Text

Exam Rept 50-244/85-11 on 850624.Exam Results:All Candidates Passed.No Generic Deficiencies Noted
	ML20133E438
Person / Time
Site:	Ginna
Issue date:	07/11/1985
From:	Dante Johnson, Keller R, Kister H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20133E430	List: IR 05000244/1985011; ML20133E427;
References
	50-244-85-11, NUDOCS 8508070702
	Download: ML20133E438 (44)
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U. S. NUCLEAR REGULAT?RY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /85-11 (OL)

FACILITY DOCKET N LICENSEE: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649-0001 FACILITY: Ginna EXAMINATION DATE: June 24, 1985 CHIEF EXAMINER: , f) I F. JohnsoY, Lead Reactor Engineer

'7////W6 Date (Examiner)

REVIEWED BY: k # ~7[// 76 R. M. Keller, Cnief, Project Sectior 1C Date APPROVED BY:

H. 'B. KisterMhief, Project Branch N / // [ T 1 Date SUMMARY: A written examination was administered to three candidates, two SRO and one Instructor Certificatio All passed the examination. No significant generic deficiencies were noted from grading of the written exam '

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8508070702 850711 PDR ADOCK 050 g 4

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REPORT' DETAILS TYPE OF-EXAMS: Replacement EXAM RESULTS:

I SR0 l Inst. Cert l l Pass / Fail l Pass / Fail l

. I I I I I I I l Written Exam l 2/0 l 1/0 I l l I i i l i I l0serell l 2/0 l 1/0 l l l l 1 Examiners:

D. F. Johnson, NRC B. S. Norris, NRC 0. W. Burke, NRC Examination Review:

The examiners and licensee personnel met to review the exam and answer key to identify inappropriate answers relative to plant specific design, and to ensure that the questions reflect current plant conditions, and would elicit the answers in the ke Examiners D. F. Johnson, NRC B. S. Norris, NRC Licensee R. A. Carroll, Assistant Training Coordinator J. Garber, Westinghouse Representative

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ATTACHMENT Comments and Resolution Question 5.03 Typographical error with respect Accepted calculations to.the given value of K,ff should using either 0.94 or have been 0.9 .009 Question 6.08 Reviewers supplied documentation Question and answer supporting another secondary corrected accordingl source of water for the standby auxiliary feedwater pumps; addi-tionally, another interlock for starting of the pump was identifie Several editorial clarifications were made to Section 8.0 as noted on the attachmen Attachment Written Examination and Answer-Key

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,. S. NUC EAR ':E G UL Al DF Y COMMISSION E E!;IO R REACTOF OPERATOR LICENSE EXAMINATION FACILITY: GINNA

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REACTOR TiPE: PWF-WEC2

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DATE ADMINISTERED: 85/06/24

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EXAMINER: D U R P.E , C. _________________________

APPLICANT: _________________________

,N,e 2 u i F...r, uu _ n N, n v n. . :. . ..

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Use sepct te :-sper for the snswer Write cnswers on one side cnl Staple quertion s H. e e t on top of the answer sheet Points for esch question are indicated in parentheses after the question. The passing

.: r s d e e vices et lesst 7 07. in each catecorY-

. . and c final crade of st lecst 80%. E ,: s nii n c t i o n papers will be pick.ed up si: (6) hours after the e;en.:nct en s t r. r t s .

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CATEGORY % OF APPLICANT'S CATEGORY UALUE TOTAL SCOPE VA CATEGORY

________ ______ ___________ ____UE____ ___________________________________

00

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_"_"___ ___________ ________ THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS n.e.0C s ee.0v, tv PLANT SYSTEMS DESIGN, CONTROL,

________ ______ ___________ ________ AND INSTRUMENTATION

. 0 .00 PROCEDURES - NORMAL, ABNORMAL,

________ ______ ___________ ________ EMERGENCY AND RADIOLOGICAL CONTROL

00 ADMINISTRATIVE PROCEDURES,

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_ _ _' _" _ _ _ ___________ ________ CONDITIONS. AND LIMITATIONS 200.00 100.00 TOTALS

________ ______ ___________ ________

FINAL GRADE _________________%

All work done on this examination is na y own. I have neither s1ven not received si .

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APPLICANT'S SIGNATURE

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.. THEORY OF NUC_EAP POWE7 FLANT OPERATION, FLUID 5 AND PAGE

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GUESTION 5.01 (2.00)

Following a recctor trip ' t o n. 100% power, how long would you expect :t to take for the source range instrumentation to be ener gized0 Show by calculation e red slso state any e s s um p t i o ris use GUESTION 5.02 (5.00) What si e the r..s t or constituents of the secondary neutron source? (1.0) Describe the react 2cns by which this source e n. i t s neutr on (2.0)

GUESTION 5.03 (2.00)

During a reactor startup, the operator stops rod pull 49 at 144 steps on Bsnk The Source Range honitor (SRh) count rate levels off at 1800 ep The initial SRh count rate was 400 ces et 0 steps withdrawn on control Bank A with Keff = 0 .U 4 . f4m // f . f r Calculate 1/M value for this control positio (1.0) Whti is t h c- new value of Keff Et this condition? (1.0)

GUESTION 5.04 (3.00)

The resetor has just reached criticalty when a very rapid 15 ppm dilution of the RCS occurs. Answer the following showing all work and assumptions * What is the resulting stable SUR f r o n, this dilution assuming that the core is at BOLT (2.25) Assume that the same events occurred at EO Would the SUR at EOL ve higher, lower, or the s a n.e 9 Explain wh (0.75)

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QUESTION 5.05 (3.50)

Enplcin (in detail) what causes reactor power to follow a turbine load increas In your discussion, include all of the various paranieter changes, incisding reactivity changes, and the reasons for these change QUESTION 5.06 (1.50)

