Text

2009 Reactor Operator and Senior Reactor Operator Written Examination Package and Post-Exam Comments
	ML092890647
Person / Time
Site:	Crystal River
Issue date:	09/28/2009
From:	Vansicklen M; Progress Energy Florida
To:	Widmann M; Division of Reactor Safety II
References
	ES-403, TRX09-0068
	Download: ML092890647 (10)
	v • d • e

a Progress Energy Cl)'stal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 September 28, 2009 TRX09-0068 U.S. Nuclear Regulatory Commission Attn: Mr. Malcolm T. Widmann Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, GA 30303-8931

Subject:

Dear Sir:

Crystal River Unit 3 - 2009 Reactor Operator and Senior Reactor Operator Written Examination Package and Post-Exam Comments.

Pursuant to ES-403, Grading Initial Site-Specific Written Examinations, please find attached the 2009 Reactor Operator and Senior Reactor Operator Written Examination package. Additionally two Post-Exam Comments are also attached.

If you have any questions regarding this submittal, please contact Mr. Floyd Lawrence, Supervisor, Operator Initial Training at (352) 795-0504, Ext. 6126 or Mr. Alan T. Kennedy, Senior Nuclear Operations Training Instructor at (352) 795-0504, Ext. 6129.

Sincerely, Mark Van Sicklen Superintendant, Operations Training MVS/ak Attachments xc:

Mr. Gerard W. Laska, Chief Examiner Progress Energy Florida, Inc.

Cl)'stal River Nuclear Plant 15760 W. Powerline Street Cl)'stal River, FL 34428 a Progress Energy Cl)'stal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 September 28, 2009 TRX09-0068 U.S. Nuclear Regulatory Commission Attn: Mr. Malcolm T. Widmann Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, GA 30303-8931

Subject:

Dear Sir:

Crystal River Unit 3 - 2009 Reactor Operator and Senior Reactor Operator Written Examination Package and Post-Exam Comments.

Pursuant to ES-403, Grading Initial Site-Specific Written Examinations, please find attached the 2009 Reactor Operator and Senior Reactor Operator Written Examination package. Additionally two Post-Exam Comments are also attached.

If you have any questions regarding this submittal, please contact Mr. Floyd Lawrence, Supervisor, Operator Initial Training at (352) 795-0504, Ext. 6126 or Mr. Alan T. Kennedy, Senior Nuclear Operations Training Instructor at (352) 795-0504, Ext. 6129.

Sincerely, Mark Van Sicklen Superintendant, Operations Training MVS/ak Attachments xc:

Mr. Gerard W. Laska, Chief Examiner Progress Energy Florida, Inc.

Cl)'stal River Nuclear Plant 15760 W. Powerline Street Cl)'stal River, FL 34428

CR3 2009 NRC Post Exam Comments SRO Written Exam question # 18 KIA Number BWIE09EA2.2 The following plant conditions exist:

-The plant is in Mode 3

- A complete loss of off site power (LOOP) occurred.

- "B" ES Diesel engine has catastrophically failed.

- Offsite power is not expected back for at least 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Which ONE of the following describes the allowable cooldown rate and maximum time allowed by TS to achieve cold shutdown based on plant conditions? (reference provided)

Start an RCS cooldown at a maximum rate of_--'{,..!o.I..... ) __ and be _-->.:{2::.<.) __

A. (1):s 50 F /12 hr (2) < 200 F in 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months B. (1):s 25 F /12 hr (2) < 200 F in 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months C.

(1) :s 50 F /12 hr (2) < 200 F in 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months D. (1):s 25 F / 12 hr (2) < 200 F in 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months Answers A and B should BOTH be accepted for the following reasons:

Because the question asks:

"Which ONE ofthe following describes the allowable cooldown rate and the maximum time allowed by TS to achieve cold shutdown...... " one could reasonably assume that the phrase allowed by TS applies to both conditions: the allowable cooldown rate AND to achieve cold shutdown.

TS 3.4.3 "RCS Pressure and Temperature (PIT) Limits" requires that RCS cooldown rates be maintained within the limits of the PTLR (pressurelTemperature Limits Report). Per the PTLR, the cooldown rate limit for the given plant conditions is :s 50 F / 12 hr.

By using this logic answer A would be correct even though the original expectation was for B to be the correct answer based on the following justification.

Based on conditions in the question stem the plant is in Natural Circulation. EOP-09, Natural Circulation Cooldown, places a procedural limit of:s 25 F / 12 hr on the RCS cooldown rate to minimize the formation of head voids. The expected correct answer was B based on this limit.

More than half of the applicants answered the question based on this interpretation of the question and selected choice B which was the expected answer.

CR3 2009 NRC Post Exam Comments SRO Written Exam question # 18 KIA Number BWIE09EA2.2 The following plant conditions exist:

-The plant is in Mode 3

- A complete loss of off site power (LOOP) occurred.

- "B" ES Diesel engine has catastrophically failed.

