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UNITED STATESpm arouNUCLEAR REGULATORY COMMISSION# o,,*

REGION 11o*

5 $ 101 M ARIETTA STREET, N.W.* 8 ATLANTA, GEORGIA 30303o,

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Report Nos. : 50-327/79-12 and 50-328/79-07

Licensee: Tennessee Valley Authority500 A Chestnut Street, Tower IIChattanooga, Tennessee 37401

Facility Name: Sequoyah Nuclear Plant, Units 1 and 2

Docket Nos. : 50-327 and 50-328

License Nos. : CPPR-72 and CPPR-73

Inspection at Sequoyah Site near Daisy, Tennessee

[I [ D'79Inspector:C. R.41 a land Date Signed

3 V3'7'[Approved by:A. R. Herdt, Section Chief, RC&ES Branch Date Signed

SUMMARY

Inspection on February 5-7, 1979

Areas Inspected

This routine, unannounced inspection involved 21 inspector-hours onsite inthe areas of noncompliances, unresolved items, 10 CFR 50.55(e) items andinspector follow-up items.

Results:

No apparent items of noncompliance or deviations were identified

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DETAILS

1. Persons Contacted

Licensee Employees

*G. G. Stack, Project Manager, Sequoyah Nuclear Project (SNP)*S. Duhan, Office of Engineering Design and Construction (OEDC),

QA Staff*R. W. Farrell, Supervisor, Quality Engineering Records Unit*E. C. Pendergrass, Engineer, QC Re:ords Unit (QCRU)*D. L. Wall, Nuclear Licensing, Division of Engineering Design

(EN DES) QA*D. D. McCloud, QA Engineer, Power Production QA*M. A. McBurnett, Nuclear Engineer, Regulatory Staff*R. B. Bruce, QA Engineer, Construction QA UnitW. M. Morgan, QA Engineer, Construction QA UnitJ. W. Hughes, General Foreman, ConstructionL. D. Clift, Jr., Mechanical EngineerJ. T. Lewis, Mechanical Engineer

* Attended exit interview.

2. Exit Interview

The inspection scope and findings were summarized on February 7, 1979,with those persons indicated in Paragraph I above. The scope of theinspection and the findings concerning the areas of noncompliance,unresolved items, 50.55 (e) items and inspector follow up items werereviewed. The inspector stressed the need for more evidence of TVAcorporate interest in closing the construction deficiencies reportedunder 10 CFR 50.55 (e). A review of the documentation available tobackup the final report by a corporate QA group such as the constructionQA group (for construction items) is a standard operating procedure atplants where the utility is not the same corporation as the architectengineer and constructor. The licensee's status reporting of NRCinspection findings will be rerevised to emphasize the interests ofTVA as well as the interests of the NRC. This will be inspected asfollowup item 327/79-12-13 and 328/79-7-13.

3. Licensee Action on Previous Inspection Findings

a. (Closed) Items of Noncompliance, Infraction 50-328/79-18-02,Piping Supports. The inspector reviewed the TVA October 25, 1978and November 14, 1978 response letters to Region II and thecorrective action steps taken by TVA to correct the problem and

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to avoid further noncompliance. The inspector reviewed SequoyahNuclear Project (SNP) Inspection Instruction (II) No. 38 "Inspec-tion of Site Fabricated Assemblies" Revision (Rev) 6 effectiveNovember 30, 1978; SNP II No. A-3, " Inspection and Cycling ofShock Suppressors" Rev. 3 effective November 26, 1978; SNP II No.50 " Equipment Lubrication Inspection", Rev. I effective December 8,1978; SNP II No. 29 " Inspection of Variable Springs" Rev.1,effective November 30, 1978. The inspector observed representativepipe supports and snubbers in Unit 2 and the work related toremoving the vibrotool marked numbers from support No. 2-RHRH-463.

b. (0 pen) Item of Noncompliance, Deficiency 327/78-27-01 and 328/78-21-01 Corporate Audits. The inspector reviewed the TVA November 30,1978 and December 19, 1978 response letters to Region II. TheOEDC QA audit of the Division of Construction, including theSNP-organization structure, responsibilities, functions, interfacesand overall QA program is currently scheduled to be conductedbetween March 26 and April 6,1979.

c. (Closed) Unresolved Item 328/78-10-01 and 328/78-07-01, SoilCompaction Documentation. The inspector and the Region II staffhas reviewed the SNP II No. 94 " Inspection of Backfill MaterialsPlacement" Revision 1, which has been revised to address documen-tation of soil compaction by the Nuclear Density Method.

