IR 05000320/1985009

Exam Rept 50-320/85-09 on 850402 & 03.Exam Results:Four Candidates Examined & One Reactor Operator & Three Senior Reactor Operator Licenses Issued.Inconsistent Answers on Written Exam Indicate Nonuniform Training Program Results

ML20128N547
Person / Time
Site:	Crane
Issue date:	05/14/1985
From:	Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20128N528	List: IR 05000320/1985009 ML20128N525
References
50-320-85-09, 50-320-85-9, NUDOCS 8506030318
Download: ML20128N547 (19)

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U.LS. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.

50-320/85-09 (OL)

FACILITY DOCKET NO.

50-320 FACILITY LICENSE NO.

DPR-73 LICENSEE:

GPU Nuclear Corporation Post Office Box 480 Middletown, Pennsylvania 17057 FACILITY:

Three Mile Island Unit 2 E'XAMINATION DATES:

April 2 and 3.

1985 CHIEF EXAMINER:

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T//y/W h.Dudley,LeadRe tor Engineer (Examiner)

Date REVIEWED BY:

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R. M. Keller, 'Chidf, Projects Section 1C Date

. APPROVED BY:

/ [f H.' B: Kisfer M hief, Projects-Branch No. 1 (Dath SUMMARY:

Four candidates were examined and one R0 and three SR0 licenses were issued.

An -improvement was noted in operator knowledge level, however, some weaknesses in nuclear reactor theory and procedures continue to occur.

The inconsistent answers on the written examination indicate non-uniform training program results.

8506030318850p320 PDR ADOCK 050 G

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REPORT DETAILS-

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,. TYPE ' 0F' EXAMS: -Repla' cement'

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EXAM RESULTS:

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Pass / Fail l-

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. Chief Examiner at'-Site:

N. Dudley

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Other Examiners:

M. King, EG&G (Idaho)

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. Summary of generic strengths or deficiencies noted from grading of written exams:

There is a. generic weakness in the area of procedures. Specif"cally, all candidates displayed weakness in the area of. evacuation requirements for the reactor building.

Also, candidates displayed a weakness in their knowledge of the Standing Orders. These orders contain detailed operating procedures and precautions which are not included in the operating pro-cedures.

Since the Standing Orders are not read prior to conducting evolutions, 'the Orders which deal-directly with plant operations must be fully understood or incorporated into the appropriate procedures. Both of

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these specific weaknesses were identified during the previous license examination.

-The range of grades in each section of the examination indicate an incon-sistency in the knowledge level of the candidates. The reason for this large disparity in candidates who had received the same training could not be determined.

The facility.itself identified weaknesses in its licensed operator train-

'ing-programs by con'cluding two weeks before the examination date that five out of nine candidates were not prepared to sit for the licensing examina-tion.

This is viewed ' as a strength of the training department which adequately evaluated the results of its training program.

2.

Personnel Present at Exit Interview:

NRC personnel C. Cowgill, Section Chief

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R. Cook, Senior Resident Inspector T. Moslak, Reactor Engineer N. Dudley, Examiner NRC Contractor Personnel M. King, EG&G (Idaho)

Facility Personnel A. Miller, Manager, Plant Operations J. Byrne, Manager, TMI-2 Licensing B. Leonard, Operations Training Manager 3.

Summary of NRC Comments made at exit interview:

All candidates were clear passes' on the operational portion of the exam-ination. The R0 candidate was well ac.quainted with the main control' room and the operating procedures.

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During the examination review, two areas of difficulty were encountered when trying to establish a " correct" answer to examination questions.

First,' lines of responsibility overlap and for some evolutions multiple permissions are required.

As a result, it becomes unclear who has ultimate responsibility and authority for certain evolutions. Second, it'

was difficult to classify events' since a given event. fell into more than one ' category.

It appeared that either classification would be acceptable-

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to the facility since it was based on the judgement of the emergency director.

4.

Summary of facility comments' and commitments made at exit interview:

The facility commented. that the written examination was better than past examinations but over emphasized and required too much detailed under-standing of the Standing Orders.

The facility committed to provide to the NRC, 60 days before any SRO fuel handling examinations, lesson plans and procedures, approved or draft, for all systems listed in Mr. F. Standerfer's letter to Mr. R. Keller dated March 14, 1985.

5.

Changes Made to Written Exam-During Examination Review:

Answer No Change Reasons.

5.07b Question-Delete The calculation of a startup rate from a 1/M plot is beyond the scope of a senior licensed opera tor.

6.10 Question Change " Pool The pool storage tanks have been Storage Tanks" to removed.

" Fuel Handling Building".

6.10 Change to read Provides correct answer for Fuel

"one gaseous and Handling Building.

one particulate (B)

scintillation detectors; all alarm in MCR and locally".

6.10 Reference Change to "T.S.

Provides proper reference for the Table 4.3-3".

answer.

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Answer No Change Reason 5.1 Add "PWST recirc".

Provides additional location of a jet pump.

5.8 Add note "no Question did not require a points lost for discussion of flow.

reference to flow".

