Text

Exam Rept 50-309/85-37 on 851210-12.Exam Results:Five Senior Reactor Operator Upgrade Candidates Passed Written,Simulator & Oral Exams
	ML20151U009
Person / Time
Site:	Maine Yankee
Issue date:	01/30/1986
From:	Dudley N, Keller R, Kister H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20151T664	List: IR 05000309/1985037; ML20151T660;
References
	50-309-85-37, NUDOCS 8602100434
	Download: ML20151U009 (43)
	v • d • e

{{#Wiki_filter:T'

 .
..
.

U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 50-309/85-37 (OL) FACILITY DOCKET NO. 50-309 FACILITY LICENSE NO. OPR-36 LICENSEE: Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 FACILITY: Maine Yankee EXAMINATION DATES: December 10-12,_1985 CHIEF EXAMINERi / W/f /- D ~ 8 h Noel Dudley, Lead Re ' Engineer Date REVIEWED BY: /[3d d

 ' Robert . Keller, CfPff, Projects Section 1C - Date

_ APPROVED BY: k Harry B. KisfJr, Chief,( I Date ' Ifo Projects Branch No. 1 SUMMARY: Written Simulator, and Oral Examinations were administered to five Senior Reactor Operator (SRO) upgrade candidates. All candidates passed and five SR0 licenses were issue , A G

-

.
.

REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS: l SR0 l l Pass / Fail l l l l l l l Written Examl 5/0 l l l l l l l l Oral Exam .I 5/0 I l l- 1 I I I l Simulator Examl 5/0 l I l l I I I Overall l 5/0 l i I I CHIEF EXAMINER AT SITE: N. Dudley, NRC OTH'ER EXAMINER: G. Streier, EG&G Summary of generic strengths or deficiences noted on simulator examinations: Curves posted on the simulator control panel are not controlled. During the first scenario the shift supervisor had to request the replacement of one set of curve On two occasions the candidates operated the simulator outside of written procedures. On a major steam leak inside containment, the shift super-visor ordered the Power Operated Relief Valve (PORV) to be used to reduce primary pressure. There was no approved procedure for this recovery technique. Also, during the restoration of off-site power, following a loss of off-site power, the candidates relied on their training since they were. unable to find a procedure to perform this recovery evolutio _ _ _ _ _ _ _ _ __

.
. 3 4. Summary of generic strengths or deficiencies noted during facility review of~the examination:

During the examination review the facility noted that allowance for critical operations up to 10P. power with no reactor coolant pumps is contained in the Technical Specifications, but is not an approved mode of operation. Also, the facility noted that the Technical Specification exception is irrelevant and never expected to be used agai The facility noted that the candidates had been informed of a letter from Byron Jackson indicating that extended operations of a backstop and lift pump is not an operational problem. However, a precaution in Procedure 1-10-7, warns against operating the backstop and lift pump more than 5 minutes to avoid foamin These items indicated a discontinuity between training and written procedural guidance. This issue was addressed by the licensee during the exit intervie . Personnel present at Exit Interview: NRC Personnel N. Dudley, lead Reactor Engineer (Examiner) NRC Contractor Personnel G. Streier, EG&G Facility Personnel J. Frothingham, Manager, Operations Department R. Bickford, Operations Training Section Head R. Nelson, Nuclear Safety Section Head M.' Evringham, Supervisor, Operator Training Group M. Swartz, Supervisor, Simulator Group

    '
      '

J. Sanoski, Senior Operations Instructor 6. Summary of Comments made at exit interview: The NRC summarized the number and types of examinations administere The NRC stated that no serious problems had occurred during the simulator examination, however, the simulator instructor was concerned that a pre-viously experienced simulator abnormality might interrupt the examinatio The NRC noted that it is the responsibility of the' licensee to maintain the plant specific simulator as close as possible to the Main Control Room and to assure the fidelity of simulator response.

L

. . 4 The NRC questioned the licensee's position on maintaining procedural and Technical Specification limitations, which are no longer required, and the training conducted on these limitations. The two items noted during the facility examination review were used as example l The licensee responded that it is their policy to keep their procedures and Technical Specifications free from extraneous or inaccurate informa-tion. There is a mechanism for identifying minor discrepancies with the Technical Specifications which would result in the correction of the dis-crepancies in the next Technical Specification Revision Request. Speci-fically, the licensee committed to review the applicability and need for the exception to Technical Specification 3.3.A.2. Also, the clarification was made that even though a report from Byron Jackson was received which indicated a reduced concern for foaming in the backstop and lift pumps, the limitation will be maintained in the procedure and appropriate train-ing conducted to ensure compliance with the limitatio The NRC noted that during the simulator examination the candidates were operating outside procedures and relying on their trainin The NRC stated that it was understood that the Emergency Procedures were under-going changes and that the operators were going through a transitional period, however, the licensee should be sensitive to operators developing a feeling that it is acceptable to routinely operate outside of emergency procedure The licensee stated that operators were not being trained to operate outside of procedures. Specifically, the procedure for reducing primary pressure with the PORV had been written and reviewed, and was waiting final approva . Changes made to written exam during examination review: All facility comments contained in Attachment 2 were considered during grading of the examination, however, not all comments resulted in a change to the examination or answer ke Question N Change Reason 5.01 Change "PCM" to " PPM". Corrects units for boron concentratio .12 Delete " Unit I". Makes question plant specifi .0l Delet Candidates are not responsible for memorizing specific plant setpoints which are not safety relate _.

. . 5 Question No. Change Reason 7.03 Delet Question is ambiguous since it is not clear that a definition of Technical Overexposur is require .01 Change to "3 (remains According to Maine unchanged)". Yankee Technical Specifications definition, shutdown margin would not chang .02 Change to " Lower Securing a reactor cool-(Due to lost pump ant pump would cause heat)". reactor coolant temper-ature to decrease adding positive reactivit .02c Add "(Lower if Allows credit for alter-MTC is positive)". nate answer if assumption is made that MTC is positiv .02e Add "(Higher if MTC Allows credit for alter-is positive)". nate answer if assump-tion is made that MTC is positiv .11b Change to "Subcooling Specific value for established". amount of subcooling is not required for full credi .11e Change to "PZR level Specific value for trending with charging / pressurizer level is letdown". not required for full credi .01 Add "(4 hour per Either battery amp-bus accepted)". hour ratings or FSAR design criteria are acceptabl _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . . 6 Question N Change Reason 6.03b Change " seal water Clarifies the loca-outlet temperature to tion of the temper-

 " seal' water HX outlet ature reading, temperature".

6.03c Change " Aux PZR spray" Modifies answer to to " fill header". . reflect discharge paths specified in IAW E0P-2-70-5

   " Emergency Bora-tion".

6.09 Add "CIS 2/3" and change Corrects logic of CSAS logic to "2/3". Engineering Safety Feature logi .02 Add "4. From ASP, shut Expands answer key-seal return MOV's; to include other RCS Drain OR-A-6". objectives of an operator during a fire in the Protetted Cable Vaul .06 Add "(also accept Expands answer key to EFCV's)". include another valve which should be checked if steam generator-pressure is lo .07b Add " 10'F". Expands answer key 8.10a Add "(no, with correct Accepts other than the reference to RCP limits answer contained in the

in OP-1-1)". Technical Specifications 8.10b Add "two PORV's required Expands answer key to for LTOP considerations", accept answers for PORV operations under LTOP condition .13 Change to " Notify Plant Allows wider range of Engineering Department". acceptable answer Attachments: Written Examination and Answer Key (SRO) Facility Comments on Written Examinations

*
'
 ,' *

lYrrRGbrncn Y /

.
.

U. 5. NUCLEAR REGULATORY COMMISSION SEtIIOR REACTOR OPE R ATOP. L ICENS E EXAMINATION FACILITY _d&lut_163dEE____________ PEACTOR TYPE _ EAR-CE _________________ DATE A DM IN I S T E R E D t _22412 /10__ ______________ EXAM!ilE _SIREltEA_G4.____________ l APPLICANT! __ ()h.$_~[_k_I3___________ IUSIEUCIIQU1_IQ_aEELICAS11 Uso separate paper for the answers. Wr i te 'an swers on one side onl Staple question sheet on top of the answer sheet Points for each quOstion are Indicated in perentheses after the question. The passing grade requires at least 707 In sach category and a final grade of at least 80 Examination paper s will be picked up six (6) hours after the examinati.on start * OF , CATEGORY ?. OF APPLICANT'S CATEGOP.Y !__MALUE. _IDIAL ___SCOEE___ _ Ya L U E _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ C alL G uil _ _ _ _ _ _ _ __ _ _ _ 25.69 _Zis00__ _&trQ& ___________ ________ THEORY Uf flUCL E AR POWER PLANT OPER A TION, FLUIDS, A t40 Tile P MOD Y N A N I C S 24.oo 24 6 R _t2I29._ _ftr29 ___________ ________ PL APli S YS T E *15 DE S IGil, CONTROL, AllD IN S TRUMENT ATI0rl at. so 29.10 _&kr2ft__ _f2TUU ___________ ________ PROCEDUNES - NORMAL, A B il 3 R N A L , E N E P.G E N C Y AND RADIOLOGICAL C0flTROL 2 s. L 4 _22cQ2__ _&2r22 ___________ ________ ADMIN IS TR A T IVE PROCEDURES, CONDITIONS, AND LIMITATIONS , 91.E '192x2C__ 100aQQ ___________ ________ T3TALS FIllAL GRADE _________________7 All cork done on this examination is ny own. I have neither given nor received ai ___________________________________ APPLICANT'S SIGNATURE l l l

-

-
.

