ML20101K971

Forwards Comments Based on Technical Review of Reactor Operator & Senior Reactor Operator Licensing Exams Administered on 920622,per NUREG-1021 (Operator Licensing Examiner Std)

ML20101K971
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1992
From:	Gates W OMAHA PUBLIC POWER DISTRICT
To:	Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
RTR-NUREG-1021 LIC-92-212R, NUDOCS 9207060178
Download: ML20101K971 (27)

Text

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Omaha Public Power District 444 South 16th Street Mau Omaha, Nebrmka 68102-2247 June 30, 1992 LIC 92 212R Mr. John L. Pellet Chief Operator Licensing S e :, ion U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington. TX 76011-8064 1

Reference:

Docket No. 50-285

SUBJECT:

Technical Review of the Reactor Operator and Senior Reactor Operator Licensing Examinations Omaha Public Power District (0 PPD) has reviewed the Reactor Operator and Senior Reactor Operator licensing examinations that were administered by the NRC at fort Calhoun Station on June 22, 1992. Enclosed are OPPD's comments on the examination, in accordance with the re Licensing Examiners Standard, NUREG-1021.quirement specified in the Operator These comments were provided to your examiner, Mr. Kriss V inedy, on June 26, 1992.

If you should have any questions, please contact me.

Sincerely, W. G. Gates Division Manager Nuclear Operations WGG/sel Enclosures c: LeBoeuf, Lamb, Leiby & MacRae (w/o Enclosures)

R. D. Martin, NRC Regional Admiristrator, Region IV (w/o Enclosures)

R. P. Mullikin, NRC 5enior Resident Inspector (w/o Enclosuras)

S. D. Bloom, NRC acting Project Manager (w/o Enclosures)

Document Control Desk 9207060178 920630 PDR ADOCK 0D000285 y PDR 45 5124 Emptyrent t onxrtunity g 2,,

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l SRO 0uestiorLAR During power operations, if containment entry is re .

Supervisor and which ONE of the following must approve? quired then the Shift

a. Radiation Protection Supervisor OR Operations Supervisor

b. Radiation Protection Supervisor AND Operations Supervisor

c. Plant Manager OR Chemistry and Radiation Protection Supervisor

d. Plant Manager AND Chemistry and Radiation Protection Supervisor ANSWER: d.

REFERENCE:

Fort Calhoun Station 1HB: 7-11-8, p.34 SR0 only KA: 103000G001 (3.3/3.9)

OPPD Comment 0FPD requests that this question be deleted. All of the choices offered are incorrect.

According to S0-0-22, " Containment Access and Egress", and RP-213, " Operational s Containment Entry", the only authorization required for a containment entry at power is that of the Shift Supervisor. The other positions having responsibilities associated with a containment entry at power are the STA and the Radiological Operations Coordinator.

REFERENCES:

S0-0-22, Section 4.0 RP-213, Section 2.0

- - _ _ _ - _ _ _ _ _ _ _ - _ _ Y

SRo92

... FORT CALHOUN STATION '

f ' STANDING ORDER ',

' S0-0-22

. PAGE 1 OF 3 3.5.2 C. Individuals departing containment will have their key cards swiped thru the Egress Reader by a Security Officer prior to having their cards returned.

3.5.3 Must operate the Personnel Air Lock Doors in  :

accordance with OI-CO-2.  ;

4O OPERATIONS CONTAIN!!ENT ENTRIES AT POWER.

NOTE: It is the responsibility of the immediate supervisor '

of the craft requesting centainment entry to ensure that the evaluation is completed.

NOTE: The FC-RP-213-1 evaluation is not required for routine chemistry sampling entries.

NOTE: Additional requirements for containment entries '

during power operation are given in RP-213.

4.1 STA must complects the entry evaluation for the tasks to be performed on FC-RP-213-1.

,/c ~

( 4.2 The Shift Supervisor must authorize the operational containment entry per FC-RP-213-1.

5.0 CONTAINMENT EVACUATIf)J[

5.1 In the event the Nuclear Emergency Alarm is annunciated, all personnel will evacuate the containment inmediately.

5.2 In the event that any containment building area monitor, portable area monitor or air activity monitor reading increases rapidly and alarms without prior anticipation or preparation, the Shift Supervisor will be notified immediately and he will ensure that all personnel evacuate the containment building irmediately until Radiation Protection and/or operations personnel have investigated the cause of

're-entry.

he alarm and determined that conditions are safe for 5.3 In the event that an announcement is made over the Plant Communication System to evacuate the containment building, all personnel will do so immediately. These announcements should be made by the Shift Supervisor.

5.4 The Security Guard is responsible for accountability.

If all personnel are not accounted ror the Shift Supervisor and Radiological Operations Coordinator must be notified.

FC/SO/01 R14

s!?'o 9 2.

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' , , FORT CALHOUN STATION' \

d1 RP-213

{ .

