IR 05000423/1985014

Insp Rept 50-423/85-14 on 850408-27.No Noncompliance Noted. Major Areas Inspected:Preoperational Test Program,Emergency Diesel Generator Status,Insp & Storage,Qa & QC Interface & New Fuel Receipt

ML20129F890
Person / Time
Site:	Millstone
Issue date:	05/29/1985
From:	Bettenhausen L, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20129F876	List: IR 05000423/1985014 ML20129F875
References
50-423-85-14, NUDOCS 8506070069
Download: ML20129F890 (22)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /85-14 Docket N License N CPPR-113 Priority --

Category B Licensee: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 3 Inspection At: Waterford, Connecticut Inspection Conducted: April 8 - 27, 1985 Inspectors: . . d 18 H. H. Nicholas, Lead Reactor /date/

En ineer Approved by: ,

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. H. Bettenhause'n, Chief ' date Operations Branch, DRS

' Inspection Summary:

Inspection on April 8 - 27, 1985 (Inspection No. 50-423/85-14)

Areas Inspected: Routine, announced inspection of the preoperational test

! program including test program implementation, test procedure review and verification, test results evaluation, test witnessing; licensee action on previous inspection findings; emergency diesel generator status; witnessing of reactor coolant system cold hydrostatic test; witnessing of new fuel receipt, inspection and storage; quality assurance and quality control interface; and, tours of the facility. The inspection involved 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> on site t'y one NRC region-based inspecto Results: No items of noncompliance were identifie .

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DETAILS Persons Contacted-Northeast Nuclear Energy Company (NNECO)

M. Brown, I & C Supervisor C. Clement, Maintenance Supervisor J. Chunis, startup Engineer

• J. Crockett, Superintendent Unit 3 J. De Marzo, Startup Engineer A. Elms, Reactor Engineer E. Frieze, Startup Engineer M. Gelinas, Security Shift Supervisor M. Gentry, Assistant Startup Supervisor J. Hamlin, Shift Supervisor J. Harris, Startup Supervisor-N. Hulme, Startup Engineer K. Jensen,-Reactor Engineer T. Lyons, Startup Engineer N. Madden, Startup Engineer J. McConnell, Reactor Engineer D. McDaniel, Reactor Engineer D. Miller Jr. , Startup Manager E. Olson, Shift Supervisor R. Sochatello, Radiation Protection Supervisor

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S. Sudigala, Assistant Startup Supervisor P. Weekley, Security Supervisor Northeast utilities Service Company (NUSCO)

• D. Blumenthol,-QA-Engineer R. Lefebure, Senior Project Engineer C. Mares, QA Engineer

• L. Nadeau,~QA Engineer

• E. Peckham,'QA Engineer R. Victor, QA Engineer Kemper_ Insurance Incorporated (KI)

F. Arujo, ANI Inspector W. Jones, ANI Inspector

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Hartford Steam Boiler (HSB)

B. Braden,'ANI Lead Inspector M. Headwall, ANI Inspector T.:Hume, ANI Inspector-R. Smith; ANI Inspector L. York, ANI Inspector-

, - R.-Zoner, ANI Inspector Westinghouse Electric Corporation (WEC)

C. Barnes, NSID Mechanical Specialist F. Bowen, Startup Engineer M. Brothers, I and C Engineer C. Callaway, Startup Engineer H. Carlson, Startup Engineer R. Clark, Startup Engineer J. Dolan, Site Manager Unit 3 J. Fernandez, Fuel Site Surveillance Engineer L. Getty, EMD Pump Specialist E. Harlow, Mechanical Engineer R. Hayes, Startup Engineer R. Merritt,-PD QA J. Moore, Startup Engineer R. Smith,_Startup Engineer J. Steffes,LStartup Engineer i Combustion Engineering Corporation R. Johnson, Reactor Vessel Specialist Stone and Webster Engineering Corporation (SWEC)

R. Bradley, Startup Engineer W. Matejek, Project Advisory Engineer T. McNatt, Startup Engineer M. Potkin, Startup Engineer SWEC Engineering Support For Hydrostatic Test E. McManus -

W. Ramsden P. Reilly W. Sullivan

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SWEC Construction Support For Hydrostatic Test C. Hale E. Jacobs

- G. Pangborn R. Thomas

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. SWEC Field Quality Control (FQC)