6.6 Add "IFF".

Provides additional sample _ point for the temporary sample system.

7.3 Change "+/- 300 Expands the acceptable ran'ge of volts" to "+/-

set points for automatic diesel 500 volts" and start.

add "Is credit for 0 to 5 sec time delay".

~7.05 Change "65 and-Corrects answer to correspond to 165 F" to "70 and Enclosure 5 of Surveillance-140 F".

Change'

Procedure Number 4211-SUR-3061.01, answer 2 to Revision 1.

" Stable". Change answer 3 to

" Deviation is less-than 15 F".

Reweight points.

7.6 For answer 1 delete Limits the detail of knowledge

"6900, 4160, and concerning use of monogoggles.

480 volt".

For-answer 2, delete

"The potential exists for a circuit to open or close unexpectedly or while opening or closing a circuit

> 480 volts AC".

Reweight points.

8.6a Add "or_ unusual Corresponds to facility event".

classification of the events.

b-Change to " unusual event".

c Change to " Radio. logical Occurrence".

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8.8a Add "or Emergency.

Corresponds to facility i

Director".

administration procedures, b

Add _" Site,0perations

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Director, Radwaste i

' Support Manager,. or Supervisor Disposal

. Waste".

e Add "Radwaste

,0perations Manager or SS/SF".

f Add."or SS/SF".

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Attachments:

1.

Written Examination and Answer Key (SRO)

2.

Facility Comments on Written Examinations Made After Exam Review.

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Number Operati Prccedure 4215.-0PS-3527.01 . . , Title q, g e. _5 7o7 Revision No.

SDS Operating Guidelines

9.1 PROCESS INSTRUCTION AND DATA SHEET COVER SHEET Batch Number: Date: Time: Procedure (s) to be used: Type of Operation (check one): I.

• SDS Feed Filtering and IX Processing II.

SDS 1.eakage Containment __ III. * SDS Vessel Movements ., IV.

• SDS Dewatering V.

SDS Flushing VI.

SDS Off-Gas Separator Tk Xfer Additional Instructions:

Operator Comments: Initiated By: Date: Time: Terminated By: Date: Time: Concurred By: Date: Time: _ Radiochemical Engineering

5 Authorized By: Date: . Time: - E (Shift Supervisor / Foreman)

• Radiochemical Engineering Concurrence Required.

e ~ l A000105011 82

Numen ProtecureO 42ii-Sun-ac53.0, Surveill ., , Title RIvision No

Shift and Daily Checks

EN:LCSURE 5 (Cont'c) G-1 pei Reacino MINIMUM CHANNELS DATA DESCRIPTION

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REOUIRED ACCEDTANCE CRITERIA NOTE INOPERABLE Incore Thermocouples INCORES BELON: All available (report Temperature Indication (Incore Desianation) all failures to Shift appears consistent with Foreman) Shift other thermocouples and Comcuter Points Foreman to commente RCS Temes. * No. 493 througn an 8 hour time clock 544 for all failures and submit an Event Report, if the clock is exceecec.

NOTE INCORES REMOVED Incore Thermo:cucles EY Z SIGMA FUNCTICN All available (recort Not acclicacle - Shift all failures to Shift Foreman to investigate Foreman) ail cnanges Comcuter Points No. 493 througn 544 NOTE: If accectance criteria is not met, proceed with ACTION STATEMENT 3.3.3.5 of Technical Specifications'. Time t l Time 2 l T i tre i l3l DEcrCovE: Ev-

' APPROVED BY: ,

The thermocouples can be considered operable if they meet the following guicelines: The indicated temcerature is between 70*F anc 140*F anc.

The deviation is less than 15*F from the 'ast computed average.

If the thermocoucle does not meet the above guidelines it should be removed from service for troubleshooting.

After repair / calibration the thermoccucle should be returnec to ~ service, if applicable, or ceclarec c mnanently out-of-service, with subsecuent removal anc/cr disconnettion of indicators.

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~ . ENuslear O e-s c' O . s o as20-oio nev o ISSUE DATE September 1983 D iTS O won C NITS DIVISION ~ SYSTEM DESCRIPTION FOR GPUN Processinc Water Storace DOCUMENT CONTROL and Recycle System CONTROLLED COP @Sd/ COG ENG M DATE "I RTR DATE l COG ENG MGR.

DATE l ! =

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4 - DOCUMENT PAGE I OF 24 . . _-

SD 3520 010 . Ger Fol .O aEv. o O 15737-2-M72-PWO2 ' J-PAGE al 0F

. in the Unit 1/ Unit 2 corridor.

A portion of the 4-inch OTSG line is used as a processed water supply line.

The OTSG line is modified with PW system piping added to allow processed water to be transferred to the following: - . a'. Evaporator condensate test tanks (ECTTs) WDL-T-9A and WDL-T-9B b.

Reactor coolant evaporator WDL-Z-1 c.

Primary containment piping penetration R-565 . d.

Demineralized service water (DW) system (boric acid mix tank CA-T-1 feed) ~ ' ~ 1.3.2 Major System Components 1.3.2.1 Storage Tanks (See Appendix A, Table 1) . . . . Two 500,000 gallon storage tanks (PW-T-1 and PW-T-2) are located in the yard (refer to Section 1.5).