List three objectives of the control rod insertion limit '

GUESTION 5.07 (3.00)

Refer to Figure 5-1 (attached):

What w;11 be the total systen. flow rate (spn.) and the operating pressure with all t hr ee pun:Ps operating? Give a brief enplanation of the reasoning process used to arrive at your solutio You may mark on the figure in doing your solution if you desir QUESTION 5.08 (1.00)

Calculzte the smount of p t : n.a r y subcooling that exists at a steady-state ten percent (10%; powe Include all a s so nip ti on s and calculation QUESTION 5.09 ( .50)

Figure 5-2 (attached) is a graph of heat flun vs. delta-T film (fuel rod surface tenperature to fluid bulk te nip e r a t u r e ) . Indicate (on the figure)

the point at which DNDR = 1 >

GUESTION 5.10 (2.00)

List four (4) system design considerations and/or systen, considerations that must exist to ensurs natural cirevlation subsequent to a loss of all RCP (xxxxn CATEGORY 05 CONTINUED ON NEXT PAGE ***xx)

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GUESTION 5.11 (2.00)

For the following questions, show all work and describe all sources of i re f o r ni a t i o n . D e t e r re i ne the quality of ssturated s t e a at 1000 PSIA if the enthalpy

s 1100 BTU /LB (1.0) Find the enthalpy change in an sentropic expansion of stecni ihrough a turbine into a condense (NOTE * Pstn1 = 825 PSIA, saturated vapor, Peond = 2 PSIA) (1.0)

00ESTION 5.12 ( .50)

When a pressuriner PORV is used to depressurice the RCS, wovid you expect pressuriner level to increase, decrease, or r e nia i n the same?

OUESTION 5.13 (1.00)

A reactor has been operating at 40% power for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the load is step increased to 50%. Describe the xenon transient that follow (rrr** END OF CATEGORY 05 rrrrr)

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DUESTION 6.01 (2.00)

What four (4) conditions must be nie t for the operator to be able to manually open the letdown isolation velve (A0V-427) f r o n: the niein control board?

QUESTION 6.02 (1.00)

NOTE: Refer to Figurc 6' (attached) when answering the questio During makeup operations, with the makeup system mode selector switch in

' auto', system control vcives will be as follows (select one): A-n.o d u l a t e d ill-open 110B-open 110C-closed A-modulated l i l- n.o d u l a t e d 1100-open 110C-open :10A-modulated 111-modulated 110B-open 110C-closed A-nio d u l a t e d ill-modulated 1100-closed 110C-open QUESTION 6.03 (1 00)

NOTE: refer to Figure 6-1 (attached) when answering the questio During nicheup operations, with the makeup system mode selector switch in

' dilute", the system control valves will be as follows (select one): .0A-closed ill-open 110E-closed 110C-open A-closed ill-modulated 110B-open 110C-closed A-closed 111-open 110B-open 110C-open A-closed 111-modulated 110B-closed 110C-open QUESTION 6.0c (1.00)

NOTE: r ef er to Figure 6-1 (attached) when answering the questio During makeup operations, with the makeup systen, n.ade selector switch in

' alternate dilute', the systeni control valves will be positioned as follows (Select one answer): A-closed 111 - n.o d u l a t e d 110B-open 110C-closed A-closed 111 - nio d u l a t e d 110B-closed 110C-open A-closed 111-open 110B-open 110C-open A-closed 111-modulated 1108-open 1100-open (r***z CATEGORY 06 CONTINUED ON NEXT PAGE xxrrz)

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GUESTION 6.05 (1.00)

What automatic actions would occur (if any) and what immediate manual oper ator actions would be required in response to a valid ' Low Feed Puntp Svetion Pressure' a l s t ni ?

QUEST'.:0N 6.06 (3.50)

What at e five (5) of he interlocks that must be satisfied before a niain feedwttet pump w:11 start?

GUESTION 6.07 (1.00)

Explain the effect of a loss of instrument air on the operation of the atmospheric stecni dump valve QUESTION 6.08 (2.00)

Answer the followina questions about the Standby Auxiliary Feedwater System Whst are the pr inia r y and secondary sources of water available to the pumps? (1.0) ed h W Whrt twc (2) interlocks will crevent startinc the pump? (1.0)

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GUESTION 6.09 ( .50)

What protective turbine * rip is blocked by use of the " Turbine Latch'

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pushbutton durin3 plant startup?

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GUESTION 6 10 (2.25)

Followins a reactor trip, the trace of one of the intermediate ranse-9 detectors levels out ct 10 anps Is the detector over compensated or undercompensated? (0.5) What is the con pensating voltase used f or? (0.75) Expalin why a compensating voltase is not necessary for the power range detector (1.0)

DUESTION 6.11 (2.00) What is the primary protection afforded by the OT/ delta-T reactor trip?

(0.5) What are the systen inputs to the OT/ delta-T setpoint calculation?(i.5)

DUESTION 6 12 (2.00)

What are the input signals used to generate the control rod drive controller d e n. s n d signal?

O U E S T '. O N 6.13 (4.50)

Relay 20 can be called the steam dump arming rela Two permissives and an orn. ins signal are required to enersine Relay 20 List the two (2) permissives (include setpoints and coincidences where applicable). (1.6) List the three (3) arnins signals, any of which will, in conjunction with the two above pernilssives, enersi:e Relay 20. Include setpoints and coincidences where applicabl (2.4) What operator action should be taken after the steani dump valves close followins an auton.atic dumping action? (Relay 20 has been enersized) ?