A. Audoin,.FQC Inspector M. Bezanson, FQC Inspector

~B. Burdick, FQC Inspector C. Card,_FQC Inspector P. Cardinal, FQC Inspector 10. Dolan', FQC Inspector D. Evans, FQC Inspector R. Guffey, FQC Inspector N. Hommer, FQC Inspector B. Kennedy, FQC, Inspecto R. King, FQC, Inspector P. La Ferriere, FQC Inspector G.-Marsh, FQC Inspector M. Matthews, FQC Inspector G. Musik, FQC Inspector J. Montanari, FQC Inspector

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B. Patenaude, FQC Inspector L. Peterson, FQC Inspector T. Rhenborg, FQC Inspector-M._. Sunday, FQC Inspector W._ Taylor, FQC Inspector R. Thorbjansen,- FQC Inspector G. Turner, FQC Inspector B. Welsh, FQC Inspector S. Wicknick, FQC Inspector U. S. Nuclear Regulatory Commission (USNRC)

W. Baunack, Project Engineer D.'Lipinski, Resident Inspector

• T. Rebelowski, Senior Resident Inspector

• denotes those present at exit interview on April 26, 1985 Licensee Action On Previous Inspection Findings (Closed) Inspector Following Item 423/85-02-02 Fuel Receipt and Storage Review. This item involved NRC review of Procedure OP 3211A, definition of the qualification of personnel to handle fuel, the activation of-radiation monitoring equipment in the fuel . building without remote indication in the control room, and review of projected items to be completed prior to fuel receip As noted in Pragraph 6, all of the above items have been resolved and/or completed during the issuance of the SNM License, and the receipt of the new fuel for inspection and storage including the' issuance of an approved copy of OP 3211A Revision 0, Approved April 22, 1985, titled, New Fuel Assembly and RCCA Receipt and Inspection. The inspector verified the adequate resolution of all aspects of this item. This item is close .

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5 Preoperational Test Program References References for the preoperational test program are documented in Inspecton Report 50-423/85-0 .1 Test Program Impl'ementation Scope The nine areas of preoperational test program requirements are the test program; the test organization; the test program administration; document control; design changes and modifications; plant and preventive maintenance; equipment pro ection and cleanliness; test and measurement equipment; and starten staff training. These areas are examined periodicallly by NRC inspectors for implementation during the test progra Discussion In the area of test program administration, the inspector interviewed the startup test manager and his staff, to verify that they were familiar with and implementing the administration of the preoperational test progra The inspector verified, by review of 4 turnover packages, that jurisdictional controls were observed for system turnover. The inspector spot checked portions of systems and components to verify that tagging was accomplished with jurisdictional controls; reviewed turnover documentation to see that jurisdictional controls were observed prior to testing, during repairs and modifications and subsequent to testing; verified by review of test procedures and interview of test personnel that test procedures were current prior to their use, personnel involved were knowledgeable of test procedures, methods to change test procedures during a test, methods to document significant events, unusual conditions and interruptions to testing, and methods far identifying deficiencies, documenting their resolutions and documenting retesting; and, verifying that a sequenced schedule is maintained and is curren In the area of equipment protection and cleanliness the inspector verified by interview of test personnel and review of marked up drawings that system flushing had not been invalidated during preoperational testin The inspector verified by review of documentation and by interviews of chemistry personnel, that water chemistry controls and sampling requirements were being implemented for the reactor coolant and for the condensate feedwater system >

In the area of test and measurement equipment, the inspector selected six pieces of test and measurement equipment and reviewed documentation and calibration records to verify that the administrative controls had been implemented.

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Findings Through discussions with the startup manager and members of his staff, review of records, procedures, logs, and documentation, the inspector verified that the test program administration is being adequately implemented by review of turnover packages, tagging system and documentation; that cleanliness controls and equipment protection along with proper documentation, have been adequately implemented; and, that test and measurement equipment, plus documentation have been successfully

. implemente The inspector had no further questions in these areas covered. Verification by the inspector of other listed areas of the test program will be conducted on subsequent inspection .2 Test Procedure Review and Verification Scope The test procedures listed in ATTACHMENT A were reviewed for technical and administrative adequacy and to verify that test planning satisfies regulatory guidance and licensee commitmer.t Qi}sVI 99?