The tanks are atmospheric via open ended .. 12-inch roof vents, and are non-Seismic Category I.

Mixing of the liquid within the tanks is accomplished by pump recirculation and an eductor , system. The mixing system provides representative sampling capability by recirculating the equivalent of three tank volumes in approximately , 24 hours. Each tank contains two 3-inch Schutte and Koerting Co_Typt 268 _ eductors and associated internal piping and w orts. ThLeductors are' fully submerged at elevation 309'-5".

Tank wetternozzles, internal . - - piping, a'nd eductors are constructed of stainless steel.

• a The tanks are provided with. freeze protection..The freeze protection consists of self-regulating heat tracing (Chemelex Auto Heat Trace System, 10 PTV-2 heater type) which encloses the bottom circumference of each tank, except the portions housed in the pump house. The heat

' tracing'is covered by weatherproofed semirigid fiberglass insulation.

1.3.2.2 Transfer Pumps (See Appendix A, Tables 2 and 3) , Two trar fer pumps (PW-P-1 and PW-P-2) are provided for procesced water pumping operations.

The pumps are the single-stage, end suction / top discharge horizontal centrifugal type with stainless steel construction.

Each pump is provided with a drip pan to collect any minor stuffing box leakage.

Pump casing drains are valved and capped locally. Motors for the pumps are supplied with electrical service. from motor control center 2-31H.

1.3.3 Process System Design Piping is designed, fabricated, and. tested in accordance with ANSI B31.1, Power Piping Code.

The portion of piping from the EPICOR 11 system tie-in up to and including isolation valve PW-V002 conforms to NRC Regulatory Guide 1.143, and is therefore classified as Important to Safety.

System piping within the boundary of primary containment piping penetration R-565 is also Important to Safety.

All other portions of the system are designated as Not Important to Safety.

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. SD 3520 010 o O-REV. 0-V . s PAGE $ OF

15737-2-M72-PWO2 ' . crossover inlet line to the storage tanks in the PW pump house (see - Section 1.5).

Isolation valves PW-V003 and PW-V004 on the crossover line permit selection of either tank for filling.

The PW/EPICOR II system interface is in the chemical cleaning building.

The EPICOR II effluent line also functions as the flow path to recycle processed water to EPICOR 11 for further processing.

The SDS feed and monitor tank system transfer pumps, 505-P-1A and SDS-P-18, are _used to deliver SDS processed water to the storage tanks.

The PW system interfaces with the monitor tank transfer pump discharge header at valve PW-V039 in the Unit 1/ Unit 2 corridor.

From PW-V039, the effluent line is routed to a common crossover tank inlet line in the pump house, which contains isolation valves PW-V007 and PW-V008, to permit selection of either tank for filling.

- Each of the storage tanks contains a drawoff sump to alTow complete , draining of each tank.

Tank drain lines are double isolated and tee into the tank overflow lines.

The common tank overflow line is routed to the - . chemical cleaning building sump.

~ Processed water transfer pumps PW-P-1 and PW-P-2 are used to transfer water from the PW storage tanks.

Each transfer pump is provided with a separate suction line and startup strainer (PW-S-1 and PW-S-2).

The suction lines are manifolded such that each tank may be used as a source of water for either transfer pump, excluding simultaneous pump-operation ^ when cross matching tanks and pumps (PW-T-1 to PW-P-2 and PW-T-2 to PW-P-1).

Connected to the manifold is a 6-inch line routed from the pump house to the Unit 1/ Unit 2 corridor where a valved / flanged connection is - provided for future use.

Each pump suction line has a double isolated ' sample line connection which is directed to the sample sink in the pump house.

The sample sink drain 1.ine discharges into the common overflow line from the storage tanks.

- Transfer pump PW-P-2 is used primarily for tank recirculation.

A re-i.

striction orifice, PW-U-2A, is provided in the tank recirculation line to ensure the correct tank recirculation flow is obtained and to prevent pump runout. 'A portion of the line also functions as the minimum flow bypass line for pump PW-P-2.

Valve PW-V076 is provided upstream of orifice PW-U-2A to direct flow through the minimum flow bypass line which contains orifices PW-U-2B and PW-U-2C in series.

Transfer pump PW-P-1 is provided with a minimum flow bypass line with series arranged orifices PW-U-1A and PW-U-18.

The minimum flow line of transfer pump PW-P-1 and the minimum flow / tank recirculation line of pump PW-P-2 tie in to a tank inlet manifold.

The inlet lines extend into the tanks and contain two mixing eductors per tank.

The transfer pumps are provided with separate discharge lines and a - common crossover line.

The main processed water discharge header is routed from the pump house, through the yard, and into the Unit 1/ Unit 2 corridor.

The other pump discharge header ties in to the EPICOR II effluent line in the pump house between valves PW-V003 and PW-V004.

The main header ties in to the 4-inch OTSG chemical cleaning system line Page 6 Rev. O - , < }}