RADI.ATION DROTECTION PROCEDURE '. PAGE 1 OF-6 OPERATIONAL CONTAINMENT ENTRY j 1.o EURPOSE I

I This procedure provides guidance on the Radiation Protection l

requirements for personnel to enter the Containment during power operation.

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2.0 RESPONSIBILITIES '

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2.1 The Supervisor-Radiation Protection Operations is responsible for implementation of this procedure. 3 2.2 i

The Shift Supervisor is responsible f .* controlling i entrance to and egress from.the Conta1 ament Building. ,

1 2.3 i

The for:

Radiological Operations Coordinator is responsible.

i f 2.3.1

{

Ensuring that Form FC-RP-213-1, Operational j Contes.nnent= Entry Evaluation Worksheet, is j

prororly ;ompleted prior to entries, other thac to routine Chemistry sampling.

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' 2.3.2 Ensuring that FC-RP-213-2, Containment Entry Worksheet, is completed prior to the first j entry of each dny when the reactor is-critical.

or Containment .ntegrity is required while.

{ shutdown. .

2.3.3 Ensuring that an appropriate Radiation Work l

Permit is issued'for the entry.

i 2.3.4 -Ensuring that proper Radiation Protection Technician coverage is provided for the entry.-

2.4 t A representative of the group requesting-the entry is responsible for:- l l

i 2.4.1 Initiating 1 Form FC-RP-213-1,' Operational Containment Entry Evaluation Worksheet

2. 4. 2 ' Arranging to- haveL- Securiti' Personnel as required for the Containment entry.-

i 2.5 The Shift Technical Advisor (L .) is responsible for completing the applicable-portions of FC-RP-213-1,

{ Operational Containment Entry Evaluation-Worksheet.

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-FC/RP- R1 i

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j ... FORT CALHOUN STATION \

c.

RADIATION PROTECTION PROCEDURE g RP-213 i

PAGE 3 OF 6 j

5.3.4 The Security Guard is re9ponsible for.

accountability. If all personnel are not i'

accounted for the Shift-Supervisor and Radiological Operations Coordinator must be 1 notified.

l 7.0 PROCEDURE W

j 7.1 i For Containment entries other Sarpling, than Routine 1 Chemistry i Form FC-RP-213-1, " Operational Containment

! Entry Evaluation Worksheet" must be completed prior to entry.

. 7.1.1 A representative of the group requesting entry I

will initiate the FC-RP-213-1. l 4

7.1.2 The representative will turn the FC-RP-213-1 over to the Shift Technical Advisor (STA).

1 NOTE: Steps 7.1.3 through 7.1.4 May be performed in j any order.

' 7.1.3 The STA will complete Steps 3.1 through 3.4

, and 3.6 of FC-RP-213-1. l_

7.1.4 The STA will obtain the " Radiological

! Conditions" from the Radiation Protection

' Department and have them initial Step 3.5 of '

FC-RP-213-1.

7.1.5 The FC-RP-213-1 will be presented to the l

Operations - Shift Supervisor. He will l determine if it is required that thu task be performed at power and sign Step 4.0 of s

FC-RP-213-1.

7.1.6 Form FC-RP-213-1 is then presented to the.

i Radiological Operations' Coordinator.- He will

. ensure that an appropriate Radiation Work Permit is issued.for the task, . complete and I

sign Step 5.0 of-FC-RP-213-1.

2 7.1,7

Form FC-RP-213-1 is then filed in the.

1 Radiation Protection records storage files.

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i FC/RP r

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FORT CALHOUN STATION \

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RADIATION PROTECTION PROCEDURE s RP-213 PAGE 4 OF 6 7.2 If not completed previously that day or if conditions in Containment are suspected to have changed, (i.e.:

Reactor Power or RM-050/051 readings increased significantly since completion of last FC-RP-213-2 as i determined by the ROC), Radiation Protection personnel will complete Form FC-RP-213-2, " Containment Entry Worksheet," to estimate the airborne radiological conditions in Containment, prior to entry.

7.2.1 Obtain a copy of the current revision of FC-RP-213-2.

7.2.2 Record the information needed to complete the calculations on FC-RP-213-2, as listed in the box labeled, "TODAY'S INFORMATION."

A. RM-050/051 Gross CPM are read in the Control Room.

B. Background CPM is taken from the current revision of the Technical Data Book.

C. Sensitivity is taken from the current revision of the Technical Data Book.

D.

Flowrate (SCFM) is calculated from readings taken from RM-050/051 in Room 69.

The indicated flowrate and vacuum readings are compared on the graph located on the RM-050/051 flowrate.

cabinet to obtain the corrected E.

Transit Time (min) is obtained from Chemistry personnel who refer to the last calibration performed on RM-050/051.

7.2.3 Using the information obtained in Step 7.2.2, complete Steps 1 and 2 of FC-RP-213-2. These calculations will yield the estimated Particulate MPC value and the estimated Beta Dose rate in mR/Hr in the Containment atmosphere.

7.2.4 Review previous FC-RP-213-2 data to check for upward / downward trends. (IF using the computer program for completion of this form, this data will be printed in Step 3, when form prints).