(0.5)

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GUESTION 6.14 (1.25)

List the suton.stic star t s i 3 r.s i s for: The turbine driven auxiliary feed pump (0.5) The notor driven a v::i l i a r y feed pump (0.75i (arrr* END OF CATEGORY 06 rrrar)

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QUESTION 7.01 (1.50)

Fill in the blanks in the following statement from Admin. Procedure A-1.1'

.All areas in which the radiation intensity is such that a na s j o r portion of the body could receive in any one hout a dose in excess of 1000 Mren, shall be-(1) _________________. (2) ________________, and (3) _______________ QUESTION 7.02 (2.00)

Plant Hectup fron. Cold Shutdown states that ...as the bubble forms, RCS

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pressure increases and a subsequent increase in letdown flow will be noted.' .

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operstor, avoid exceeding the maximum letdown flow rate under these conditions?

QUESTION 7.03 (1.50)

What are the purposer for Shift Relief Turnover in the Control Room?

OUESTION 7.04 (5.00)

With reference to immediate operator actions, section 2.0 of procedure E-1.1 [Immediate Action and Diagnostics for Spurious Actuation of SI, LOCA, Loss of Secondary Coolant, and Stean Generator Tube Rupture] answer the followins questions' Article 2.2 under immediate operator actions for the above procedure

, states, ' Verify the followins actions and system state If any of the followins automatic actions have not occurred and are required, they should be manually initiated.'

Give the ten (10) automatic action verification (4.0) Article 2.3.3 under immediate operator actions for the above procedure states, ' Verify that heat is being removed from the reactor plant via the steani senerators by noting the following -

Give the two verifiestion (1.0)

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Rd656L6GibEL C6sTE6t

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QUESTION 7.05 (2.50)

In procedure E-1.5, Void Formation in the RCS, the statement is made

'The following indicate a potential approach to inadequate core coolins:'

Give five (5) possible symP t oms of void formation.in the RC QUESTION 7.06 (4.50)

Listed below are s i:: (6) of the immediate actions for a Station Blackout (procedure E-4). E:: Plain the basis for each: Verify that at least one service water pump is in operatio Start one containment fan coole , Clear all loads off non-safesvards 480v buses 13 & 15 and energize by closins bus ties 13-tn-14 and 15-to-1 Start two instrument air compressor Restore instrument bus ID by enersitins totor control center 18 and reset alarm Restore emersency feed to instrument buses by energining MCC-1 QUESTION 7.07 (3.00)

In accordance with procedure E-5, Control Room Inaccessibility, what are the emergency stations and primary responsibilities of the: Shift Supervisor . Head Control Operator ' Control Operator Primary Side Auxiliary Operator (armr* CATEGORY 07 CONTINUED ON NEXT PAGE ****m)

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QUESTION- 7.08 (1.00',

What is the primary source of radiation in the containment under the following conditions Entry into the containment while at power (0.5)

. Entry into the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown (0.5)

QUESTION 7.09 (1.00)

What would be-your response to finding an employee working in. violation of a radiation work procedure or special work Permit?

00ESTION 7.10 (3.00)

What four (4) things should be done followins the discovery of a potentially contaminated' spill?

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QUESTION 8.01 (2.00)

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What conditions must enist for containment integrity to exist in accordance with the Technical Specification definition?

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OUESTION 8.02 (2.00)

-List the two (2) criter:a required to mak.e a change 2n the sequence of l steps in procedure t OUESTION 8.03 (1.00) i What are the limiting conditions for operation applicable to the reactor coolant loops when the reactor power is above 130 MWT?

l GUESTION 8.04 (2.50)

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la s w r k a. wth & 1* cam 4rfpeesfs M t.COs, 1 ghat CVCS conditions must be met for the reactor to be made critical?

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GUESTION 'B.05 (1.25)

There is an LCO that Epplies to the availability of electrical power for

, the operation of plcnt ovniliaries. It says that 'The reactor shall not be '

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Supply the five-(5)' electrical power source requirement ,

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operation is not nie t , except as provided in the associated ACTION l requirements? (1.0; l

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QUESTION B.07 . ( TM ekl i u*

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What is the, limit pertaining to steam senerator tube leakage?

DUESTION 8.08 (2.50)

What conditions pertaining to the safety injection and heat removel systems must be met before soins criticci (except for low tempercture physics testins)? Give five (5) conditions exclusive of those pertsining to various valve positions.

I I OUESTION 8.09 (1.00) .

WhaE 5 ion should be taken in response to the following situation:

Durins shift turnover, you notice that the time limit for the repair of 91A chargins punip has passed without the pun.p beia3 returned to service; 41B chargins pump is tassed out for surveillance o e in QUESTION S.10 ,( 2.00) Who may initiate a Ginna Station Event Report? (1.0) Who n.ust perf or n. the initial assessment of the reported event? (1.0)

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GUESTION 8.11 (1.00)

During a reactor post-trip review, the shift supervisor assisr.s the

Condition Three' classification to the even What would this indicate about the trip?

I GUESTION 8.12 (2.25)

Discuss the relationship amons Limiting Conditions for Operation, Limiting Saf ety Systeni Settings and Safety Liniits with resard to prever. tins release of radioactivity to the environmen (xxxz* CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)

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8.__ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 14

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DUESTION 8.13 (2.00)

Answer the following concerning Reactor Coolant System (RCS) limits: Technical Specif:estions provide steady state and transient RCS chemistry. limit What is the period of time you are allowed to operste if the cetus 1 chemisty concentrations are bett,een these two limits? [1.0] RCS specific activity limits refer to the tern. Dose Equivalent I-13 What is Dose Equivalent I-131? [1.0]

OUESTION 8.14 (2.00)

The monthly surveillance tests for the containment spray pump were performed on September 4th, October 6th, November 9th, and December 15t The Operations Supervisor states that it was still within the extension time allowed by the '- '- -. Erc:f'i ;'.._n: '

ha4,35.a h h+c /wec lw Is ht. correct? Explain your answe !