.

-
 .
 '

12__IUEUE1_QE_UUCLEA&_EDMER_ELA3I_DEEEal10Ut_ELul01t_43Q PAGE 2 IUEEdQQldad1C1 QUESTIUN 5.01 (1.00)

uith the plant operating at 855 power and a i systems in a nor7al configurations the operator bor a tes 100 Shutdown mar gin will ... 90 (1 0)

1. Increas . Decreas . Remains unchange QUESTION 5.02 (2.50) Coapare the C ALCULATED Estimatad Critical Position (ECP) for a startup to be performed 4 hours after a trip from 1000 ponar, to the ACTUAL centrol rod posi t ion (ACP)s if the following event s/condi tions occurre Considor each independently. Limit your answer to ACP is HIGHE4 than, LOWER thans or SAME as the EC c. Une reactor coolant purp is stcpped two minutes prior to criticality.(Assume no reactor trip) (0.5) The startup is del ayed until 8 hours after tne tri (0.5) c. The steam Jump pressure setoolnt is increased to a value just below the Steam Generator Saf e ty setpoin (0.5) Condenser vacuum is reduced by 4 incnes of Merc ur (0.5) e. All Stean Generator levels are being raised by 51 as the ACP is reache (0.5) , QUESTION 5.03 (2.00) a. Why is the indication of neutrons important durinJ Col d Shutdown? . (1.0) State four posslote sources of neutr ons in the core durino Cold Shutdow (1.0) l . l QUESTION 5.04 (1.50) State the three basis for maintaining Rod Insertion Limitse, (1 5) l (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) l-

, ,-- _ - _ - - -_-- - _ - - -- - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - _ _ - - _ - - - - - - _ - - - - - - _ - - - _ _ - -

-
.
 -
.
,. ,

34__IUEQdi DE UUCLEA&_EDMER_ELAMI_DEERA110Nt_ELU10Sa_Ah2 PAGE 3 IBEE50Q1B&BICE QUESTION 5.05 (1.00) Wnon the flow rate through a centrifugal pump is increased by Cp3ning the discharge valves the required NPSH _______, and the evallable NPSH ________. (INCPE ASE or DECREASE) (1.0)

w QUESTION 5.06 (1.50) TRUE or FALSE? a. The f aster a centr i f ugal pu ap rotatess the greater the NPSH required to preven t cavitatio (0.5) b. One of the pump laws f or centr if ujal pu mps s t at es that the volumetr ic flow ra te is inversely propor tional to the speed of the pum (0.5) c. Pump runout is the term used to descrioc the condition of a centrifugal pump r unn ing wi th no volonetr ic flow rat (0.9) QUESTION 5.07 ( .50) In order to maintain a 200 F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam cener a tor pres sure mus t be r educed to approximately psig b. . 445 psig psig psi g (0.9)

 (***** C ATEGORY 05 CONTINUED ON NEXT PAGE        *****)

_ _ _ _ _ _ - _ _ _ _ . - _ . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ __ __ _ _ _ ____ _ _ _

. ,' ,

  ,
  .

1.__luEudi_QE_duCLEAE_EDEEE_ELadI DEED &I1Dut_ELUlQSt_ANQ PAGE 4 IUE15021NA51El QUESTION 5.08 (4.00)

c. ish a t ido parameter s can the operator control to prevent pressurized therma l shock? (1.0) b. What is the sequence of events that could lead to pressurized thermal shock conditions? . (2.0) c. Why does the concern about brittle fracture of the r eactor pr essur e vessel Increase as the Maine Yankee plant ages? Include in your answer the specific matcci al property that is affecte (1.0)

  '
  .
  (***** CATEGDPY 05 CONTINUED ON NEXT PAGE   *****)

.

,' .
*
 ,
 .

23__IUE0dI_QE_UUCLEAE_EQWER_ELASI_ DEES &Il08t_ELU10St_AMd pAGE S IBEEddQIdadlCS QUES TI0tl 5 09 (1.50) Ch0ose the correct response to each of the followin (1.b) 1. Moderator temperature coef f icient becomes more negative from BOL to EOL primarily because oft

a. The larger change in resonant escape pr obabili ty per degree' change in moder ator tenperatur b. The l ar ger change in core Icakage per degree change in moderator temperatur c. More thermal neutrons ar e available for absorption in the moderato d. The smaller change in th?rmal utilization factor per degree change in moderator temperatur . Doppler coe f fi cient (pcm/ degree F fuel) becomes more negative from t10L to EOL because o a. An increase in effective fuel temper atur o. Clad creep and fuel pellet swel c. The production of plutonium-24 d. The overlapping of resonant peak . Control rod wortn is greates a. At higher boron concentr a tions b. At higher modcr ator temperatures c. At low boron concentrations d. At lower moderator temperatures QUES TI0l4 5.10 (2.00) a. List two causes of waterhamme (0 8) b. Give two examples of how waterhammer can be minimize (1.2)

 (***** C ATEGORY 05 CONTINUED ON NEXT PAGE *****)

,

.
.
.- .

2a__IBEDS1_DE_UUCLEAd_EDME8_EL&SI_DEElallDUz_ELul01t_ANQ PAGE 6 luEddQQ1UAtIC1 QUESTION $.11 (3.00) For each of the p ar am e te r s listed belows provide the desired indication or trending that would be expected for natural cir culati on cooli ng and what might result if the p ar ameter was not trending as expecte a. Th Subcooling Steam Generator Pressure d. Steam Generator Level o. Pressurizer Level (3.0)

    .-
' QUESTION 5.12 (2.50)
-Thc(U$ EIlbreactor is operating at 507 power, BOL, when a steam dump f all s ope Assume rods are in manual, no operator action is takens and no reactor trip occur Explain HOW and WHY reactor power ~and Tave will chang (2 5)
.

QUESTION 5.13 (2.00) Why is the time to reach a stable count rate after each incremental withdrawal of the contiol rods not a constant? Assume reactor does not reach criticalit (2.0)

   ,
 (***** END OF CATEGORY 05 *****)

a

F-

.
- *
. .

6s__ELaul_SISIE51_DESIGut_CDSIE0Lt_LUL_INSIEudEdlaIIDU PAGE 7 i. o o QUESTION (4 ,4 M -- a..What is I e design length of time the battery banks can supply power to all DC and 120 voit AC vital loads during a complete loss of AC~ power-with both diesel generators inoperable? (1.0) b- %2t ! s the--m-i-ft t ette--OC-v o4t-49 e-t h e t-t-he-i n y e r-t e r1-c s n-r-e 9 u 14 t-e-tc-110 vcM5 AC4 ( 1. 0 h QUESTION 6 02 (2.50) HOW and WHY will the 12 steam dump and turbine bypass sys tem val ves respond if tne system is attempting to main t ain no-load Tave in not shutdown and the tamporature is S35 deg F7 (2.5)

 .-  ..

QUESTION 6.03 (4.00) If the Residual Heat Demoval ( F,H R ) System is lined up to the purification system and the temper atur e out of the RHR heat ' exchanger is above 140 dea F7 kill the demineralizer resin be damaged? Explain your an..seY (1.0) Explain how RCP seal is maintained between 140 deg F and watersupply} 145 deg (8, temperature (1.5) c. What flow path other than through cnarging pu (P-14A, B or S) can be used to emergency b or a te the primar Include TWO (2) poss ib l e sources and TWO (2) oossible discharge point (1.5) QUESTION 6.04 (3.50) a. What will happen if a Backs top and Li f t punp is run for greater than 5 minutes? (.75) What actionss if anys should be taken if the computer alarm

" Thrust Runner Oil Fl ow Minimum" is recei ved after s ta r t ing an RCP7 Explain
 .
       (.75)

c. What conditions must be met in order to operate with two of the lower three seal stages failed? ~(2.0)

    .
 (***** C ATEGORY 06 CONTINUED ON NEXT PAGE *****)

-_

'
,' .
 ,
 .