7.2.5 Complete Step 4, " Demographic Information."

Tritium concentration is obtained from Chemistry personnel.

FC/RP R1

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S Ro 92 i

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FORT CALHOUN STATION RADIATION PROTECTION PROCEDURE

(, . RP-213 PAGE 5 OF 6-ei 7.2.6 i Submit FC-RP-213-2 to the Radiological' i Operations Coordinator for Containment entry approval requirements.

and determination of respiratory I

7.2.7 The remaining items on FC-RP-213-2 will be completed following the Containment entry '

!, using actual measured values.

7.3 The Radiation Protection-Technician assigned coverage j

responsibility for-this-task will ensure that the following items are available, (as required): ,

7.3.1 An appropriate radiation monitoring instrument, which is in current calibration and has'been function checked for the day.

1 7.3.2 A neutron monitoring instrument which is in

j. current checkedcalibration for the day.and has been function.

1 7.3.3 Air sampling equipment for gaseous,-Iodine and

{ particulate contaminants.

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7.3.4 A copy of tno current revision of FC-RP-205-1, l

" Airborne Radioactivity Area Entry Log." _

a 7.3.5 The appropriate Radiation Work Permit for the i

task to'ba performed.

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7.4

Notify the representative of'the group requesting the i

entry that preparations are-complete.

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! 7.5 l

The representative.of:the-group supervisor requesting the entry'will1 arrange with_ Security 1to. provide l l personnel as required:for.the Containment: entry.

7.6-Personnel making the Containment entry ~ willi review the Radiation Work Permit with the Radi.. tion Protection

{

Technician providing task coverage. They1will-be

[.

informed ~of the RP requirements and the expected /known radiological conditions.

P'

!_ 7.7 1 Ensure that the neutron dose tracking is used when j

entering data into=the. access" control computer, e

7.8 l-Immediately prior to entering Containment complete-the following:-

i in any order) (Steps 7.8.1-through;7.8.42 maybe performed' 7.8.1 Notify the Operations - Shift Supervisor that 4 you are ready to make the entry and receive -

c his permission. '

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7.8.2 Sign in on FC-RP-205-1 if-posted.

FC/RP

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FCRT CALHOUN STATION Sfo 92' l

.- RADIA, TION PROTECTION PROCEDURE

• RP-213 PAGE 6 OF 6 )

7.8.3 Check in with the Security person at the PAL '

door.

7.8.4 Ensure Badge.

Security that the TLD's are not left with the NOTE:

If the scope of the task or the radiological conditions change during the entry, exit Containment and contact the Radiological Operations Coordinator for resolution.

7.9 Enter containment and complete the task as described on the appropriate Radiation Work Permit.

7.10 While in Containment, the Radiation Protection Technicisn will perform radiological surveys, including airborne as needed, to assess the current conditions.

l 7.11 When all personnel are clear of Containment, the Radiation Protection Technician will lock the PAL door. Another individual will verify that the door is shut and locked. Both will sign Form FC-RP-204-1, "Very High Radiation Area Verification Check," upon exiting thc Radiation Controlled Area.

NOTE:

order. Steps 7.12 through 7.14 maybe performed la any 7.12 Notify the Operations - Shift Supervisor when all

[__ personnel are out of containment.

7.13 Sign out on FC-RP-205-1, if posted.

7.14 Check out with Security.

7.15 The Radiation Protection Technician will document and submit for review the radiological survey completed during entry.

7.16 When results of the airborne radioactivity samples taken during entry are 6vailable, complete Step 5 of FC-RP-213-2 and submit to the Radiological Operations Coordinator for final review,

8.0 REFERENCES

8.1 Standing Order 0-22, " Containment Access and Egress."

9.3 ATTACHMENTS FC/RP R1

=_ - _ _ . - . . -. . .

4 FORT CALHOUN STATION FC-RP-213-1 RADIATION PROTECTION FORM R1 OPERATIONAL CONTAINMENT ENTRY EVALUATION WORKSHEET 1.0 Tasks to be performed:

1 2.0 Entry Request by: Date:

3.0 Entry Evaluation (Attach additional sh6eCs as needed).

2 2

Initials /Date 3.1 Indication and Parameters  !

Ops /or STA Date

! 3.2 Potential causes outside containment /

j STA Date 3.3 Alternate means /

STA Date 3.4 Can the task be delayed /

STA Date L

3.5 Radiological Conditions /

R.P. Date 3.6 Benefit of performing the task ,

/

1 STA Date 4.0 It is required that this task be performed curing ceactor operation.

i Operations Shift Supervisor Dato 5.0 Forward to Radiation Protection to issue appropriate RWP.

RWP# has been issued for this task.

Radiological Operations Coordinator Date FC/ FORM (RP-213)

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l SRO Ouestion 77-4 F

, If a women operator declares that she is pregnant and she has already received:

!. 600 mrem since conception, which of the follwing exposure limits apply for. the

!_ remainder of her pregnancy?

r

a. No further exposure [0 mrem]

1

b. 5 mrem

, c. 25 mrem

d. 50 mrem ANSWER: d.