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e + c, s a n. s --..: e - n (0.5)

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Energy Trcinir; Ccrp. Mcnuti for Resctor '" h e : ' y Chspter 4, pcse 61

. > ru r. .:r- rs . vr s, ,e,.

t .-

, , . -

.s'

Assun.pt:or.s: Boron worth : DOL) = - ? . 5 p e ni / p p n (1600 p p ni Bcr on > (0.25; e n. b d a' =, (0.2 , :, . .- r; ,

. .<< . :. n_ ;_ ,

-

= ? . t, n. .:.

-

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' - -

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r-

..n r, c:e

- * * * * ' - -

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- (4 -/2 i ,/2 ~0.5)

= (0.006 - 0 . 0 01 C 5 ' ' O ,1 ) ( 0. 0 014 2 5 )

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-- a.- . . .-

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-

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,s. r;. .,- Tne SUR w;3; be greater ct EOL (0.251 ove to t decreese in d #'

(0,(

.

e- - - e .g .y m b . N Yhh . .D . O

.

h f . f' -. -- -- 7 I'.L_

-7 Energy i r r : r. : n 3 C o r ,r . M i r.v t ; for Recctor Theor, CBSp;e: (, ecses 25 t 2:

Chapter 7, page 41

.

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ur

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f: . is0 ,-

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n k. r. . , _ .:r;n e s .ur. r- .

"he d ollowing s o,u s ~.-; e n s y be .' c e d :n lieu of rJ . s c u t n i o n :

. . . : -i t 2 ( : :. ', t c , ' . - ', -

": r . - U ( ( T a v.: - T1,1-

,-

= * 1 s e f.J e ; i z - H '

. .

ta.es .

e ... . _,_.,

,s ,,.,

,

. Turbine e t.n t t 0 ; .::.er open w:de- thus decter:.:n3 the tesistence to

'

s t.e r flow wh:ca c a u t,e c the r.i c i c flos rate of the : e c o n d s t ,- to incre;ne s tnd s t e e pr e _ i ur e to ej e c t e t s e .

..

r a nce tne

.

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.

t t'..r e v 1,.

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.

esuse a cecrecse in t e n. p e r E t :. r e . t, ,, n. ./ . .

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moe _.;

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.oe : ,f -u

-

u .,,o 'e _= r 4sou_,e i e_ u .u-

,

t i t n r. f c - : n 3 a. o r e ener 3y f r c the p r i n.t r y cocisn . 2 a.o e ene*3y 15 Temoved from tnc primary. Tc decrease . As Tc ., n c' tha Tcvc oecr e ase. pocitive reactivity it Edded to the core .e. . vn .

vy

+ _,w .,

_c ,. ;. n c r e e_ z.e. e .

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,

_ .,c_.,..,

-

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.. c meur r e c c +. o f , c ,.

r

...

. _..ne _....e my-&s .... ....n. . e . e .;v . . ., ., e_.c._ c h c._ new w m. e c y. . -& ..c.. .,, c.sour _ ...e n .,,o.__e

. . _ .

e

. . ._

_ _. . o n . -

cf the MTC and the fuel recctivity "cefficient of reactivit .

: : : Lsc.r.w -

. , _ . m

- . .

. .

n c t m., ,- . r I ; r.: n .: u o r ...o . ,enutA ,or

,

. .:ccetor r -.near-i Chc eter 5, o.sce: 1" 10 & 38 .

Ener:' T r s i n i n .: Caro. Manuel for Thermodynan.ics & Fluid Flow C n.Citer -- C7 oEQei .-

._

.

<

my r '

_ b b Y

.

. .

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T' r*.,.r. _ 5_

- - - -fr r - . .. .- rn . , dtiI ,. r,c.>,,- ----------------------------------------

e , e

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

ANSWERS -- SINNA -35'06/24-EU:SE- O. L'.

.

Ah.,..--:+=n e.c.se a , . ,...e.,v

.. Mcintcin cccepteble power dictt: o: t on dur ing nor t.cl o p e r s t i e r. . ( 0 . 5 '- M:kt t h c :e..tencer of c pottulcterd rod e;ection reciden:

-

e_m... . n .c _e. o- . c., . t, r.v.es . Into:c e c.i n i c:v shutdovr: .-tvsin(cf 1.80% r.egrtive recet:vity to

.

preven 1 ,et u n tc cr ticality during the ciedible stecm 1 r. e breck cetident} (0.5'

RE:ERENrr i.' e : - e.ncure d c c .. n. e n - *~hr .vucieer

'

~

es gn enc. Core M : n t g e n.e ra er the

.

i. GN.r.: h.cie - Reactor C y t ;,f; 14' prge 4^

.

T .S. - 3.10 e, N w. .an -. v . .s ,

,-

s3.0v-)

On rigure 1, sketch in he flow vs. pressure curve for cl1 three pump; .r opercting ct the scoe t i c: e . '!e note that Punip No. 3 will continuously r

dischcrge ^ 5 3 p n- tnd chst P u c. p Nc. I wil2 have :erc flow since : 12

'

c:errt. . . < e- cressure crerter thcn :ts thviof' 5 ec .

The ecnbinec ' '. s

.2 . pressure cur <e :In ce generated by adding 45 spn, to the flew rcte of

ump No. 2 si the .rtious pressure >

The intersection of this curve with the E y c t e n. head Icss curve determines the operating poin (1.0)

The a p p r o x i r.. e t e value:. are:

,-

- ,t o v r e ,s e = e. g p ri .