6*._ELaNI_SISIE51_DESIGut_CDUIEDLt_AUQ_IUSIEUdENIAIION PAGE 8 QUESTION- 6.05 (2.50)

What two parameters are measur ed to provide a turoine trip signal to reactor plant protec tion sy stem (RPS)? Indi c at e the coincidence required and which paraneter is considered the backup signa (2.5)

QUES TION 6.06 (1.50) Explain how the design of the spent fuel stor age r acks will provent criticality even if th e boron concentr a tion is reduced to zer (1.5) QUESTION 6.07 (2.00) .- If the #1 steam generator (S/G) level detectors which supplies an input sign'ai to the level c omp ar ato r portion of'the feedwater con tr o l systers fails LOWS and the plant is at 707 power, steady s ta te : a. expl ain the immediate ef f ec t on #1 S/G leve (1.0) what will be the long term effects on plant operations if no operator action is taken? (1 0)

   .
 (***** C ATEGORY 06 CONTINUED ON NEXT P AGE *****)

-
.
- '

-

. .

ba__ELaul_1111EdS_DESIGut_CD3Il0Lt_aB2_1USIEudENIALIDd PAGE 9 QUESTION 6.08 (3.00) True or False c. The Power Range safety channels use a fission cha.iber for detecting neutron (0.5) The core loading channel uses an uncompens ated ion chas! J 'or detecting neutron (0,5) The wide range indication i s made up of the Campbell Circuit signal and the output of th e countrate circuit at high power level (0.5) The Zero Moce 6ypass distable nper ates contacts below 15 powers to allow oyoassing cer tain reactor trip (0.5)

--

c. Uncompensateo Ion chanbers are b or on-10 lined, n i tr o ge n filled . detectorss operating in the Ionizatson region of the gas amplification curvet (0.5) The power r ange con tr ol channel output gain potentiometers are located in the rear of the core loacing cabine (0.51 QUES TION 6'09

 . (3.00)

If during reactor plant operations at 957 power a feedline ^ rupture were to occur inside the containment, what are the THREE Engineering Safety Features (E SFs ) that could possibly be actuated and wnat signals will cause th es e actuations? Include setpoints and logi (3.0) QUESTION 6.10 (1.00) TRUE or FALSE? Each S af ety Injection Tank nas a flow restricting orifice in its di scharge line which is provided to extend the accumulator blowdown time which in turn reduces the peak fuel cladding temper ature in the event of a LOC (0.5) The design condensing capacity of the quench tank is based on accepting all postulated load rejections with no steam dump system availabilit (0.5)

   .
 (***** END OF CATEGORY 06 *****)
     -

. . .

Is__EEDCEQUEES_:_UDadatt_AB30EdaLt_EdEEGENCI_adQ PAGE 10 EaQ1DLDGICaL_COMIEDL QUESTION 7.01 (3.50) If a Xenon oscillation occurred as a resul t o f a r apid power reduction followed by a return to full powert e. how could the oscillation be dampened? (2.0) what are the upper and lower limits associated wi h gr ou p 5A and B? (1,0) what restriction exists when c on tr o l l i n g on group 5A and 587 (0.5)

OVES TION 7.02 (1.50) In accordance with EOP 2-90-1 (pl ant shutdown plan for fire) when a fire is detected in the Pr otected C able Vaults an operator is dis patched to per form THREE najor objectives. State those THREE major objective (1.5) s. c o QUESTION 7.03 F2 . 50 ) a,--Un4+r-what-T-W0-con d it-E ons c7 o a R 4 d ; a t-+-,eWerher-r-ec e 4-v e-a-

-TEG+WI-gat-OV EREXPOS UR E-?-    (- A b'. What ac is required when a TECHNICAL OVEREXPOSURE has been receive     (1,0)

QUESTION 7.04 (1.50) What TWO peoples by position titles have to approve a loop cntry while oper a ting at power? (1.5) QUES TION 7.05 (2.00) What FOUR criteri a must be met to allow termination of an " unjustified SIAS"? (2.0) i I

 (***** C ATEGORY 07 CONTINUED ON NEXT P AGE *****)

*
-

. .

. .

Za E80CEQuBES_:_UD8delt ABUDEd&LA_EUERGEUC1_AdQ PAGE 11 RAQ1DLDGICAL_CDUIEDL

QUESTION 7.06 (4.00) Wh at F OUP. valves per EOP 2-70-4, must be checked closed if one or more steam generators are less than 400 pseo during a steam line break? (2.0) TRUE or FALSE - a 1. It is possible to damage tn'eJreactor vessel Dy allowing safety injection to continue woen it isn't needed? (1.0) An SIAS must be reset before the atmospheric dump valve can be used? (1.0) QUESTION 7.07 (3.00) ~

,_

a. In accordance with ADP 2-3 (HELB isolation system act lon), what FOUR syst~ ems are involved in the HELB i so l a t ion s che me, (2.08 What t emp er ature in th lower level PAB will caus e a HELS isolat ion actuation? (eInclude the logic require.d). ( 1 0) 00ES TI U;4 7.08 (1.00) During a loss of off-site power why is the auxiliary feedwater not realigned to the first point heaters until the steam generator levels are above 407 narrow range? (1.0) QUESTION 7.09 (4.00) a. What THREE required immediate actions are performed when 11 or core CEA's fall to insert upon receiving a reactor trip signal? (1.5) State FIVE methods that may be use to increase subcooling if it is < 50 F f o l l ow i n g a reactor tri (1.5) c. Wnat TWO actions shall be performed following a Reactor trip if the core exit thermocouples indicate > 800 F? (1.0)

   .
 (***** CATEGDP.Y 07 CONTINUED ON NEXT PAGE *****)

. .

.

. .

I*__EEQCEQuRES_:_uDEdalt_ARGQE5 Alt _EDERGENCI_ANQ PAGE 12 EAQ1DLOGICAL_CD3IEDL

.QdESTION 7.10 (2.00)

The following concern the Waste Gas Release procedure (OP 3-21-3): e. Who prepares the r elease permi t for the gas release? (1.0) Who's permission is required to commence a waste gas release? (1.0)

.
 (***** END OF CATEGORY 07 *****)

. . .
, ,

as__AQ31HISIEAIIEE_EdQCEQUEElt.CQuQ1110GSt AUQ_LI511al103S PAGE 13 QUESTION 8.01 (1.50) Tha inner door of the containment air lock leaks excessivel The plant is at 100% power when a Maintenance Request (MR) to rcpair the gasket is brought to the PS State the ac t ions PSS sh0Jld take and your reasonin (1.5)

 .
-QUESTION- 8.02 (1.50)

For each of the f ollowing si tuati ons shoul d a WHITE tag, YELLOW tag, or NO TAG be used? (1.5)

     ~ Reactor Protection System high pre s sur i ze r pressure channel A is byp asse b. ~Following maintenance on a service water heat exchanger a relief valve.ls blocked in accordance with a bydros tatic test procedur A valve on the service wa te r s ys tem is to De repacke QUESTION 8.03 (2.00)

a. What is'the minimum shift crew composition for a cold shutdown plant according to the Tecnnical Specifications (1.25) How long can the crew composition be below minimum before a Technical Specification violation occurs? (.75) QUESTION 8.04 (2.00) If during a reactor startup, with power at 10 E-10 power, the pressure in two Safety Injecti on Tanks drops to 200 psia, is it permissable to continue raising power? Justify your answe (2.0) l l l

   .
 (***** C ATEGORY 08 CONTINUED ON NEXT PAGE *****)

-
. . .
. ,

Ea__AQUISISIEallVE_EEQCEDUEESt CQUDIIl03St_AUQ_L1311AllGNS PAGE 1 QUESTION 8.05 (1.50) a. How many consecutive hours is an operator permitted to work while meeting the crew staffing requ i remen ts ? (.75) b. How many hours.may that person work in a 4 8-hour per io d? (.75) QUESTION 8.06 (2.00) What are TWO (2) required actions if a Safety Limit is violated according to the Technical Specifications? (2.0) O UE S T10N 8.07 12.50)

...

In accordance with Maine Yankee's OP's Memo 9-E-3, prior to removing a Diesel Generator from service, you must perform a review of five (5) i n f o r.g a t. i on a l items to ensure compliance with . Tech. Specs. What are these five i n f or m a t i on a l i t'e m s ? (2.5)

..

QUESTION- 8.08 (2.00)

For each of the following leak locations, give the maximum leak rate allowable according to the Technical Specification Unknown locatio Through a pr essur izer code safety valve to the Pressurizer Relief Tan Through the wall of the line between the pr essur izer relief valves and the pressurize TOTAL Steam Generator' tube leakag (2.0) >

 (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) . .
- .

34 _ aDuld11IE AIIEE_EdDCEDUEESz_CudQ1Il0GSt_adt_L1111 All0NS PAGE 15 QUESTION 8.09 (2.50) Wh2never the RCS temperature is less than MPT and the RCS is not vcnted, the RCP's may not be s tar ted unless WHAT TWO condi tions oxist? (2.5)

     -
     '

_

      \
      %

QUESTION 8.10 (2.50) 7 c vg r [! /A/ 3 '- Do theinMaine plant Yankee a critical condiTec ti onSpec with noever allowcoolant reactor operation of thessR pumps qP ,Pc z (J operating? Explai (1.5) g N Explain when the Power Goer at ed Pel i e f Valve (s) are required by Tech. Specs. to oe operabl (1.0) _, QUESTION 8.11 (1.50) Explain what each wor d below means when it is used in a Maine Yankee procedur . May Should 3. Shall (1.5) QUESTION- 8.12 (2.00) What are FOUR of the FIVE required conditions necessary to consider the Steam Generators oper le for decay heat removal according to the Maine Yankee Tech. Spec (2.0)

   .
 (*****' CATEGORY 08 CONTINUED ON NEXT PAGE *****) .
-

... . .