- Offsite power is not expected back for at least 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Which ONE of the following describes the allowable cooldown rate and maximum time allowed by TS to achieve cold shutdown based on plant conditions? (reference provided)

Start an RCS cooldown at a maximum rate of_--,,(.=-1).I.-__ and be _--",,(2:,t.) __

A. (1):s 50 F /12 hr (2) < 200 F in 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months B. (1):s 25 F /12 hr (2) < 200 F in 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months C.

(1) :s 50 F /12 hr (2) < 200 F in 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months D. (1):s 25 F / 12 hr (2) < 200 F in 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months Answers A and B should BOTH be accepted for the following reasons:

Because the question asks:

"Which ONE ofthe following describes the allowable cooldown rate and the maximum time allowed by TS to achieve cold shutdown...... " one could reasonably assume that the phrase allowed by TS applies to both conditions: the allowable cooldown rate AND to achieve cold shutdown.

TS 3.4.3 "RCS Pressure and Temperature (PIT) Limits" requires that RCS cooldown rates be maintained within the limits of the PTLR (pressurelTemperature Limits Report). Per the PTLR, the cooldown rate limit for the given plant conditions is :s 50 F / 12 hr.

By using this logic answer A would be correct even though the original expectation was for B to be the correct answer based on the following justification.

Based on conditions in the question stem the plant is in Natural Circulation. EOP-09, Natural Circulation Cooldown, places a procedural limit of:s 25 F / 12 hr on the RCS cooldown rate to minimize the formation of head voids. The expected correct answer was B based on this limit.

More than half of the applicants answered the question based on this interpretation of the question and selected choice B which was the expected answer.

3.4 REACTOR COOLANT SYSTEM (RCS)

RCS PIT Limits 3.4.3 3.4.3 RCS Pressure and Temperature (PIT) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cool down rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION A. ---------NOTE---------

Required Action A.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met in MODE 1, 2, 3, or 4.

B. Required Action and associated Completion Time of Condition A not met.

C. ---------NOTE---------

Required Action C.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met in other than MODE 1, 2, 3, or 4.

Crystal River Unit 3 A.1 AND A.2 B.1 AND B.2 C.1 C.2 REQUIRED ACTION COMPLETION TIME Restore parameter(s) 30 minutes to within limits.

Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for continued operation.

Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Initiate action to Immediately restore parameter(s) to within limit.

Determine RCS is acceptable for continued operation.

3.4-4 Prior to entering MODE 4 Amendment No. 149 3.4 REACTOR COOLANT SYSTEM (RCS)

RCS PIT Limits 3.4.3 3.4.3 RCS Pressure and Temperature (PIT) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cool down rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION A. ---------NOTE---------

Required Action A.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met in MODE 1, 2, 3, or 4.

B. Required Action and associated Completion Time of Condition A not met.

C. ---------NOTE---------

Required Action C.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met in other than MODE 1, 2, 3, or 4.

Crystal River Unit 3 A.1 AND A.2 B.1 AND B.2 C.1 C.2 REQUIRED ACTION COMPLETION TIME Restore parameter(s) 30 minutes to within limits.

Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for continued operation.

Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Initiate action to Immediately restore parameter(s) to within limit.

Determine RCS is acceptable for continued operation.

3.4-4 Prior to entering MODE 4 Amendment No. 149

a.

b.

ALLOWABLE HEATUP AND COOLDOWN RATES

i.

ii.

iii.

i.

ii.

iii.

and, For the temperature ranges specified below, the heatup rates are:

T > 280°F 280°F ~ T > 85°F 85°F

~ T > 60°F

~ 70°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period,

~ 50°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period,

~ 15°F in any I hour period For the temperature ranges specified below, the cooldown rates are:

T>280°F 280°F ~ T > 150°F 150°F ~ T

~ 50°F in any 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months period,

~ 25°F in any 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months period,

~ 25°P in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

c.

A maximum temperature change of less than or equal to 5°F in anyone hour period during hydrostatic testing operations above system design pressure.

These limits are referred to by Technical Sl'ecification 3.4.3.

prr LIMITS REPORT, Rev. 4 F97-0013 Rev. 4 Page 5 of 10

a.

b.

ALLOWABLE HEATUP AND COOLDOWN RATES

i.

ii.

iii.

i.

ii.

iii.

and, For the temperature ranges specified below, the heatup rates are:

T > 280°F 280°F ~ T > 85°F 85°F

~ T > 60°F

~ 70°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period,

~ 50°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period,

~ 15°F in any I hour period For the temperature ranges specified below, the cooldown rates are:

T>280°F 280°F ~ T > 150°F 150°F ~ T

~ 50°F in any 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months period,

~ 25°F in any 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months period,

~ 25°P in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

c.

A maximum temperature change of less than or equal to 5°F in anyone hour period during hydrostatic testing operations above system design pressure.