<1.0, Operet:ng pressure = 82 psis ( 1. 0 ',

.. --. ,nn

. . t r a n : rm t Energy iteining Corp. Manual 'or Thermocynamics E Fluid Flow Chapter 6 pages 18, 2 '. E 35 C h a. t, t e r 7 :. c ,r., e 5 n- h e>:r .-c.,- e.c s s t, . . tn n.. ,

,

t

.

u .. - s-s

> c . . n- >, +

.

e-e~; - eau , . e:

652.0 F Stt. temp. for 2250 psic freni the steen, tables-552.5 : Operating Th at 10% power

.--

09.5 : Subcooled at 10% power (1.0)

.

S P

.

*,

, J l u. . . q :. v, pr >;g :w r. A ,

a : R,

_ . ..

T P L t". * l ' ' P :'ts.1O T UTh .

.. srJ ~

r L r.:. r '. o

.

________________________________________________________

THERMODYNAMICS

______________

ANSWERS -- GINNA -85/06/24-BURKE, D. REFERErJCE Ginne draw:ns RGE-RC-L (from S y s t e ro Description 120) 8 steam t a b '. e s ANSWER 5.00 s' .50T See Figure :

RErEREt'CE Energy Trs_ning Corp. Manuel for T h e r r.i o d y n a m i c s E Fluid Flow Chrpter o. Pese 2~

A N S'W E R 5.~0 (2.00)

'. The heat source c:v s t be physically leccted below the heat sin . P r 2 ro t r y system subcool ng must be n.z i n t s : n e d . The sten generster tubes must be crvered by secondsry wate . Stern f '. c u f r o the s t e a Senerttor must be niainttined (heti s i n i>. ) .

(0.5 each, all 4 recuired'

.,___.,_b.--. t r. ; u Enero,v, Trcinine s Corp. Manual for Thermodynsmics & Fluid Flow Chcpter 9, pases 42 & 45

%& o-o

_

.

., , i ta rni c-J ~ e' C t- u- r.- r0'--

-

i rn.* *t O pt- e n' 'i~~t

u-. r-' i_'u* - ees-

-- -

te J> '-e mut c e-

THEPMG'YNAhlCS s

ANSWERS -- CINNA - 8 5 / 0 6 / 2 4 - E: U R I'E - .

n h.oWc . -.

.., ( c .C.eis Irem t'ie stecm tables, e 2000 psla* hf = 542.6 E:T U r l b n-hfe = 650.t E: T U / l b ho- = ' 1 "' : . :- E: T U / l b .

' = '!.

- nf)(100)/hfs = (3:.00 - 54 2. 6 ) (100 ' 'd 50. / = E 5 . 7 ". (1.0) Usine -i o l l : e r d 13 a. .r e n. , r e e ." 1198 B T U / l b n. enthaley . for toturated varcr r et 525 pri l t 7. r e constant entrop. lane to its intersecticn with the 2 psia .:n Read h = 820 B T U / l b ni .

D e l t s - P- = .t : :E - 820 = 378 ETU/lb (1.0)

AL T E;:N A T E SOLUTI0t- using stean, tables:

For scturated v: pct & 825 psit. - = 1105.7 B T U / l b cs -- . . *tn . .i n e D6-r ;J e z o m i

Fint r e a quality r1 2 p s. i t and S= 1.4129 n = (1.4129 - .1750)(100)/1.7450 = 70.94%

G t csic = (1022.;)(.7004)

-

+

-

94.02 = 819 BTU /lbm

-

.. .,. o. p . / _

,-e = )/, 0,.d P,T bt/'. w'.b E' 4 e

- - .-.- - .. .

r :. r c r e_ -:

Stecm tables or Mollier diagrsm Energy Trt:ning Corp. Mrnval of T h e r m o d y n c ra i t s E Fluid Flow Chapter 9, pages 21 & 29 n. N ~o r,-en,. s . ,..,-

e- -

s . es n. )

Increase ntrtrt,---. h. -t. t s

E-1.4*6 H ie: W-.

,

ar e..-.c v f, ...VJ,c3 Ihe 'enon O C n c e n i r B '.,i o n deCreEEEE "'olloWing the power :ncrease (due tc an

.

i increase in the burnout) E0.53 and then it later increases to the higher equil:.br vm vclue for 50% power E C' . 5 ] .

REFERENCE Energy -czining Corp. Menval on Reactor Theory Section 6 page 12

.

..

. r . ,a. . _ c sc r.: ..s e - :. _ ns ,4, -

C sn h. . r. :.

.

n fye ,.N,: c , . a , .%

. _1 10 ,., ; ;- -.

________________~________________ ,

______________________

-_

AtJSWERS -- CD$ A -85/06/24-BURKE, ANSWER 6.0; (2.00:-

(0.5 ecch. Eil r e e,0 ; r e d All letdown or i fic e isolation velves (ACV-100A. B, and 20;, must be cio e . Pressur:rer ~. e s e l mus. te cicater - her :. 0 . 6 ':r e r c e n t . Proper control vcitage(&/mor ,m Yihbe evcilable to the velv . No cont inment isolation cigncl presen R - rt- ncr,,t.-

-

RGE-16, pa;e 5 ANSWER 6.0: (1.00)

REFERENCE RGE '8 page , 6, 7, & 10; and drswing RGE-VC-4 & 6 ANSWER c.03 (_.00'

R._ :::

. - = u~e _:

FGE-18, pages 3, 6, 7, & 10; and drawing RGE-VC-4 & 6 ANSWER 6.04 (1.00)

f4 REFERENCE RGE-18, pcses 3, 6, 7, t 10, and drawing RGE-VC-4 & 6

... - .

.

.. ..

, PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION PAGE 22

______________________________________________________

ANSWERS ~-- GINNA -85/06/24-BURKE, D. ANSWER 6.05 (1.00)

If the condensate bypass valve is in automatic', the valve will open. If

"

in ' manual', operator must open the bypass valve from the main contro boar _the-c.s.ua. e REFERENCE-RGE-43, page 11 ANSWER 6 06 (3.50)

(5 required, 0.7 each) Suction valve open Suction pressure greater than 185 psis c.- Dischargevalveclosed( M ) Recirculation valve open Lubrication system operating with oil pressure above preset valu Seal water booster pumps operating with seal water pressure 15 psig greater _than feedpump suction pressur Blowdown selector switch in nor mal REFERENCE REG-43, pages 12 & 13 ANSWER 6.07 (1.00)

No effect, instrument air is automatically backed up by pressurized nitrogen with no operator actio REFERENCE RGE-40, page 6

.

n-

,.--wr -

-,-,--r,..- , , - , v-- - , , , - , . - - - - - , , - , . , ,,-w,,,,,-- . y-, ~ .

- _ _ _ _ _ _ _ _ _ _ _ _

_

.

t

*s

. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATIO* PAGE 23

. -

ANSWERS -- GINNA -8 5 / 0 6 / 2 4-E:U' .;E , D. ANSWER 6.08 (2.00) Primary - service water (0.5)

Secondary - a v::i l i a r v ' ..idensate stor age tanker bin Nek.bws- '^ (0.5) N tmal auxiliare eedwater pump breaker closed j/ (0.5)

nssociated - ondby pump suction valve closed '

(0.5)

REFERENCE RfWPANAh & I

&

RGE-42, & 8 .

% L,<.pages 76 m - u23. 3/b nap e nWe c w k - 3026 M '

ANSWER 6.09 ( .50) g Low vacuum trip REFERENCE RGE-49, pages 10 E 20 Logic Diagram Sheet 43 ANSWER 6.10 (2.25) Undercompensated (0.5) Counteracts the signal produced by the samma radiation so that only the neutron level is indicate (0.75) In the power ranser the signal due to samma is much smaller than the signal from the neutrons (0.5) and is also essentially proportional to the power level (0.5). (1.0)

REFERENCE RGE-33, pages 16 E 17

.

-

.

, ..

s 16. . PLANT SYSTEMS' DESIGN, CONTROL, AND INSTRUMENTATION PAGE 24

.------------------------------------------------------

ANSWERS -- GINNA -85/06/24-BURKE, O. ANBWER 6.11 (2 00) Protection from DNB (0.5) (1) Tavs (0.5)

(2). Pressuri er pressure (0.5)

(3) ~ Axial f l u:, difference (0.5)

REFERENC RGE-20, pag '

.RGE-35, page 17 LANSWER 6.12 (2.00)

(4 required, 0.5 each) Averase Tavs Tref c. Turbine first stage pressure d.', Nuclear power level REFERENCE 888 RGE-20, page 5 RGE-30, page 13 o

.

2

=

. _ _

,

-

.

,

.

..

.

-. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 25

,

ANSWERS -- CINNA -85/06/24-BURKE, ANSWER 6.13 (4.50)

a.(1) Condenser vacuum must be at least 20 inches vacuum as sensed by 2/2 pressure switches in the condensers ' Condenser Available.' (0.8)

(2) t, t least one (1) cirevlating water pump must be running 'Cirevlating Wcter Runnins' sensed by pump breaker contact (0.8)

b.(1) The steam dump mode selector switch is in MANUA (0.8)

(2) The steam dump mode selector switch is in AUTO, and ' Turbine Trip'

exists Eas sensed by 2/3 ' Auto Stop Oil pressure switches <40 psis or 2/2 turbine main stop va3ves shut and as indicated by, alarms D-24 (Turbine Auto Stop) or D-32 (Turbine Valves)]. (0.8)

, (3) The steam dump mode selector switch is in AUTO, and P-4 is enersized (psttial loss of turbine load 210% step decrease or >10% decrease in

,

120 seconds). (0.8)

, Reset or deenergine Relay 20 usins the steam dump ' Reset-Auto-Manual'

switch on the MC (O. y REFERENCE RGE-45 pases 4 &5 ,

ANSWER 6.14 (1.25) D/331ow-low level in both'S/G's hd T (0.25)

Loss of voltase on both 4160 volt busesCN#dB) (0.25) h/3Ilow-low level in either S/G [4f75) (0.25)

Open on both MFP circuit breakers (0.25)

Safety injection signal (SIS) (0.25)

REFERENCE BOP system descripticns, Auxiliary Feed Section, pase 4 I

h n

i i

i f - - . - - - , . , - , - .---,-w - ,.- -, , , , , - - , , - .--

-

n .

\ .

,

. ..

,:-

.

7.- PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND PAGE 26

'~~~~55656L66565[~6 UTE6[~~~~~~~~~~~~~~~~~~~~~~~~

____________________

ANSWERS -- GINNA -85/06/24-BURKE, D. ANSWER 7.01 (1.50)

(0.5 each)

(1) barricaded (2) posted (with a high radiation sign)

(3) locked REFERENCE Procedure A- ANSWER 7.02 (2.00) Reduce the chargins pump speed. / rh a& Pc(v f jg- (O{}

g Place excess letdown systen. in servic ( 0.I)

' Place Letdown Temperature Divert Valve (TCV-145) in divert (0YES Shut off the pressuriner heaters for a short tim "

'

(05 )

EFEhEi/CE k'*D '

. Procedure 0- article 5 36.1, pases16kA'

ANSWER 7403 (1.50) To provide an aid to awareness of plant conditions at the time of shift chans (0.5) To formalize review of control board seneral status to assure proper configuration of controls and system (0.5) To provide for identification of vital safety parameters and equipment deservins particular attention durins shift turnove (0.5)

REFERENCE Procedure 0-9 ,

s

.

l l

1

._ _

.. .