[

REFERENCE:

FCS RP-AD-600, Section 5.6.2, p.7 SR0 only I- KA: 19400lK104 l

OPPD COMMENT OPPD requests -that the correct answer be changed to choice A, no further i exposure.

4 In General Employee Training, ~it is emphasized that "0 PPD has established a j prenatal limit in accordance with Reg. Guide 8.13 of 500 mR/ gestation period."

! The exposure limit established in RP-602,, table 1 and in RP-AD-600 section 5.6.2 L is 50 mrem / month and.500 mrem / gestation period. Since the operator has received -

in excess of 500 mrem / gestation period, she would not be allowed to receive any-l additional occupational exposure during the duration of her pregnancy.

Note 4 on page 7 - of RP-AD-600. establishes the predominance 'of the-- 500.

' - mrem / gestation -limit -over: the 50 mrem / month limit for a pregnant worker. The intent of the~ note is to state that the pregnant worker may NOT be allowed to

receive up to - 50 mrem / month if that -exposure: will'.be -- in excess of - the 500

. mrem / gestation period limit.

4-

REFERENCES:

General Employee Training' , Station Orientation, p, RP17- - - ..

!- Regulatory Guide 8.13," Instruction- Concerning Prenatal Radiation

Exposure" RP-602, TABLE 1

RP-AD-600, section 5.6.2 L

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REGULATORY GUIDE 8.13 i

POTENTIAL INCREASED RISK TO A FETUS DURING

} THE GESTATION PERIOD l MOST SENSITIVE DURING THE FIRST TRIMESTER INCREASED RISK OF INFANT CANCER AND LEUKEMIA i

PRENATAL EXPOSURE INSTRUCTIONS i

4 OPPD HAS ESTABLISHED A PRENATAL LIMIT IN ACCORDANCE WITH REG. GUIDE 8.13 OF 500 mRIGESTATION PERIOD i

PURPOSE FOR ESTABLISHING LIMIT:

S EMBRYONIC AND FETAL DEVELOPMENT IS A PERIOD OF VERY RAPID CELLULAR DIVISION

9 BIOLOGICAL DAMAGE MAY OCCUR MORE FREQUENTLY TO AREAS OF THE BODY THAT EXPERIENCE RAPID CELL DIVISION 9 AT PRESENT OCCUPATIONAL DOSE LIMITS.

THE ACTUAL RISK TO THE UNBORN CHILD IS l SMALL, BUT OPPD WOULD LIKE TO MINIMlZE

DOSES AND KEEP EXPOSURE TO AS LOW AS REASONABLY ACHIEVABLE i

i RP 17

SRO 77 l

• FORT CALHOUN STATION \

RP-602 I \

RADIATION PROTECTION PROCEDUBE PAGE 4 OF 8 l

TABLE 1 ADMINISTRATIVE EXPOSURE LIMITS Stipulation Level 80%

Individuals with a facilities 1000 mrem /qtr 800 vritten estimate or official record of WB dose for the current quarter. Individuals with no current quarter cxposure.

Current quarter exposure and 250 mrem /qtr N/A no written estimate provided by a facility.

Whole body exposure 4000 mrem /yr 3200 for the year.

Extremity exposure for 18.75 rem /qtr 15.0 the quarter.

Skin exposure for the 7.5 rem /qtr 6.0 quarter.

-- /

m Declared Pregnancy 500 mrem / gestation 400 50 mram/ month y

7.3 Dosimetry Issuu 7.3.1 Obtain the next available TLD, and verify the insert number on the TLD issue log.

7.3.2 Fill in the requested information on the TLD issue log. (See Attachment 1 - PRISM TLD Issue Log). +

7.3.3 Write individual's PID number and name on the TLD label.

7.3.4 Instruct the individual on the proper placement of dosimetry and the requirements for returning the TLD when leaving site.

7.4 Data Entry into PRISM Computer System 7.4.1 A computer Data Entry Worksheet (FC-RP-602-11) should be used to ensure complete data entry into PRISM.

FC/RP R5

FORT CALHOUN STATION k9 77 ADMINISTRATIVE PROCEDURE RP-RD-600 A

. PAGE 7 OF 34 5.6.2 The administrative limits listed below are used to ensure that regulatory limits are not reached without warning and as an administrative tool to 4

identify persons or processes that are not in keeping with ALARA principles.

Whole Body Exposure 4.0 rem / year Whole Body Exposure 1.0 rem /qtr Whole Body Exposure (1) 0.25 rem /qtr Whole Body Exposure (2) 0.1 rem /qtr Whole Body Exposure (3) ~

50 mrem / month l hole Body Exposure (4) 0.5 rem /gestationJ Inhalation Intakes 10 MPC-hrs / 7 days

1. This limit applies only to individuals who

)

have received exposure during the current quarter and have not provided documents to substantiate the exposure.

