ML20238F363

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Forwards Comments on NRC 870904 Written Requalification Exams Administered to Licensees.Comments Discussed During 870904 Exam Review Meeting & Addl Comments & Refs from Reviews Conducted Subsequent to Meeting Encl
ML20238F363
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/09/1987
From: Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
MP-10831, NUDOCS 8709160103
Download: ML20238F363 (13)
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['[",Z',2',,,7 '""" P.o. BOX 270 enost vrun uan, cwn., H ARTFORD, CONNECTICUT 06141-0270 g d ewac wcana ewacacwa.- (203) S65-5000 September 9, 1987 l MP-10831 1 Re: NUREG-1021/ES-201/ para H.1 U.S. Nuclear Regulatory Commission Document Control Desk j Washington, D.C. 20555 {

Reference:

Facility Operating License No. NPF-49 Docket No. 50-423 September 4, 1987 NRC License Requalification Examination Comments Gentlemen: 1 1 Attached is the compilation of comments on the written j requalification examinations administered to Millstone Unit 1 No. 3 license holders on September 4, 1987. l These comments were the result of a review of the examinations conducted by members of the Millstone Unit No. 3 training staff. Included are both the comments discussed during the exam review meeting of September 4, 1987 plus additional comments resulting from reviews conducted l subsequent to this meeting. Attendees at the September 4, 1987 meeting were: i R. Stotts - Northeast Utilities R. Temps - NRC M. Moehlmann - Northeast Utilities The exam reviews were conducted considering the following: 1. Does the question elicit the correct response? 2. Is the key answer correct? 3. Is there potential for additional correct responses? 4. Is the question appropriate? References are provided, where necessary, to substantiate the commentsa i V $1 8709160103 B70908 i i PDR F ADOCK 05000423 i PDR _a

U.S. Nuclear R3gulatory Commiccion R33.NUREG-1021/ES-201/ para H.1 Pcge 2 of 2 Please contact Mr. Ron Stotts, Supervisor, Operator Training, Millstone Unit No. 3, with any questions concerning our comments. Yours truly, NORTHEAST NUCLEAR ENERGY COMPANY-IW1 Stephen E. Scace Station Superintendent Millstone Nuclear Power Station SES/RFM:jas

Attachment:

Reactor Operator and Senior Reactor-Operator E.am Comments and applicable references cc: S. Collins, Branch Chief, Region I. R. Temps, Operator Licensing Branch, Region I B. W. Ruth, Manager Operator Training

j REACTOR OPERATOR EXAM 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS l 2.07 Agreed to change the Waste Neutralization Sump Monitor - j Condensate Polishing Facility automatic action from ) " Auxiliary Condensate is diverted to the aerated drains" to " Discharge of sump contents is terminated" (Reference, OP 3336D, Rev 1, Pg 43 Section 8.9) ) 2.07 Agreed to include an additional acceptable answer j stating " Auxiliary Condensate Monitor: Diverts Auxiliary Building auxiliary condensate to the Auxiliary Building Sump" (Reference, P& ID EM-135C Area M6) 2.09 Agreed to change part 2. of this answer from " Unblocks the low pressure SI signal" to " Unblocks steamline low pressure SI and blocks main steam line isolation on high steam pressure rate of change" (Reference, Westinghouse MP3 Functional Diagrams (Logics] Sheets 6 & 7) 3. INSTRUMENTS AND CONTROLS 3.05 Agreed to add "(CS)" as amplifying information to part

1. of this answer 3.05 Agreed to add "(Rod Control /C-16 selectable)" as amplifying information to part 3. of this answer 3.05 Agreed to include an additional acceptable answer stating " Steam dumps (Tref) 1 ad reject controller" (Reference, NSSS Vol.

5, I&C Failures, pg 35 section 6.1) 3.07.a Agreed to change answer from "T " to "T " (Reference, c H NSSS Vol. 4, PZR press and level, pg 14)

SENIOR REACTOR OPERATOR EXAM n 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS AND THERMODYNAMICS L 5.03 Agreed to grade this question on a case by case basis depending on assumptions made by the examinee l 6. PLANT SYSTEM 3 DESIGN, CONTROL AND INSTRUMENTATION 6.10 Agreed to change the Waste Neutralization Sump Monitor - Condensate Polishing Facility automatic action from " Auxiliary Condensate is diverted to the aerated drains" to " Discharge of sump contents is terminated" (Reference, OP 33367D, Rev 1, pg 43 Section 8.9) 6.10 Agreed to include an additional acceptable answer stating " Auxiliary Condensate Monitor: Diverts Auxiliary Building auxiliary condensate to the Auxiliary Building Sump" (Reference, P& ID EM-135C Area M6) 8. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 8.09.b. Agreed to take into consideration the fact that the knowledge required to answer this question is not required knowledge per the 1987 Requalification Objectives. Millstor.e Unit 3 Technical Specification required memorization policies do not include 6 hour action statements. (Reference, 1987 Licensed Operator Requalification Objectives pg 18, and Ron Stotts letter OT3-87-030, to K. L. Burton, dated February 25, 1987) (

