ML20206D047

Exam Rept 50-361/OL-88-02 for Units 1 & 2 on 880726-0811. Exam results:11 Reactor Operator Candidates Passed Operating Exams & Nine Passed Written Exams.Twelve Senior Reactor Operators Passed Operating & Written Exams

ML20206D047
Person / Time
Site:	San Onofre
Issue date:	10/21/1988
From:	Elin J, Johnston G, Meadows T, Royack M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20206D037	List: ML20206D033 ML20206D047
References
50-361-OL-88-02, 50-361-OL-88-2, NUDOCS 8811160511
Download: ML20206D047 (79)

Text

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Examination Report No. 50-361/0L-88 02 Facility: San Onofre Nuclear Generating Station Units 2/3 Docket Nos. 50-361, 50-362 Examinations Administered at: SONGS 2/3, San Clemente, California from July 26, 1988 through August 11, 1988, s Chief Examiner: ,

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Examiner: M 7 e ~ ~ ' ~ -

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Michael J.

Examiner Examiner: 2 =4/h -- c/h /e' /

Thomas Meadows, Operator Licensing Date Signed Examiner Approved by-in O. Elin, Chief b *

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Operations Section Sumary:

Examinations on July 26, 1988 to August 11, 1988 ,

Written and operating examinations were administered to eleven Reactor Operator  ;

candidates and twelve Senior Reactor Operator candidates. Eleven Reactor Operator candidates passed the operating examinations, and nine passed the i written examination. Twelve Senior Reactor Operator candidates passed both the i operating and written examinations.

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REPORT DETAILS

1. Examiners i

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• G. Johnston, RV M. Royack, RV T. Meadows, RV

!. Kingsley, Sonalysts-

G. Weale, Sonalysts

• Denotes Chief Examiner 1

2. Persons attending the Exit Meeting M. Royack, RV i T. Meadows, RV i

L. Simmons, SCE, Operations Training Administrator T. James, SCE, Simulator Administrator

R. Mette SCE, Supervisor Operations Training

3. Written Examination and Facility Review The written examination was administered on July 26, 1988 at the training j center. At the conclusion of the examination, copies of both the Senior j and Reactor Operator examination keys were given to the facility staff for i review and comment, l The facility provided comments and proposed resolutions as a result of

their review of the two examinations. in accordance with NUREG-1021 rev. 4.

1 Facility Coments and final NRC resolutions are included as attachment I to this report. Based on the facility coments and NRC resolutions the i examination keys were revised prior to grading the examinations. Some 1

additional changes were made subsequent to the resolution of facility 1 coments and these are ducumented in Attachment 1.

The facility training staff voiced a concern about the length of the J

examination. It was apparent during the conduct of the examination that the majority of the candidates were still present at the end of the six

hour time limit. All of the candidates did, however, complete the i examination. Therefore, although the exam was lengthy, the exam was valid j with regard to adequate time for completion.

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4. Operating Examinations:

The operating examinations were conducted over the interval from July 27, 1988 to August 11, 1988. No areas of general weakness among the candidates were identified during the course of the operating examinations. However two areas related to Emergency Operating procedure interpretation were identified during the conduct of the simulator portion of the operating examinations. These interpretation problems did not concern a generic weakness of the candidates, rather they were indicators of a programatic concern.

The first situation concerns the condition where a pressurizer safety relief valve is stuck open. The problem appears to be that there is no apparent success path for this condition, unless, the SR0 determines that he must trip the Reactor Coolant Pumps to enter "Loss of Forced Circulation" which does have a success path involving the stuck open valve.

Secondly, there was confusion on the part of the candidates about tripping the Reactor in the event of a S!AS. Apparently there were some individuals who had received instruction to trip and others who did not. The discrepancy involved some Night Orders related to the need to trip the Reactor in the event of a CIAS, one of the scenarios caused both a SIAS and a resulting CIAS to occur concurrently. This lead some candidates to take the action of tripping the reactor on the indication of a CIAS, despite the apparent inadvertent nature of the actuation.

Some minor simulator problems were identified during the course of the simulator portion of the operating examinations. These problems were conveyed to the simulator staff.

5. Exit Meeting On August 12, 1988 an exit meeting was condt.cted with licensee representatives, as noted in Paragraph 2 of this report.

The concerns of Paragraph 4 were conveyed to the staff, and the course of the examination process was discussed. The facility staff reiterated a concern over the length of the written examination. The examiners stated that they were cognizant of the concern and would take all prudent consideration during the examination grading and review process.

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'. RESOLUTION OF FACILITY CO.v ENTS AND GRADING KEY CHANGES Reactor Operator Examination:

Question: 1.07 Facility Comment:

The facility staff requested that if a candidate made a calculational error, that partial credit be awarded.

Resolution:

The examiner points out that the objective format does not lend itself to partial credit because some candidates may not provide any written calculations, it would therefore be unfair to allow partial credit.

Question: 1.08 Facility Comment:

The facility staff requested that the answer be changed to (c.) rather than(b.).

Resolution:

3 Agreed. The key will be changed.

Question: 1.17 i facility Comtrent:

1

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The facility staff requested that if a candidate made a calculational

, crror, that partial credit be awarded.

Resolution

This question does not require a substantive effort in tertns of calculation. In fact it can be readily deduced by rules of thumb.

Therefore the examiner sees no reason for the award of partial credit.

The examiner also points out that the obiective format does not lend itself s

to partial credit because sece candidates may not provide any written calculations.

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i Question: 1.21 Facility Coment:

The facility staff rectuested that if a candidate made a calculational '

error, that partial credit be awarded, j Resolution:

Same as for question 1.07 l I

Question: 1.22 Facility Coment:

The facility staff requested that if a :andidate made a calculational error, that partial credit be awarded. ,

f Resolution:

Same as for question 1.07.  !

Qutstion: 1.25 l l-Facility Coment- '

t The facility staff requested that if a candidate made a calculational erroi, that partial credit be awarded.  !

t Resolution: l This question involves a rudimentary calculation that should take a competent operator very little time to tom 91ete. The fortnat of an i objective answer question makes it too hard to award partial credit i because some candidates would not show work. No award of partial credit a can be given.  ;

Question: 2.03 j Facility Comment:

The facility reviewers requested that this question be modified due to i confusion over two separate actuations being requested for part (a.). The i suggested resolution is to accept one answer. j Resolution:

Part (a.) will be changed to require cnly one response and the point value  !

reduced to reflect that change. l l

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Question: 2.04 Facility Coment:

The facility requested that the examiner accept other terminology for the makeup stop valve.

Resolution:

This question was deleted. The reasoning is that it requires memorization of the control schemes of the valves and their reset operation.

Question: 2.05 Facility Comment:

The facility reviewers requested that only two answers rather than three be accepted. These were Nuclear Service Water and the Fire Main.

Resolution:

Any combination of possible sources will be acceptet provided that a hose connection could be made up. Three responses will :till be required.

Question: 2.06 Facility Comment:

For part (a.) tne reviewers requested that the examiners accept power removed from the the valve as an alternate snswer.

l Pesolution:

Agreed. Will change the key. Another answer was also added to the key for part (a.) on further review by the examiners. The addition is "Administrative Controls", which is an acceptable means for control of operation of the gas vent system.

Question: 2.08 Facility Coerent:

"Allow "Gravity feed Yalves" as an alternate answer."

i L.; 'ation:

A. Will change answer key, 1

Question: 2,09 No facility cenrent. Regien y persernel added the ARRD lube oil flow low alam to the answer key.

Question: 2.10 Facility Coment:

For part (a.) answer the reviewers requested that the examiner allow Letdown Relief Valve terminology be used. And for part (c.) the reviewers requested that the examiner accept either the lag circuit or a snubber in the airline as the answer.

Resolutior.:

Agreed. Will change the key.

Question: 2.11

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Facility Coment:

In part (a.) the reviewers expressed the opinion that the answer implied that only P001 has an excess ow check valve. The reviewers also proffered that increasing Que,ch Tank level would indicate a CB0 valve was leaking.

Resolution:

Agreed. Will change the key.

Question: 2.12 Facility - Coment:

The facility reviewers requested that the examiners accept responses with or without lieat Exchangers for full credit.

l Resolution:

I Agreed. Will change the key. Tha candidates were also allowed to provide

! both gas strippers as answers. The reason is the question did not l eliminate this as a possibility.

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Question: 2.14 Facility Coment:

The facility reviewers requested that part (c.) be deleted because the pump is no longer part of the system.

Resolution: l l

Agreed. Will change the key,  ;

Question: ,2.15 Facility Coment:

of The facility control valvereviewers requested be eliminated that for:n the the 60%

answer setting (a.)the standby flow fer part .

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-Resolution:

Agreed. Will change the key.

Question: 3.02 .

Facility Coment: f The facility reviewers requested that the entire question be deleted. [

Their reasoning is that it requires a knowledge level far in excess of  ;

that required for a system question.  ;

Resobtion:

The examiner agrees that part (b.) be would require extensive knowloc'ge of the system and procedures to.such a detail that it would be unreasonable.

However part (a.) does not require that knowledge level and will be left in.

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! 3,03 Question:

Facility Coment:

The revie,<ers noted that the loss of load trip is no longer in service at

the facility.

Resolution:

The response will be deleted.

) i Question: 3.04  ;

l Facility Conrent: i For part (a.1.) the reviewers requested that "remains as is" be accepted; I part (b.1.) should have as an answer "Min Speed"; part (c.1.) should be j 0%. The facility reviewers also reauested that part (d.) be deleted. }

Resolution:

part (a.1.), (b.1.), and (c.1.) wii' tm changra, Dart (d.) will be changed >

to require that only a valid flow decund signal is aquired. On further '

review during grading the examiners determined toat part (e.) was double t jeopardy, it was therefore deleted.  ;

1 Question 3.05 Facility Comment:

The facility reviewers requested that anothar acceptable answar be "There is no other back up instrumentation for items 2, 3, or 4 of the answer key."

Resolution:

The examiners initially accepted the facility coment. Subsequent grading .

revealed that all of the candidates had correctly answered the question.

The examiners therefore determined the coment was without merit and l retained the question as is.

Question 3.07 ,

Facility Coment:

Tiie facility reviewers asked that the examiners accept 2/4 logic in addition to 1/3 for part (a.). Their reasoning was that the answer could be considered 2/4 witn the high trip in for the failed transmitter.

Resolution: ,

The comment was not accepted. The question asked "What is the remaining RPS trip logic?". This i.colias that the failed channel is not to be

. included.

Question 3,08 Facility Coment

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The facility reviewers requested that part (a.) also have as an  !

alternative answer axial power distribution. For part (b.) and (c.) they l 4

requested that another answer be considered, "It does not prevent the CPC i from calculating an incorrect LPD."  ;

Resolution:.

i For part (a.) the examiners changed the key. The other coments were not accepted.

Question 3.10 r

No facility coment. The call of the question was not consistent with the i answer key in this case. The key was changed to allow full credit for depressing the low pressure reset push-buttons for the low pressurizer -

pressure setpoint. l

1 Question 3.13 Facility Comment:

The reviewers indicated part (b.) has "Only CCAS" or "CCAS and CRIS" as possible answers.

Resolution:

Agreed. Will change the key.

Question 4.04 No facility coment. Full credit will be given for "trip the reactor", and "be in Hot Standby". This resolution also applies to Question 8.11b of the SRO examination. This is for consistency.

Question 4.07 No facility coment. Questico 4.07 was deleted because it required the Reactor Operator to comit to memory the three people who must authorize exceeding the administrative quarterly dose limits. This varies with the dose limit being exceeded. The question is too specific, while the lesson objective is very general with regard to what is required knowledge.

Question 4.10 No facility coment. The key was modified to reflect that several conditions other than steam binding (i.e. water hammer, overheated bearings etc.) could be the cause of inoperbility due to high temperature.

Question 4.12 Facility Coment:

The facility reviewers expressed the view that this question was beyond the scopa of Reactor Operator knowledge, and would require the R0 to have memorized the Floating steps of the E0Ps.

