ML012690559

Final - Section a Operating (RO)

ML012690559
Person / Time
Site:	Susquehanna
Issue date:	08/13/2001
From:	Peal R Susquehanna
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-387/01-301, 50-388/00301 50-387/01-301, 50-388/01-301
Download: ML012690559 (32)

Text

Operating Test Number Cat UA" Test: 1 Examination Level RO Administrative Topic A. I Subject

Description:

Plant Parameter Verification Question Number: 1 Calculate the reactor period given that IRM level has gone from 10 to 20 in 54 seconds.

Doubling time = time to change from 10 to 20 or 54 seconds.

54 x 1.44 = 77.76 seconds for reactor period.

fGO-1 00-002, Section 6.39 12.1.7 3.014.0 CCG.. iiii........................................................................ iiiiiiii~i~~i~~iii iiii*!i~i**!*

uperaung 1esT rumoer Loat -,K I est: 1 Examination Level RO Administrative Topic A. 1 Subject

Description:

Plant Parameter Verification Question Number: 12

~ ~~ ~.. ........... ........

During a reactor startup the mode switch is about to be transferred to RUN. What method is available to you to determine that the APRMs are accurate, other than reading the APRMs or using the LPRMs? Give an example of the method.

Bypass valve position is an alternate indication of Reactor power.

Per RE-1TP-026, Validation of Core Thermal Power Heat Balance:

A Channel Check is performed at approximately 7-10% power, as determined by the APRMS, prior to moving the mode switch from Startup to Run.

a. Confirm Pressure Set at 955 psig.

b. Record number of open bypass valves (blank if using computer point NBA13).

c. Record percent core thermal power utilizing Attachment D, "Bypass Valve Position vs Calculated % Power," or computer point NBAI 3.

d. Attachment D is attached for use in the demonstration.

RE-I TP-026 2.1.7 13.0/4.0

uperaung I est rMumDer Ial -/A I esi: -I Examination Level RO Administrative Topic A.1 - I Subject

Description:

Logs and Log Keeping Question Number: 1 Unit I is at 100% power. When performing the daily logs, the following are observed:

• LIS-B21-1N042A: +39 inches

• LIS-B21-1N042B: +32 inches

" LIS-B21 -1 N024A: +34 inches

• LIS-B21 -1 N024B: +36 inches

• LIS-B21 -1 N024C: +37 inches

" LIS-B21 -1 N024D: +35 inches What are the required actions, if any?

NOTE: Only the information in "BOLD"is requiredto answer the question.

Additional information describes how the necessary actions are determined.

Providethe attachedlog sheets from SO-100-006 (Attachment A, pages 18-19)

CHANNEL CHECK is outside the agreement criteria for the 42A-B instruments.

CHANNEL CHECK is within the agreement criteria for the 24A-D instruments.

Initiate a CR to investigate the instrument response for the 42A&B instruments and complete it (determine the problem) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the investigation is NOT completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, declare both channels inoperable.

Note: Logged values for LIS-B21 -1 N024A-D and LIS-B21 -1 N042A-B should be:

" LIS-B21 -1 N042A: +39 inches

• LIS-B21-1N042B: +32 inches

• LIS-B21 -1 N024A: +34 inches

• LIS-B21 -1 N024B: +36 inches

• LIS-B21 -1 N024C: +37 inches

" LIS-B21 -1 N024D: +35inches i... f. ......

txamination Level Administrative Topic I A.1--9.

Subject

Description:

Logs and Log Keeping Question Number: 2 Unit 1 is at 100% power. During the performance the daily logs, the Recirculation Loop "A" Drive Flow versus total core flow is plotted at +11 %.

You are directed by the Unit Supervisor to complete SO-1 00-007, Attachment C, step "c" under SR 3.4.2.1 Acceptance Criteria for LOOP "A" and determine if the LOOP "A" jet pumps are OPERABLE or NOT OPERABLE.

NOTE: "A" Loop JET PUMP DELTA P's are provided on the attachedpage.

I~~~~ . . .

XX............... . . . .

NOTE: Only the informationin "BOLD"is requiredto answer the question.

Additional information describeshow the necessary actions are determined.

JP 17 is NOT OPERABLE.

Calculationis completed as follows (e.g.):

Average JP dip = 36 (sum all 10 JP values and divide by 10).

Calculateeach JP deviation by subtractingthe average value from the individual JP value. The resultantvalue is dived by the average value.

This resultant value is multiplied by a factor of 100. Forexample:

(JP 11-A) - A x 100 = [(36.1-36) ÷ 36 x 100] = +0.27, JP1 1 calculated deviation is

+0.27 (JP17-A) ÷A x 100 = [(38.3-36) ÷36 x 100] = +6.38, JP 17 calculated deviation is

+6.38 NOTE: After JP1 1 deviation is calculated (or the first calculation is completed),

provide a completed Attachment C (page 3 of 8) with all calculations complete.