These limits are referred to by Technical Specification 3.4.3.

prr LIMITS REPORT, Rev. 4 F97-0013 Rev. 4 Page 5 of 10

Table 1:

Required OTSG levels Table 2:

Nat Cire eooldown rate limits Table 3:

OTSG Tube to Shell

,0, T Limits Table 4:

Minimum adequate SCM target values EOP-09 "LLL"

> 20 in

1 RCP running with adequate SCM "NAT CIRC"

> 70%

No RCPs running with adequate SCM "ISCM"

> 90%

Inadequate SCM RCS Tincore Cool down limit RCS PRESS maintained above S; 25°F/% hr Nat Circ curve of Figure 1 and Figure 2 RCS TEMP> 150°F and RCS S; 5°F/Y2 hr PRESS below Nat Cire curve of Figure 1 and Figure 2 Tensile I1T Limit (Avg Tshell - Teold)

Compressive I1T Limit (Thot - Avg Tshell)

S 60°F Reps Running RCPs not Running REV 09 PAGE 75 of 75 (LAST PAGE)

NCCD Table 1:

Required OTSG levels Table 2:

Nat Cire eooldown rate limits Table 3:

OTSG Tube to Shell

,0, T Limits Table 4:

Minimum adequate SCM target values EOP-09 "LLL"

> 20 in

1 RCP running with adequate SCM "NAT CIRC"

> 70%

No RCPs running with adequate SCM "ISCM"

> 90%

Inadequate SCM RCS Tincore Cool down limit RCS PRESS maintained above S; 25°F/% hr Nat Circ curve of Figure 1 and Figure 2 RCS TEMP> 150°F and RCS S; 5°F/Y2 hr PRESS below Nat Cire curve of Figure 1 and Figure 2 Tensile I1T Limit (Avg Tshell - Teold)

Compressive I1T Limit (Thot - Avg Tshell)

S 60°F Reps Running RCPs not Running REV 09 PAGE 75 of 75 (LAST PAGE)

NCCD

4.0 FIGURE 1 Res PRESS AND TEMP (WIDE RANGE)

.2' tn Co -

(/)

w 0:::

0..

(/)

0 0:::

CP C)

C co 0:::

CP

'C

§ Co 0

0

..J to

~

0

~

2300 2100 1900 1700 1500

. ____ L I

1300 I

1100 700 500 +,~~~~~L-~~~--~~~=-~~~~~4=~~~=-=-~

250 300 350 400 EOP-09 REV 09 450 Tincore (OF) 500 PAGE 71 of 75 550 600 650 NCCD 4.0 FIGURE 1 Res PRESS AND TEMP (WIDE RANGE)

.2' tn Co -

(/)

w 0:::

0..

(/)

0 0:::

CP C)

C co 0:::

CP

'C

§ Co 0

0

..J to

~

0

~

2500 2300 2100 1900 1700 1500

. ____ L I

1300 I

1100 900 500 +,==~--~~~--~~~--~~~-'~~~~~~~~~~~~

250 300 350 400 EOP-09 REV 09 450 Tincore (OF) 500 PAGE 71 of 75 550 600 650 NCCD

CR3 2009 NRC Post Exam Comments SRO Admin JPM COl Correction for the STANDARD in Step 4.

Problem: Standard incorrectly required performance of CP-152 Step 4.8.1.5, instead of Step 4.8.1.6, which is the correct step for the revised plant conditions.

ALL candidates correctly detennined that the actions ofCP-152, Action Level 3, were required.

Additionally ALL candidates correctly determined that TS 3.4.12, RCS Operational Leakage, Condition B, was also applicable.

Furthermore the "Examiner Note" in Step 4 stated the following: Candidate may summarize the actions by stating that the actions ofCP-152, Action Level 3, are required.

The values for RM-A12 readings were modified during Prep Week. The Standard required Step 4.8.1.5 of CP-1S2 be performed, which was correct for the original values. During Prep Week the new values given for RM-A12 were modified such that this step was no longer applicable (did not meet the ~ 30 gpd/hr increase). The correct procedure step to perform, with the new values, was Step 4.8.1.6. This modification to the Standard was missed and the old Step 4.8.1.5 was erroneously left in the Standard.

Further justification for the change is that the ONLY reading that can be confrrmed with two indications lAW CR3 procedures and the EPRI Primary-to-Secondary Guideline is the time NOW data at 1300 which is a leak rate of greater than or equal to 150 gallons per day.

The purpose of confrrming the correct leak rate required by CR3 procedures and the EPRI Guideline is to avoid unnecessary plant shutdowns. From the EPRI Guideline:

Leakage is qualitatively confirmed when two independent radiation monitors (typical monitor pairs like off-gas/SGBD monitors, off-gaslN-16 monitors, or N-16/SGBD monitors) trend in the same direction with the same order of magnitude.

The JPM queue sheet does not provide the ability to qualitatively confrrm the leakage until the 1300 data point. The JPM in its original form was written to provide confirmation of the readings using the data provided in the queue sheet. However, through the revision process the confrrming information was omitted and the key was not changed to reflect the time NOW confrrmed leak rate of greater than or equal to 150 gallons per day.

CR3 requests that STEP 4 of JPM COl reflect Step 4.8.1.6 with a standard of:

IF leak rate is 2: 150 gpd is confirmed, OR Action Level 3 was entered from Step 4.3.1, THEN be in mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AND that STEP 4 of JPM COl reflect an "N/A" for step 4.8.1.5.