Resolution:

The procedure, 5023-12-7, infers that the operator wou?d know the satisfactory running current for the Reactor Coolant Pumps because the Floating step (FS-1B) does not contain the criteria. The NRC K/A's for this arec have importance factors over 2.5, and that would infer significance from an industry and regulatory point of view. The key was changed to indicate that 650 +/- 150 amps was an acceptable answer. The amperage was taken frein the RCP operating procedure (S023-3-17).

Question 4.17 Facility Coment:

The facility reviewer requested that this nuestion be deleted as it was

• outside the scope of an R0's duties.

Resolution:.

Agreed. Will delete the question.

Question 5.03 Facility Comment:

The facility staff requested that if a candidate made a calculational er*or or used the correct methodology, that partial credit be awarded. -

Th ir reasoning involves the fact that all of the plant's key

• inscrumentation does not use psig, rather psia and psid are used. They feel this obviates the need to convert to psig.  ;

-Resolution:

This question does not require a substantive effort in terms of calculation. In fact the conversion by adding 15 psi would be accurate enough to deduce the answers from the steam tables. Therefore the examiner sees no reason for the award of partial credit. The examiner also points out that the objective fonnat does not lend itself to partial credit because some candidates may not provide any written calculations.

Question 5.04 Facility Coment:

Again the facility reviewers want partial credit if the ca:iidate shows his calculations.

Resolution:

This question does not require a substantive effort in terms of calculation. Therefore the examiner sees no reason for the award of partial credit. The examiner also points out that the objective format does not lend itself to partial credit because some candidates may not provide any written calculations.

Question 5.06 No facility coment. Region V personnel in reviewing this question noted i that it presents a possible double jeopardy situation. This is due to the fact that it is essentially a two part question. It presumes that MTC is the dominant effect to explain why Unit 3 at E0L will have a hiy Tave.

The key will be changed to reflect that CEA worth changes over core life  !

and to allow prtial credit to eliminate the double jeopardy case.

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i Question 5.10 Facility Comment:

The facility requested that (c.) as well as (b,) ba included as an answer.

Resolution:

A review of the reference mattrial shows that density compensation is not used in this circuit. Therefore only (c.) would be correct. (c.) will be

indicated as the correct answer in the key.

Question 5.12 Facility Comment:

Again the facility reviewers want partial credit if the candidate shows his calculations.

Resolution:

This question does not require a substantive effort in terms of calculation. Therefore the examiner sees no reason for the award of partial credit. The examiner also points out that the object 1/e format does not lend itself to partial credit because some candidates may not provide any written calculations.

Question 5.23

. No facility comment. The key did not provide all of the possible correct answers. Any three of the following will suffice for full credit:

Increased neutron leakage.

Neutron flux shifts.

Total neutron flux increases.

Burnable poison depletion.

Flux hardening.

Lower boron concentration.

Question 5.29 Facility Comment:

The facility requested that this question be deleted because none of the provided answers were correct.

Resoletion:

Agreed. Will delete question.

Question 6.01 Facility Coment:

The facility including calculation (requested its that theand inputs) examiners accept Power, ASI as acceptable delta T pcwer answers.

Resolution:

The question clearly asked for those inputs "in addition to the excore f inputs". That specirically excludes ASI because it uses excore detector inputs. However, the examiner will accept the following, RCS flow, Pressurizer pressure, and delta T power (in place of any of its inputs).

Question 6.02 F.tcility Comment:

The facility reviewers requested that_ the examiners accept Startup count rate as an alternative to Source Range count rate.

Resolution:

Agreed. Will change key, d

Question 6.05 Facility Coment:

The reviewers requested that the examiners accept "300 psia if bypass is removed from service" as an alternate answer.

Resolution:

The reference material provided does not support the comment. There will be no change to the key.

Question 6.08 Facility Coment:

The reviewers requested that the examiners accept pressures over the range of 711 to 729 psia.

Resolution:

AgreeJ. Will change the key.

Question 6.10 Facility Coment:

, The reviewers pointed out that the key did not include the possibility of loss of power or loss of instrument air as alternate answers for part (c.).

Resolution:

The examiners will accept answers which would cause a loss of air to

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-air-operated valves. Otherwise no change to the key.  ;

Question 6.11 Facility Comment:

. i In part (b.) the fccility reviewers requested that "HPSI pump seal cooler"  ;

be added as an additional answer.  ;

i Resolution: l Agreed. Will change key. [

1 Question 6.12 '-

! Facility Comment: i i

The facility requested the addition of "gas stripper" to the list as an I acceptable answer.

l Resolution: f Agreed. Will change key.

Question 6.13 Facility Comment:

The facility provided a list of items to be added to part. (a.). These add the following to the list:

Control Room Emergency Chiller starts.

CR Cabinet area ECU starts.

Emergency Chill Water pump starts.

Emergency Vent supply unit starts.

CR outside air dampers close.

CR Cabinet area ECU suction damper opens.

CR complex exhaust fans stop.

Resolution:

Agreed. Will change key.

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G;estion 6.14 facility Comment:

The facility reviewers requested that the following changes be made to the key:

Part(a.): 1 - 5% or minimum speed 2 - 0%

3 - 0% or 5%

Part(b.): Question should be deleted and points redistributed.

Psrt(c.): 1 - Variable (S/G 1 FRCS) 2 - 0%

3 - 0%

' Resolution:

Part(a.): The proposed answers are not accepted. They presume inputs from both steam generator FRCe exist. The question clearly identified the S/G-2 FRCS as the source of the flow demand signal. With a S/G-2 HLO rnd RTO present, all associated .FRCS components will receive a 0% flow demand signal (minimum). The key has beeb modified to reflect this.

2 Part(b.): The key was changed to reflect caly master controller flow 4

demand or a valid flow demand signal.

Part(c.): All the answers have been changed to reflect a 0% flow demand J signal.

Question 7.03 Facility Comment:

The facility requested this question be deleted. Their reasoning is that

this question requires procedural actions they feel are more appropriate j

1 for Health ?hysics personnel.

Resolution:  ;

Agretd. Will delete question from key. i I ,

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l Question 7.04

-Facility Comment:

The facility requested that this question be deleted. Their reasoni7g is that they view this as memorizing an app oval enain documented in a procedure.

Resolution:

This question was originally deleted per the facility requcst. There-is a <

lesson plan that does require that this is required knowledge, therefore the question ha.s been included. No change to the key.

Question 7.05 Facility Comment:

The facility reviewers asked that answers be accepted either on procedural cooldown rates, or Technical Specification cooldown limits.

Resolution:

The examiners determined that this question requires memorization of procedural rates. This is not required, especially in Mode 5. The NRC expects a responsible operator to rely on and carefully follow procedures rather than relying on memorization in this situation. The question has been deleted.

Question 7.12 Facility Comment:

The facility reviewers requested that the examiners accept subjective responses such as "normal" running current for part (b.). They pointed out i that the company does not expect its operators to memorize acceptance  !

criteria.

Resolution:

The key has been changed to allow for a 200 to 800 current range for the response to part (b.). This is certainly sufficient to account for the '

range of running current expected for the RCP's. [

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-Question 7.14 Facility Comment:

The facility reviewers argued that the resnonse for part (b.) was too narrow in secpe. They requested that a ret,ponse such as "could induce plant transient" be considered.

Resolution:  ;

There it sufficient room fo- examiner discretion, therefore no change to

, the key is warranted.

Question 7.15 l Facility Comment:

For part (a.) the facility requested that the question be deleted on the grounds it requires the candidate to recall from memory a procedural "note". The reviewers also raquested for part (c.) that the examiners accept "verify disch rge line valve lineup" for full credit.

Ret.o'. u ti on :

Part(a.): ' A note stating the advantage of discharging from Unit 3 precedes at least six of the site liquid radwaste procedures. It is also system knowledge that should be possessed by all of the SR0s.

Part(c.): The key will be changed to allow full credit for either response.

Question 7.16 Facility Comment:

The facility reviewers requested that the four criteria be accepted without the setpoints.

Resolution:

l Agreed. Will change the key.

4 Question 7.17 Facility Comment:

The facility requested that the examiners accept for part (b.) "to prevent

. electrical bus /buswork damage from overheating. And for part (c.) "RCP motor damage".

I Resolution:

Agreed. However examiner discretion covers these concerns and no change

will be made to the key.

ID L

Question 8.01 Facility Coment:

The facility reviewers requested this question be deleted. Their reasoning is a view that the question is misleading by asking for an action to maintain the plant in compliance within the Technical Specifications. It is not possible to do that under the conditions specified in the question.

Resolution:

The question only asks "when must the plant be in Hot Standby?" to comply.

This only required the direct application of LCO 3.0.3.

Question 8.03 facility Coment:

4 The facility requested that this question be deleted because the answers appear to require detailed knowledge of procedures.

Resolution:

The examiners recognize this and have changed th". key to meet the call of the question.

Question 8.05 No facility comment. During review of this question in Region V, the examiners noted that although the procedure identifies the responses in part (d.) as "Immediate Actions" we cannot support the view that they constitute required knowledge to be memorized. Imediate actions are manipulations of controls and equipment that require performance by an operator in such a short time that reference to procedures is not possible.

An imediate Notification List requiring notifications to be made within a proscribed time period certainly does not meet this test. Therefore part (d.) has been deleted.

Question 8.06 Facility Coment:

The facility reviewers requested that part (c.) be deleted. Their reasoning is that the calculation used is an approximation of ASI as calculated by the CPC. The calculation would not be used to satisfy the Tcchnical Specifications.

Resolution:

The key has been changed to allow full credit if the coadidates provide the general formulation of ASI.

Question 8.12 Facility Coment:

The facility reviewers indicated that the correct response was not included. They requested the question be deleted.

Resolution:

Agreed. Will delete the question.

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./5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 76

,. / THERMODYNAMICS ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 5.01 ( .75) ,

d.

REFERENCE SONGS REACTOR THEORY TEXT, PG 104, J' 'd 3.4 192006K106 ...(KA'S)

ANSWER 5.02 (1.00)

• To determine flow in NC:

Q = m cp delta-T => 100 = 100

• cp

• 60 => ep = 100 100

• 60

. cp = 1/60 (0.5)

THEREFORE: 3% = m

• 1/60

• 30 => m= 3% = 6% (0.5% tolerance)

(0.5) 1/60

• 30 REFERENCE GP HTT&FFF PG 179

.3. 4 002000K501 ...(KA'S)

ANSWER 5.03 ( .75) '

b.

REFERENCE Steam Tables O.4 193003K125 ...(KA'S)

ANSWER 5.04 ( .75) d.

l

5. "ilB iE OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND

- DYNAMICS PAGE 77 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

REFERENCE ,

SONGS REACTOR THEORY TEXT, PG 176, 196 3.6 004000A404 ...(KA*S)

ANSWER 5.05 (1.00)

Unit to 3 (0.50),will reactivity because be greater). it has the smaller Beff value (so its response (0.50)

REFERENCE SONGS REACTOR THEORY TEXT, PG 147, 181 3.1, 3.6 192008K114 192008K124 . . . (KA*S)

ANSWER 5.06 (1.00)

,' Unit 3 (0.50), because it has the more negative HTC value (so it will rcquire

, (Umt 2 a smaller temperature drop to offset the CEA reactivtity). (0.50) wtTH c sA w e st.TH cH Ao MS o v&R. core L lFG (o, f- t+ Ar.s ceso f 7)}

REFERENCE SONGS REACTOR THEORY TEXT, PG 147, 181 3.1, 3.6

.192008K114 192008K124 ...(KA'S)

ANSWER 5.07 ( .75)

C. '

REFERENCE SONGS REACTOR THEORY TEXT, PG 181 i 4.2 001010A207 ...(KA'S)

ANSWER 5.08 ( .75) b.

REFERENCE GP HTT&FFF PG 257 3.6

-.-..-y -----e,,,---. -

---

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

---

,w-, - - - --.

n

-5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 78 l

IHERMODYNAMICS ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

193008K105 ...(KA'S)

ANSWER 5.09 ( .75)

C.

REFERENCE RTD Circuit Analysis 2.9 ,

191002K114 ...(KA'S)

ANSWER SJO .75) f)

y - b @f/'y# )( C o R.Rg or MJ wG/2. /S ,C,,

+

REFERENCE GP HTT&FFF PG 285, 311

, 2.9 191002K102 ...(KA'S) i ANSWER 5.11 ( .75) d.