, ,

2 __aDdlNISIHAIIME_EBUCEDUEESt_CONDIIl0diz_ABQ_L1511A110NS PAGE 16 QUES TION 8.13 (1.50) During a b ac ks h i f qqro r k is being done to replace and reposition supports for the discharge piping of an HPSI pump. Tne workers cannot find the supports specified in the work package and have determined that it is impossible to ~ install the supports at the required location Tho workers have located some pipe hangers in the shop and want per m i ss i on' t o.. i n s ta l l them as close as possible to the specified location What actions, if any, should the shift supervisor take? Suppor t your answe _m

 .
 (***** END OF CATEGORY 08 *****)
 (************* END @F @XQQRGoFROM ***************D

'
.
\
  .
. .

, h__ INEQ R1_DE_U u L L Ea3_EDh EE_ E La 3I_ DEEE AIIUu t_E L u1DS t_ AU Q PAGE 17-IUE150DidadICS ANSWERS -- MAINE YANKEE -8 5 /12/10-S T R E I E R , ANSWER 5.01 (1.00)

-4-44no+-etse4- 3 ( r e.m *'. n s ecbm (1.0)
     -

REFERENCE C -E Mot-o r-Theo r-y_ m ,n.3anwe tech.spc del.w'.W n ANSWER 5 02 (2.50) a . -G4#E-Lowec (du b ha pump WoA)

       ~ HIGHER  .      . HIGHER (Lue<\4  MTC '5
    *

f * 'n'* M

     ,
       -. SAME  -' '?
 , . u'. n     - - LOWER L--~~ '"  "'. -.  t- (. . : - >[35
    <?
    .

each) (2.5) R E F E R E t4C2 - C-E Reactor Theor y

ANSWER 5 03 (2.00) (Without some neutrons ther e is no instrument indicatio Without instrument indications you do not know core reactivity status or whether the status is changing.) Neutrons are needed to assure thst the reactivity status of the reactor is known and the instrumentation indication is available to guide operator actio (1.0) . Spontaneous fission of fuel 2. Reactor start-up sources 3. Sustainer sources Pho to neutr on s our ces Alpha-Boron reaction 6.' Alpha-D-16 reaction [Any 4 9 0.25 each] (1.0) lie F ERE NCE Gsncr al Physics Vol II chap. 5

-
.
 .
. . .

12__IUEDE1_DE_BUCLEAE_EQWER_ELa3I_DEEEaIl0ut_ELU1QSt_ABQ PAGE 18 IBEEdDuldadlCS ANSWERS -- MAINE YANKEE -95/12/10-STREIER, ANSWER 5.04 (1.50) Ensure that' acceptable power distribution l imi ts ar e maintaine . Ensure that the minimum SDM is naintaine . Limit the potenti al effects of rod m i s al i gnmen t on tne as s oc i a te d accident analyses. (rod ejection) [0.5 each] (1.5) REFERENCE T. S. 3.10 basis ANSWER 5.05 (1.00) Increasess decreases (1.0)

^"

REFERENCE General Physics Heat Transfer and Fluid Flow ANSWER 5 06 (1.50) a. True b.' Fatse c. False [0.5 each) (1.5) REFERENCE Gsneral Physics Heat Transfer and Fluid Flow

' ANSWER 5 07 ( .50) (0.5) REFERENCE ! stoam tables I

. . , . . 2A__IUEDEE_DE_UUCLEAE_E0 HEE _ELASI_DEEEAllDut_ELul0Sz_ABQ PAGE 19 IUERdQQ1UA51CS ANSWERS -- MAINE YANKEE -85/12/10-STREIER, ANSWER 5.08 (4.00) c. Coolant temper atur e [0.5] Coolant pressure [0 5] (1.0)

 ' Rapid cooldown and depressurization [1.0] followed by rapid repressurization [1.0].    (2.0)

c. Neutron exposure (integrated) [0 5 3 makes the material more brittle (raises NDTT) [0.5 (1.0) REFERENCE C-E Lecture Concept of the Fracture Analysis Diagram

   --g  -

ANSWE (1.50) 1.- d C.50] . 2. c [.50] 3. b [.50] 'e (1.5) REFERENCE C-E Reactor Theo r y ANSWER 5.10 (2.00) Valve op er a t i o n, opening or closin; Pump starting or stopping Osci ll at ion of auto control valves (TLo Regu. ired ) (0.8) Slowly opening of valves between voided and full sy s tems Proper venting of components Adequate level on tanks in systems where the tanks provide supply or surge function Proper use of s te a m traps and vents Pr op er sequencing of valves in pressurized systems (lido EetuVEd (1.2)

REFERENCE Nuc lear Ene rgy Tr ai ni n g, Thermodynamics, NET 4-2, pg. 2.1-4,5

'
.
 .
. . .

, 2s__luEQal_QE_uuCLEa8_EDEE8_ELadI_DEEEaI10dz_ELu125t_aMQ PAGE 20 IUEEdQDIULd1CS ANSWERS -- MAINE YA NK E E -85/12/10-STREIER, + ANSWER 5.11 (.3. 0 0 ) s U P I* W

~a. Th stable or decreasing [0.3)    bgw "T ~

-5 Loss of Watural c i r c u l a t i on ..f l o w. [0.3J G F subcooling 5k. d Voiding i n co r e b[ r-nut3 3 leg

   * , At.t:

whi ch would interrupt. flow. [0.3] SG pressure tr acking Tave saturation pressure. [0.31 SG not removing heat. [0.31 d. SG level in Narrow Range [0.31 SG no longer available as heat sink. [0.3] c. PZR Ieve1 5 C '. [0.3] Ped % w h caus % lt,+ b e Voiding of hot leg which would interrupt ficw. [0.3J

,d.-TCT iner ess es-[0.-3-1-becattse-th e cfTO heat-trmns f er-cao ac i ty . i s
   ~
-r-educed- ( i ncr ease t prp e r a tu r e d u e t o l o we r-- c ond u c t i.v. i.t y_o f. c r.u d ).
-EO.43 -       (3.0)

REFERENCE General physics; Heat Transfer Thermodynamics and Fluid Flow fundamentals, . ANSWER 5.12 (2.50)- T ave decr eases s ince more energy is being removed. [0.7) Rx Power increases due to the. positive reactivity added through MTC and doppler. [0.8) Power stabilizes at a higher.value. [0.5J Tave stabilizes at a lower.value. [0.53 (2.5) R G E R E ^) c- T. * c.E h <_ b v- %eg roonuaA ANSWER 5.13 (2.00) With each incremental rod withdrawal, Keff is incr eased towar d a value o f 1.0 The larger the value of Keff the l on g er it will take to reach a new higher neutron. level since more generations will have s i gn i f i canc [2.03 REFERENCE Introduction to Nuclear Engineerings Lamarch, C hap 8, Sec 8.2, p 313 Chao 7, S ec 7.5, p 295-298 Chap 4, Sec 4.1, p 102

'
.
 .
.

6A- ELAHI IXSIEUS_DESIGut_CDMIEDLa_AUQ_luSIEudENIAIIQU PAGE 21 ANSWERS -- MAINE YANKEE -85/12/10-STREIER. .00 ANSW ER 6.01 42.00) a. 8 n o u rfmle ma(9 bucs e,s lou s utopW.1) (1.0) t w lO-5-vo4t= AC 4h0 )- REFERENCE Ch. 33 pgs. 48-49 ANSWER 6.02 (2.50) Dump valves shu Valves do not open until 5 deg F above setpoint (552 deg F ) . C. I . G 2 nypass valves open 3 bypass va! ves r amped open Two groups of bypass v al ves open sequentially on difference in pressure above 900 psi Tave of 535 deo F pr oduces 915 ps i a in SG which will fully open one set of valves and ramp open second set of valves.[i 5] (2.5) REFEkENCE Vol V Cnp. 25 pgs. 8 C 12 and Fig. PSG 14-8 ANSWER 6.03 (4.00) a. Yes. ( Res in is damaged by temperatures above 140F) RHR in terf aces wi th CVCS downstream of neat exchange Bypass valve senses temperature downstream of HX and will not bypass O demineralize ( 1./') 9x The T on condensate discharge line is controlled oy seal w a t e r" 2u t t e_t_ t empe r a t u r e and regulates HX condensate leve Condensate level e f f ects HX heat tr ansf er surfac (1.5) Tnrough aux i l i ar y charging pump RWST, BAST, BAMT (any two) f' charging to Loop 2 or 3 r -Au ; "ZP r p r ay, HPSI header (any two) ( L .,6) c;o A e de v REFERENCE Val I Chp. 4 pg. 39 C 67 and Fig. NS-4-3 _

'
,
 '
. . .