OP 3336D Page 43 Rev. 1 m y [ Subsequent u 1. . Notify th'e Chemistry Department.- 2. When the Chemistry Department has completed sampling Waste Neutralization Sump 3CND-TK11, remove it from recirculation as'.per Section 7.1 step 7.1.5. 8.9 WASTE NEUT SUMP DIS RADIATION HI CDX 2-4 Initiating Device S_etpoint 3CND-RIYO7 Sample.t 2X Background / Analysis Action Auto 1. Waste Neutralization Sump to Circulating Water Discharge Tunnel 3CND-A0V245 CLOSES. Initial 1. If Waste Neutralization Sump 3CND-TK10 (3CND-TK11) I contents-are being pumped to the Circulating Water Discharge Tunnel:- ( a. OPEN Tank 10 (Tank 11) Waste Neutralization Sump Recirculation 3CND-A0V298A (3CND-A0V298B).at CDX b. CLOSE Tank 10 (Tank 11) Waste Neutralization Sump Discharge 3CND-A0V244A (3CND-A0V244B) at CDX. c. Note the final reading on Waste Neutralization Sump Discharge Flow Quantity Indicator 3CND-FQI246 (CDX) Subsequent v 1. Notify the Chemistry Department 2. When the Chemistry Department has completed sampling Waste f Neutralization Sump 3CND-TK10 (3CND-TK11) if it was previously lined up for pumping the contents to the f _,q Circulating Water Discharge Tunnel, either [ a. Restore the lineup to the Circulating Water Tunnel if ' radiation levels are within specification as per Section 7.1 step 7.1.2. b. Pump.the contents'to the Regenerant Evaporator Feed [ . Tanks as per Section 7.1 step 7.1.2 s __.__.___.___._C

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7 i 8 n i t4 S S S Voi.15, It C Foldore s I i,. R :.(a : E 7 6~.1 PT 505 consider.first channel 505. _The: output from PT 505 is used'to perform the following functions: ~ o Block automatic rod withdrawal when PT 505 senses that ' percent. turbine. load has dropped below 15 percent-(if selected by PS 505Z switch on MB7) o. 'Sent to,the reactor protection system to develop the'P-13 7 signal. If both PT 505 and PT'506 sense that percent I turbine load is be' low 10 percent, a signal is sent to P-7. (along withithe 3 of 4 PR < P-10).to block the "at power" t rips ~. o . Generate-a reference temperature signali-Tref,2 (if selected by PS 505Z switch on MB7) for usage by the automatic' rod-control' system, temperature error circuit (Tref-Tavg) o Generate.a reference temperature signal, Tref, for usage in {E the steam dump system. o Be compared to auctioneered high nuclear power for use in the automatic rod control rate of change of power mismatch circuit (if selected by PS 505Z switch on Mb7) 6.1.1. PT 505 Instrument Failure High Consider first a high failure of PT 505. PT 505 provides an input to the Tref circuit for use in both the rod control and steam dump systems. The Tref c3reuit, however, is designed with a high limit on its output of 587 F - regardless of the magnitude of PT~505 impulse pressure. With the reactor plant already at 100-percent power, the rod control system should be maintair.ing auctioneered high Tavg very close to 587 F. Thus, no error ,/- s j i