The calculated deviation values are then plotted on Figure 1, TWO LOOP JET PUMP DISTRIBUTION LOOP A, the results indicate JP 17 is inoperable.

Deviation Values: (JP11 +0.27, +JP12 +0.27, JP13 -2.77, JP14 +2.77, JP15-0.55, JP16 -1.11, JP17 +6.38, JP18 -2.77, JP19 -2.77, JP20 +0.27 so-1~

o0-. ~~ At.a.h..en . .......

SO-1 00-006, Attachment A, Item C1 2.1.7, 2.1.18, 2.1.25 13.7, 3.9, 2.8

Attachment C SO-100-007 Performance Data Sheet Recirculation System Dual Loop JET PUMP INST PANEL 1C619

1. Jet Pump Delta P's UPPER RELAY ROOM JP11 36.1% JP12 36.1% JP13 35%JP14 37% JP15 35.8%

JP16 35.6% JP17 38.3% JP18 35%JP19 35% JP20 36.1%

Attachment C SO-100-007 Revision 34 Page 27 of 60 LOOP A JET PUMP AP PERCENT DEVIATION FROM THE AVERAGE A = Average Jet Pump AP Loop A (Calculate below)

JP 4P%  % JP AP Dev.

1. JPI 1 3G,I (JP1I -A) ÷AX 100 = +-0,!2ý PLOT ON FIG. I

2. JP12 (JP12 -A) +AX 100 = ATTACHMENT I

3. JP13 35- (JP13-A) +A X 100= -2.17

4. JP14 3-7 (JP14-A) +A X 100 = +. Z.-7

5. JP15 35,8 (JP15 -A) +AX 100=

6. JP16 (JP16-A) +A X 100=

7. JP17 (JP17-A)+A X 100 =

- bit'

--2,*-77

8. JP18 35 (JP18-A)÷AX-100=

9. JP19 55- (JPl9 - A) +A X 100 =

-Zro?*

10. JP20 3&0 1 (JP20-A) +AX 100 =

A= 36>0 X0.I= 340 (Sum of &P%)

JP11 thru 20 Page 3 of 8

uperatina ivestTUMAer Examination Level RO Administrative Topic 1A.2 Subject

Description:

Tagging and Clearances Question Number: 1 During an outage it is necessary to apply blocking on 4.16 KV Breaker, 2A20409, 2B Turb. Building Chiller, The work will require cycling the breaker in TEST, NO work will actually be performed in the breaker or on the 4.16 KV Bus.

Where must the blocking tags be placed?

A nswe .r.. .......................... p .. he.o..

The breaker will be placed in TEST and tags placed on the following:

a. Local Control Switch on the cubicle door

b. Trip Control and DC Power knife switch

c. Alternate Trip DC Power knife switch

d. Racking screw Note: The candidate may indicate the associated bus must be declared inoperable when the breaker is in TEST, This information is NOT necessary to answer the question.

NDAP-QA-0323, Sect. 6.3.8 12.2.13 13.6/3.8

%.jIBhS~I8W~ ~ ~ ...... ......*....................

uperaung Iest NumDer uat -4 i esi: 1 Examination Level RO Administrative Topic A.2 Subject

Description:

Tagging and Clearances Question Number: 2 After the work is completed the Sign On requested a uTemporary Lift of Red Tags to allow testing 4.16 KV Breaker, 2A20409, 2B Turb. Building Chiller.

The testing is successful and operations requests the chiller remain in service.

What requirements apply to clearing and closing the permit?

.'~~i1..w...... . . . . . ....

The Sign On may permit the chiller remain in the temporary lift position by immediately signing off the permit. This allows:

a. Energy isolating devices may remain in the "Out of Permit Condition".

b. All tags lifted shall be turned over to Ops to support the subsequent permit clearance.

c. Notify any active Sign-Ons of the status.

d. Sign-On shall notify Shift Supervisor of the equipment status

e. A Field Operator shall physically verify equipment status.

Techr~~cnl Retere....

NDAP-QA-0322, Sect. 8.4.8.e.( 3),8.10 12.2.13 3.6/ 3.8 X..%..:I...X. X` X.:X

Uperating I est Nul Examination Level RO Administrative Subject

Description:

Topic A.3 Radiation Protection Question Number: 1 QuesO~~n~ .....................

RWP 2001-0037 is attached for your use.

Given RWP 2001-0037, determine which dose reduction activity results in the GREATEST reduction in the general area dose rates before starting jobs #1, #2, and #3.

The contents of the Waste Sludge Phase Separator will be transferred to a High Integrity Container (HIC) prior to the start of the tank rinsing. NOTE: If the student states ALARA blocking, ask them to be specific.