, hi__ELaGI_11SIEd1_DESIGBt_CDUIEDLt AdQ_IUSIdudEMIallOS PAGE 22 ANSWERS -- MAINE YANKEE -85/12/10-STREIER, ANSWER 6.04 (3.50) a. Foaming will d ev e l o p (a ndoil pressure will be lost.) (.75) Co G No action.4When RCD comes up to speed the back stop pump auto shuts down and a low oil pr e s s ure issensea.Eo.35] (.75)

@   lee Lower seal cavity temperature (below 200 deg Seal water return flow temperature (below 200 deg f .) Low 6DIncreased leakage can be handled by CVC ) Seal water supply flow to RCP seals creater (than 5 gpm)above seal water return flo P' # S* 4 **WC (2.01 REFERENCE Proc. # 1-10-7 pgs. 4E8
      .-

ANSWER 6.05 (2.50) af Os Main turbine auto s':op oil p r e s s u r e [ 0. 51(}14.,[ 0. 5 ] . Tur b i ne generator'stop valvas shut [ 0. 5 ] 4/4 (in par ~allel) [0.5]. Valve position i s the backup [0.5]. (2.5)

REFERENCE Chap. 11, pg.22 and Fig. NS-12-9 ANSWER 6 06 (1 50) ,

Storage facility' designed to maintain 20-inch center to center spacing between each assembly and shleided wi th Boral plate (1.5) R E FE etnc t'. ANSWER 6.07 (2.00) FWRV control system will "s e e" a low a/G water level and attempt to recover level [0.5]. #1 S/G water level will raise

~[0.5].      -(1 0) Turbine trip on nigh S/G level (at 917.)   (1.0)

_ _

 -
.
. . .
,

ka__ELANI_11SIEd1_DE11ENt_CDMIEQLt_AH2_lBSIEudEblallDU PAGE 23 ANSWERS -- MAINE YANKEE -85/12/10-STREIER, REFERENCE System description s30 and #25 pg. 22

ANSWER 6.'08 (3.00)

a. False (0.5) b. False (0.5) c. True (0.5) d. False (0.5) e. True (0.5) True (0.5) REFERENCE Excore Instrument s ys t em des cr i p t i on

      -..
      ,.

ANSWER 6.09 (3.00) SIAS [0.5] and CIS [0.5) - High c ontai nment p r essur e [0.3], ,, 5.0 psia [0.~33, 2/4 [0.2) C16 'v2 CSAS [0.5) - High containment pressure C0.3] 20 osig [0.3) 2//3[0.1] (3.0) ~ REFERENCE _

~~

Volume II sect 1, 3 E 4 ANSWER 6.10 (1.00) a. False (.50) False (.50) REFERENCE Chapter 6 pas. 26-28 _

-
.
 .
-
.

22__EEQCEDURES_:_dDEUALt ABUDEL4L4_EdEEGEUC1_a3Q PAGE 24 EAQ10LDGItaL_CDBIEDL ANSWERS -- MAINE YANKEE -85/12/10-STREIER, ANSWER 7.01 (3.50) If the symmetr ic of f set (S/0) is above the upper control line insert rods [0.53 un til the S/D is at the upper control line

[0 5]. As S/0 decreases below the upper control line CO.5]

withdraw rods [0.5 (2.0) steps [0.25] or above PDIL [0.25); ARO [0.5 (1.0) c. Ma in ti an subgroups SA and 50 within 3 s teps of each othe (0. 5 ). REFERENCE Procedure 1-8-1 ANSWER 7.02 (1.50) (3hyd<cs) Remove. power from the p0RV's Man the Alternate S hu tdown P a n e l (ftS P') Start Di ese l G ener a tor #2 (1.5)

*i . From A SP~ shi seaA reb.% maid  5. R C S b m h M 'l'
-PEFEKENCE E0P 2-90-1 1. 0 ANSUER 7.03 (-3,-54 a l._W herua n-i ndhr Fdua t r'ec el'res-ex t'er na l-r-etf Fa ti-o n-ex po sure-t r-e xces s-o f-r e7utTro rrt inri tr-i n any-cel-ender-quar _ter [ 0. 7 5 jn 2 Wnen-en-indbritua-i is exposed Io a i r o o r n e- rs dFonet14e- mat er-i-e I-4n-emces s o-f i e y JtTr0 r y IImIts (B77t h   6-1 s+}

l h(' Th e individual shall be r emoved from further exposure during the remainder of the applicable perio (1.0) REFERENCE Radiation Protection manual pg. 2-6 l l' l

     -
  -    -
,
 -
.
  *
. .. .
,

Ic__EaQCEDURE3_=_UDEdaLA_aBUQEdakt_EdEEGEUC1_aUD PAGE 25 BADIDLOGICAL_CDUIRQL ANSWERS -- NAINE YANKEE -8 5 /12/10- S TR EI ER s ANSWER 7.04 (1.50) 1. Plant Manager 2. Radi ol ogica l Contro ls secti on hea (1.5) REFERENCE Radiation Protection manual pg. 2-9 ANSdER 7.05 (2.00) 1. RCS subcooling >50 F Pzr. level >SO 7 3. One S/G at least lgp" WR <- - SIAS no longer required to maintain Pzr level o r p r e s s'U r e . (2.01 RE F E R E N.C E E0P 2-70-3 pg. 2 ANSWER 7.06 (4.00) ,, . Feed reg valve Bypass feed reg valve Aux feed reg valve

 ' Aux feed isolation valve [0.5 each)   (2.0)

Cans acca p + a ve v'13 . True (1.0) True (1.0) REFERENCE EDP 2-70-4 pg. 1-2 .

 +
*e
**

_

"' ; ~ . - --
- *

-
.
 -
. .
.

, Zs__ERQCEQuRES_=_BDEd&Lt_ABUQ2dalt_EdElGENC1_aBQ PAGE- 26 SADIDLDGICAL_CDUIEDL ANSWERS ---MAINE YANKEE -8 5 /12 /10-S TR E I ER , ANSWER 7.07 (3.00) . S/G blowdown Letdown system Aux steam to PAB

.. Aux steam to spr ay building    (2.0)
 " 'Ds 75 ] s 2_ ou t of 2 logic [0.25]   (1.0)

flO*F REFERENCE AOP 2-3 p2 1

..

enes ANSWER 7.08 (1.00) To prevent thermal stress [0.51 and water hammer to the feedring

[0.5].      (1.0)

REFERENCE E0P 2-70-9 pg. 1

    .-
      ..

ANSWER 7.09 -(4.00) a. 1. Open mg set output bre ak er s Emergency berate Reenergize CEDM's and dr i v e roos (1.5) . Increase chargi ng/r educe letdown 2. Prevent unnecessary heatup 3. Energi ze heater s when level > 28 . Reduce spray 5. Isolate PORV .. 6. Initiate SIAS [3ny five 9 0.3 eacn] (1.5) . Ini ti ate SI AS Open PORV's and PORV's block valves (1.0) REFERENCE EOP 2-70-0

*
.
-  .
.

' Is__ EEQC EQuRE1'_=_d Dad &LA_aShl0 R5 &L t_EHERGENC1_ A NQ  PAGE 27 R&Q1DLOGICAL_CDMIEQL ANSWERS -- MAINE YANKEE  -85/12/10-STREIER, ANSWER 7.10 (2.00)

a. Chemistry department (1,o)

-b. .The PSS     (1,o)

i REFERENCE OP 1-21-3 pgs. 1-3

fY ,

     '*w f
    .

.-
,
 .

.

-
     !

Ha__AQd1HISIEAIIVE_EEQCEQUEElt_CONDIIl0 Ult ANQ_LidlI&llDUS PAGE 28 ANSWERS -- MAltlE YANKEE -8 5 /12 /10-STR EI ER , ANSWER 8.01 (1.50) Do not en te r a i r- lock for repair Entry to air lock would violate Tech Spec cont ainment requirement (Walt until SD or enter through escape hatch) (1.5) REFERENCE T..S. 3-11-A ANSWER 8.02 (1.50) a. No tag Yellow tag c. White tag (0.5 each) ,f (1.5) REFERENCE Proc 16-1, Cps meno 9-E-8 A NS tJ ER 8.03 (2.00) a. 1 SQL 1 OL 1 Non Licensed (1.25) hr (.75) REFERENCE T. S. Table 5.2-1 ANSWER 8.04 (2.00) No., cannot change-modes with reliance on remedial a ct i on s .