The proceduret ware examined for: management re"t9w and approval; grcC6 dure ?tra.at; t!D M: > 4 eiac cett abaectives; prerequisites;-

t;<ironmental conditions; acceptance critreia; soorte ci a curts ev$

criteria; references; initial conditions; attainment of test objectives; test performance documentation end verification; degree of detail for test instructions; restcration of system to normal after testing:

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' identification of test personnel; evaluation of test data; independent verificaton of critical : 'rn; or parameters; and, quality control and quality assu.ance involvemen Findings The review indicated that the procedures are consistent with regulatory requirements, guidance, and licensee commitments. No discrepancies or unacceptable conditions were identified. The inspector had no further questions on these procedure .3 Test Results Evaluation Scope The completed test procedures listed in ATTACHMENT B were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform criteria were being applied in the evaluation of completed

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preoperational tests in order to assure their technical and administrative adequac m ,

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Discussion

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i The inspectoi. reviewed the test results and verified the licensees' $

evaluation of test.results by review of: . test-changes; test exceptions;

' test deficiencis5; "as run" copy.~of test procedure; acceptance criteria;

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. performance verification; recording of the conduct of tests; QC inspection records; restoration of system to normal after the. test; independent

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verification'of. critical steps or parameters; identification of personnel conducting and evaluating test data; and, verification that the test results have been approve '

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No. discrepancies or unacceptable conditions were noted in the review of

.these procedure .4 . Test Witnessing Scope-The inspectors witnessed portions of the following tests and preparations being made for upcoming test '(1) .New Fuel Receiving Crane Test (2)~;New Fuel Handling Crane ~ Test -

'(3) New Fuel Inspection Machine Functional . Test

.(4) Fuel-Handling Machine Load Cell Monitor

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. (5). - New Fuel Elevator (6) Spent-Fuel Bridge Crane Test

'(7) Reactor Fuel Handling Tools

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-(S) . Fuel Building Area Radiation Monitors

. (9)1 Spent Fue1~ Pool Cooling Functional Test l- , <(10) New Fuel. Receipt, Inspection and Storage Preparations (11). Hydrostatic Test Preparation .

Discussion- '

Test witnessing by the inspectors included observations of:

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Use of latest, revised and approved procedure available and in use by

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the. test personnel '

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' Designation of one person in charge-of conducting each test or-preparation.for testin .

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Coverage fof test prerequisites

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_Use of acceptance criteria to evaluate test.results

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Verification that plant supporting systems are in: service

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In service; status of. calibrated special test equipment required by

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Adherence to the test requirements of the test procedure during the

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Timely and corrective actions by test personnel during the performance of the test

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QC and QA interface and' coverage of events

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Data col,lection for final analysis by proper personnel The inspectors made independent measurements and calculations of some of the tests during their performance, including start and stop times, travel times, weight lifts, distances, limits, lengths, heights, as well as flows, temperatures and pressures, including pump curve Findings Test results observed by the inspectors indicated that acceptance criteria had been met for those portions-of the tests that had been witnessed. No items of noncompliance were identified and no unacceptable conditions were note . Emergency Diesel Generator Status Scope The emergency diesel generator sets are the vital components of the emergency-standby power supply system to Unit 3 in the event of loss of coolant accident with the loss of offsite power during operation of the Unit. During the preoperational test program it is verified that the diesel engines, or a prototype, have completed 300 successful starts and stops; the EDG sets have mechanical and electrical load tests including 22-hours at rated power and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at overload rating; followed by qualification testing of the EDG sets which consists of 35 successful starts and stops, loading to at least 50 percent load; and lastly, observing the performance of the EDG sets when in standby,to respond to a simulated loss of coolant accident, with and without loss of offsite powe Discussion The emergency diesel generator sets to date are still in the testing stage of the preoperation1 test prcgram with the EDG "A" set mechanical and electrical load testing complete, and the EDG "B" set with only mechanical testing complete. As documented in Inspection Report-50-423/85-10, the inspector pointed out the concern for the recurring problem of EDG fuel injection pumps seizing. After removing'all fuel injection pumps from both engines for disassembly, inspection and-reassembly, the fuel injection pumps were reinstalled on EDG "A" set in order _to have the "A" engine as a standby power back up for the RCS cold hydrostatic tes In running the EDG "A" set one of the fuel injection pumps again seized.