4 d

2. This_ limit applies only to Visitors and is for exposures received solely at FCS.

\

l 3. This limit applies to women who have

[, declared they are or may be pregnant.

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4. For a declared pregnancy. Ifthepregnancy~)

is declared after the individual has received more than 450 mrem since conception, the limit is 50 mrem for the remainder of the pregnancy.

t FC/RP-AD R6 i

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R0 Ouestion 58 Which one of the below is the MINIMUM RCS makeup rate that is sufficient to

replenish the boil off from decay heat following a loss of shutdown cooling?

a. 15 gpm

b. 55 gpm

c. 1500 gpm

d. 5500 gpm ANSWER: a.

REFERENCE:

A0P-19, p.3 RO only i

KA: 005000K301 OPPD Comment The correct answer to this question is choice B, 55 gpm. The answer key incorrectly lists choice A, 15 gpm, as the right choice.

, AOP-19, Loss of Shutdown Cooling, states that "An RCS makeup rate of 55 gpm is sufficient to replenish the boil off from decay heat".

REFERENCE:

A0P-19, p.4 1

1 1

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fo 59 s

, g, AOP 19 Page 4 of 82 3.0 PRECAUTIONS The following specific cautions and notes apply prior to or throughoui this procedure.

A. CAUTIONS

1. Containment evacuation is required when boiling is imminent.

2.

If the HPSI Pump suction, the LPSI Pump suction or the CG Pump suction is aligned to the SIRWT, do not operate the HPSI Pumps, the LPSI Pumps or the CS Pumps when SIRWT level falls below 16 inches.

3.

If the Charging Pump suction is aligned to the SIRWT, do not operate the Charging Pumps when SIRWT level falls below 72 inches.

4.

If the HPSI Pump suction, the LPSI Pump suction or the CS Pump suction is aligned to the Containment Sump, do not operate the HPSI Pumps, the LPSI Pumps or the CS Pumps when Cor'tainment sump level is below five feet as read on L1-387 and L1-388.

5.

Do not operate the CS Pumps or the LPSI Pumps if the pump flow rate can not be maintained above 200 gpm.

6.

Do not start the LPSI Pump (s) until the cause of SDC loss has been determined and corrected.

7.

Charging Pump operadon could cause excessive RCS pressure. Charging flowrate must be carefully regulated to prevent overpressurization of the RCS.

B. NOTES 1.

Establishing Containment integrity requires approximately 30 minutes, if RCS water level is at or near the centerline of the hot leg, the remaining time to boil may be less than 30 minutes.

2.

An RCS makeup rate of 55 gpm is sufncient to replenish the boil off from decay heat.

3.

Use of CS Pumps for SDC is subject to BOTH of the following limitations:

e RCS temperature is less than 120*F e

RCS is vented with a vent area is greater than or equal to that of the Pressurizer Manway Part 1 RO

. - . - . - . _ - . _ = . . _ - - . - - - . - _ . - . - . . - . - . . . - -- .. .- - -. - .

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j~ R0 Ouestion 9/ SRO Ouestion 9 i

Which ONE of the following should be commenced only AFTER on-coming personnel j have assumed the shift?-

) a. A Pre-Shift briefing for on-coming personnel,

b. Sign the Licensed Operator Shift Turnover-Log.

c. Review of surveillance tests.or special tests in progress.

l d. Review items affecting plant operations by-the on-coming and.off-

going Licensed Operators.

ANSWER: a.

i i

REFERENCE:

Fort Calhoun Station 'S0-0-1, p.58,59,60,61 i Both 1

i KA: 194001A103 [2.5/3.4]

j OPPD COMMENT i -

OPPD requests that this question be deleted. None of the choices offered. is correct.

j:

4 -

l Normal operating practice is to accomplish all of the items listed -in the choices i prior to the on-coming personnel assuming the shift. Choices-B,C and D are.part p of the turnover process - and are completed -prior to the on-coming personnel j assuming the shift.

Current operating practice, as outlined in the attached memo, is for the off-i going Shift Supervisor to conduct'a. pre-shift briefing for the on-coming Shift

! Supervisor, Operators and STA. This pre-shift briefing is= conducted outside the

control room and prior to the' watchstation turnover. Therefore, choice A is i incorrect.

, This-practice was established on-2/8/92 which:was during the License candidates-OJT period.- A revision to S0-0-1 which reflects the current practic.e was issued i on 6/15/92 and the applicable sections are attached.

! REFERENCEi S0-0-1, RS, section~6.1 D Memo FC-0170-92 I

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Fort Calhoun Station Unit No. 1 i

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! SO-O-1 i

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STANDING ORDER 3

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Title:

CONDUCT OF OPERATIONS t

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l Setpoint/ Procedure Form Number (FC-68): 37439 Reason for Change: Update procedure.to reflect current operations policy.

