ML19257A200

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Submits Followup to RO-79-15.All Analyses & Evaluations Completed.Summary of Corrective Actions on Pipe Supports & Restraints Provided.Power Operation Will Not Resume Until Further ASLB Order
ML19257A200
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/27/1979
From: Broehl D
PORTLAND GENERAL ELECTRIC CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19257A201 List:
References
TAC-12369, NUDOCS 8001020454
Download: ML19257A200 (2)


Text

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_ PortlandGeneralBectricCoritxuly i

'C DonaldJ.Broehl Assistant Vce Pescert e

December 27, 1979 i

Mr. R. H. Engelken, Director i

U. S. Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California Blvd.

Walnut Creek, CA 94596 Dest Sir:

As a follow-up to information provided in LER 79-15, and Supplements 1 ar.d 2 thareto, this is to confirm that all analyses and evaluations have been completed and that the final summary of corrective actions on pipe supports and restraints is provided below:

Corrective Actions on Single Wythe and Mortared Double Wythe Walls System Throughbolt Modify Total Safety Injection 13 19 32 Residual Heat Removal 5

21 26 Containment Spray 2

6 8

Chemical & Volume Control 8

5 13 Boron Injection 1

5 6

Spent Fuel Pool Cooling 2

7 9

Component Cooling Water 2

3 5

Containment Chilled Water 0

1 1

Steam Generator Blowdown 0

1 1

Service Water 5

12 17 Diesel Fuel Oil 1

6 7

Auxiliary Feed Pump Diesel Jacket Water 0

2 2

Total 39 88 127 1663 143oo2 ~ 3 121 S W Samon S:reet. Portat. Oregon 972M ll 4su 8001020 v-g

Mr. R. H. Engelken December 27, 1979 Page 2 Corrective Action on Structural Steel, Concrete Slabs and Composite Walls A modification associated with one seismic support attached to a structural steel member was performed as a result of our reviews described in LER 79-15. This support is on the Safety Injection System at Elevation 23 ft of the Auxiliary Building. The modification consisted of supporting the top and bottom flange of a steel beam. I-One support attached to a concrete floor slab has been modified. This restraint, on the Component Cooling Water System, is located at Elevation 45 ft in the Auxiliary Building and carries primarily thermal loads. The modifiestion consisted of adding a column and horizontal restraint to the pipe. Eight supports for the hydrogen vent system, which were attached to a composite wall located adjacent to Containment near the Control and Turbine Buildings, have been removed from the wall and connected to a structural steel frame. All of the modifications summarized were completed on December 21, 1979. In accordance with your letter of December 20, 1979, power operation will not commence before our reevaluations have been resolved to the satisfac-tion of the NRC Staff. In addition, power operation will not resume pending further order of the Atomic Safety and Licensing Board assigned to the Control Building Proceeding. Sincerely, { /Mr.A.Schwencer, Chief c: Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy Coatrol Building Service List !I _____. _____-.}}