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Findings The licensee and the vendors representatives are exploring this recurring problem. The resolution and subsequent testing of these engines will be a follow-up on subsequent inspections. This is Unresolved Item 423/85-14-0 . Reactor Coolant System Cold Hydrostatic Test 5.1 Introduction The test objective was to perform initial fill and hydrostatic test of the reactor coolant and associated high pressure systems. During the initial fill various piping dead legs were flushed to complete cleaning of the react)r coolant and associated high pressure system. The reactor coolant pumps were checked and then used to sweep, vent and heatup the reactor coolant system. The integrity of the reactor coolant system for strength and leaf tightness is verified at 3110 PSIG for a minimum of 10 minute .2 References Supplementary Documentation (1) RCS and Associated Systems Turnover Package 3301 (2) Stone and Webster FSK Drawings (3) Stone and Webster P & ID Drawings (4) Stone and Webster TSK Drawings (5) Vendor Equipment Instruction Books, Operating Manuals, Purchase Specifications, Vendor Drawings and Correspondenc (6) Nuclear Steam Supply System 2240.000 - 001 (7) Electronic Pressure and Differential Pressure Transmitters 2472.510 -

662 (8) Vendor Equipment Technical Manuals

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Pressurizer Manual 6

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Steam Generator Manual 8

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> -. Reactor Coolant Pump Manual 36

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8" Motor Operated Angle Type Globe-Valves Manual 12

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27.5" and 29" Motor Operated Gate Valves Manual 37 (9) FSAR Section 5 (10) ASME Boiler and Pressure Vessel Code Section 3 (11) NNECO Unit 3 Flushing Reference Manual (12) General Hydrostatic Test Procedure NEU-SU-1. Detailed Test Procedure (1) .T3301-Pool, Revision 0, Approved March 18, 1985 titled, Reactor Coolant and Associated System Fill and Hydrostatic Test

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5.3 Discussion (1) -The hydrostatic test consisted of filling the reactor coolant system and associated high pressure systems to their first boundary valves as. indicated on the boundary diagrams and composite drawing (2) Flushes were conducted until all areas appeared clean as evidenced by

inspection of the flushina cloth (3) System was pressurized to 60 PSIG and a round of sweeping and venting was conducted to purge all pockets of air or gases from system (4) Initial heatup of the coolant. system was obtained by supplying heated water to the charging pumps. When all venting was completed, temperatures above 70 F, and reactor vessel head tensioned, pressure was raised to 350 PSIG and subsequent heatup was accomplished by running reactor coolant-pump (5) With the temperature of the reactor pressure vessel head and the pressurizer above 120 F; and the steam generator temperatures above

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-150 F,'the reactor coolant system was pressurized to 500 PSI (6) With the reactor coolant temperature above minimum for boltup and tensioning of the reactor pressure vessel head, and above minimum for p.essurization, the hydrostatic test was begun with pressure plateaus of 500 PSIG, 1000 PSIG, 2250 PSIG, and a final hydrostatic test pressure at 3110 PSIG for a minimum of 10 minutes. The average temperature at these prsssure plateaus was 155 (7) After completion of'the 3110 PSIG hold for a minimum of 10 minutes, pressure was reduced to 2400 PSIG and held there until leak inspection of all welds and mechanical fittings within the test boundary was performe .4 Observations Prior to the test, the inspector verified the following:

(1) Valve positions were checke (2) Latest. drawing revisions were used in conjunction with the vcive lineup list (3) Latest boundary diagraas were in us (4) Calibrated, serialized, and dated pressure gauges of proper range had been installed with gauge number 1 having been designated as the

" Official Gauge" and gauge number 2 as the "back up" guage. Pressure gauges were also installed at the charging pumps, the hydro pump, and the backup hydrolaser pump.

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.(5)' Overpressure protection was provided by an installed pressure range and capacity. stamped, calibrated and tested, serialized relief valve with backup relief valves at the hydrolaser pump discharg (6) -Temperatures at the reactor pressure vessel, pressurizer, steam generators, reactor coolant pumps as well as the reactor coolant loops; were above the specified minimum temperatur .(7) Required supporting systems were functiona (8) All welded joints and mechanical corrections were uncovere '

(9)' A11 temporary instrumentation had been installed and calibrate (10) Communications had been established between all stations, the control room, and all inspection team (11) QA and QC provided complete coverage for the entire even .5 Crew performance The inspector observed the following:

(1) The RCS cold hydrostatic test procedure with the latest revision was available and in use by crew member (2) The minimum crew requirements had been me (3) Briefings had been conducted with the crew and the inspection team (4) All test prerequisites were me (5) Appropriate systems, as needed, were in service.

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c (6) Special test equipment and instrum' ~ ation required by the procedure was calibrated, in service, and mi ' by test personnel .

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(7) Testing was being performed as req d by the procedur (8) Crew actions appeared to be correct and timely during the performance of'the tes (9) All test data were collected for final analysis by the cognizant test personnel.