4. Unresolved Items

Unresolved items were not identified during this inspection.

5. Licensee Identified Items

TVA has reported a number of items to Region II as reportable items incompliance with 10 CFR 50.55(e) and the inspector reviewed the itemsbelow and the supporting documentation, and discussed the items withresponsible staff during the inspection.

a. (CLOSED) Item 327/78-09-03 and 328/78-06-05. Deficient concreteCells in the ERCW Pumping Station Access Roadway. The Region IIstaff has reviewed the TVA revised final report to Region II assubmitted enclosed to their letter dated November 29, 1978, theinterim reports referenced therein, and the final report submittedAugust 1, 1978, SCR 37. Certain concrete cells were removed, thetremie concrete placement procedures were revised to ensureproper foundation cleanup and to bring the tremic concrete placementprocedure in accordance with ACI 304, " Recommended Placement ofTremie Concrete," An elaborate foundation inspection program wasutilized. Cores were taken and analyzed, and the results aresummarized in the revised final report. The SNP FSAR is being

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revised to incorporate the description of the ERCW pumping station,access roadway and cccess dike. Field observations by Region IIinspectors were previously reported in IE Ppts. 50-327/78-34 and50-328/78-25.

b. (CLOSED) Item 327/78-01-14, Shield Building Interior ConcreteSurface Strength. The Region II staff has reviewed the TVA finalreport to Region II submitted July 21, 1978, and the additionalinformation requested by Region II at an exit meeting October 13,1978 and submitted by the TVA letter dated January 31, 1979. NCR72 D. Core samples taken from the Unit I and Unit 2 shieldbuilding walls at SNP and have been tested at the TVA SingletonMaterials Engineering Laboratory (SML) and the U.S. Army Corps ofEngineers, Waterways Experiment Station (WES). The TVA evaluationdetermined that the expansion anchors in Unit I were fully adequatefor design requirements; however, replacement anchors in Unit 2will have a deeper seating anchor.

c. (CLOSED) Item 327/78-14-04, and 328/78-10-03 High Pressure FireProtection System Submersible Pumps. The inspector reviewed theTVA responses to Region II dated September 14, 1978, November 29,1978 and December 28, 1978, relative to the subject identified asNCR 962. Pressure signature tests of the pump indicated that theapparent reason for the separation of the impeller from the shaftwas due the method of attaching the impeller to the pump shaf t.The pumps are being modified to reattach the impeller by thethrust ring construction method rather than a lock collet method.The inspector reviewed documentation of the corrective action anddocumentation of the TVA review of all the vertical turbine type

pumps in Sequoyah and Watts Bar. There are no other pumps withlock collet construction at either plant.

d. (CLOSED) Item 327/78-38-03 and 328/78-27-03, Grounding of Tempera-ture Controller Power Supply Chassis. The inspector reviewed theTVA responses to Region II dated August 17, 1978 and November 24,1978, NCR 1065. The inspector reviewed the cogineering documenta-tion (EN DES memo dated August 4,1978) and the QC inspectionreport dated September 20, 1978 confirming the completed correctiveaction of installing suitable insulation to prevent electricalshorts.

e. (CLOSED) Item 327/78-38-05 and 328/78-27-05, Plant ConfigurationDrawings. The inspector reviewed the TVA responses to Region IIdated October 16, 1978 and January 4, 1979, NCR-2P, 3P. The

inspector reviewed: (1) TVA training records (for three grouos)relating to Standard Operating Procedure (SOP) No. 308 "Configura-tion Control" Revision 1 dated December 29, 1978; (2) reviewedS0P No. 308 relative to the " drawings of record" for the actual

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configuation, and for the transferring of a system of drawings ofrecord that represent the "as constructed" plant configuration;(3) Construction Procedure (CP) No. P-10 " Control of QualityAssurance Documents" Revision 17 dated December 29, 1978; and (4)the closed NCR-2P and 3-P verified by engineering and inspection.CP No. P-10 has been revised to document the method used tocontrol drawings relative to design drawings and plant configura-tion changes at the time of the tranfer of responsibility fromConstruction to Power Production

f. (OPEN) Item 327/79-12-01 and 328/79-07-01, Upper Head Injection(UHI) Rate. Region II has received the TVA final report datedDecember 28, 1978, NCR MEB 78-4. Redesign and test work is beingconducted to correct deficiencies in the preoperational testingof the UHI system of Unit 1. This item was not inspected.