REFERENCE SONGS REACTOR THEORY TEXT, PG 196 2.8 192004K109 ...(KA'S)

ANSWER 5.12 ( .75) c.

REFERENCE SONGS REACTOR THEORY TEXT, PG 138 3.8 192008K104 ...(KA'E)

5. "HEORY

" OF NUCLEAR POWER PLANT OPERATION. FLUIDS. ABD PAGE 79 r E 1HODYNAMICS ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 5.13 ( .75) ,

b.

REFERENCE W0stinghouse, Thermal-Hydraulic Principles and Applications to the PWR, Vol. 2, 1982, p. 13-60 3.6 002000K518 ...(KA'S)

ANSWER 5.14 ( .75) a.

REFERENCE SONGS HTT & FFF, p. 126, 196

. 2.9 193008K106 ...(KA'S) e ANSWER 5.15 ( .75) b.

REFERENCE W stinghouse. Thermal-Hydraulic Principles and Applications to the PWR, Vol. 2, 1982, p. 11-29 3.0 191002K109 ...(KA'S)

ANSWER 5.18 ( .75) o.

REFERENCE ITT Barton, Differential Pressure Unit, Manual 509-2, 1976, p. 5-3 2.7 191002K104 ...(KA'S)

5. THE0BY OF NUCLEAR POWER PLANT OPE 86 TION, FLUIDS. AND PAGE 80 IBEBdQDYHAdlRE l i

ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I. l ANSWER 5.17 ( .75) ,

d. ,

REFERENCE SONGS REACTOR THEORY TEXT, p. 224 SONGS HTT & FFF, p. 203, 204 192006K108 ...(KA'S)

ANSWER 5.18 ( .75) c.

REFERENCE SONGS HTT & FFF, p. 320 2.7

.191004K112 ...(KA'S)

ANSWER 5.19 (1.00)

(sur)t P = P(initial) x 10

-4 (.75)2 P = 10 x 10

-4

.5 P = 10 x 10

-3 P = 3.16 x 10 percent (0.25 for correct formula, 0.25 for correct substitution, 0.50 for correct answer)

REFERENCE SONGS REACTOR THEORY TEXT, p. 139 4.4 001000A106 ...(KA'S)

5. 'THEQRY OF NUCLEAB POWER PLANT OPERATIQHulLilIDS. AHD PAGE 81

. IBEBdQMHAt1ES ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 5.20 ( .75) ,

d.

REFERENCE SONGS REACTOR THEORY TEXT, p. 201 2.8 192005K107 ...(KA'S)

ANSWER 5.21 ( .75) d.

REFERENCE SONGS HTT & FFF, p. 319, 320 3.1

- 006020K601 ...(KA'S)

ANSWER 5.22 ( .75) b.

, REFERENCE SONGS REACTOR THEORY TEXT, p. 141 3.3, 3.0 192003K106- 192003K107 ...(KA'S)

ANSWER 5.23 (1 g o,s sAcy m Mr s od m. 50) set.cman) g,

1. ncreased neutron leakage,(at EOLM 1ower boron concentration). (0.50)

2. Neutron ilux shif tc.iuithin the corej (to outer edges) . (0,50)

3. Total neutron flux increases.(compensates for fuel depletion). (0.50) 4 W mam t> ort.ersJ T. W5 d>APeWa+y REFERENCE SONGS HTT & FFF, p. 200 SONGS REACTOR THEORY TEXT, p. 63 3.1, 3.7, 2.9, 3.4 015000A103 015000A106 015000A107 015000K504 ...(KA'S)

I

~5. THEORY OF HUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 82 IliEBtiQD1tiati1GS ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 5.24 ( .75) .

---

c ---- ,

REFERENCE

• Steam Tables 193003K125 ...(KA'S)

ANSWER 5.25 ( .75)

---

c ----

t REFERENCE SONGS 2 TS PG B 3/4 4-7 193010K105 ...(KA'S) ,

ANSWER 5.26 (1.50)

S/G heat transfer = Q = UA(Tavs - Tstm) (0.25)

Q, U, and Tste remain constant; A1(Tavg1 - Tata) = A2(Tavg2 - Tatm) (0.25)

A2 = 0.95 x A1 (0.25)

From Steam Tables: Tsat for 995 psia = 544 F (0.25)

A1(587 - 544) = 0.95A1(Tavg2 - 544) (0.25)

Tcvg2 = 589.3 F (588.5 to 590.0 F acceptable) (0.25)

REFERENCE i GP HTT&FFF PG 166 191006K113 ...(KA'S)

I t

5. "LEORY OF NUCLEAR POWER ELANT.OPEBATION..ELUIDS. AND PAGE 83 2:E3t)RDYHAt119S ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 5.27 ( .75) .

C ,

REFERENCE GP HTT&FFF PG 320 193004K106 ...(KA'S)

ANSWER 5.28 ( .75) b ----

REFERENCE GP HTT&FFF PG 100 193007K101 ...(KA'S)

ANS 5.29 ( .75)

REFERENCE SONGS REACTOR THEORY TEXT, PG 211 3.0 192005K109 ...(KA'S)

ANSWER 5.30 ( .75)

G.

REFERENCE SONGS HTT & FFF, p. 200 SONGS REACTOR THEORY TEXT, p. 104, 221 2.9 192005K108 ...(KA'S)

8. PLANT SYSTEMS _ DESIGN. CONTROL. AND INSIBUMENTATION PAGE 84 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 6.01 (2.50)

c. 1. (Adjusts the excore signals such that) each detector l's effectively rosponsive only to the flux immediately adjacent to it. ( 0.;50 )

2. (Adjusts the excore signals to) account for abnormal flux leakage ccused by rod insertion. (0.50)

3. (Adjusts the excore signals to) account for reduced neutron leakage from the core at lower temperatures. (0.50)

b. 1. CEAC penalty factors

2. CEA position (Radial peaktng factors)

3. Azimuthal tilt (operator input) (any 4 at 0.25 each)

- old a ) *$OSEl*W($0?If**d)

7. L pnnuee 10, p. 37,38,48,49,53 O* O T / 0Wff;I 9; Ys dj 94 7 /1#f 23.2 012000K607 ...(KA'S)

\NSWER 6.02 (2.25) c,. 1. Startup - Fission chamber (0.25)

2. Safety - Fission chamber (0.25)

3. Control - Ion chamber (uncompensated) (0.25)

b. 1. Boron dilugiopcount monitors (on CR50)

2. Sourcp478g8 rate (on CR50)

3. Audible count rate (any 4 at 0.25 each)

4. Plant monitoring system

5. Dual pen recorder

c. 1 E-4 % power (0.50)

REFERENCE SD-SO23-470, p. 5,8,9,11,15 3.2, 3.2, 3.7 015000K604 015000K601 015000A103 ...(KA'S)

6. PLANT SYSTEMS D2EIGH. CONICOL. AND_1ESIBUdERIAllg8 PAGE 85 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY. I.

ANSWER 6.03 (1.00)

1. High pressurizer pressure pretrip

2. Local Power Density pretrip (0.25 each) ,

3. DNBR pretrip -

4. CEAC pennity factor received by any CPC REFERENCE SD-SO23-480, p. 2 SD-SO23-510, p. 38 3.5, 3.8 0010000010 001050K401 ...(KA'S)

ANSWER 6.04 (1.50)

c. High containment pressure (0.25) at 2.95 psig (0.25)

-b. Each time the pretrip alarm is received (or when pressurizer pressure drops to approx. 150 psi above the trip setpoint) (0.25) the operator must

-d: press the RESET pushbuttons (on the PPS Operator's Consoles) (0.25).

Wh:n pressurizer pressure decreases below 400 psia (0.25), the operator cust bypass each PPS channel (key-operated) (0.25).

REFERENCE SD-SO23-720,

~

p. 7

. SO23-5-1. 5, Attachment 6, p. 7, 18 3.9, 4.4, 4.4 011000K412 013000K101 013000A403 ...(KA'S)

ANSWER 6.05 (1.50)

1. No setpoint

2. 300 psia (0.50 each)

3. 550 psia REFERENCE SD-SO23-720, p. 7 SO23-5-1.5 Attachment 6, p. 7, 18 3.9, 4.4, 4.4 013000K412 013000K101 013000A403 ...(KA'S)

Eu__ELANT SYSTEMS DESIGN. CQHIBQL. AND INSTRUMENTATION PAGE 86 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 6.06 (1.00) c.

~

T-ave < (666 degrees F) (0.50)

b. The operator places the Permissive Switches of the affected SBCVs in MANUAL. (0.50)

REFERENCE SD-SO23-175, p. 30, 31, 37 3.9, 3.3, 3.4, 3.0 0410000007 041020A302 041020K409 041020K417 ...(KA'S) -

1NSWER 6.07 (1.00)

1. Increasing pressure will cause SBCVs to open at a lower steam pressure (or lowers SBCS program setpoints). (0.50)

2. Decreasing pressure will have no effect on SBCS. (0.50)

' REFERENCE SD-SO23-175, p. 30, 31, 37 3.9, 3.3, 3.4, 3.0 041020K417 041020K409 041020A302 041000G007 ...(KA'S)  ;

tNSWER 6.08 (2.50) i

c. 49% " ' - (0.50)

(7ll f0 7el f f f /q)

b. SG-2 (E-088 or unfaulted) (0.50)

1. low level - <25% (0.25)

2. 50-2 pressure > SG-1 pressure by >/= 50 psig (0.25)

c. SG-1 (E-089) - 0% (0.50)

SG-2 (E-088) - 25% - 30% (0.50)

REFERENCE SD-8023-720, p. 15, 21, 49 3.7, 4.6, 2.9 061000K411 061000K402 039000K402 ...(KA'S) e

f. PLANT SYSTEME DESIGN. CONTROhi_AHD INSTRUMENTATION PAGE 87

' ANSWERS -- SAN ONOFRE 2&3 -88/07/28-KINGSLEY, I.

ANSWER 6.09 (1.75)

o. It prevents bypassing more than 1 trip channel (0.25) for a given RPS trip (0.125) at the same time. (0.125) -

b. If a second trip channel bypass is attempted for a given RPS trip (0.25), all trip channel bypasses for that RPS trip are removed. (0.25)

c. 1. Low pressurizer pressure

2. Low SG pressure (0.25 each)

3. Low SG 1evel REFERENCE SD-SO23-710, p. 24, 25 SD-SO23-720, p. 7 3.6, 3.5 012000K604 012000K603 ...(KA*S) t ANSWER 6.10 (2.00)

c. 1. Ion exchangers

2. Boronometer (0.25 each)

3. Process radiation monitor

b. Thermal shock to the inlet nozzle of the RCS loop receiving charging.

c. 1. SIAS p . /,m cu4 mag) (0.50

2. CIAS Wemperature J @(0.25 each) @y

3. Letdown high g g REFERENCE SD-SO23-390, p. 12, 22, 27, 54 g pd 3.1, 3.0, 4.3, 4.2, 3.1 1 004020K404 004020A203 004010A401 004010A205 004000K509 l ...(KA'S) l

• - f

6. PLANT SYSTEMS DESIGN. CONTROL. AND INST @d_ENTATION PAGE 88 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 6.11 (2.00) {

c. 1. Waste gas compressor *

2. Gas strippers

3. Misc. waste evaporator '

4. Radwaste condensate sample cooler

5. PASS sample cooler (0.25 each)

b. 1. Shutdown cooling heat exchanger

2. Letdown heat exchanger (any 3 at 0.25 es. i

3. Spent fuel pool heat exchangers

4. RCP seal coolers C*

REFERENCEf/f35)*adMf 394l C edft r.$

SD-SO23-400, p.6, 20 SO23-13-7, p. 10 3.4, 3.3, 2.9, 2.8 008030A404 008030A202 008000K104 008000K102 ...(KA'S) hANSWER 6.12 (1.00)

1. Letdown heat exchanger

2. Boric acid concentrator (any 2 at 0.50 each)

3. Misc. wgsge evaporator V. 6ers,5ir/p/P/*

REFERENCE

'SD-SO23-400, p.6, 20 SO23-13-7, p. 10 3.4, 3.3, 2.9, 2.8 008030A404 008030A202 008000K104 008000K102 ...(KA'S)

ANSWE8 6.13 (1.50)

c. 1. Normal A/C onit isolates. (O. 75 P

2. Emergency isolation dampers close. (,.

. .,,- Y 9g,y

3. Emergency A/C unit starts. t^ . 2 51-

4. Emergency ventilation unit starts. (^.25i

b. The operator must position a (key-operated) Transfer Selector switch, g g fp q, gpfpyg (0 60) nEFERENCE 8. C A fecryency Chl//er jfer kg SD-SO23-700, p. 37 6 . C R Crbin& Ore g FCK Ste rfJ 3<be 29 7. Fin ery. / S fe e t.s 5 .l? m ery . CW Ve n t.sTymp p /p u nN r Yer Yr

1. Ctt o utsh/e aie'y's//eY/an s c/es,fer.1 c./cae.

/0.CeLWf erte Mcy rs<chen c/e w o p e n .5

// . CA coqler exAag.sf Pgnce) S

L__ ELANT SYSTEMS DESIGN CONTROL. ANDJESTRUMENTAT108 PAGE 89 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

073000A201 072000K204 ...(KA'S)

ANSWER 6.14  %) 7.18

c. 1. O/% (M*'ni < M J/ *

2. 0% (cleftd 0. -

3.O $% (sje;ed) $Q each) ,

/,4r1~. ref su'/ t V (

b. 1. "'i-^ dalav +4- r rut, a..d  ;;.ibi  ?

es l VAUD / l u s>[

2. /

Master controller flow demand < 5%) ((0,25)o.,3 J') F u LL C A0 # ec zk/wL 0'7

1. O "=.-Lab 1 w s

..~GL c.