Contact Person

David J. Bannister i

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ISSUED: 06-15-92 4:00 pm R5

FORT CALHOUN STATION Ro 7/seo y .\

S0-0-1 f- STANDING ORDER '\ PAGE 70 OF 114 6.0 SHIFT OPERATIONS '

6.1 Pre-shift Briefinos 6.1.1,, Conduct of Pre-shift Briefinos

~~~)

A. At the beginning of each shift, the on-coming Operating crew shall report to the common briefing area outside the {

Conttol Room for n Pre-Shift Briefing.

B. The briefing shall be conducted by the off-going Shift Supervisor or designee.__ ,

NOTE: Extra Operators chall report to the briefing room as part of the operating crew.

C. The following on-comming Shift Personnel shall attend the Pre-Shift Briefing:

(1) Licensed Operators (2) Equipment Operators (3) Auxiliary Operators (4) Shift Technical Advisor (5) Shift Chemist (6) Shift Radiation Protection Technician D. It is permissible to conduct the pre-shift briefing without full attendance by the required personnel if these individuals are unavailable due to the performance of other Job specific tasks.

6.1.2 Content of Pre-shift Eriefinos 2

A.

• The Pre-Shift Briefing is ntended to be approximately ten (10) minutes in duration

' and provide an overview of plant conditions.

B. During the Briefing, the off-going Shift Supervisor will ensure the following (as applicable) have been reviewed wita the on-coming crew:

(1) Plant status (2) Crew composition (3) Operational priorities FC/SO/09 RS

Wa f/.sRo y

'; FORT CALHODN STATION 'g' i S0-0-1 STANDING ORDER PAGE 71 OF 114 6.1.2 B. (4) Major equipment out of service (5) Surveillance Tests scheduled or in progress (6) Preventative mainten;nce scheduled or in progress l

(7) Maintenance scheduled or in progress (8) Newly installed Temporary Modifications (9) Unusual occurrences within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (10) Other items of operational significance NOTE: The requirements of Standing Order G-92 (Conduct of Infrequently Performed Procedures), may apply.

6.1.3 Special Briefines A. Special Briefings Irr e-Job etc.) may be conducted prior tc S:ccial or complicated evolutions. Only .9 personnel direc*.ly involved in the evoluLion are n6rmallir required to attend such briefings.

6.2 Shift Turnover and Relief 6.2.1 Resonnsibility A. It is the responsibility of the personnel being relieved to brief the oncoming personnel.

B. It is the responsibility of the Operator assigned a work station to perform rounds including equipment checks and a general inspection for that area.

C. No person shall assume a shift position unless he/she is physically and mentally fit to competently discharge his/her duties.

D. No person shall permit his/her relief to assume the shift if there is doubt that he/she is alert, coherent, and fully capable of performing his/her assigned duties.

FC/SO/09 R5

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.,. FORT CALHOUN S?ATION e' S0-0-1 STANDING ORDER PAGE 72 OF 114 6.2.2 Shift Relie# Instructions A. The on-duty operating shirt shall complete and sign the appropriate shift turnover log priot- to being relieved.

Position Turnover Loo Form No.

Control Room FC-95 or 95A Operators Auxiliary Bldg. FC-165 Turbine Bldg. FC-166 Water Plant FC-167 B. The oncoming operating shift shall review the shift turnover sheet with their 4 respective counterparts and sign the sheet at the end of the turnover. The Shift Supervisor's review may be conduct r; cfter turnover.

C. The on-duty operating shift shall remain on duty until they have been properly relieved by qualified personnel, j D. The oncoming shift shall familiarize themselves with conditions in areas to which they are responsible, prior to assuming the duties and responsibilities of their respective job.

E. The oncoming and on-duty Control Room Operators shall walk-down the control boards to verify turnover log items.

F. Prior to being relieved of their respective jobs, each person will brief his/her relief on the condition and status of that portion of the plant to which he/she is assigned. The following is a list of items which may be included in the pre-shift briefing, (when applicable).

(1) Shift Turnover Log (2) Operating Logs (3)

Abnormal conditions or alignments (4) New alarms (5) Inoperable equipment FC/SO/09 RS

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"* FORT CALHOUN STATION STANDING' ORDER g S0-0-1 PAGE 73 OF 114 6.2.2 F. (6) Surveillance tests or special tests in progrecs (7) Rei.ently issued Special Orders, i

O'j erations Memos , Night Notes ,

S.A.O's (8) Recently installed Temporary Mods (9) Technical Specification problems or LCO's in effect (10) The oncoming shift shall perform a walkdoun of their assigned equipment or control boards shortly after assuming the shift G. Prior to assuming the shift, each Operator shall personally verify the status of important system operating parameters, especially those relating to safety systems.

H. The off-going Operator shall not leave his/her work area until he/she is satisfied that his/her relief is fully aware of existing conditions.