g. (OPEN) Item 327/79-12-02 and 328/79-07-02, Signal Cable UsedWithout Proper Environmental Qualification Tata. Region II hasreceived the TVA final report dated January 4, 1979 and therevised final report dated January 23, 1979, NCR EEB 78-4.Fully qualified cable will be used to replace the deficientsignal cable. This item was not inspected.

h. (OPEN) Item 327/79-12-03 and 328/79-07-03, Omitted LateralRestraints in the Chemical Volume Control System (CVCA Piping.Region II has received the TVA final report dated January 12,1979, NCR CEB 78-2. A lateral restraint, which is needed duringa seismic event, was discovered to have been omitted due to aninadvertent omission from the load tables. One lateral restraintwas omitted on each unit. This item was not inspected.

i. (OPEN) Item 327/79-12-04 and 328/79-07-04, Heating, Ventilatingand Air-Conditioning (HVAC) Penetrations in Containment Design.Region II has received TVA's first interim report dated January 121979, NCR CEB 78-3. Deficiencies in the load definition in thedesign specification have been identified. Proper loads havebeen supplied to the contractor / designer. Reanalysis has been

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initiated. This item was not inspected.

j. (OPEN) Item 327/79-12-05 and 328/79-05, Additional Fire Dampersand Fire Doors in Control Building and Auxiliary Building. Region IIhas received TVA's first interim report dated January 17, 1979,NCR SWP-78-S-2. Eight additional fire dampers in the HVAC ductworkand eight additional fire doors in the Control and AuxiliaryBuildings will be provided to more clearly define the compartmen-tation boundaries. This item was not inspected.

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k. (OPEN) Item 3/7/79-12-06 and 328/79-07-06, Seismic Qualificationof Heating and Ventilating (H&V) System Ductwork. Region II hasreceived the TVA final report dated January 29, 1979, NCR SWP-78-S-3.Additional hangers will be installed in the auxiliary building toprovide seismic catagory I integrity. This item was not inspected.

1. (OPEN) Item 327/79-12-07 and 328/79-07-07. Metal Shavings in

Valve Operators. Region II has received TVA's first interimreport dated February 1, 1979, NCR 1354. Metal shavings werefound in certain hydraulic operators of the discharge pressurecontrol valves of the motor driven auxiliary feedwater pumps.

This item was not inspected.

m. (OPEN) Item 327/79-12-08 and 328/79-07-08, Piping Embedded inStructural Concrete. Region II has received the TVA first interimreport dated February 8, 1979, NCR CEB 79-1. Differences in thecode requirements of the ASME and the Americat Concrete Instituteare to be analyzed and evaluated. This item was not inspected.

n. (OPEN) Item 327/79-12-09 and 328/79-07-09, Main Feedwater LineWater Hammer. TVA informed Region II of a potential 10 CFR50.55(e) item (NCR MEB 79-01) relative to the subject on January 15,1979. In response to a Westinghouse report on water hammercomputer analysis of the potential problem have been initiated.This item was not inspected.

o. (OPEN) Item 327/79-12-10, High Flow Alarm in the ERCW CoolingWater Piping. TVA informed Region II of a potential 10 CFR50.55(e) item (NCR MEB 79-4) relative to the subject on January 29,1979. A high flow alarm may be needed in the ERCW piping toalert the operator to close certain isolation valves following abreak in certain class H ERCW piping in certain modes of operation.This item was not inspected.

p. (OPEN) Item 327/79-12-11 and 3?8/79-07-11, Relay TachometerFailures on Diesel Generators. TVA informed Region II of apotential 10 CFR 50.55(e) item (NCR SP) relative to the subjecton January 30, 1979. Dynalco type RT 2429 relay tachometers havefailed to date. This item was not inspected.

q. (OPEN) Item 328/79-07-12, Deficient Concrete in Unit 2 CraneWall. Region II has received the final report dated January 4,1979, NCR 1079, and an additional information letter datedFebruary 5,1979, on the subject. Thin steel plates are to beinstalled to protect the soft concrete identified at a certainsection of the Unit 2 crane wall. This item was not inspected.

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