2. 0% (c/af *tmHM sfed)t 50 each) "

3. 0%(g./gsg REFERENCE SD-SO23-250, p. 56, 57, 62, 63, 87, 88, 89 3.0, 3.1 059000K418 059000A203 ...(KA'S)

7. PROCEDURES - NOPMAL. ABEREMAL, EMEBGEEQ1_AND PA0E 90 BADIOLQQ1 GAL CONIBQL ANSWERS -- SAN ONOFRE 2&3 -86 ,7/26-KINGSLEY, I.

ANSWER 7.01 (2.50) ,

c. 1. Failure of 2 or more CEAs (0.25) to drop following a reactor trip. ,

(0.25)

2. One or more regulating groups (0.25) telow the PDIL. (0.25)

3. Shutdown Margin is determined to be < 5.15% (0.25) when T-ave is >

200 degrees F. (0.25) 1

4. Shutdown Margin is determined to be < 34 (0.25) when T-ave is < 200 degrees F. (0.25)

5. Uncontrolled cooldown of the RCS (T-ave > 25 degrees F below T-ref)

(0.25) caused by excessive feedwater addition (or excessive steam cithdrawal). (0.25)

6. During refueling (0.25) wis 's Xeff > 0.95. (0.25) 1

7. During refueling (0.25) with boron concentration less than 1720

' ppm. (0.25)

(any 4 for full credit) l

b. 'RWST (0.50)

'.RIFERENCE l AOI SO23-13-11, p. 2,3,4 l EOI SO23-12-1, p. 3 4.4, 4.4 l

i 000024K302 000024K301 ...(KA'S) 1 ANSWER 7.02 (1.00)

o. Through the fuel transfer tube. (0.50)

b. Because the fuel handling butiding was at a lower pressure than the c:;tainment. (0.50)

REFERENCE LER 2-87-013 3.7, 3.6 072000K403 072000K203 ...(KA'S)

1  ? .

g ABNORMAWtiEBQENCY_AllD PAGE 91 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 't . 0 3 (1.50) ,

1. The alarm sour t e determined. (0.50) ,

2. Any removable co nat n u's be r moved. (0.50)

3. HP supervision or managemen at r iew the situation and approve rolease. (0.50)

REFERENCE LER 2-87-026 LER 3-87-003 3.4, 3.5 194001K104 104001K103 ...(KA'S)

ANSWER 7.04 (1.75)

.. o . Normal - 1.25 Rem (0.25) t Maximum - 3.0 Rem (0.25)

b. 1. Lifetime whole body exposure < 5(N - 18) (N : age in years) (0.25)

2. Comp ted NRC Form 4 or equivalent (0.25)

.. d . 1. HP ur Dosimetry Supervisor) (0.25)'

2. Station Ma (0.25) ONeMNC D64972

3. Worker's supervi (0.25)

REFERENCE SO123-VII-4.8, p. 18 10CFR20.101 3.4. 3.5 194001K104 194001K103 ...(KA'S) 4

7. PRQQEQQBES - NORMAL, ABNORMAWtiEBGEt!QY_.MQ PAGE 92 B&DlQLOGICAL CONTBQL ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 7.05 (1.50)

a. 0 (0.75) oCy - 0795

[} QC[j~/0l(,

b. 0550 .75) OJYI' REFERE! ICE SO23-5.15, p. 4 Tcchnical Specification LCO 3.4.8.1 3.9, 4.0 002000G011 002000G010 ...(KA'S)

ANSWER 7.06 (1.50)

o. 1. Pressurizer pressure < 1430 psia. (0.50)

2. Pressurizer pressure uncontrolled. (0.50)

b. CIAS actuated. (0.50)

REFERENCE S023-12-1, p. 6, 10 3.7, 4.0 000015A210 000011A103 ...(KA'S)

ANSWER 7.07 ( .75) c.

REFERENCE SO23-12-1, p. 6, 10 4.1 000007G010 ...(KA'S)

ANSWER 7.08 (1.00)

~1515 (1430 - 1600)

REFERENCE 8023-13-2. p. 17 3.1 l 194001A108 ...(KA'S) i

L._ flDCE3URES - NORMAL.__ ABNORMALJMEBGENCY AND PAGE 93

.R_A>10LOGig&L CONIBQL ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 7.09 (1.50) ,

c. To prevent turbine blade damage. (0.50)

b. Pump discharge bypasses lube oil cooler and filter. (0.50)

c. To prevent overfeed during RTO events. (0.50)

REFERENCE SO23-2-1, p. 4 2.9 059000G010 ...(KA'S)

ANSWER 7.10 (1.25)

.o. Backleakago through check valve (in AFW supply line to SG-2). (0.75)

b. AFW pumps P-140 and P-504. (0.25 each)

REFERENCE SO23-2-4, p. 17, 47, 48 4.2 061000K101

...(KA'S)

ANSWER 7 11

. (1.25)

c. 1. Voltages +/- 14 (voltages matched). (0.25)

2. Synchroscope within 5 minutes of straight up position (proper phase cngle), (0.25)

3. Synchroscope rotating once per 10 seconds (proper frequency slip).

(0.25)

b. To prevent a EDG trip (from anti-motoring). (0.50)

REFERENCE SO23-2-13, p. 63, 65 4.3, 3.4 3.3, 3.0, 064050A101 064000G010 064000A401 064000A209 ...(KA'S)

.- .J

7. PRQQE MBES -'HQBB & ABNORd6L. EMEBQENCY A@ PAGE 04 E.QIOLOGICAL-CONTBQL ANSWERG -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 7.12 (1.00) .

c. At least once per 10 minutes. (0.50) s oe- O!;

90 0 -

b. 000,'.00 1^^ amps (0.50)

REFERENCE S023-12-7, p. 25, 28, 33 2.0 3.4, 3.2 003000A402 000017G012 000017G010 ...(KA'S)

ANSWER 7.13 (1.00)

c. (Direct an operator to) lower upender to horizontal position. (0.50)

(b. (Direct an operator to) lower fuel assembly into core. (0.50)

.' REFERENCE SO23-13-20, p. 7 4.1, 3.7, 3.8 000036K303 000036G010 000036A104 ...(KA'S)

ANSWER 7.14 (1.50) l o. The ion exchanger resins have a greater affinity for boron absorption

, Ct lower temperatures. (0.50)

b. To prevent control (throttiv) valve opening if CVOL fails high. (0.50)

O. To prevent (an out of sequence) trip from CPCs. (0.50) i REFERENCE SO23-5-1.7, p. 5, 6 3.4, 2.8, 3.5 045000G010 0040000010 001000G010 ...(XA'S)

~ -

7. ?ROCEDUBES - _ NQBtf&L. ABNOBt1AL. EtiEBGEtiGLAND PAGE 95 1 36D10k221 GAL CONTROL  ;

ANSWERS -- SAli ONOFRE 2&3 -88/07/26-KINGSLEY. I.

ANSWER 7.15 (2.00) ,

c. The Unit 3 release line is submerged. (0.50)

b. The radwaste discharge isolatiori valve will shut. (0.b0)

c. 1. Additional samples are taken and analyzed to be within limits of 10CFR20. 3^ or2

, ( p, fp) j W

2. Valve lineup is verified. ' O . 0 5^7 Co,J"d)

d. Estimate flow periodical.ly. (0.50)

REFERENCE SO23-3-7, p. 49, 93 SD-SO23-700 Tcchnica) Spect.fication 3.3.3.8 4.2, 3.1, 3.9, 3.3, 3.9 073000K301 073000G010 073000A401 068000A204 000059A205

'...(KA'S)

ANSWER 7.16 (2.00)

1. Pressurizer pressure *-200 pri (0.25' - ' nrt d e r r r r:1.; . (0.2t) ( #. JFdh)

2. Pressurizer level 00% ;0_ 5; ...d .m'. I:::;;;i..;. (^.25' ( ao Jrd)

3. Core exit saturation margin e 20 dr:r^^r "- (0.50)

4. Keactor vessel level : SC': . (0.50)

REFERENCE SO2?-12-3, p. 26 4.3 000011A211 ...(KA'S)

2 PROCEDURES - NORMALJHQBHAutfEBGEELAg PAGE 96 BADiQkQQICAL CONTBQL ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER' 7.37 (2.00) ,

c. To prevent core lift. (0.50) ,

b. To provent bus feeder breaker from overheating. (0.50)

o. To prevent RCP motor winding damage. (0.50)

d. To minimize seal damage. (0.50)

REFERENCE SD-SO23-360, p. 28 SO23-3-1.7, p. 3, 4, 5 3.6 0030000010 ...(KA'S) 9 1

8. ADMINISIBATIV2 PROCEDUBES. CONDITIONS. AND LIMITATIONS PAGE 97 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 8.01 (2.00)

c. 1745 (1.00)

b. 2000 (by LCO 3.8.1.1.e), or 0$13 (by LCO 3.0.3), or (1.00)

a. plus 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> REFERENCE Tcch. Spec. LCO 3.8.1.1 Tech. Spec. LCO 3.0.3 SO123-0-1, p. 4 3.7, 4.3 000055G010 000055G008 ...(KA'B)

ANSWER 8.02 (1.50)

-c. Control Room Supervisor (or On-shift Operations Superviso)) (0.50)

b. Only when:

1. The unit is in Mode 5 or 6, (0.50) and

- 2. The CRS and SS are absent from the control room. (0.50)

REFERENCI S0123-0-2, CRS Authority, Responsibilities, and Duties, p. 6 3.9 194001A109 ...(KA'S) 6 F M e M N O W S' G. Va.tvt i s she kal To V.Lm y y c /e r a ti tu

• f,0 h vu + oe t v u 1, e cf f lW? (W4ffW ANSWER 8.03 (1.75) o_p, q, ge,ing ,s coure.c re c #9 a n y et f H a 1. out, raSt J.

c. Ysive is ked to verify proper operation, (0.25) position itdication, f .2 ) and pr g packp g leakage. (0.25)

b. Pump is brAted/bnt8/gprager) re stabilized, (0.25) and then indicati ve h (0.25)

o. Annunciators are verified to be in the proper status for existing plant c:nditions (0.25) and actuate upon receipt of signal setpoint. (0.25)

REFERENCE SO123-0-21 Equipment Status Cont.rol, p. 22 4.1 194001K102 ...(KA'S) t

L. ADtf1HISIBATIVE..EBOCEDUBEL_CQEDITIONSJND_ LIB 11AI; sq PAGE 98 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 8.04 (1.b0)

c. The valve operator is turned in the "close" direction. (0.50)

b. The vlave operator is turned in the "close" direction. (0.50)

c. The valve operator is not operated. ('isual v observation only) (0.50)

REFERENCE 80123-0-23, Valve Operation, pp. 8,9, and 10 3.7 194001K101 ...(KA'S) 0

• S*)

ANSWER 8.05 ( Aarb )

s o. 0815 (0.50) ,

b. 0825 (0.50)

c. 0830 or a. + 15 minutes 0 09 W a. . + 3 6 min u te(s . 50 )

d. 1. Ann nee to all personnel: -

a. Eme ency Classification and time of declaratio, (0.25)

b. Name of mer ncy Coordinator (0.25)

2. Direct Shift o q{ptorto:

a. Initiate ou/ggent (0.25) b.