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5.6 Test Witnessing By direct observation, the inspector witnessed the following:

(1) The manning and conduct of the test at the charging pump station, hydro pump station, the backup hydrolaser pump station, control room including-the temperature, pressure and flow monitoring panels; as well as the upper and lower reactor pressure vessel head areas of the 4 steam generators, and the 4 reactor coolant pump cubicle (2) Water sampling and results for water qualit (3) System pressure at 60 PSIG and reactor pressure vessel and pressurizer temperature above.120 F while steam generator temperatures were above 150 (4) System pressure at 350 PSIG and temperature at 165 (5) System pressure at 500 PSIG and temperature at 164 (6) System pressure at 1000 PSIG and temperature at 161 (7) System pressure at 2250 PSIG and temperature at 159 (8) Reactor pressure vessel flanges, upper head area, upper area of pressurizer and hydro pump station (9) Attaining and holding pressure at 3110 PSIG with temperature at 155 F for a minimum of 10 minutes as read on the official test gauge at the top of the pressurize (10) Depressurizing to 2400 PSIG and holding for detailed inspection of all welds and mechanical joint _(11) All assembled inspection teams passing into containment and to their respective areas of inspectio (12) Accompanying inspection teams into containment and inspecting welds on' reactor pressure vessel penetrations, pressurizer, steam generators, residual heat removal system,-surge line, spray line, instrument lines and incore tube (13) Use of allowable heatup rates, cooldown rates, pressurizing rate,

depressurizing rate and maximum allowable differential pressures and differential' temperature _

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I 5.7 Independent Measurements

'(1) . Temperature the inspector made independent measurements of temperature at the following areas; Reactor pressure vessel upper, lower at:d flange areas; steam generators flange and lower head areas; pressurizer upper, lower, and shell areas including surge line and spray line; and reactor coolant loop lines; with a portable platinum tipped hand held pyromete (2) Pressure The inspector timed the increase and decrease of pressure at the *;ctious plateaus while monitoring the "heise" official and backup pressure gauges using a hand held portable stop watc (3) Time The inspector timed rates of change of temperature increases and decreases as well as rates of change of pressure increases and

,y decreases along with timing the hold time at 3110 PSIG hydrostatic test pressur (4) Vibration The inspector made independent measurements of vibration of

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the Reactor Coolant Pumps using a portable hand held vibration mete The calculations and measurements made by the inspector in the areas of pressure, temperature, time, vibration, flow, and rates of change in

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parameters in addition to test results observed by the inspector, indicated.that acceptance criteria had been me '

. Findings The inspector established by records review, by independent calculations and measurements, by direct observations, and by test witnessing, that testing was conducted in accordance with approved procedures. The inspector' independently verified the acceptability of the test results, and evaluated the performance of the licensee personnel involved in the tes No items of noncompliance were identifie . New Fuel Receipt Inspection and Storage References

.EN 31068 New Fuel Inspection Machine Functional Check OP- 3211A New Fuel Assembly and RCCA Receipt and Inspecton

0P 3303A Spent Fuel Bridge OP 3303B New Fuel Elevator OP 3303C Fuel Transfer System

0P 3303D Fuel Handling Tools OP 3303G New Fuel Handling Crane OP 3303H New Fuel Receiving Crane-T3305-P Spent Fuel Pool Cooling and Purificaiton Test

.T3303-IIO2 Fuel Handling Machine Load Cell Monitor T3303-1M02 Spent Fuel Bridge Crane

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T3303-1E04 New Fuel Handling Crane T3314-C1M05 Fuel Building Dampers and Valves T3314-C1M01 Fuel Building Normal Exhaust Fan T3314-C1E01 Fuel Building Normal Exhaust Fan T3305-1M03 Spent Fuel Pool Cooling and Purification Valve Tests T3305-1M02 Spent Fuel Pool Purification Pump T3305-1M01 Spent Fuel Cooling Pump T3305-II01 Spent Fuel Pool Cooling And Purification Instrumentation T3305-1E03 Spent Fuel Pool Submersible Dewatering Pump T3305-1E01 Spent Fuel Cooling Pump T3305-1E02 Spent Fuel Pool Purification Pump T3305-IF01 Fuel Pool Cooling and Purification System Flush T3303-1E09 New Fuel Inspection Station T3303-1M05 Reactor Fuel Handling Tools T3303-1E07 New Fuel Elevator T3303-1E10 Spent Fuel Bridge Crane T3303-1E05 New Fuel Receiving Crane Test T3303-P001 Fuel Transfer System Test Letter to B. J. Youngblood, NRC, from W. G. Council, NNECO, dated March 14, 1985, titled: Control of Heavy Loads NRC IE Information Notice 80-01 NRC IE Information Notice 85-12 SER.Section 9 FSAR Section 4, NNECO Unit 3 Application for Special Nuclear Materials License,_USNRC Materials License SNM-1950 dated April 16, 1985 6.1 Introduction The objective of this inspection was to ascertain whether nuclear fuel '