I. Each shift position shall be relieved by a person who is properly licensed and/or qualified to assume the shift position.

1 J. The off-going Operator shall not be i

relieved until the equipment he/she is responsible for is in a stable condition.

i K. The Control Room Communicator may be relieved and conduct shift turnover in the i

Control Room. Such relief will not be 4

conducted in the "at the controls" area.

e 4

FC/SO/09 RS

t Memorandum #UFor E l l

. 2 :1 l

Date: February 8, 1992 FC-0170-92 From: D. R. Trausch i

To: Shift Supervisors

SUBJECT:

Compensation for Watchstation Turnover Effective February 9, 1992, you are required to begin compensation of operators for overtime worked as a result of watchstation turnover.

Compensation directly related to watchstation turnover shall only be given j under the following circumstances.

A. If the operator is standing one of the following watchstations: '

ControlRoomLicensedSeniorOperators(LS0)

ControlRoomLicensedOperator(LO)

Control Room Licensed Operator (LO*)

Auxiliary Building Operator Turbine Building Operator Water Plant Operator B. If an operator not assigned a watchstation, is performing an activity for which a turnover is required.

C. If the operator assigned the communicator watch, is performing an activity for which a turnover is required.

Compensation will be given in accordance with Article IV Section 4 Contract Agreement Local 763. On a short term basis only, it will be the responsibility of the Shift Supervisor to complete the titre sheets for each

of his operators. It will be the responsibility of the irdividual operator to report to the Shift Supervisor, prior to leaving the protected area, any overtime worked as a result of tha turnover process.

As usual, overtime should be paid to the nearest tenth of an hour. It will be the responsibility of the Shift Supervisor to ensure all operators are aware of this change in employee compensation.

As a result of this agreement, additional changes to the shift operating crews " routine" are required. These changes will be implemented the week of February 10, 1992. Guidance will be provided to the Shift Supervisors  !

shortly.

Major aspects of this new program will include:

A. Official start hours for all operators (excluding operators scheduled for classroom training) will be 0700-1500, 1500-2300, and 2300-0700.

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• I Shift Supervisors FC-0170-92 l'~

j. Page Two i B. The operating crew (Shift Supervisors, Operators, STA) will report to a l ' common briefing area outside the control room for a pre-shift brief conducted by theroff-going Shift Supervisor.

C.

Operators must be in the briefing room, with personal items stored, no later than 0700, 1500, 2300 or be considered late for work. Operator tardiness for these briefings will be considered unacceptable.

9. Extra operators will report to the briefing room, with personal items stored, as part of the-operating crew.

y E.

The pre-shift briefing will be_ conducted by the Duty-Shift Supervisor-

/

or other operations staff member as appropriate. .

Please fee free:to contact me with any questions concerning the

implementation of this program.

i hdT/L -

0. R. Trausch

Supervisor - Operations h ORT

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c: W. G. Gates '

T. L. Patterson

All Operations Personnel

Mike Lazar

-l Bob Luikens Bob DeMeulmeester i

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l SRO Ouestion 74 4

Personnel entry into a confined space is permitted if toxic gas in the confined i

space is less than 50 ppm Carbon Monoxide and the confined space atmosphere also meets which ONE of the following conditions?

1 l a. Oxygen concentration is not less than 19.5%; explosive concentration j is not greater than 10%.

i

! b. Oxygen concentration is not less than 19.5%; explosive concentration j is not greaterithan 4%.

I

c. Oxygen concentration is not less than 20%; explosive concentration l is not greater than 4%.

i d.. Oxygen concentration is not less than 20%; explosive concentration j is not greater than'10%..

l t

j ANSWER: a.

REFERENCE:

50 G-45, p.1

SR0 only KA

194001Kll3 [3.3/3.6) l-

OPPD COMMENT f

OPPD requests that this question be deleted.

j It is the responsibility of the Chemistry Department to sample the confined space i atmosphere, to determine if the oxygen and explosive concentrations are within

i. limits, and to issue the Confined . Space Entry Pennit.. Senior Operator Licensed

i. Individuals and operators under their supervistun era required to obtain a l: Confined Space Entry Permit from Chemistry prior to entry _ into a confinod space.-

4 KA' 194001- Kl.13 requires knowledge of safety procedures u related to an oxygen-

deficient environment. Memorization of specific limits is not-required since they are listed on the Confined Space Entry Permit.

REFERENCE:

FC-1200, " Confined Space Entry Permit" 50-G-45, paragraphs 1.6.1, 1.6.8, 1.6,9 r