NK Activate onsi mys e@y' j pirens (0.25)

c. RepeatPAannouncenh) (0.25)

d. Initiate emergency recall (0.25)

REFERENCE S0123-VIII-1, p. 30 S0123-VIII-10 p. 27 S0123-0-1, p. 5 3.9, 4.4, 3.9 194001A116 194001A102 000055G010 ...(KA'S)

8.

ADM1HISTRATIVE PROCEDURES. 00HDII1QHS. AND LIdlIAllONS-PAGE 99 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 8.06 (2.50)

c. Neutron flux detectors are inaccurate below 20% power (or, core noise level is too large below 20% power). (0.50)

b. 1. -0.27 to +0.27 (0.25 each for a total of 0.50)

2. -0.20 to +0.20 (0.25 each for a total of 0.50)

c. Lower core power - Upper core power 7J

---

= ASI (0.6&# Tor correct equation)

Lower core power + Upper core power 25% - 29% &~ (*  % JYf $g

= ASI (0.25 for substitution) #" L - ).

25% + 29% A 7' I f' d~

.000 8I '

f.C: - 0.074 ./ (0.05' =

REFERENCE

( $, inkgfr o t>n Tcchnical Specifications, LCO 3.2.7 (including basis)

Technical Specifications, Definitions, p. 1-1 3.8, 3.9, 3.7 015020KE03 001000G011 0010000006 ...(KA'S)

ANSWER 8.07 (2.00)

c. 0850 (1.00)

b. 1. DNBR (0.25) shall te > or equal to 1.31 (0.25).

2. Peak linear heat rate (0.25) shall be < or equal to 21.0 kw/ft.

(0.25)

REFERENCE Tcchnical Specifications, LCO 2.1.1 Tcchnical Specifications, L-C0 2.1. 2 3.8 0100000005 ...(KA'S)

3 ADMINISTRA?IVE EBQ.CEDMBE W QliDITIONS. AND LIMIIAIl0lLS PAGE 100 ANSWERS -- SAN ONOFRF 2&3 -88/07/28-KINGSLEY, I.

ANSWER 8.08 (3.50)

c. 3.96 gpm +/- .1 gpm (0.50 for use of procedure, 0.25 for math, 0.25 for answer) -Cs/ M? JM 6AAnyt. M6egy ??hw est es.ta:

b. 3.44 gpm +/- .2 gpm (0.50 for use of procedure, 0.25 for math, 0.25 for answer)

c. 1230 (0.50) '

d. 1. One steam generator tube leakage (> 720 gpd) (0.50)

2. 81T check valve (pressure boundary valve) leakage (> igpm) (0.50)

(No credit subtracted for other answers if supported by a. or b.)

REFERENCE 8023-3-3.37, RCS Water Inventory Balance.

'Tcchnical Specification, LCO 3.4.5.2.

3.9, 3.9 194001A102 000037G008 ...(KA'S) fANSWER 8.09 (1.75)

O. ,

Boron concentration at least 2350 ppm (0.50)

b. Height of water at least 23 feet (0.25) over top of reactor vessel fitnge. (0.25) g

c. Ensures sufficient water depth is available to remove 99% (0.25) of iodine (0.25) released from a ruptured irradiated fuel assembly. (0.25)

REFERENCE Tcnhnical Specification LCO 3.9.1 Tcchnical Specification LCO 3.9.10, including basis 3.5, 3.6, 3.5 ,

.o '

7 y

c. 4

• T .

I

-. e l ..? i -  :  :-_ ,

~

i & a a

- - . .: .: =

C m' as

!f 'N a a  !. S-a ,- . * ,

imo e N .

I 3' o C i ta l3 A ' g'; D b; Nw Dl N O y g us -

p af i

-' !Mi % wt i i .i N N

s DR.-  ?-  !

i ,

g p i - ,

E

. J.; I H n N W

5 .

a u a t _ , ,

! i fe fe

!j

E

- iJ if E 15 1 i W i c. g>a C

. . g .- M.:: 3; 4 O -

2 > 5 > -

i *  :: * = -

a a

- - =

5 I

l-a h" 99 $

~

9 9 't a

9 %

a  :  : i 3

x. :. :. a a2 - -

l, =y

.2 2 2 2 x -

. .! ge.s x x x t 9

• c x x x x x x i-nt , ,

E n.

2 ic:9

=<s g- ,

, a a . . . .. -

M y %; R, s

< N .l__l i E b N k I

- -I ' '

\

5

. . M

( -

.a

. , , i, .

}{j 4:.

1-i 3

- ,f .. .. t p.. h"i x 03 d x e o e oi o1 '-

h%k O O -

y%gg o.. > > yli t e e.==

l

.N. * - (

- i

. . . . . . . . . . U 0:

72

~ o' N %!;

• S i

-02* -

Q 3 1 -- O  % o a 'O O t O' N s

D? 'e D O > > y -- * .  !

=

~

z

, i% g ygj r

- -. z

. d2 M.: %!

i_ _

e --

- ,a k t 2 12  %

r- N se:u ru sk tk tt

%s !n 2= hi s g

i. ] % 4-g . e

.. -- 6 --

a s -

dv 5' g -

- Se e 1* ci 3 t ,1 .:3 .22 -. -- -e

• m

-1

$" a

y2 23 25 d5 G8 33 Em G 5 e

2 S af 5I e:!

U-E b' .,$ 6; O .

t '

NilCLEAR GENERATION SITE 9 UNITS 2 AND 3 SURVEILLANCE OPERATING INSTRUCTICN 5023-1-3.3 REVISION 9  ; 4 g 10 C; J.3

( ATTACHMENT 1 TCN 4 - 4 _

2.0 DRCCEDURE (Continued) INITIAL.S 2.2 Determine the Instrument Uncer'.,31nty Value for calculation of Total Leakage. (Check one) .

m Data from Control Board instrumentation was u used. Enter 86.3 gallons for Uncertainty in step 2.3.1. q,;

p Data from PMS or CFMS was used. Enter N

8.2 gallons f or Uncertainty in step 2.3.1.

2.3 Total Leakage Calculation 2l3.1 Add volume' changes from Table 1:

(Algebraic sum) (Circle sign) agal VCT [)(-) /# 9 4/, j(, gal agal PZR 4

(+) @ 8 5. 2- gal agal H 0 Integrator + gal agal B.A. Integrator

+ gal Agal Tavg,

(+) @ 9 7. 3 gal

. Instrument Uncertainty + 8.A_ gal

~

Subtotal 9.f #, / gal

E !1'h2l}2:

Calculate (divide):

~

= ,. '

.'.'.:.?

_ .s:[. ~ . Subtotal 950, / gal Test Duration + 2#C min TOTAL LEAKAGE I. 74 gpm 2.3.3 If c.alculated total leakage is less than 1 gpm, then proceed to Section 2.7 and reark N/A for Sections 2.4 through 2.6.

l aTTarWWENT 1 0 4 e 2 7 tir 1 A

NUCLEAR GENERATION SITE UNITS'2 AND 3 SURVEILLANCE OPERA?!NG INSTRUCTICN'$023-3-3.37 REVISION 9 P4E 11 CF 43 ATTACHMENT 1 TCN , 4_4 2.0 OROCEDURE (Continued) INiil At.S 2.4 Identified Leakage ,

NOTE: Data for steps 2.4.1 thr'ough 2.4.3 is obtained from Table 1 of this Attachment.

2.4.1 Calculate SIT in leakage

.1 Determine the Instrument Uncertainty value for calculation.of SIT in-leakage:

m Data from Control Board instrumentation

'u was used. Enter 14.2 gallons for 9'I Uncertainty'in step 2.4.1.2.

E Data from PMS or CFMS was used. Enter 2.0 gallons for Uncertainty in step 2.4.1.2.

.2 Add volume changes:

T'008 2 85 gal T-007 + 0 gal

. T-009 + /7/ gal

. T-010 + 0 gal .

Instrument Uncertainty -

S.# gal '

Subtotal 8Y gal

.3 Calculate in-leakage rate: -

Subtotal '/ 54 gal Test Duration + 2 70 min TOTAL' SIT IN-LEAKAGE

/,8 7_ gpm e

s i

ATTACHMENT 1- PAGE 8 0F 14 -

. I

NUCLEAR GENERATION SITE UNITS 2 AND 3 SURVEILUNCE OPERI1'ING INSTRUCTION 3023-3-1.3 REVISICN 9 PAGE .2 0F 23

'* ATTACHMENT 1 TCN 9-d, 4 i -

2.0 PROCEDURE (Continued)

INITIALS 2.4.2 , .Qalculate RCDT in-ieakage

.1 Determine the Instrument Uncertainty value for calculation of RCOT in-leakage:

' Data from Control Board instrumentation was used. Enter 16.5 gallons for Uncertainty in step 2.4.2.2. .

E Data from PMS or CFMS was used. Enter 1 gall'on for Uncertainty in step 2.4.2.2.

.2 , Calculate the in-leakage rate:

RCOT Volume Change /d Y gal.

Instrument Uncertainty -

/ gal. .

Subtotal /(3 gal. ,

C RCDT A Time + MO min- .

RCDT IN-LEAKAGE ,88 gpm

, t 2.4.3 Calculate Quench Tank in-leakage

.1 Determine the Instrument Uncertainty value for .

calculation of Quench Tank in-leakage:

t

.i Data from Control Board instrumentation , ,..

was used. Enter 14.6 ga.l.lons for '

Uncertainty in step 2.4.4.2.

r1 U

Data from PMS or CFHS was used. Enter  !

2.1 gallons for Uncertainty in step 2.4.3.2.

.2 Calculate in-leakage rate:

Volume change / gal  ;

Instrument Uncertainty -  ! gal.

, Subtotal  ! gal.

Test Duration +

min

(. QUENCH TANK IN-LEAKAGE C gpm ATTACHMENT 1 . D ar. 0 or 'la I

NUCLEAR GENERATION SITE-SURVEILLANCE OPERATING INSTRUCTION $023-3-3.3?

UNITS 2 ANO~3 REVISION 9

- FAGE 13 CF 13 ATTACHMEN 1 TCN _ 9-2.0 ' PROCEOL'RE (Continued) INITIALS -

2.4. 4 - Obtain the latest St'eam Generator Tube Leak "

Rate resu1ts from Chemistry. (Ref. 2.2.1)

.1 Calculate (add):

SG E-088 800 gpd SG E-089 + V5O gpd Subtotal ./2 56 gpd

.2 Calculate (divide):

Subtotal /). 5 0 _ gpd Conversion + 1440 gps /gpd TOTAL S/G LEAK RATE .&7 gpm

( 2.4.5 Request from Chemistry the volume of any ACS samples drawn during this test.