received at the construction site is properly accepted and safeguarded, and whether it is stored in accordance with the NRC license requirement This was accomplished by direct observation of activities and review of documentation at various times over a period of three weeks prior to the issuance of the NRC materials license and the arrival of the first shipment of nuclear fuel, and by witnessing of the first shipment of fuel, from its arrival at the main gate, to its final storage place in the spent fuel poo .2 Discussion The inspector reviewed documents in the following areas pertaining to the receipt, inspection and storage of new fuel for Unit 3, such as Nuclear Materials License, Qualifications and Training, Fire Protection, Health Physics and Radiation Protection, Physical Security, and Preoperational Testin .-

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Documents reviewed and discussed with licensee representatives were:

(1) -Application for SNM License (2) Nuclear Materials License (3) Health Physics and Radiation Protection Procedures (4) Security Plan Procedures for Fuel Receipt and Storage (5) Training Procedures (7) Preoperational Test Procedures (8) Material Transfer Log (9) Material Accountability Log (10) Fuel Assembly Receipt and Inspection Form (11) Thimble Plug Receipt and Inspection Form (12) Spent Fuel Pool Map For Fuel Assembly Location (13) New Fuel Receiving Crane Check List (14) New Fuel Handling Crane Check List (15) New Fuel Inspection Station Check List (16) New Fuel Elevator Check List

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'(17) Spent Fuel Bridge Check . List (18) . Visitor Control Access List Area Authorization (19) Daily Log of Access and Exposure Control (20) Radiation Survey Sheets-(21) Radiation Work Permit (22) Test Certification Reports On All Cranes Used

.(23) Shipping Container Receipt'and Inspection Sheet (24) Prerequisites and Precautions For New Fuel Receipt Under the SNM License (25) Bill of Lading, C & H Transportation Company (26) Consignment of Fuel From Westinghouse Electric Company to Northeast Utilities (27) Product Shipment Notice Westinghouse Electric Company (28) Quality Release Westinghouse Electric Company (29) Prerequisite and Initial Conditions Sign Off Sheet (30) Precautions Sign Off Sheet (31) Fuel Assembly Receipt and Inspection (32) Thimble Plug Assembly Inspection (33) Burnable Poison Assembly Inspection The inspector witnessed receipt, preparation, cleaning, inspection, and storage of 14 fuel assemblies from arrival at the fuel building truck bay

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to storage in the spent fuel poo The activities included radiation surveys of the truck and outer. metal casks; opening of the casks; the initial survey of the two fuel assemblies in each cask; the removal, cleaning and-inspection of each fuel assembly one at a time; the final inspection and measurements at the.new fuel inspection station; and the final storage of each fuel' assembly in the spent fuel pool. The inspector observed the use of the new fuel receiving crane,'the new fuel inspection station, the new fuel handling. crane, the new fuel elevator and the spent fuel bridge including the use of the new fuel handling tool as well as the use-of the

, spent fuel handling tool.

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The inspector discussed with licensee representatives IE information notices 80-01 and 85-12, having to do with recent fuel handling events.

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Discussions with the licensee representatives and review of documentation verified that the licensee had taken proper action in the area of procedures, precautions, prerequisites, and alarms and interlocks so that these events cannot occur at Millstone Unit The inspector also reviewed documentation and made observations, on a sampling basis, during this evolution, in the areas of Administration, Physical Security, Health Physics and Radiation Control, Reactor

. Engineering, Quality Assurance and Quality Control. QA and QC provided coverage for the entire fuel receipt evolutio Findings The inspector verified that receipt, inspection, cleanliness, assembly and storage, including documentation of completed fuel assemblies was accomplished in accordance with NRC license requirements. The inspector also verified that all license requirements had been implemented for new fuel receipt, inspection and storage; security controls were exercised; health physics and radiation protection controls were implemented in the areas of swipes, surveys, air monitoring, and personnel protection and dosimetry; control of the environment of the fuel storage and assembly area; verification of documentation, procedures, and records review such as fuel manufacturer, transportation, quality assurance and quality control; inspection of shipping casks; reportable events; and qualification of personnel involved in management and implementation of receipt, inspection, and storage of nuclear fuel. The inspector witnessed the evolutions and verified documentation and proper use of procedures for fuel _ movement within the fuel building and spent fuel pool location No items of noncompliance were identified and no discrepancies were noted during these inspections. The inspector will continue to observe and inspect this evolution of new fuel receipt, inspection, handling and storage on subsequent inspections until all fuel is on site. The inspector has no further questions at this tim . Quality Assurance and Quality Control Interface AS described in Paragraphs 3, 5, and 6, and as indicated in Paragraph 1, QA and QC were involved with many aspects of testing, the RCS cold hydro test, and with final fuel receipt, inspection, and storage. QA maintained assigned personnel coverage and audited the entire hydrostatic test performance. The RCS cold hydrostatic' test and the irrival of new fuel are both major milestones in the Millstone 3 preoperational test program schedual and a QA/QC interface was in evidence in each phase of the test progra _

