and megger check followed by an inspection to determine if other repairs are required to properly restore the equipment. Coordinate all activities with B&W site representa-tive.

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10) 18" Motor Operated Gate Valve 1-DHR-V-1A - Serial Number 2N1161

11) Stainless Steel Pipe Spools 1-DHR-411808-3, 1-CCS-411679-3, 1-DHR-411808-4, 1-CSS-411679-4, 1-CSS-411677-1, 1-CSS-411677-2 1-CSS-411822-4, 1-DHR-411802-5, 1-DHR-411802-10, 1-DHR-411802-1, 1-CSS-411822-1, 1-CSS-411822-2, 1-DHR-411802-4, 1-DHR-411802-3, 1-DHR-411802-14, 1-FWA-411923-6, 1-DHR-411802-6, 1-DHR-411690-7, 1-DHR-411802-12, 1-DHR-411809-5,1-DHR-411690-1, 1-DHR-41169-2

12) Containment Spray Pump Motor CSS-M-1A, CSS-PMP-1A

13) Containment Spray Pump Serial Number - N2428381-1

14) Class I - Conduit Location 21U 4 & 4.5 U - W Location North Pit 21V - 395' 7.2 & 9.2 2CLlVX - 23' 2MWlSX - 40' 2CTIVX - 18' 21dlPX - 40' 2AB/JA -

6' 21J2SX - 41' 2CJ/VA - 18' 3UTlSX - 40' 2CJ2VI, - 14' 2BG5VA - 20' 2SWISA -

6' 2BG4VA - 15' 2BG2VA -

Location 21U 4.5 - 5.5 & W - U 2NilSA - 15' 2CRlVX - 12' 2BG3VA -

2CVlVX - 13' 2BGlVA - 10' 2CulVX - 22' 2AD/JA -

6' 2AK/JB -

5' 2JYlVX - 22' 2CNIVB - 22' 21SlVX -

2CN2VB - 14' 21X 10 & 11 2VAlSB - 10' 4JCISX - 30' Location South Pit 21V - 395' 6.5 & 7.2 4AllVX - 30' 2MMISX - 45' 4CulPX - 30' 21F2SX - 45' 4CVlPX - 30' 21FlPX - 45' 4CU2SX - 30' 3USISX - 40 4CV2SX - 30' 2AVlVA - 25' 4JDISX - 30' 2AV2VA - 10' 4FQlVA - 30' 2AC/JA -

3' 47YlSX - 80' 2JllVX - 25' 4FTIVX - 80' 2MZlSA - 10' 4KZlSA - 80' 2FVlVX - 30' 6' E of U 4FFlVX - 60' 2CC1VA -

3' 3' W & 7.2 1313' Total Footage

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10) 18" Motor Operated Gate Valve:

Rework-clean interior and exterior of valve, check limotorque for excessive moisture damage.

If damage exists beyond corrective action at the site, return to the factory for refurbishment,

11) Stainless Steel Pipe Spools:

Disposition same as Item 1 above.

12) Containment Spray Pump Motor:

Under the direction of Gould representative, remove the motor from pump assembly and return to Westinghouse Electric for dry-out and megger check.

The latter actions are to be followed by an inspection to determine if other repairs are required to restore the motor to satisfactory operating condition. All actions are to be coordinated with the Gould representative.

13) Containment Spray Pump:

Have Gould representative at the site to assist with the cleaning and restoration of the pump to its original condition. Coordinate all activities with Gould representative.

14)

Class I Conduit:

Remove mud or other residue.

Inspect for any deleterious effects which might have resulted from submersion.

In addition to the above, a random sample of metal surfaces exposed to the flood water will be swipe tested after decontamination as part of the aforementioned halogen survey. In addition to the corrective actions taken to restore the affected equipment and material, all temporary and permanent fire lines have been identified on a drawing SKC-036. This drawing has been given to site security as well as all cognizant plant personnel. In addition, all personnel that have responsibility in this area and that are on call during off shift hours, holidays and weekends have been issued radios or paging devices in case they cannot be contacted by telephone in the case of emergency such as this.

The entry point of the water into the General Service Building has been walled off and at a later date a permanent concrete slab will be poured.

I Current Status To date not all of the actions identified above have been carried through to fruition and with the current construction slowdown at WNP-1 it will be some time before the work can be completed.

When a date has been established for completion of the work we will so inform your office.

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