. ' .1 Calculate (divide) Chemistry-Sampling Rate:

l Volume collected d , gal

. Test Duration e min i

)

TOTAL SAMPLING RA'TE O spo. '

' ' . . . .j c , c . . : e n: . . . . .. . . , . . . ,

2.4.6 If Additional tenkage Calculah,r Methods are required to fdentify leakage, then perform

, Attachment 5. Otherv.fse, mark this step N/A and record zero for Attachment 5 Leakage in step 2.5.1. -

o. .,

i I

9 l ATTACHMENT 1 PAGE 10 0F 14-t

NUCLEAR GENERATION SITE UNITS 2 AND 3 SURVEILLANCE 0PERATING INSTRUCTION' 5023-3-3.37

. REVISION 9

' PAGE 14 0F t3 ATTACHMENT 1

, TCN 4-4 2.0 PROCEDURE (Continued) INITIALS 2.5 Identified Leakage Calculation' 2.5.1 Add leakage rates from, previous steps:

_ /,8 9 SIT In-leakage + gpm (step 2.4.1.3)

RCDT In-leakage

+ ,68 gem (step 2.4.1.2)

• Quench Tank In-leakage + 0 gpm (step 2.4.3.2) <

i 5/G Total Leak + ,87 g pm .' i (step 2.4.4.2)

Sampling Leakage + C gpm s

(step 2.4.5)  ;

Attachment 5 Leakage + O spm'

'(step 2.4.6)

, =:.w n ====

1 IDENTIFIED LEAXAGE .7, W gpm 2.6 Unidentified Leakage Calculation * '

. 2.5.1 Calculate' difference (algebraic sum) between Total L.eakage, Identified Leakage, and Uncertainty:

TOTAL LEAKAGE gpm (step 2.3.2)

IDENTIFIED LEAKAGE -

gpm (step 2.5.1) >

s--u- =

. 9.t ,

(WIDENTIFIED LEAKAGE _. gpm 2.7 Perform calculation check. This is to be performed ,

independently by a qualified individual.

ATTACHMENT 1 PAnF 11 0F 14

8. ADMINISTRATIVE PROCEDMBES,_ CONDITIONS. AHD_Liti1IAI1QBS PAGE 101 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 8.10 (1.75)

c. 5.15% (0.50)

b. By verifying that CEA group withdrawal is within the Transient Insertion Limits. (0.75)

c. Steam line break. (0.50)

REFERENCE Tcchnical Specifications, LCO 3.1.1.1, including basis 4.4, 4.1 001000K508 001000G005 ...(KA'S)

ANSWER 8.11 (2.00)

c. 520 degrees F (0.50) oA. TAP TMC /k!WW

b. De in Hot Standby 4(within the following 15 minutes) (0.50)

c. The limit on T-ava ensures:

1. The MTC is within its analyzed temperature range. (0.25) ,

2. The protective instrumentation is within its normal range. (0.25)

3. The pressurizer is capable of being in an operable status with a etcan bubble. (0.25)

4. The reactor pressure vessel is above .its minimum RT-NDT. (0.25)  !

REFERENCE Technical Specifications, LCO 3.1.1.4, including bases 3.9, 3.8 004000G005 004000G011 ...(KA'S)

L I

8. ADMINISTRATIVE _PROCED.tjRES. CQHDlH ONS. AHQ_LIMII&HQH3 PAGE 102 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-KINGSLEY, I.

ANSWER 8.12 ( .75) ,g ' ,, ,, ,,

{_fM

@WW 406 D C C,7 7 " C '^%

i <'

Yr b

DQ(6[Q REFERENCE S0123-0-21 Equipment Status Control, p. 18.

4.1 194001K102 ...(KA'S) t ANSWER 8.13 (1.00)

July 26 at 1900 REFERENCE Tcchnical Specification 4.0.2 3.9, 3.8

, 0040000011 004000G005 ...(KA'S)

9' 4

t' 5 Alb ONOFRL 243 KO EgnM KEY e

e 9

l

~

~ 1l PRINC1ELES_QLHELEAB POWEB. PLANLQEEBAIlQH. PAGE F1

$tiEBtMDXHbtilh HEAT TRANSEER_AND_EL91D_EhQW_

$NSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE G.

ANSWER 1.01 ( .75) i

---

b ----

4 REFERENCE GP HTT&FFF N 100 193007K101 ...(KA'S) 4N2WER 1.02 ( .75) i

..o.........................___......

REFERENCE i SONGS REACTOh THEORY TEXT. PG 138 192008K104 ...(KA'S) o- v " !< 1. tia ( .75)

L'TERENCE GP HTT&FFF PG 320 193004K106 ...(KA'S)

\MSWER 1.04 ( .75)

---

a ----

REFTuMCE SONGS REACTOR THEORY TEXT, PG 224 192005K116 ...(KA'S) 4HSWER 1.05 ( 75)

---

d ----

REFERENCE SONGS kEAUTOR THEORY TEXT, PG 196 192004K109 ...(KA'S)

L.__f81HCIELES QE_tu!GLE6B_E0MEB_P1ANI_0REBAIION. PME 76

. JBEBtKMHAMIE_HE67 TEANSEEB_AND_ELVID_ELOW  ;

.ANGWERS -- SAN ONOFRE 2&3 88/07/26-WEAL.E. G. j ANSWER 1.06 (3.75) ,

S/G heat transfer = Q : UA(Tavg - Tstm) i (0.50)

Q. U, arid Tstm r+: main constant;  ;

r A1(Tavel - Tatm) : A2(Tavg2 - Tatm) (0.50 Gi'scii: A2 : 0.!s x A1 (0.25)

From Steam Tables: Tsat for 995 psia : 544 F (0.25)

A1(587 - $44) = 0.9A1(Tavg2 - 544)

Tavg2 = 591.8 F (591.5 to 592.2 F acceptable) (0.25)

REFERENCE GP HTT&FFF PG 166 191006K113 .. (KA'S)

WSWER 1.07 ( .75)  ;

Y.---c---- i

! REFERENCE ,

SONGS REACTOR THEORY TEXT, PG 141 192008K123 ...(KA'S)

. I t

i WSWER 1.08 ( .75) ti ,,  ;

---

b-- bbbbpabbbt bbb bW M REFEREF _M-85, 311 GP HTT4 i 1C1002K ...(KA'S) i I

l i

l i

1. PBIHCIELES OF.HUCLEAB_EQWEB._ELAHI_0EEBAIIQNi PAGE 79 IdEb W DXHablG L HE6I_IBAHHEB_AND FLUID __FLQW ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE. G.

ANSWER 1.09 ( .75) ,

---

b ----

REFERENCE GP HTT&FFF PG 257 193008K105 ...(FA'S)

ANSWER 1.10 ( .75)

---

c ----

REFERENCE

. "rcuit Analysis

. . . . . . d 'i 1 4 ...(KA*S)

(NSWER 1.11 (2.50)

Keffi = 1/(1-rhol) to.50)

S,ince Rhol = .02500, Keffl = 1/(1-( .025)) = .9756 (+/- .001) (0.25)

(0.50)

CR1/CR2 = (1-Keff2)/(1-Keff1) 135/405 = 1/3 = (1-Keff2)/1 .9756) Kelf2 = .992 (+/- .001) (0.25)

Rho 2 1-1/Keff2 (0.50)

Therefore, Rho 2 = 1-(1/.992) = .008io (+/ .001) or 0.814 delta-rho (+/- .1%) (0.25)

Re:ctivity added = Rhol - Rho 2 = .81 -(-2.50) = 1.694 delta-rho (+/- .1%)

(0.25)

REFERENCE 10 HGS REACTOR THEORY TEXT, PG 136 192008K104 ...(KA'S)

HUGLIAR MWEB_PLMIJEEBAIlh PAGE 80 1,.-

II M 35 M6 HEAT TMNSIER ASD 'rLUID FLOW ANSWEkS -- GAN ONOFRE 233 -88/07/26-WEALE, G. ,

ANSWER 1.12 ( .75)

I REFERENCE i GP HTT&FFF PG 296 191002K109 ...(KA'S)

ANSWER 1.13 ( .75)

---

d ----

REFERENCE SONGS REACTOR THEORY TEXT, PG 152, 163 192004K107 ...(KA'S)

ANSWER 1.14 ( .75)

---

d ---- [

EEFERENCE SONGS REACTOR THEORY TEXT, PG 150, 151  ;

102004K111

...(KA'S)  ;

r ANSWER l.15 ( .75)

---

c ----

17TERENCE 1 LONGS 2 TS PG B 3/4 4-7 l 193010K105 ...(KA'S)

ANSWER 1.16 ( .75)

.... e ....

REFERENCE I SONGS REACTOR THEORY TEXT, PG 181 192008K102 ...(KA'G) ,

t h

I l

L_._EBIRQ1ELES OF. NUCLEAB_EQWER_ELAHI_QEEBAIJOH2 PAGE 81

, IHERMODYHAMICS. HEAT TRANSFEB AND FLUID FLQH ANSWERS -- SAN ONOFRE 233 -88/07/26-WEALE, G.

ANSWER 1.17 ( .75) ,

t

---

d ----

f REFERENCE SONGS REACTOR THEORY TEXT, PG 141 ,

192008K103 ...(KA'S)