(Can commence power escalation af ter SIT pressure is restored) (2.0)

REFERENCE T. S. 3-0 pg. 1

.
..

a

.
. .-
~Rs__ AQuid1SIE AIIEE_ESQCEDUEES t_CDd u1110dS t_ AdQ_ L1311& IlQd3 PAGE 29 ANSWERS -- MAINE-YANKEE  -85/12/10-STREIER, ANSWER d.05 (1.50) hours     (.75) hours     (.75)

R EF ER EllCE Proc. 1-201-3 pg. 1 ANSWER 8.06 (2.00) The facility shall be placed in at least a hot shutdown concition within one hou (1.0) Ga.6 3 The NRC shall.be notified as expeditiously as possibles4but within 24 hour Ops shall not be resumed antil au th o r i zed by the commission]. (1.0)

  (0.W]

REFERENCE T. S. 2.0 pg. 1 , wgy:* ANSWER 6.07- (2.50) 1.-White tag book Yellow tag book ECCS s ta tus bo ard Shift turnover Control room log b o ok [0.5 each] (2 5) REFERENCE Ops memo 9-E-3

 ., . . . - - - .-- ._ . - _ _ .

r

-
.
 -
 .
,
. ..

E4__AQ51d11IEAIIME_EEQCEDUEElz_CONDII10 Nit _AUQ_L1511AI1081 PAGE 30 ANSWERS -- MAINE YANKEE -85/12/10-STREIER, ANSWER 8.08 (2.00) ypm [0.5] gpm [0.5) O gpm [0.5] gpm [0.5] (2.0) REFEREllCE Technical Specification 3.14 ANSWER 8.09 (2.50)

-a. Pressurizer level is <807 [1.25] S/G Temperature is <100 F a bo-v e RC S temp. [1 25]  (2.5)

R EF EP. ENC E Maine Yankae T.S. ANSWER 8.10 (2.50) a. Yes E0.75]- During initial te ting to permit power lev els not to exceed 107 of rated powers natural circulation is permitte [0.75].4 v;g 4ce,g no, w 4 gyee,y u4,.<cwee 4o Re? L td.h Wo9-8-h(l . 5 )

  - At least one PORV is requ ir ed operable whenever RCS temp >210 (1.0)
[Two Ford's op;<< d for 'T * " ^I'6"'O'"5 3
 ' " "' '

REFERENCE Naine Yankee T.S. pg. 3.3-1

TL ,

.
 .
 -
,
..- -

as__&QB181EIEAIIEE_EEDCEDUEESt_CD3DIllDUEt_auQ_ Lid 11allDUS PAGE 31 ANSWERS -- M AIN E YANK E E -85/12/10-STREIER, ANSWER 8 11 (1.50) Denotes permission 2. Denotes a recommendatio,n 3. Denotes a requirement (1.5) REFERENCE Proc. 0-06-1 pg. 1 ANSWER 8.12 (2.00) ~ RCS pr ess. - 100 ps i > saturation pres ~2. Tc & Th stop vavles open 3. S/G water level above the top of the tube bundle 4. Inventory of > 100,000 gallons of primary grade feedwater 5. Feed pump available C4 a 0.5 each] (2.0)

REFERENCE T. S. 3.8-9 "- -

     -
  -  .. _

ANSWER 8.13 (1 50) In +3a e a Repair n c.de r-e nd-for-.44 r d t e the Pl ant Engineer ing Department [0.6] Job cannot be handled as On-the-S pot C hanges . [0.9] (1.5) REFERENCE Proc. 0-07-4

f

% *

j pg D 09 l*V I '

       ,. ( r.J. d, G M)

g g,, -l ,y

 .
 , . _ .       . . . ..-   . _ . _ . ~ , . _  . -  . - , . -  - - . . . .  . - - - -  - - - - - . . - - . - - . , - _ _ _ , . . . , _ ,
   ,.-,--.4ww   w-----   e--  -   -e*   -w--     .- A--  -'w' 3, aw -'**v,=.,
                          ==4e--ewe . usa,m,e4e
- . . _.---.     -- . _ - _ - - _ . - _ _ - - -          --     - .-.  .._ .   -  -
                             ..-

ew .- . ex *,.-me . , _ -. .

  -_    _  _-       . . - -    .  -_     . - .    - -
  .=m..pisse-  .--i.-.se.h=ma-   wem9..ah-N* - _ - -    m- - - - -  w==e.m-+-=+--me =* -*-  .-g*   -g---- -  * - - a ghw~++T eM - * Ave   eensh*e- p aru-m..-e.

N= -$- .mJu o .e.,a-- * - .-.-, . -- - -- -- - - - ==w - ---,- - -,' ---- ~, - . - ___ _._ _ ____ _ _ _ _ _ _ _ _ _ _ . . _ _ _ __ . _ . . , _ _ . _ _ . _ _ _ _ . _

  -.-==mma.-=8=     , , * . o  .   ,,   _  ,,    , ,  , , ,  ,g,

_ _ _ . . Alkup Mu 6ks._ skoolA cs ue_sktcw his.Dcqu\oa-% _Johec6 Anw %_ . _ty. cm , A_is_ . c _. _ _ . _ . _ . _ _ poh Aeksbet .b_nuoihA wikb 3Rc_ _ ___ m6wct\i u.cm xuiu.o 3 -_ c w%ce r.b. s.1 _ _ _ . - - - - _ _ - - _ _ _ . - . - - _ - . _ - --_- . >-88*8"* =e wh -.-ga..-w-mm... .# . , -e m , , , , , , , , ,, ,_.,.,._ _ , _ , , 3_ k o *_o_ _ o m s w .s a - w W\ McL+ 3. Ae_ph.i w p _ _ .

   - . _ .-.._twy%6bs  o pcw1       . a.ss um        M T c_ . _ Ca.w _ _ _
  -_Cposh _ at_.m_pkt cw_03             . B oz_ .. __

- _ ___

                -
                      .-- _-. _ __
 :L11_EA . hoh+c.d.mptucwAs           ydbicd\h    o 9 Ici ko
                            '

b .- _ - . - ._- _ _ - -. - - . . . - - o- - - , - - - - - . , . -.-- . #.,--- . - - - = -me -*sa __ decgv.s.s_s. . s o\o co o\ t w ptco o ih e_3.pO ---=* -+----* = _s Acco\t % wit 6_ A y shA cm . che.s.a., . Sce 6s _%_ hss Q . Cowc_ch uus _ __- sA c o.t L b _ a w N = s & coc h c3 _s k o i .e.% h _psok - _ _ _ . _ __3cbMct\_+.tsoWcmk. A s obceouwp.M4v4. a k_ _

 --     cac>o_\ L Wa ._ \os s       c& And-vraI c n ec olad-i cw           -m  -
 - . - - - -      _ - - _ -     . - - - -       - . . - , - . _ - -        --_-

beimund ee.neos.mm o we ,g- aw...-*a-.-+-* . .- + . . m - -- > -- -- = a---a-m ._ta.,xSL h mLmatc.ucelakha_ ___ _.._ - __. _._ U wsSL m .c q 6___.o W - h u twhtec N . . _ - __- -._ n s n hy.kcavMs c,x x Man p L . _ . _ - _ _ _ > A40rcJ ccccolab cx Lem.cl m__ _ _ _ _ ._ _ _ _ 6# _a h _ ct du 0 4ila r-g bi ^l4b . eu.s a s obeau wc3 ._Co _ .__ ms pe% u sbd k WA _ ht. bwd. _i s hltwe _ _. _ .. _ cotw u_M.y h c b y g [tal heu.~ cwa 9 6y _ _ _

      - catte AA         ut st .        -_ . F e
.
.. .
<.. '
                              .

g_

  ~
     ,  _   ... . _ _ Ct   hh(   ._OMb b    ._bo   ~bs      -

- - _ . - .-- . - - - - - _ - O_-. m u

    .    .-      -        .  . .  .
                           . .
        - sawatt,_A m s_._ _ - . . .

_ - - . _ - - . -

            --- -       - - - - - - - - - . - - _ -

eem.m.y- - .m -=m W4 .e- w .w.a, .gm- . .

                         -
                         .,a.mmaa4-- ,..-a s aka s    ts-. m.a.m eqL, m r c -@           86 L 3 s'o3o -pc ww ___         __ _ _

xp. . As-.Q. .hLA rc isscu .- ---.. .

      - -- - _.- ._ _ .-_ - - _ - -            --.   ---_ -- --      _. - .-

__ _ ew .w--er.e,.e .m .-.ee-w,...-w-- . . =--4 .-m.,,e.o.-- ., * - - - + em ~- ..a- e.- a-'-e., ..--..w-, -. ,. --w -emi-..9--a

,   .,,4  _w-  ,.=u.--.-m-  -. =..  -. wa--r-. ,. - -
                  . , _ . , _

m..-- we , ---.A w m, e-.g

     - -._--- - ---         - . _ .-    _ -. -. - _ - -         .
 $    ,_   _ -  -  4,..-    --   . . . . .  ..    ---     ..~ ._-..a

____umuunn.w2.hn Tw_Acl.hs_habws_ _ _ _ . _ _ _c% . me.Ls uc.Chk hy _ cum o p p 4W_u_ ___ cmhCwpc.y 1 J on k _ oEkokk _b se.s_b _.. _

     .u.Thu  wtc.t_%cm       hmuch.Lh A .hu e_s:._

_ _toeod h. h h 4_ ack _.het b p._ _

  .. _

cm_s a p csMuks_ppRs wLionocA .h.s %_ W ots. _ _ce4o.ogAlus &xcM .__ _ _ ____ _ _ ._ h u h a t c A c c h k ., h . s b6 h _ .. cwa.Ac 4_ h aby AmHo o L_tcelh s __ _ . _ w_% m q__... Ac w ooL 1t gs_ , CVJ4 ..Cy b t.AA.__.C b __ M 2.M \.T t . . FCt . _N IS dit$Luct _

--_

n cat. 4 so-_ h - 9 tta vt.- .

