05000366/LER-1981-005-01, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed

/01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed

ML19291D210
Person / Time
Site:	Hatch
Issue date:	02/09/1981
From:	Baxley S GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19291D211	List: 05000366/LER-1981-005, Forwards LER 81-005/01T-0 05000366/LER-1981-005-01, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed
References
LER-81-005-01T, LER-81-5-1T, NUDOCS 8102170455
Download: ML19291D210 (2)

LER-1981-005, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed

Event date:
Report date:
3661981005R01 - NRC Website

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DISTRIBUTION Docket Files HGEB Reading DEC B 1331 Wy d>,

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MEMORANDut! FOR: 1J1111am T. P.ussell, Chief Systematic Evaluation Program Branch 73 Division of Licensing s

FROM:

George Lear, Chief t 'l s

ilydrologic and Geotechnical Engineering Branch Division of Engineering SUDJECT:

ADDITI0f1AL IftFORMATION REOUIRED FOR GE0TECHi!ICAL ENG!flEERIllG REVIE1! (TOPIC II-4F)

Plant name: Millstone Nuclear Power Station, Unit 1 TAC Mumber: 41267 Responsible Branch: SEP0; T. Cheng, LPM In order for us to conplete our review of the licensee's submittal on SEP Topic II-4F, " Settlement of Foundations and Curied Equipment," dated April 28,1981, we need additional information as shown in the attachment.

The geotechnical engineering reviewer is Dr. Owen 0. Thompson.

Origin::I signed by Ccorge Lear George Lear, Chief Hydrologic and Geotechnical Engineering Dranch Division of Engineering cc: w/ enclosure J. I' night G. Lear L. lic11er T. Cheng J. Pearring

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_121.p..ja1 12/.f./81 12/.f, /.a1 om, OFFiClAL RECORD COPY u w e mi-m m tdC FORM 318 OD 80; NROM Cm

Subject: Additional Information Needed (SEP Topic II-4F)

Plant Name: Millstone Nuclear Power Station, Unit 1 TAC Number: 41267 Responsible Branch: SEPB; T. Cheng, LPM Prepared by:

Dr. Owen 0. Thompson, HGEB, DE Topic II-4.F.

Settlement of Foundations and Buried Equipment In order for the staff to be able to concur in the licensee's 'inding that

" total and differential settlements are expected to be negligible", the bases for the licensee's conclusion must be presented in t ie Safety Assessment Report. We expect that the following information will meet this need:

1.

Depths of principal structures below original and final grades i.e.

elevations of structures, and original and final grades.

2.

Approximate size of foundations and their spatial relationships to each other.

3.

Approximate locations and elevations of safety-related pipelines and cenduits.

4.

Field explorations made at the site, such as summary details of the number, depth, spacing and sampling for test borings, and the type and quantity of geophysical explorations.

5.

Summary of types and quantity of laboratory tests performed on soil and rock samples.

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Summary of the properties of foundation soils and rock that were developed from field and laboratory investigations and used for design; including special attention to unusual or potentially detrimental characteristics such as weak zones in bedrock, expansive soils, loose (liquefiable) sands, etc.

7.

Groundwater levels recorded, predicted groundwater level fluctuations and design groundwater level.

8.

Brief discussion of dewatering before, during and after construr. tion.

9.

Identification of problems or unusual conditions encountered during excavating and backfilling, and the basis for concluding that such conditions were properly handled,

10. Details of safety-related backfill, including:

source of backfill material locations where safety-related backfill was used summary of laboratory tests performed on backfill materials to define the material properties description of the backfill material and the backfill soil properties used in design (gradation, shear strength, classification etc).

compaction criteri1specified.

bases for concluding that backfill was properly compacted (e.g. summary of field density test results, test fill results, inspection records,etc).

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ll. Summary of design magnitudes of foundation loads for static and dynamic loading conditions and comparison of these loads with allowable or ultimate bearing resistance of the supporting soils.

12.

Brief description of the methods used to calculate the settlement of structures for static and dynamic loading conditions, including the predicted magnitudes of total and differential settlement.

13.

Brief description of the methods used to calculate the predicted settlemont of safety-related pipelines and conduits; i.e., the basis for concluding that such appurtenances will be safely supported during the Safe Shutdown Earthquake (SSE).

14. Brief description of analyses of liquefaction potential that were made for the site soils and the resultant settlement, or the justification for not performing liquefaction analyses.

15. Magnitudes of movements of foundation soils or structures that have been recorded during construction and operation of the plant.

16.

Conclusion assessing the safety of the plant foundations and ouried structures against excessive settlement and the bases for the conclusion.

In the Safety Assessment Report, reference to docketea information can be used to supplement the Report contents, but the Report, itself, must contain sufficient information to show that the bases for the licensee's conclusions are well-founded.

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