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, Plant Tours The inspector made several tours of the facility including the containment structure, auxiliary building, turbine building, service building, control building, emergency safety features building, emergency diesel generator rooms, battery rooms, control room, auxiliary boiler area, fuel building, circulating and service water pump house and hydrogen recombiner buildin Particular attention was given to the emergency diesel generator set problems and repair work in progress, preparations being made for the receipt of fuel and the eventual witnessing of the new fuel receipt inspection and storage; the preparations being made for the RCS hydro test and the eventual witnessing of the RCS cold hydrostatic test, and other testing and work-in progress. Items of inspection also included housekeeping, cleanliness controls, storage and protection of components, piping and systems. No items of noncompliance were observed during these tour . Unresolved Items Unresolved items are matters about which more information is required to accertain whether they are acceptable items, items of noncompliance or deviations. An unresolved item, resulting from this inspection is discussed in Paragraph . Exit Interview At the conclusion of the site inspection on April 26, 1985, an exit meeting was conducted with the licensees' senior site representatives (denoted in Paragraph 1). The findings were identified and previous inspections items were discusse At no time during this inspection was written material provided to the licensee by the inspector.

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ATTACHMENT A

, iTEST PROCEDURE REVIEW

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(1) T3314 - FP'_ Revision 0, Approved April 10, 1985

~ Control Building HVAC System 3-INR - 2001- Computer Programs (2).' Test Appendix 3J2 Revision 0, Approved 21, March 1985 Reactor Coolant System Heatup/Cooldown Rate-

. (3)~ 3-INT - 3000 Hot. Functional Testing-Appendix 3029 Revision 0, Approved April 10, 1985 Cheraistry Guidelines

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(4) T3316'- BP Revision 0, Approved April 3, 1985

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Steam Dump Controls-(5). T3315 - DA Revision 0, Approved March 25, 1985 Technical Support Center Ventilation 1(6) T3314 - AP Revision 0, Approved March 27, 1985

, Auxiliary Building HVAC System (7) T3304 - AP001 Revision 0, Approved April 6, 1985 Charging Letdown and Purification System

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-(8). T3305 - P- Revision 0, Approved April.11, 1985 Spent' Fuel Pool Cooling Purification Test

.(9)_ T3303-P001 Revision 0, Approved April 10, 1985

' Fuel Transfer System Test-

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'(10) T3303 - IMOS Revision 0, Approved March 20, 1985 Reactor Fuel Handling Tools (11) T3305 - IE01 Revision 0, Approved November 11, 1983 '

Spent Fuel Pool Cooling Pump 3 SFC-P1A and PIB-(12) T3305 - 1E02 Revision 0, Approved December 1, 1983

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-Spent Fuel Pool Purificaiton Pump 3 SFC-P2A and P2B

' (13).T3305 - IE03 Revision 0, Approved January 30, 1984

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Spent Fuel Pool Submersible-Dewatering Pump 3 SFC-P4 (14) T3305:- 1F01 Revision 0, Approved March 12, 1985 Fuel Pool Cooling and Purification System Flush (15) T3305 --IT01 Revision 0, Approved November 11, 1983 Spent Fuel, Pool Cooling and Purification Instrumentation 3 SFC

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(16) T3305 .IM01 Revision 0, Approved November 14, 1983 Spent Fuel Cooling Pump 3 SFC-P1A and PIB

~(17) T3305 --IM02 Revision 0, Approved June 6, 1984 Spent Fuel- Pool Purification Pump 3 SFC-P2A and P2B -

(18) T3305 - IM03 Revision 0, Approved November 14, 1985 Spent Fue' Pool Cooling and Purification Valve Tests (19) T3314:--C1E01 Revision 0, Approved December 17, 1983 Fuel Building Normal Exhaust Fan 3HVR-FN9 (20) T3314 - C1M01 Revision 0, Approved August 26, 1983 Fuel Building Normal Exhaust Fan 3HVR-FN9 (21) T3314_- C1M05 Revision 0, Approved March 12, 1984 Fuel Building Dampers and Valves