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SRO J y 20 f CALHOUN STATION \

GENERAL FORM FC-1200 R0 PAGE 1 OF 2 OPPD NUCLEAR AND PRODUCTION OPERATION DIVISION CONFINED SPACE ENTRY PERMIT OPERATING AREA VALID FROM (Date and Time) VALID TO (Date and Time)

DESCRIPTION AND LOCATION OF WORK TO BE DONE GAS TESTS:

FORCED VENTILATION MUST PREVIOUS CONTENTS OF CONFINED SPACE BE OFF DURING TESTING OXYGEN READING COMBUSTIBLE GAS TEST (19.5%-22%) TOXICITY TEST READING TYPE READING (110%) (LESS THAN S0 PPM CO) GAS

[ ]  %

[ ] %LEL PPM

[ ] CHECKED OTHER TOXIC TEST READINGS (Specify) POTENTIAL HAZARDS SIGNATURE OF PERSON PERFORMING TESTS DATE TIME SYSTEM PREPARATION REQUIRED EQUIPMENT TAGGING AND LOCK-OUT VESSEL BLANKED GFCI PROCEDURES FOLLOWED OR PHYSICALLY AIR SUPPLIED MASKS GROUND FAULT CIRCUIT SCBA'S/ AIRLINE DISCONNECTED INTERUPTER

N N/A Y N N/A Y N N/A Y N N/A VESSEL CLEANED FOR VENTILATION ON CHEMICAL BOOTS EETRY DURING ENTRY CHEMICAL SUIT /

Y AND GLOVES SPECIAL CLOTHING N N/A Y N N/A Y N- N/A Y N N/A CONTINUOUS OR INTER- PERMIT PROVIDED HEARING PROTECTION MITTENT GAS TESTS SAFETY HARNESS &LINE FLAME / CHEMICAL /

NEEDED RWP Y N N/A Y N N/A Y N N/A l

Y N N/A l

RADIATION SOURCES OTHER FIRE EXTINGUISHER SECURED OTHER Y N N/A Y N N/A Y N N/A Y N N/A LIST ANY SPECIAL PRECAUTIONS NECESSARY A PREJOB BRIEFING HAS BEEN CONDUCTED AND I HAVE PERSONALLY EXAMINED THE ABOV AND BEINGCERTIFY TAKEN THE EQUIPMENT SAFE FOR EITI'RY WITH THE ABOVE NOTED PRECAUTIONS W ERVISOR/ CREW LEADER DATE TIME FC/ FORM /10

~ . .. _ . _ . . _ _ _ _ . _ . ._ ._. _ . - - - - . . _ ._. . - . - - - - -

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• FORT CALHOUN STATION "*: SO G-45' Y STANDING-_ ORDER O

, PAGE 2;OF 5

! 1.5.2 Entries into confined spaces with atmoepheres.

1 which are Dnmediately dangerous to life or

( health are not permitted under-this procedure.

i . 1.5.3 If ventilation is required to insure j acceptable explosive and oxygen levels, take i

care that the method of ventilation does not '

result in an explosive or oxygen deficient j atmosphere elsewhere. Also, be sure the. air 1 intake is placed in an area that will' draw in j fresh air-only.

1.6 Procedure

{ 1.6.1 Obtain a Confined Space Entry Permit from the 7f.

l Chemistry Department. o i- L. - #

l i

1.6.2 The. confined-Space Entry Permit Form (ref. FC-1200) is to-be filled out by the craftsmen involved, and' posted at the. confined space access-point until the space is closed

! out or the permit expires.

! 1.6.3 A prejob briefing shall be conducted by the job foreman / supervisor and attendance documented on. Fort-Calhoun Form FC-1200,:

Page 2. .The briefing shall be'given to all personnel = supporting the-confined space ~ entry.

The briefing shall consist of but not limited l

to the followings- l-

- A. A detailed sequential description of all i

phases'of work to be completed in the i space. Assign-tasks required to_ perform j the job-if applicable.

~

! B. Assign tasks.to ensure all equipment ~1s l- available and inspected' prior'to: confined space ~ entry if' applicable.

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3 i-i j FC/SO/02 k7 i

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

4 FORT CALHOUM ""V'c2N SfD 79 *

,- STANDING ORDER

• SO G-45 PAGE 4 OF 5 1.6.4 C. Disconnecting belt and chain drives and mechanical linkages on shaft driven equipment where possible.

D. Securing mechanical moving parts within confined spaces with latches, chains, 4 chocks, blocks or other devices.

1.6.5 Flush the confined space as required to maintain as low as reasonably achievable exposure if required.

1.6.6 Pump or drain confined space to the lowest practical level.

J.6.7 Remove the manway cover from the confined

/ space.

i l.6.8

]

{ Chemistry sample the atmosphere of the tank to i i

j ensure that combustible gases are locs than [

10% and oxygen is 19.5% or greater, and CO is less than 50 ppm. If the atmosphere was found unacceptable and then ventilated, ensure it is retc.sted before entry.

1.6.9 If the combustible gases are~1ess than 10% and the oxygen is 19.5% or greater, and CO is less s

than 50 ppm record the_ values on the form.

% The space may be cleared for entry.

1.6.10 f Chemistry Confined assign Space an Permit.

Entry expiration date to the , '~

i NOTE:

If more than one craft will work in the

same e.'nfined space, the craft to which the l Confined Space Entry Permit was originally l issued will be contacted, and joint work

coordinated with that craft.

A. Determination of the expiration date should consider:

(1) If the conf?.ned space normally

, contains water solutions and is not l

blanketed with an inert or oxygen displacing gas, then an expiration date for the duration of the planned r work (but not to exceed 14 days) is appropriate.

l j (2) If the confined space is normally blanketed with an inert or oxygen displacing gas, then a permit duration of one day is appropriate.

FC.'SO/02 R7

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