,

c; -

-

B- . PROCEDURES -~ NORMAL, ABNORMAL, EMERGENCY AND PAGE 27

~~~~RE5i5E55fCEE E5NTR5E~~~~~~~~~~~~~~~~~~~~~~~~

ANSHERS -- GINNA -85/06/24-BURKE, D. ANSWER 7.04 (5.00) (all 10 required, 0.4 each)

(1) Reactor trip (all rods on bottom) and turbine stop valves close (2) Busses 14, 16, 17, & 18 are energized and at approximately 480 volt (3) Main feedwater isolation has occurre (4) Containment isolation has occurrec (Alarm A26), and all X & Y relay Steen lights are off on Containment Isolation pane (5) Auxiliary feedwater pumps have started and the auxiliary feedwater system valves are in their proper emersency alignmenti that is, the discharse MOVs are fully open and after pump start, throttle back to deliver approximately 230 sp (6) S T. & RHR pumps have started and the monitor lights indicate that the safety injection system valves ar e in the proper safesvards positio (7) Service water p. ops have started and indicate sufficient service i water pressur (8) Containment ventilation isolation has occurred (Alarm A25).

(9) Containment recire. fans running and charcoal filters in servic (10) SI pump suction swap-over if <10% BAST level, 825 A and/or B ope (both required, 0.5 each)

(1) Automatic steam dump to the condenser is occurrin (2) Reactor coolant average temperature is decreasing toward prostammed no-load temperatur REFERENCE Procedure E- &

_

, _ .

-

.

, .

.

i H,. ..

q

-

. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 28

~~~~~~~~~~~~~~~~~~~~~~~~

~~~~R 5656L65565L66NTR6L

____________________

ANSWERS -- GINNA -85/06/24-BURKE, O. ANSWER 7.05 (2.50)

M 5 - , = ' : 1, 0.5 each) Core thermocouple temperature reach or exceed saturation for existins RCS pressure (approximately 700 F). Possible low runnins current on running RCP . Loss of, low, or erratic RCS flow with RCP runnin . Possible over temperature delta-T s;t point decreas . Erratic or high pressuriner level followins either a loss of coolant, a loss of coolant flow, a loss of heat sink, or rapid depressurizatio . La- 99-8 ' '

REFEREtECE -

Procedure E- ANSWER 7.06 (4.50) Supply service cater to the emersency diesel senerator (0.75) Maintain containment temperature below design limits (0.75) Reduce load on eniersency bus prior to starting [ backup the sequencer]

(ot' k edu$Itv IAT& 45% yph . (0*75) Ensure valve operability to ensure capability to isolate and provide system safety operations (0.75) To provide minimum vi*.a1 instrumentation (0.75) To restore normal vital instrumentation (0.75)

REFERENCE C " AT inCallT gg fa) "1 i , - ,, d -er

-

' 9 Q) g M

.

-

e O

<.

E

.

. ..

. PROCEDURES - NORMAL, A E: N O R M A L , EMERGENCY AND PAGE 20

~~~~~

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ANSWERS -- GINNA - 8 5 / 0 6 / 2 4 -E:U R K E , O. ANSWER 7.07 (3.00) The SHIFT SUPERVISOR will supervise the i ninie d i a t e and subsequent cetions of those ind2viducis below hin, and provide other guidance or assistence as necessar (0.75) The HEAD CONTROL OPERATOR will report to the control station neer the auxiliary feedwater punips and commence directing the manual operstions required for the hot shutdown xenon free conditio (0.75) The CONTROL OPEATOR . ill report to the charging Pump r o o ni , being knowledgeable of the fact thct he is in a high radiation are (0.75) The PRIMARY SIDE AUXILIARY OPERATOR will report to the boric acid storcse tank tree for boric acid injection operations required for the xenon free hot shutdown conditio REFERENCE Procedure E-3 ANSwEe 7.05 (1.003 N-16 9anneG e Ac-a Ptu .

<c,s, G a m ni c s f r o n> corrosion productsj M M (0.5)

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ANAWER 7.09 (1.00)

, W 444 m'd&itJ f_,/eport A

the incident to the Health Physicis REFERENCE Procedure A-1:22

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% PROCEDURIS - Normal, A E:9 0 P M AL , EMEEGENCY AND PAGE 20

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ANSWERS -- GINNA - 8 5 / 0 6 / 2 4 - E:U R K E , D. ANSWER 7.10 (3.00) Notify c11 personnel in the crea of the spill and advise them to leave the cree if a possible r adiction hacerd e::ist (0.75)

^

o If poss:ble, stop the source of the spill and confine its spread.(0.75) Notify the control room and radiation protection sectio (0.75) All persons involved shovid be monitored and decontaminated as neces sar , (0.75)

REFERENCE PPoCedVTe A-1!35

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& ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 31

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ANSWERS -- GINNA -85/06/24-CURL (E, O. ANSWER 6.0; (2.00)

(all 5 required, 0.4 each) All rion-auton.ctic contcinment isolation velves that are not required to be open durins accidnet conditions are closed end blind flanges are installed where require . The e q u i p n.e n t door is properly closed and seale . At least one (1) door in each personnel air lock is properly closed and seale . All automatic containment isolation valves are operable, or are secured in the closed position or isolated by closing manual vlaves or flange as permitted by limiting conditions for operatio . Conttinment leskese satisfies T.S.- requirement REFERENCE RGE-21, page il

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ANSWER 8.02 (2.00) The procedure consists of valve line-ups or an inactivated system whereby the sequence of steps will not affect safe plant operatio (1.0) The procedure is written in de#initive sections whereby the change of sequence will not affect safe operation of the plan (1.0)

REFERENCE Procedure A-50 ANSWER B.03 (1.00)