                   . -   - .
                         . _.- - --

__-- AcA-c a Lo.as tue-4a Ai s-guelb es i a <botrL __-._ - _ _ - - __ __ _ . - .. _- . - - hhv e-.p-m*. cy W wei-.e-w.- , ew - - e.i-b -

          .. -.-  ee   *-
                    *.   .

4 ,,. . g ~ %uM _.Xeat L o p.mb s . 2 n fact __._ L _ _ Sk s . _ Mcd .Is - 4 4e a m.ce d /n _ & _ _ _

 - ..--

9ves4tc e h o _ losc p _. pacure m %L 5ys k us - , . __ncu'a in d amval_ 3 3-._ A Cdhco//y _ ..- o cc ut a L '

-_--      - lo.a.L .    -In.pirl     aI   rnt   clse s           .-
._ -

buss _ lhcwt 10 Oo 14 3. -.. .. . . .. .. - . . . - - . . -

-  ,__   -. - _                  .   .- - .- _
-    -   __   _    . .  -     -     .
                             -
     .----~..e-.-..w.-.w-    =
         -
            .._4  .... -  .. , - - .       ..  ..m     ..

_.we 4-~~%, .hopeew.emp..,.-m,-.@e.we .e-m s i.._ - , . . .- , a,. 4 m-wi

- o

; ; ,
+
, .

Ioao_7 - Eyack._s e9wat.ciapoL}vrhIa hypst.Dqlves .-. - Cat _._ R.__%p A ss__v cdw. s_ o p.m .3_h y pe ssac ha.s_ ._ t-c % p k p l .a s _ w o k M c .u N c.ch he unc1cp g . _ ca_m. Lop +chs...au3_.th-cAacw fcm___ b.c.\cok_ Seep ms cm p& stV s_ wot_ o.maa.bC_ _

k. %-- kn c - M c 8 . Op+abt cm - . -- _- ox.xc4 sys k .Luch k y m u_kes-whccAcmlms_%_ Whds__skoAk hb ieAsh ch. ht.B\cAe _h_hmuc n_ o+____ _

__S\CXmkis.hp Ass Mcdw._ S ysk_ kic w - m - cem k o\ % Loa.- ]pess u a. . h o-h --_-- _sto-{ __ex c zl.. acp%1cu s$- q._,_ _ - - _ - - . - - __ _ . . _ _ . _. _ __ . . _ _ _ _ _ _ . . _ _ mw - me,-em e . w%- - - . - . +.m%%..,#--,3s <..,,m._m , ,--,.,,.u .m,-.__._....-- u

                    - u-~.---.-4eh-k.01cd -    QuuM cm._ _A ees_se-L ehc.Ot _spik c.._ As u#teJ %

_ _ - _.._ Asw Xoy__ __ _ _ _ - ._ . ._. _._ _ _ . _ _ _ _ h_Tus\ ~Ttccktcm3ay buL Y..ierc,Y OpYhtYog ._S P- - - - . Rutl-Ficaka+taEla L A-ns tu.a+ leth- d

                 - - _poe s.n c&_ .--_cph t h --       ._--.-.._ - _

_- -- _ - - -- - __.--. -.- . . -

    .- -diEx (sb.h_yout_ o susw " _ccm h.e.c,u_ _ - .

_ . _ _ - \oksi_cA %hcgs_!._ An_m/ lamadiovt._ oE___ _-- _Asin-._.dcustay aux.y accun. AWhtq44

n _--.

    ._-qves41cm laad.s Lcyzuabe Jo_ el.iscoss-

____Aae4_ m4.- r-L ua%;ealt w.s-_liaA _L - ___ _- up 01A c.ucs Ske 8.ygA.ss_Vctive wlIl _ _ -

--- -
  - -
    ._.ao-k.yoderl ag arashb .' }llawl1ucAvcL

_ - - .- - ._ t

                 -. . - -   _ _ -
                      - -..

_

   -- ---  .,--we =--   ..----.m  -%,-...._.-.  - . _ . . .  -,,.-,_%.  ---,-,,..,,,,..._..._,._,,__a-meaw    eu-me  **'ea8-4,.e  af-.-  e  w   ..  ,, ,  .
              .,     , , , , , _ _ ,,  -.e4.s .e w dm mos IEbEs4EE[.chee.s_5bbe t$sscu Uh cIM [. _ _   _sw A u       A mss-.. cam on      _

_ _ _ _

     ._c ent dcas ctk       _ centdr-o    ysfe w . _ _ _ __
 -- ~LX%      N oce n62a   Lonuna  - nmicaae - m o. , us    3 We uhV
- -  - _. -   m
._  ____ _

a.cc qu61 by %s - i 6 e s r A M E ) -- )

        .-
                               ,
 *
.
,
'q 9
   , - .    . . -         . - -

wy__'

                 - --   --
                      -    --     -- - - -
        -
         %b g ..e o+ J54eom.ingmof Ai
- . .-----     _A>ect.c-a)cmd Mer Duke de

___ . _ _ _ _ _ Ady udtu vsk. 0E_Ce deuSok _ Q _beit obM

--

W . _. _ . - . _-- -__. - ..- -.-.. . - - --. .--. w.q-A.am--..ww- =A.ka- -Mw W""9' **T'*"- -*^"O

            '
             " " * " ' " ' - " ' ' ' '   - 
 ,.  . -m e m  -.m , - . - ,me***   ' * * ' "-"   #-*  -'  -  '
        *

oh u".5ov+ceS... . ccw. h.c .-- Ces h sac _h . 04bd ----- y _ _as. cb ytohs_.c.w_ _ .. --- . -- --- - - - -- t -. .- - . - -

              ,   _. -   - - - . - - . - - - - - - -
. _ . . _ _ _ _ - - . - - - -         -  Y '
             --. NbSI-     WO C LV~ --- -- ---- - - -
 . _ _ . - _ - _ _

___ __=.3 . 3S _ # A SI lu eMe - --- ---- - - - - - -- - -- -- m -_______ 1 EW.A .. __ ._ . . - - _ . _ _ ._ _ _4 C b eg gAac h _ _.._- _ _ _ -

  --     -        -.
     .
                   . .   - . . - --- -      -. .-
  . -- _ _ _          ,  e-         - - _ _ _ .      _

-- - - - - -

             ._---.      - - - - _    _  .- . . - -    - -. .

_, __ - ., - _ ~ _ , - ,- - - . - . . , ..- -.---,- - - ---6--*-- - *-- - ~ '

                        "-'*' * " * * " ' - ' " " * ~ - ' " * * " * - * * - ' ' ' ' ' - * ' ' ' "

e w .-h . .. ..*e-

      -
        = +

__h. pend .hM tes.be g.. Aa.ss ccwcae-w Ahh_ _ _ _ - anacw.----. ... - .. - - -- - - . . - - -

  - -
     . - - - - - . - . - . - - - . - . - - . - . - - _ - - - - - - - - . . - . - - - . . .----
-
   .m h  Sm-e,-em4    ,e-,= _ -    -

w,a wwh- + >% .e w4e- m wa,w gang b__ ho m._ h ._. m y__ b. h c.L _ .

  . - -

A e - p.vo t e. k e-10 .t is _ cuppop ada . %-. .- _ ._h . s h cA h ._..-.._ -

                    ._  - ___   __  _ _ .- ___
   - -_ . . - . - .         - - _
                - . - -. . -       ..-

O .agiea-w<=s*e s - - .- . . -an.r.~ ==u.- ' - - "- ^-- - - i. + == *--, we **E*%4

 ._   _  ~T r-1p 3 sl   _

o ll LTmw

                   ._ ph d St y rea_ .. - .- _ --.
                .

w s - A - 3 Q.

'

                       ._ - - --- - }

__ _ . -

    - -. - _--- .          _ . ._. - .-

4t>A_Ou t.AA me_t. s p ca r.#.c- - --y - - -dtskte.lG% _

                        - .. ----    .--

_ . - ._b w cws we C e aA mcxs - vo" cto _ _._mCM5) ._ E.YCLcb . MSj w r (5 MON MCW i A4.kb 3 f% _ -. _ _ _ . ecq h h mc6 ic m.. c m to e q __ _ __ .- _

   -.. . -    _ - - - . - - -       -  - . ._ .. . -   .  .
                            -- . -.-
    .4 m-@g.-w .e-em- , . *  -  *=a-r--.,   .-.s.-  . - . --- 4 ,-. e-m IbW.h--y   as %...wsi- . ewe- awis -, a -- ---% -+'-nn---w--  -4 w+--        -
                         - .--.. +  m .  \  . -W  -.
              - .. ,W    . CS A5   $h .1 b - - -     .e - - - . - - - _ ,
  -.