ANSWER 1.18 ( .75)

~~~~ a ----

REFERENCE SONGS REACTOR THEORY TEXT, PG 198 192004K110 ...(KA'S)

ANSWER 1.19 (1.50) ,

To determine flow in NC: ,

- i = m cp delta-T (0.50)

" Therefore, at 1004 100 = 100

• cp

• 60 => cp = 100 100

• 60

=> cp = 1/60 (0.25) '

. . f a

At 34 3 3% = m

• 1/60

• 30 (0.50) 34 4

=> m= --------

= 64 (0.5% tolerance) (0.25) 1/60

• 30 REFERENCE GP HTT&TTF PG 179 193008K122 ...(KA'S) L f

l f

1 I

1. PikhC12LES_QF__ NUCLEAB_19 WEB __ PLANT _ OPEBAIIQH.

PAGE 82

, I:E#10DYNAM1pS _ HEAT TRANSEER AND fly 1D_ELQW ANSWEh8 -- SAN ONOFRE 2&3 -88/07/26-WEALE, G. ,

4 ANSWER 1.20 ( .75) ,

---

d ---- , j REFERENCE  !

SONGS REACTOR THEORY TEXT, PG 182 1 192004K106 ...(KA'S)

ANSWER 1.21 ( .75)

---b--- ----------------

REFERENCE '

Stcan Tables 193003K125 ...(KA'S) i ANSWER 1.22 ( .75)

--d----------------------------------  ;

REFERENCE i SONGS REACTOR THEORY TEXT, PG 176, 196 l 004000A404 ...(KA'S) l

• NSWER 1.23 (2.00)

Unit 2 will have the smaller Beff value so its response to resetivity will be greater (1.00)

b. Unit 2 will have the more negative MTC value so it will require a smaller temperature drop to offset the CEA reactivtity (1.00) l REFERENCE i SONGS REACTOR THEORY TEXT, PG 147, 181 192008K114 192008K124 ...(KA'S)

T

1. PRINgifLES OF NUCLEAR POWEB_ELANT OPEB&I19th PAGE 83 li38tj0 DYNAMICS HEAT TRANSFER AND FLUID FLQW ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

l

{

ANSWER 1.24 ( .75)

~~-- c --~~

i .

REFERENCE Stcan Tables 193003K125 ...(KA'S)  ;

i ANSWER 1.25 ( .75) [

---

c ----

REFERENCE QP !?T7&FFF PG 179 -

193007K106 ...(KA'S) l r

' ANSWER 1.26 ( .75)

---

n ----

REFERENCE

^'"]S REACTOR THEORY YEXT, PG 140, 141

' 1LL6K120

- ...(KA'S)  ;

I

. I ANSWER 1.27 ( .75)

---

d ----

[

REFERENCE  :

SONGS REACTOR THEORY TEXT, PG 104, 221 [

192006K!C6 ...(KA*S) l l

I-I I

r l

l

2 PLANT DESIGtLlHCLUDlHQ_SAEEIOND_EMEBGEllGY_SYSIEdS PAGE 84 A!1SWERS -- SAN ONOFRE 2&3 -08/07/26-WEALE, G.

ANSWER 2.01 ( .75)

Wh n HV-8160 (or Shutdown Cooling Standby Flow Control Valvej fails (or loses power) (0.75) ,

REFERE!1CE SD-740 p. 45, 46 006000A202 ...(KA'S)

ANSWER 2.02 (2.00)

c. 1. Ion exchanger resinh

2. Borm.ometer (0.50 each)

3. ?cacess radiation monitor

b. U,etwal shock to the RCS loop charging inlet nozzle (0.50)

REFERENCE

SD-SO23-390, p. 16, 22, 27, 54 004000K509 004020K404 ...(KA'S) 1 AI:SWER 2.03 4 2. 501: h.CC) g y-gifg

'O. Starts /checksstartedp026orP-025(oroneCCWP).... , _ . - __g%_,__

"b. Tsolates (or closes supply /ratur- ' alves to/f rom) non-critical loop

o. Opens return valve (or HV 6500) . om SDC HX

d. Cuts in (or opens supply / return valves to/from) Cntat Emer Cool Units (0.50 each)

L u.

' ~ ~ ' ,; a _

o 4. .

.,,,,,e

.. . t. r,.;Q. .

. > / - - A-4 x a -

r REFERENCE SD-400 p. 7 008030A304 ...(KA'S) i

2. PLANT DESIGN INCLUDING _SAEETY AND EMERGElLQY_.SYSIEtLS PAGE 85 ANSWERS -- SAN 0"OFRE 2&3 -88/07/26-WEALE, G.

)

ANSWER 2.04 (1.50) r-

c. PrfmaryMakeu Water low Control Valve ( -0210X  :

Ma} eup Stop alve (FV- 253) ,

(0.5C each)

b. Push the C SE pushbutton on HS' 9253-1 >(or Makeup St p \. - FV-9253 oper ing witch) g , , 10.50)

REFERENCE Q O. i, .ahe.e. d M~

SD 390 p. 75 004000K404 ...(KA'S)

\NSWER 2.05 ( .75)

1) Nuclear Service Water (et. b4 (Jaded

2) Firemain (et nulil fam,5vwh aA,4 4 A I

3) Fire pumper / tanker unit (O.g5,each)

M "

REF E > 0* I hh SD-400 p. 24 008010K101 ...(KA'S)

WSWER 2.06 (2.50) kl. 1) ates over the OPEN pushbuttons l

2 gr,pp%

CTd1 oard valve control e a are deenergized (0.50 e aw qu(M ' $4 Two-)

b.

>-----SOV----->-----SOV-----> Quench Tank l l PRZR>---------- ^-----SOV-----!

i

>---- SOV-----l l l RX Vesnel Head >----- ^-----SOV----->-----SOV-----> Containment (0.5 for all components and valves, 1.00 for all originations/dastinations)

(1.50 total)

REFERENCE .

SD-360 p. 40, fig 1-1 ? S O'A S 2,9'h 002000K104 002000K403 002000K405 ...(KA'S) 1 1

I

2, PLANT DESIGN INCLUDING SAFETY ANQ_EMEBGEUQY BYSTEMS PAGE 86 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSWER 2.07 (3.00)

c. Pressurizer surge, RC drain header, Refueling level indic4 tor

b. Shutdown cooling (0.25 for each connection, 0.25 4ach location)

c. Sampling, Hot leg injection REFERENCE '

SD-360 p. 14  !

002000K106 002000K109 ...(KA*S)

ANSWER 2.08 (1.00)

1) Open(BAMT) Gravity Feed Valves (HV-9235, HV-9240) (0.50)

2) Close VCT Outlet Valve (LV-0227B) (0.50)

REFERENCE

.SD-330 p. 72 004000K404 ...(KA'S)

ANSWER 2.09 (2.00)

o. 1) Motor winding overcurrent/ overheating damage can occur while starting an RCP that is reverse rotating (0.75)

Hotor bearing damage can occur 6tring reverse rotation with no oil lift pressure (0.75)

b. 1)."9P P002(NE) Reverse Rotation annuciator(0.25)'

2) Loss of the Zero Speed indicating light (0.25) 0,2Sfts

% qsygr_

jg;c go l

O AGAb l.M o gL Fhw Lsw(eq gdLng .) OOC) G l REFERENCE

' SD-360 p. 20; SO23-3.1.7 p. 3 002000K602 ...(KA'S) l

2 PLANT DESIGN INCLUDING SAEETY AND_EMEBGENCY SYSIgdS PAGE 87 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

.=

1 ANSWER 2.10 (2.50)

c. Lifting (IntermediatePressure)LetdownReliefValve(PSV-9206) (0.75)

b. Steam flashing / water hammer in the letdown line i (0.75)

c. The lag unit (or electrical unit between pressurizer level controller (LIC-01LO) and letdown throttle valve controller (HIC-0110)) (0.50 d.

JO MDMi MM 04.4 #4ma.4 to ALth vain 44 The letdown accumulator )

(0.50)

REFERENCE SD-360 p. 66; SD-390 p. 14-18 004020A202 004020K612 ...(KA'F)

ANSWER 2.11 (2.00)

c. The excess flow check valve (on 3 pes. controlled bleedoff) (0.25)

b. 1) RC PUMPS BLEED-OFF RELIEF VALVE LEAKING annunciator

2) Increasing temperature on relief valve (or PSV-9215) tailpipe (or on temperature indicator TI-9416)

3) Increasing quench tank pressure

4) Increasing quench tank temperature (Any 5, 0.25 each)

, 5) Decreasing VCT level

6) Increased VCT makeup cperation

7) Momentary RC PUMPS BLEED-OFF PRESS HI alarm followed by low bleedoff pressure indication r appropriate indications will be considered on a case-by-case basis)

c. CloseTttmM$M the C66 reliefMvalveM isolation valve (HV-9216) (0.50)

REFERENCE SD-390 v. 36,98 004000A204 ...(KA'S) i

---r

L._ELANT DESIGH_IUCLUDING SAFETY AND_EBEBGEHQY_SYSIEb3 PAGE 86 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G. l l

ANS%ER 2.12 (1.25)

- . -a.tw -- wu .u4as 5e41

,, t , . , ,

1) Waste gas compressor hXs) '->

l g ,' $g [M /e. gf Ad----L-A e gm h wagp - @ 4V

2) Gas st, ripper (HXs) ,

3) Hisc. wasteevaporator(HX) Y. $

_gg

4) Radwaste condensate return sample (cooler) U~ ~n ~, [,~

e m,L; T - l C) PASS sample (cooler) 885' (0.25 each) l REFERENCE SD-SO23-400, p.6, 30 008000K102 ...(KA'S)

ANSWER 2.13 (1.25)

c. All three pumps (or P190, P191. and P192) (0.25)

.h. P025 and P026 (or B yump and swing pump) (0.50)

. PotA nu.ns yWJ% % e4 W sto icv.s en % A

.\. P018 and P019 (or B pump and swing pump) (0.50; REFERENCE SD-720 p. 68,69; SD-390 p. 43 013000K411

...(KA'S)

ANSWER 2,14 (peTC

. 004

c. SIAS

.' .C- dAA.N

d. CSAS (0.25 each)

REFERENCE SD-740 p. 65 013000K105 ...(KA'S) f

L_ .fkAHLDESIGN IELUDING SLEEIX._AND_EllEBGEEY SYSTEt'.S PAGE 89 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSW3R 2.15 w b h d?d Y Add h (1.00) $[3 # A p cud} y W " h*b f# .

The ma,:imum open positionnt Wh . cLch o&'ne d 8- DD VaA'#d

c. SDC standby flow control (HV-8160) is limited ^ 2rrrn. CO ,crccc.t h12 :,w (0.50)

b. A cavitating venturi on the discharge of the pump limits the maximum flow rate (0.50)

REFERENCE SD-740 p. 46; SD-780 p. 5 006030K603 ...(KA'S) e9 O

t

3. INSTRUMENTS AND_ CONTROLS PAGE 90 AGWERS -- SAN ONOFRE 2&S -88/07/26-WEALE, G.

I ANSWER 3.01 (3.00)

c. Spray valves open '(0.25 ea h)

Proportional heatern go off N o 4.: g

• x c u d f 4 1 & o[

Backup heaters are tripped off (or disabled) hddQDhd

b. Standby charging pump will start (0.25 each)

Letdown flow will go to minimum (28 gpm)

Vital bus A 1E backup heaters (Bank B3) are tripped off (or disabled)

c. (1) Pressurizer level increases (0.25) because letdown control valves fail closed (0.25)

(2) Pressure continues (toc1 increase AtAets.bs4(0.25)

A Adx.because spray valves are g

failed closed (or because failed-closed spray valves will not stop the pressure increase) (0.25)

d. Allows the operator to energize the vital bank backup heaters after they have been deenergized by an SIAS/EFAS (0.50)

REFERENCE SD-360 p. 62-66, 69, 139, 150 002000A201 002000A202 ...(KA'S)

ANSWER 3.02 -(1.001- (0,5%

b. Shitt(RE-7824-1) Transfer Selector Switch (t,n 2/3 L-104)(to Unit 3) (0.60)

J.1"Lw...r.cr.M00(Bhyvnut ouygly Glik-ku, lu L7.. loch )(t c

'"^ _

"g0)-

REFEREFE SD-8025-700, p. 37, 64, 65 072000K403 ...(KA'S)

ANSWFR 3.03 41. ::) 4.cc) Fadcu # ft4 M #^* W #d

1) High linear power e M A wdp(EMWd6 c,26

,4N6-

2) High local power density 'O M ;;;h)

3) Low DNBR tJ]ariabl,e overp wer (or CPC auxiliar;r trip)ngpag e6 pq/{

-r s..cm ... uvou amam m u ausuino ..rn

_ . _cr gpe g gA3 p ami

3. INSTRUMFNTS AND CONTROLS PAGE 91 AN'SWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

.~

REFERENC8 SD-710 p.e 8, 9, 43; SD-470 p. 13 012000K402 ...(KA'S)

T,CO- 2. 0 0 (

AHSWER 3.04 4 ^ 75 I C Fl.C6 I '

c. 1. 100%

p Metneem4 ssmkk&; MM en re & 4 a4 g

2. 0% (0.25 each)

3. 100%

b. None (0.25) h ( 2 each

d. .h I .5 t4$M '

_  ! n *1

. t flow demand signal ,  % sAub\(d.> decrease to less than 5%)(0.25) 1 .

Ten,]rn 'Kign M learing if the controller is set above 5%

1 (or can clear t e signal too soon if the manual controller is set below

~

5% .i (0.50)

REFERENCE SD-SO23-250, p. 56, 57, 61, 62, 63, 87, 88, 89

...(KA'S)

~

059000A203 059000K418 i

0'4' 3 e.o.(k A'36 d 4NSWER 3.05 (2.00)

LE CN

o. 1) CPC inputs for RCS flow determination M yggm g tw of$U

2) COLSS inputs for RCS flow determination MQF

3) Start /stop signals to the oil lift /ARRD pumps

4) Zero speed indication 12. 2 5 =9 '-

b. Steam generator differential pressure transmitters (1.00) s^ / / e / Li~ ,

REFERENCE

^'

WM ~ ^^

f v',/^. s4,<J,~ /. ,+ f:,