Both reactor coolant loops and their associated steam generators and reactor coolant p u n.p s shsll be in operation REFERENCE Technical Specification LCO, page 3.1-1

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.- ADMINISTRATIVE PROCEDURES, CONDITIONS. AND LIMITATIONS PAGE 32

, ANSWERS -- GINNA -85/06/24-BURKE, O. ANSWER 8.04 (2.50)

(all 5 required, 0.5 each) , At least two (2) charsins pumps shall be operabl . Both boric acid transfe g shall be operabl . The boric ceid tanks osether shall contain a n.inimum of 2000 sellons of a 12% to 13% by weight boric acid solution at a temperature of at least 145 F) System piping and valves shall be operable to the e:: tent of establishing two flow paths fron, the boric acid tanks to the reactor coolant system and a flow path from the refuelins water storase tank to the reactor coolant syste . Both channels of heat tracins shall be operable for the above flow path REFERENCE Technical Specificatior. LCOs for the CVCS, Spec. 3.2.2, page 3.2-1 ,

i ANSWER 8.05 (1.25)

(all 5 required. O.25 eacn)

- .5 KV-4160 volt station service transformer in service volt buses 14, 16, 17, a 18~enersized volt buses 12A and 12B energized Two diesel generators operable with onsite supply of 10,000 gallons o#

fuel availabl . Both batteries and both DC s y s t e n,s operable, and at least one 150 an:p battery charger or two 75 amp battery chersers in service for each batter REFERENCE Technical Specifications for LCO 3.7.1, page:3.7-1

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' ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 33

ANSWERS -- GINNA -85/06/24-BURKEr ANSWER 8.06 (1.50) It is capable of performins its specified function (s). (0.5) k'i t h i r, one hout action shall be initiated tc place the recctor in a MODE in which the specification does not apply by placing it in the appropricte shutdown conditio ( REFERENCE procedure A-5 ANSWER S.07 (2.00)

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Steam senerator tube leakage shall not e::ceed 0.1 spm when averased over 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months REFERENCE Lesnase specification 3.1.5.2r page 3.1-2 ANSWER 8.08 (2,50)

(all 5 requiredr 0.5 each) The refuelins water tank contains not less than 230,000 sellons of waterr with a boron concentration of at least 2000 pp . Each accumulator is pressurized to-at least 700 psis, with an indicated level of at least 50% and a maximum of 82% with a baron concentratio of at least 1800 pp Neither accumulator may be isolate . Three safety injection pumps are operabl . Two residual heat removal pumps are operabl .. Two residual heat exchangers are operabl REFERENCE Tech. spec.LCO 3.3.1.1, page 3.3-1

. ANSWER 8.09 (1.00)

Report the. condition and the circumstances to the NRC within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , _ _ -__ _ __ - . _ . _ , _ . - . - _ _ .__ . _ . - . . . . _ ..._ _ . _ _ _ _ _ .. _. . _ .

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e ADMINISTRATIVE PROCEDURES, CONDITIONS, AND PAGE 34 g ____.__________________________________________ LIMITATIONS

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! ANSWERS -- GINNA -85/06/24-BURKE, D. W.

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Technical Specification 6.9, pase 6.9-4 ANSWER 8.10 -('2.00)

l Any person who thinks one is required (1.0)

Shift Supervisor (1.0)

REFERENCE Procedure A-25.1, pages 1 & 2

-

ANSWER- 8.11 (1.00)

The cause of the trip is not know REFERENCE Procedure A-25.4, page 2 ANSWER 3.12 (2.25) (@ .f db-LCOs indicete thelowestfunctionalcapabilityorperformance level of equipmentsrequired for safe operation of the facilitya [0.75] As long as automatic protection occurs prior to exceedins a LSSS, then the abnormal condition will be corrected prior to exceeding a Safety Limit. [0.75] The integrity of the physical barriets which guard against the uncontrolle release of. radioactivity is protectr-J as lons'as a Safety Limit is not violate [0. 7 5] .W#

REFERENCE 10CFR50.36 M'f JM ANSWER B.13 (2.00)

- hou r s whe, <M/; 2*g w > 2# E1.03 Dose Equivalent I-131 is that concentration of I-131 which slone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. E1.0]

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ANSWERS -- GINNA - 8 5 / 0 6 / 2 4 - E:U R r' E , O. REFERENCE TS 1.18- TS 3.1-32 ANSWER E.14 (I.00)

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The 3.25 rule has beer, e::e e e d ed . (1.0)

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T = (a - o)/(Io) 534 = ( - K ,g)/K ,g

'o = (K ,g-1)/K ,g = aK ,f ,rK,g t= = 10 sec:ncs l I = 0.1 secones-I l o = [(~1=/(T K,g)] + [i,g/(1 + IT)]

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P = ( av)/(3 x 1010) g;g1 22 2

= -N R/hr = (0.5 CE)/c (meters)

R/hr = 6 CE/d2 (f,,g) . l War.ee Parmeters Miscellaneous 0:nveMiens 1 gal. = 8.345 le curie = 3.7 x 1010:33 1 ga] . = 3.78 litars 1 kg = 2.21 lba 1 fp = 7.46 ga nc=2.54x103Stu/nr Density = 52.4 10m/f-3 1 "JW = 3.41 x 103 3:u/hr Density = 1 ;=/c:p lin = 2.54 c=

Hea of vascrization = 970 Stu/lem *F = 9/5'O + 32'

Heat cf fusion = 144 Stu/lem "O = 5/9 (**-32)

1 A:= = 14.7 :si = 29.9 in. M ~

1 BTU = 778 ft-lbf I ft. H O 2

= 0.4325 luf/i .

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v t e Inspection Report - Ginna - 1985011
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 11(0) 18(0) 20(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000244/1985011

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