'(22) T3341 - AIM 06 Revision 0, Approved May 7, 1983

'NSST/ Fuel / Waste Fire Protection Water (23) T3404 -'1I01 Revision 0, Approved March 25, 1985 Fuel Building Area Radiation Monitors (24) T3303 - IE05 Revision 0, Approved November 11, 1983 New Fuel Receiving Crane Test (25) T3303 - 1E07 Revision 0, Approved October 12, 15d4 New Fuel Elevator-(26) T3303 - 1E09 Revision 0, Approved May 12, 1984 New Fuel Inspection Station (27) T3303 - IE10 Revision 0, Approved August 10, 1984

, Spent Fuel Bridge Crane (28) Letter to B. J. Youngblood NRC, from W. G. Council NNEC0 dated

,

March 14, 1985 titled Control of Heavy Loads 1 (29) T3303 - IIO2 Revision 0, Approved April 3, 1985 Fuel Handling Machine Load Cell Monitor (30) T3303 - 1M02 Revision 1, Approved May 21, 1983 Spent Fuel Bridge Crane (31) T3303 - 1E04 Revision 0, Approved March 30, 1985 New Fuel Handling Crane

_(32)~EN 31068 Revision 0, Approved April 18, 1985

_1 New Fuel Inspection Machine Functional Check

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I(33) OP'3211A Revision 0, Approved April 22, 1985-

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New Fuel. Assembly-and RCCA Receipt and Inspection

~'(34) OP 3303A Revision 0,-Approved April 23, 1985 Spent- Fuel Bridge

(35) OP 33038 Re. vision 0, Approved April 16, 1985 New Fuel Elevator (36) OP 3303C Revision 0, Approved April 23, 1985

. -

. Fuel Transfer System

~ (37) OP-33030 Revision 0, Approved April 15, 1985 Fuel-Handling Tools (38) OP 3303G Revision 0, Approved April 21, 1985 New Fuel Handling Crane

.

. (39) OP 3303H Revision 0,' Approved April 19, 1985 New Fuel Receiving Crane (40) T3346.- AP003 Revision 0, -Oraft Copy Emergency Diesel / Generator A Licensing Test (41) T3346 AP004 Revision 0, Draft Copy-Emergency Diesel Generator B

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Licensing Test-(42) T3323 - AA001 Revision 1, Approved April 10, 1985

- Electro Hydraulic Control

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ATTACHMENT B TEST RESULTS EVALUATION (1) T3345 - BP001 ~ Revision 0, Approved March 5,'1984 Channel 1 120 VAC Vital Test Results Approved March 27,-1985 (2) T3345 - BP002 Revision 0, Approved March 5, 1984 Channel 2 120 VAC Vital Test Results Approved March 27, 1985

.(3) T3345 - BP003 Revision 0, Approved March 5, 1984

~ Channel.3- 120 VAC Vital Test Results Approved March 27, 1985 (4) T3345 - BP004 Revision 0, Approved March 5, 1984 Channel 4 120 VAC Vital Test Results Approved March 27, 1985-(5) T3345 - BP005 Revision 0, Approved May 23, 1984 Channel 5 120 VAC Non-Vital

. Test ~Results Approved March 27, 1985 (6) T3303 - 1E05 Revision 0, Approved November 11, 1983 New Fuel Receiving Crane Test Test Results Approved April 16, 1985 (7) T3303 - IIO2 Revision 0, Approved April 3, 1985 Fuel Handling Machine Load Cell Monitor Te.t Results Approved April 22, 1985 (8) T3303 - 1E04 Revision 0, Approved March 30, 1985 New Fuel Handling Crane Test Results Approved April 18, 1985

'

(9) 13303 .1M02 Revision 0,. Approved May 21, 1983 Spent Fuel Bridge Crane Test Results Approved April 18, 1985-(10) T3303 - IMOS Revision 0, Approved March 20, 1985

'

leactor Fuel Handling Tools Test Results Approved April 19, 1985

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.'(11) T3303 - IE07 Revision 0, Approved October 12, 1984

.New Fuel Elevator' . .

Test Results Approved April 22, 1985 -

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(12) T3303 - 1E10 Revision'0. Approved August 10, 1984

. Spent. Fuel-Bridge. Crane

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. Test Results Approved April 18, 1985 r

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