s" G n Jm wJt5T SD-360 p. 15, 20 . "// o- , e _ L ., . , _

[ 002000A105 ...(KA'S) " <

' ~i - ' u o i

7"",J A e L A './ ""sJ (['~j- rscob _ -

q s

3. INSTRMdEi./S AND SQNTROLS PAGE 92 j AtiSWERS -- SAN ONOFPE 2&3 -88/07/26-WEALE, G.

l l

ANSWER 3.06 (1.50)

c. Corrects each excore output signal to more accurately reflect the power ouput in the third of the core immediately. adjacent to the detector (or eliminates the ef fect of the cross-flux each detector see's f rom the other two-thirds of the core) (0.50)

b. Adjusts the excore signals to account for CEA insertion / withdrawal.

(0.50)

c. Adjusts the excore signals to account for reduced neutron leakage from the core at lower RCS temperatures. (0.50)

REFERENCE SD-SO23-710, p. 39 012000K607 ...(KA'S)

A3WER 3.07 (2.00)

'c. 1/3 (0.50) b 2/3 (0.50) 2/2 (0.50)

Hone (0.50)

REFERENCE

.5D-710 p. 24, 25 012000K401 ...(KA'S)

ANSWER 3.08 (1.50)

c. Radial peaking factors (from lookup table) o shadowing corrections)et. (0.25 each)

Axi 1 gfg _

b. CEA Calculators send penalty factors to CPCs if an individual CEA position deviates significantly from that of others in its group (0.60)

c. The operator enters an azimuthal tilt f actor provided f rom COLSS (0.50)

REFERENCE SD-710 p. 35-39 l 012000K607 ...(KA'S)

2L_ _1HSIBUt)ENIS AND CQUIBQLS PAGE 93 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSWER 3.09 (1.00) 4Acd- &du ddl fMd%k

1. Boron dilution monitors y .ubes fg &g g c gg

2. Source rangs count rate y

/, @ g

3. Audible count rate ( ny 4 at 0.25 edch)

4. Plant monitorini; system inputs

5. Dual pen recorder input l l REFERENCE

! SD-SO23-470, p. 8 015000K604 ...(KA'S)

ANSWER 3.10 (1.50) o.(Eachtimethepre-tripalarmisreceived/eachtimepressurizar pressure drops to approx. 150 psi above the trip setpoint 'O.50}

theoperatordepressesthepressurizerpressuresetpoint} reset pushbuttons (on the PPS Operator's Consoles) 40.25,.

c. When pressurizer pressure decreases below 400 psia (0.50), the operator shifts the PRZR/SIAS bypass (key-operated on each PPS channel) to BYPASS (0.25).

REFERENCE SD-SO23-720, p. 7 SO23-5-1.5 Attachment 6, p. 7, 18 013000A403 013000K101 013000K412 ...(KA'S)

ANSWER 3.11 (1.50) b.' 0p (0.50 each) 7 Cm /e4

c. 550 psia jg 94&l i myyAd{ W 202 gm at p/,4.

REFERENCE SD-SO23-720, p. 7 l SO23-5-1.5. Attachment 6, p. 7, 18 013000A403 ...(KA'S) l

J HSIBUMEbS_AHD._CQUIBQLS PAGE 94 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

s' ANSWER 3.12 (1.50)

a. 1) Reactor tripped signal ~

2) T-ave less than 566 degrees F (0.25 each)

b. Causes SBCVs to open at a lower steam pressure (or lowers SBCS program setpoints) (0.50)

c. Open (or lined up for either quick-opening or modulation actuation of the associated steam bypass valve) (0.50)

REFERENCE SD-SO23-175, p. 30, 31, 32 041000G007 041020A302 041020K409 041020K417 ...(KA'S)

ANSWER 3.13 (1.50)

o. Main Steam Isolation Valves Main Feedwater Isolation Valves (0.25 each)

CCW Non-critical Loop (and Containment) Isolation valves b.Am ntainment Cooling Actuation Signal (CCAS)

_ _ _ _ . _..__ _ - . , _ _ _ , (0 0

,n 5,e)___us

.E"d. A S ~ M ditl5-{0,id M 7""

~ ~~~"'

g. Push the RED (or GREEN) SIAS manual pushbutton (0.25)

' REFERENCE S0-8023-720, p. 8 013000A302 013000A403 ...(KA'S) l 4NSWER 3.14 (1.00)

c. COLSS calorimetric Manual (or PC-assisted) calorimetric (0.25 each)

b. (Gainadjustment)on'PPSRemoteOperatorsModule(0.50)

REFERENCE SD-470 p. 12 015000A103 015020A201 ...(KA'S)

3. INSTRUMENTS AND CONTROLS PAGE 95 ANSWERS -- SAN ONOFRE 2&3 -88/07/28-WEALE, G.

i ANSWER 3.15 (2.00)

e. 1) LPD re-trips) '

2) DNBR pre-trips)

3) CEAC enaltyfactor(,receivedbyaCPC) i (0.50 each)

b. Below 1 E-4 percent power (0.50)

REFERENCE SD-510 p. 38, 39; SD-710 p. 41 001050K401 ...(KA'S) 5 9

e F

1 t

1 f

4 e

-n, , , - . - - - - - - - - - - - . - - -

, - . , , , , , . - - - - - - - - , - , , , - . ~ . , - . ,,,,,,-r- - .- - , - - , . , . , - - , ,

i

4. ?ROCEDBES - NORMAL. ABHQMAL. EMEBGENCY MD PAGE 96 l

. MDIOLggicAL CONTROD ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

I l

ANSWER 4.01 (2.50) j 1

c. 1. Failure of 2 or more CEAs to drop following a reactor trip (0.50) l 2.

n %Me/dm9% W'/

One or more regulating groups below the PDILg (0.50) l l

3. Shutdown Margin less than 5.15% delta-k/k (0.50) l

4. Uncontrolled cooldown of the RCS (T-ave > 25 degrees F below T-ref) j (0.26) caused by excessive feedwater addition or excessive steam  ;

withdrawal (0.25) l

b. Open LV-02270 (RWT to CCP suction) (0.25); close LV-0227B (VCT Outlet)

(0.25)

REFERENCE AOI SO23-13-11, p. 2,3,4 EOI S023-12-1, p. 3 000024K301 000024K302 ...(KA'S)

\NSWER 4.02 (1.00)

o. By verifying that CEA group withdrawal is within the Transient -cf/'tVL Insertion Limits. (0.50)

b. Steam line break.

(0.50)

REFERENCE Tcchnical Specifications. LCO 3.1.1.1, including basis 0010000005 001000K508 ...(KA'S)

ANSWER 4.03 (1.50)

1) Stop (0.50 each)

2) Place plant in safe / stable condition

5) Inform SRO OPS Supervisor (co.itrol room supervisor)(to obtain resolution)

REFERENCE SO123-0-20 p. 5, 6 194001A102 ...(KA'S)

1

4. gBQQEEEES - NOBtML. ABNQBt&_EMBQENCY A@ PAGE 97 MDIOLOGICAL CONTROL .

1 ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSWER 4.04 (1.50) ,

c. 520 F (0.50) ,

b. 15 minutes (0.50) ,

of TG \P THL (LhCDL)s

c. Be in Hot Stand y 3 (0.50) .

REFERENCE Tcchnical Specifications, LCO 3.1.1.4, including bases 004000G005 004000G011 ...(KA'S)

ANSWER 4.05 (1.00)

To minimize the depth of wear (0.50) (th.at will occur on wear sleeves, Cuide tubes, and CEA cladding) due to CEA vibration (0.50)

REFERENCE

• SO23-3-3.5 Att 2 001000G005 ...(KA'S)

ANSWER 4.06 ( .75) 5 ninutes ,

REFERENCE Technical Specifications, LCO 2.1.1 Technical Specifications. LCO 2.1.2 0100000005 ...(KA*E)

ANSWER 4.07 (1.50) h6kb

1. P Ha g (or a etry up isor) (0.50) Shh h

2. .tati n H nage (O. 0) d.442 E i d h $r M a

3. rk r's a pe isor (0 50) g j .,g REFERENCE .d4L( #p gre,co&g SO123-VII-4.8, p. 18 U ""

194001K103 194001K104 ...(KA'S) l l

1 l

l l

LEBQCEDUEES - NORMAL, ABNOBM6WHEBGEF_QLAND PAGE 98

. BhDlQLQ9196k CONTROL E \

ANSWERS -- SAN ONOFRE 2&S -88/07/26-WEf.LE, G. '

1 ANSWER 4.00~ (1.50) ,

c. 1. Pressurizer pressure less than (1430 psiai (0.25)

2. Pressurizer pressure uncontrolled. (0.25)

b. CIAS actuated. (0.25)

c. 1. At least ene RCP running. (0.25)

2. Core delta - T less than (10 degrees F) (0.25)

3. Core exit saturation margin greater than (20 degrees F) (0.25)

REFERENCE SO23-12-1, p. 6, 10 000007G010 000011A103 000015A210 ...(KA'S)

ANSWER 4.09 (1.50)

c. To prevent turbine blade damage. (0.50)

b. The discharge of this pump bypasses lube oil cooler and filter.(0.50) c.- To prevent overfeeding SGs during RTO events. (0.50)

JRENCE

! .v23-2-1, p. 4 059000G010 ...(KA'S)

ANSWER 4.10 (1.00) o, Backleakage through check valve (in AFW supply line to SG-2) (0.50)

b. Steam binding of the MDAFWP (0.50)

REFEkNCE O O K bl .'. KA ) gqQ 4

' v .' M

~

h I

e

4. PROCEDUREfi - NORMAL. ABNORMAL. EMEBGEH.GLMD PAGE 99

. B6D19LQQLQAL CONTROL A$SWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSWER 4.11 (2.00) .

c. 1. Voltages +/- 1% (voltages matchet.). (0.53)

2. Synchroscope within 5 minutes of straight up position (proper phase angle). (0.50)

3. Synchroscope rotating once per 10 seconds (proper frequency clip).

Alof*L : Credit 4 esp .M,&MbAsp %tsist..SY%'M%d k fdfala$

ed Clul

.be6r,th.) C a (0" 50.Y) N

b. To prevent a rom cti motoring). 0.50) ,

REFERENCE SO23-2-13, p. 63, 65 064000A209 064000A401 064000G010 064050A101 ...(KA'S)

ANSWER 4.12 (1.00) 650 +f.-

- Gr2ater than 200 amps, but not fluctuating over 400 amps (or 300  :/ IS0 100 Q:)

REFERENCE SO23-12-7, p. 25, 28, 33 i

000017G010 000017G012 ...(KA'S) l .

ANSWER 4.13 (1.50)

c. The ion exchanger resins have a greater affinity for boron absorption at lower temperatures. (0.50)

b. To prevent control (throttle) valve opening if CVOL fails high. (0.50)

c. To prevent (an out of sequence) trip from CPCs. (0.50)

REFERENCE SO23-5-1.7, p. 5, 6 0010000010 004000G010 0450000010 ...(KA'S) 1

4.  ? WB_ES - NQBMAL ABEQBMAL ..EMEBGENCY AND PAGE 100

, 1 Lw lCAL CONTROL ANSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

ANSWER 4.14 (2.00) et b<a d. '

O. To prevent a bus feeder breakerg from overheating. (0.50)

b. To prevent RCP motor winding damage. (0.50)

c. To increase RCP seal life (0.50)

d. To prevent possible core lift. (0.50)

REFERENCE SD-SO23-360, p. 28 SO23-3-1.7, p. 3, 4, 5 003000G010 ...(KA'S)

ANSWER 4.15 (1.00)

1. The unit is in Mode 5 or 6 (0.50) and

2. The CRS and SS are absent from the control room (0.50)

REFERENCE S0123-0-2, CRS Authority, Responsibilities, and Duties, p. 0 194001A109

...(KA'S)

ANSWER 4,16 (1.25)

c. 1. -0.27 to +0.27 (0.25)

2. -0.20 to +0.20 (0.26)

b. Lower core power - Upper core power

_______---------------------------- = ASI (0.50)

Lower core power + Upper core power 29% - 25% Iddi A' MM

---

= +.074 = ASI (+/ .002) opMM g (Y)#0.25 cPc4 Ar@a/;

29% + 25% gg cAJn L }- pg REFERE%CE TcchnScal Specifications, LCO 3.2.7 (including basis)

Tcchnical Specifications, Definitions, p. 1-1 001000G011 015020K503 ...(KA'S) 4 m

L__.EBQCDUBES - N0_BMAL. ABNORMaka._EtEBGENCy__6@ PAGE 101

,,36E10 LOG 196L CONTROL

.KNSWERS -- SAN ONOFRE 2&3 -88/07/26-WEALE, G.

00s 6.Ge& h sd ) Jg MO & E (

g*g '

& p {ct 44 6b f Y Y'$

l ANSWER 4.17 (1. kh ,

T M Fe Mb dv Oteot 50 23 3 Am *li" O 4OAV

1) uipment being ternately contielled (A/C) by another d cument

2) T porary Chan e Notice (TCN) issued an in place (0.50 each;

3) Pro edure Ho ification Permit (PMP) impi mented with a least Initial App val daw REFEREN E oudag da &.]

S0123-0-20 p. 13 cadj/p A A$ca MMA o.g 194001A102 ...(KA'S) g ANSWER 4.18 (1.00)

c. Boron concentration at least 2350 ppm (0,25)

Height of water at least 23 feet over top of reactor vessel flange (0.25)

~

b. A ruptured irradiated fuel assembly (0.L0)

• • "~!:. : cE

'ie'il Specification LCO 3.9.1

.euasical Specification LCO 3.9.10, including basis

,033000K401 033000K405 ...(KA'S)

_ . _ . _ . _ . _