~ h k6$$ Mol. k > hM kfCSI BVB LE switches associated with the PORVs and block valves, there are two " arm / block"' switches, train A and train B, on MB4. The switches are in the " block" position during normal operating v conditions and are placed in " arm"'when the plant is cooled down. The redundant' train A and train B pressure protection circuits identical; only the source of their pressure and temperature are ~ inputs dif fer. [ Temperature signals from each of the four hot leg { wide-range RTDs' (TE 413A, 423A, 433A, and 443A) are compared. f The lowest temperature is-auctioneered out and used for train A actuation of PCV 455A; the lowest reading cold leg RTD (TE 413B, 423B, 433B, 4438) passes through a similar auctioneering unit and is used for train B actuation of PCV 456. The two auctioneered outputs enter their own programming circuits. The programmers purpose is to develop a PORV pressure actuation setpoint as a function of RCS input temperature. Because of the nature of the brittle fracture phenomenon, the protection setpoint automatically lowers as wide-range temperature lowers. The .1 characteristics of the pressure versus temperature program are directly related to the analyzed vessel fracture limitations. Actual reactor coolant system pressure, as measured by the wide-range transmitter PT 405 and wide-range transmitter PT 403 for train A and train B respectively, is compared to the programmed setpoint. As actual plant pressure rises, indicating that an unsafe condition is being approached, the following cold overpressure system events occur: when pressure comes to within approximately 30 psi of the o current protection setpoint, a control board alarm alerts the operator to find-and correct the scurce of the problem. o when pressure reaches the setpoint, the " armed" PORVs open ] and relieve to the pressurizer relief tank. The cold overpressurization protection system is placed in service on a plant cooldown. The train A and train B " arm / block" -~ switches are selected to " arm". During heatup, the system is I.______-____-__L

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i1 . 12aZ_LIGENSgg_9EEB6T9B BE996 LIE 196I19N_QBJggI1Ygg r t C-3A2A List the requirements for. accumulator operabi11ty and state ~ whether one -inoperable accumulator involves a -one hour action statement (Modes 1,- 2, 8 3). -C-3A2B Describe the actions required for one accumulator inoperable- 'due to'the. isolation valve being closed (Modes 1, 2, a 3). .C-3A3 State whether the-accumulator isolation valves have Tech. Specs associated with their thermal overload protection -i devices. C-3A4 Describe the requirements for accumulator isolation valve A.C. circuit operability inside containment and state whether noncompliance involves a one hour action-statement (Modes 1, 2, 3-8 4). .1

C-3ASA.

Describe-the minimum shift crew composition requirements for all modes of operation and include any exceptions or provisions to these requirements. .C-3A5B l Deucribe the action required for noncompliance with the minimum shift crew composition Tech Spec. 18 Page: 18 of 75 I i .__----_-_---------A

,.O e NORTHEAST UTILITIES S 1 =Cf07. ' *,=%~ g ..........u._ L J % $ 0 "0 0 0 0 ~. February 25, 1987 OT3-87-030 l TO: Ken Burton 'MP3 0 ra pervisor av~ FROM: Ron Stotts MP3 Training Supervisor

SUBJECT:

Application of Tech Specs Objectives Attached are the general objectives for Tech Specs knowledge as approved by TPCC in September '86. You and I discussed as early as 1984 the expectations of station management in terms of required operator knowledge of Tech Specs. I recommend that we revisit this important area, and that Licensed Operators should achieve the following minimum level of Tech Specs understanding: 1) Know what items / components are covered by some U 3 or another (e.g., if a name, a system, or component, the student must recognize that there is something in Tech Specs about it) 2) Be able to locate anything in Tech Specs in a minimal amount of time (I suggest 5 minutes to look anything up, read it, and tell me what is required) 3) Operators should commit to memory any action required by Tech Specs that the time frame for initiating action precludes looking it up in the book. While this last item may appear to be associated with #2 (above), the issue is not readily disposed. The time frame for demonstrating the ability to use and interpret the Specs assumes that this is the only task required, no other concurrent duties. For this reason, I believe we must arrive at auidance for Item #3 by one of the these two methodst analyze situations that could lead to entry of each a. LCO action and determine whether or not there is sufficient time to allow referer.ce to the book prior to taking action, or OS'O REV 3 83 BN1

~,. Application of Tech Spec Objectives OT3-87-030 February 25, 1987 Pcge 2 of 2 j b. Assign a general cut-off time (as we have traditionally done) within which we assume that reference to Tech Specs would not be convenient.for-l any situation. To date, we have established this time to be less than one hour. I believe we should implement the method of the generali' cut-off time, and perhaps devote attention to the otherigore detailed approach at a later date. If this is acceptable, I further proposa the following modification to our existI~ng criteria: 1) Operators with RO licenses should not be authorized to (or responsible for) take actions directed by Tech Specs from memory without direction by the SRO in the control room (i.'., SCO or SS). For those required actions that ar. "immediate", the RO should probably have a good understanding of what the SRO will be directing to be done; hence, to ensure our graduates of initial training have this solid base, they should be required to memorize action statements of 15 minutes or less. 2) . Operators with Senior Reactor Operator licensep should commit to memory) as we had previously defined, actions to be taken in less than 1 hour.f i If you concur with this proposal, I will initiate the j required changes to our existing Tech Specs learning i objectives and present them for our joint approval as soon as possible. RGS/ tap c: R. Martin M. Moehlmann File 4.3.2.4 l

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