_1hhus rnA..~ cq..xs -r .-hug.sA ,6,isAso{
- -- - - - - - .._.--.. . . .. - .._ -.-- . . . . . ._, - - _.. . . .
__ zL:21on&ETaKsws]Gi amg_n ALu.m u-. Q iGk&LGE ___ _ ~ _.1x Eu co.5AEEA$k NYN 5N
- napocesoasasM >p&NNan2e SI-icNs sn4s . --
1pGsLcnman4 reu u w p ea u % s_ - - - Jnn.h_jroedud us.a- . . - - - . - - - _- - - - . - - . . - . --
- _ . - . - -- . - _ .-
g gym 46 - ,,p- -me- - m.m=.- .* - - *-. ---eA--. -
--w y- -.i - .- m-E l =%H E R A a Z E E A a 6 M E-cc % e u A h c A - = so4.- -.-- - . . -
_
.y
- - . - . . . -
m- -- - -
.w . . . . - . . - - -o m a psu w _ _ - - . _ . _ . - - _ --__- -. - - . _.-- - - . . - - -*4 -- **r+--,sm-4,kA= t - a s -w-m.=.4 +es- + = .+ --d--- - -r- ~ .- ---.r *. - '7 D!o-.Cu .
1 EEC$ WOI .. Q 6C>-. Chil.C k C - C OS2 0 --*.=8---*&w ..-..
- . . . - - -- .._--- ..-:- - - . _ - . - . - . . . --- . - ..- - .. - .--. _ _ . _ - . _ . . . - - - - . ___ --Aas_ nL ccanna Jy a vado W -.. .-.-- - --- - . - _ .
n.sya A ym a c.A Q . - - . - .- -
- . - . - -. . - . - . - _. . - - ~ .c--,-. .- +.._._,.s ,_.-... _ . .._ . . _ . . ... ~ , _ . _. .. _. - ,. .~ . _ , - ~,. . .- , _ . . . . . ~ . . . . _ . , _ _ . . . - _ . . , , . . _ . _, . _ , , . ._ . . ... . . ...
4=p.9%hede.sm u tu am%'- n es tbe**.4omsm m ,of-. ---re,- ,- 3 -,
.4,,3 ._,,,,,._ ,, ,%.,. . ,. ~ ~ m .#.. m.-4 s-++e+- .-,em4mmm--+hh-ww.J.ee e . 6-i -.-pe4%,.g.,.w-.+ -n.>1-+v .ev .. -m,m.hu ._,%= .- -n v- - - - % % **8 '"*f -d " " "' >'E.G4.4Wm+w.-ump-a m N e wgreme mw w*%, .-..- * . ----i+ w---=-_-me-.y ae =aww -- - m e.- -,e*m,m* -- +-m ---a.'w - + -dha-*- e tra 4.hw stew - -meav--s- .wg== rem,*eameise 's. et ga'd'wr>+e.'=> 9 ha e n- +-6.Me.^d- -nmm . -----e e-*-me --ep.-->- -*m- = .'-'e - +- - - -9 -*P'**' "
L-
- , ,
.
7 3
.
a O [ b 1 . O at
* :- , . _ - W_ .__O h k.t b R ._.-. .._ C M 4 _.lhb S i h __.._- ,.- --_.- . - - _ - . _ _ . . - . . - .-- ._- .- . ---
g.mensgreen.-. hw4w - , e g.,. g
. - . . .m.46 , e . .. . Ace <__=m,at .we' -.emma.pasM - -^- -
g_ _ _3g_ 3:3 _ :_3_ 3. 6:33~__-_ -
- . - - - - - . - . . - - . - . .-.-_... - . . . - . - . . . . _ _ . _ . . ~ . - .- ,. -
_ _ _ . . __. - .-,~mm...-- _ h _ khu _ %cf c>c-1_ _ _ _ __ __ _ __3_
-
gg. ;g a _ g;3
- .
_ r y3_ _ . _ . . - _ - _ _ . . - - .. _ _- - - - - - - _
,.,cwe.p.-,mq.pweem i %. - -.ae .-m-g-- e-- = aem *..e--
e . - *-e-- ea-a-m<be-a d +=m
-._-- . . . _
lL:At~)Q__ __ _ _- _ _'a-***-.%-+ _._ --,
. . _ $ L- M - ML .
_._______ _ __. _ . ._ . _ _ 4 E - A A _ _ .. Id e i h d d 5 0 1 3 A w d c. E Y e s c A A 2 5 [ - ms_qushmme skam.220___ _Ex.cm.3 as4.yce 1_ tuCmo__c bs_ Jhh_ to As_ AL.Od- -_L e ctcg u-esk... Ms_puq u4Mdovt _...._ w:A _ b t _ ositc L iw A . h k v4. M h oo3 _ ._ _ m oAihecA h ,_ ___ _ _._..-_ _ . . __ _ _ .
-- . . . - . - . - . . - - . - - - - - - . - - . - . .. . - - - - - . . - - , - e .-. sme.ue * * Je , - - , . n.- =-m-e . --_ _ . - - - - . . . - . . - - - - -. - .e . -.--w --3 eea+*m..+ .-e ,e+.- %.. ee - - m. - --me-.a-Jun e . %----- s a w-. ' .m-- -'-i.se+,mm .emia.
L - A3o$cUAkoiA_.crjaxsb1 Eid _mugno ms._#0h%%-4_ _ ___ess ctMtcm ._ _-- __ . . _ _ - _ _ _. ._ _ __
. _ _Zi:A _ x _c m s 6 i 'e A M Qa h n ck iAQihcElill
} 2.o uAo m a Nv- sycs piy_ ae d _xnLu% . skMKy w canae,aL _.a llo u .
- - .
_ _ - w x aaa m . .
- - . .. ;
_ _ _ .. _ _ - - --_ .. __ __ . . - l _ a C _ .
%,. . U
. . ,
d' * _ _I N t --_ __ _ -_ b N.~ O .- _ b kU -_ - -- . . _ - - - _ . _ , - . , - - - . - . _ - _ . - ___mtmM ca w+
- A o A h A k ide_s d l S $ $ A k [c 1 _ll -._- __ _ _ . . - - - - _ - - - - . - . . . . - . - . - - - - . _ - - - -
e,t-.q,. wy a i- e_ = = - . - m.aom- a a* - a --4 _ pbasa_ _ _ _. _ _ _ - ._ . - _ _ _ _ _ . _ _ ___ _ _ _ ..__ l _ lApo AEU p.o lho awsaac g o A A fa,_-. ictec [.d C El __ 11 1E1Tll55k~c velRud45iiAAck;cmAlcmT lT
~ -
_- _ _- u Lopsa w csw w c m stpa.aL kk y _ _____ Ellllll:E5N _ ass.- ________ c h . k _ M i __ - _ ._ _ _ _. %_ - _ _ _ Wed % awow ufisil-a%Te}M As _ i _ _ _ li l il l i _ _i l l lc i b$rc h l A c l AAs O A5/a:.; Q il
^
e - - _ _ _ _ _ _ _ _ _ _ _ . _ _ . .1. A fl _CENs _cuve__ _ __-._ _ . _ _ y Ell _ht W CLu- _d __ _
. _ _- _ ._%cchfslove_ cowu - , al. zuscdc!..A. lo y_ __ - .._ .
c<cld ili m _ ~ZEETTEEEllia s s GREEEik o E111111E11 m su REi.aEL L IE L ctN&t W :Lai b m qu K EiE ~ _-_mw_cAurah oc croA_ _-_.- - A % n.ee 7 s 3. L - - - . - -
- _ . - - - _ _ _ - - - - _ . - - - _ - _ . - - - -.A.*eg . %,,, , ,,. , ., .,,, , , , , , , , . , . ,,,,,,,,,,,. , .,, .. , , . - -- d.th6 hw Yup-- . =_- - - _ . _ _ _ _ .
_ __ ._ _ _ . y_ .W.,, e.__ . _ _ _ . _ _ _ _ TEEE1TEEEEE _ _ _ _ ckam p.,m EE6XW4Eh Ac a wicaGJ# LAZE J _ _ _ . . _
- _ - _ _ m u m u c A %p h ve s Iuw pply _ - _ _ - - . - - _ _ _ _ . - -- . .- . ~ - _ _ . .
}}

v t e Inspection Report - Maine Yankee - 1985037
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
1985 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 9(0) 10(0) 11(0) 12(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 20(0) 21(0) 22(0) 23(0) 24(0) 25(0) 26(0) 27(0) 28(0) 29(0) 30(0) 31(0) 32(0) 33(0) 34(0) 35(0) 36(0) 37(0) 98(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000309/1985037

Text

Navigation menu

Search