TechicalRefrenc~s) ...~.....

NDAP-QA-0626 RWP 2001-0037 and ALARA Brief

:;-=*-.

2.3.10 2.9/3.3

Administrative Topic A.3 Subject

Description:

I Radiation Protection Question Number: 12 RWP 2001-0037 is attached for your use..

Given RWP 2001-0037, determine the contamination and radiation levels adjacent to (within 4 feet) and at the strainer.

......... 77777=

Contamination levels are 5K outside the piping (#1), 100K on the strainer (#2),

and 10K on the floor (#3).

NDAP-QA-0626, and pre-job brief.

RWP 2001-0037 2.3.1 2.6/3.0 2.3.10 2.9/3.3

SSES Radiation Work Permit RWP 2001-0037 Rev 000 Unit: Common Control Point: U-2 HP CONTROL POINT Building: RWASTE RWASTE 646 System: 068 RADWASTE SOLIDS HANDLING Elevation: 646 Room: R-030 WASTE SLUDGE PHA Component ID: 0T331 R-029 PHASE SEPARATOR Job

Description:

T/PSCEEANCUT7RINSE-OT733-f WASZTE SLUD(GE'PF-ASESEP IANK; CLEAN BASKE SiTIRAINER ON lPMrP OUP33Z. INCLUDES ANON-CONTAMINATED AREA SUPPORT.

Special Instructions For HP Technicians:

Constant / intermittent coverage requirements:

1. CONSTANT COVERAGE required in tank room, if areas >= 1 R/hr are accessible, or if ALARA blocking is not applied.

2. Surveys required for initial entry into unsurveyed work areas and system breach, Daily dose rate verification survey in pump and tank rooms.

3. BZA required for system breach and rinsing tank.

4. ALARA blocking IAW NDAP 00-0626 is required prior to entry into Phase Sep. tank room.

5. Access is Limited to the pump room and waste sludge phase sep tank room.

6. Ensure air sample lines, extension cords, and hoses utilized can be readily broken down to allow door closure when necessary.

7. Back-out dose rate during HP survey 3 R/hr general area.

8. Alert levels for suction strainer: Pre-breach contact dose rate: 1 R/hr System internal contamination: 200 mRad/hr/1OOcm2.

9. Monitor for Hot Particles as described below.

1*****INSTRUCTIONS PERTAINING TO HOT PARTICLES*****

Moniter personnel involved in the breach of the WSPS Tank and Basket Strainer for Hot Particles. Include a hot particle check of the work area. If Hot Particles are found, take immediate action to minimize the spread of the particles; T- stop work; and notify HP Supervision. Document all 1,'"survey results.

w

• W i*crW*v**r****** aJ R* * *W w

• ww n ww ww-* w *w Contamination Levels (in Work Radiation Levels units of Activity per Airborne Levels (mRem/hr) l00cm2 k=1000 DPM) (DAC)

Activity zu5 iLK* ~

15'g1K U.3 SU I b U U 5UALA .A Est'd Person-Rem: 0.338

Contact:

MADARA*CHARLES W 0.300 Outage: NON-OUT Blocking: YES Person Rem-Goal:

Actual Person-Rem: 0.000 Type: Routine Pre Job: YES Name Section Date Authorizing Signature Requested by:

339-HP TECH II 02/22/2001 07:31 HARDER*KURT T Written by: HARDER*KURT T 339-HP ALARA 02/22/2001 07:37 GALLAGHER*DAVID A ALARA Review: GALLAGHER*DAVID A SUPERVISION 339-HP FOREMAN 02/22/2001 07:47 BELL JR*MARK R Issue by: BELL JR*MARK R Terminated by:

Form NDAP-QA-0626-1, Rev. 0, Page 1 of 1 (file R6-1).

SSES Radiation Work Permit DWP: 2001-0037 Rev: 000 11II1 11111 IIIII IIIIIII IIIIII I1111

Description:

• P*:*L*.*N ~1 - VVA6 A*

• t/IS ST*

LU UD3 P HA* t St: I A  ; ULE. N A T l lN E-R ON PMP UP 332. IN CLU DES* PU MP RM AN U N UN-

,CONTAMINATED AREA SUPPORT.

RWP Activities:

1I. Support work in non-contaminated areas.

2. Misc. support in pump room.

3. Breach manway, rinse tank, misc support in tank room and breach and clean pump strainer. on

• • • • • • • • • • • • • • • • • • ACTUALS ******************* ** PAD Settings **

Contamination Levels (in WORK Rad. Levels units of Activity per Airb. Levels Minimum Dose Rate Time (DAC) Dose(t=Rerm) (mRem) (mR/hr) (HH:MI)

Activity (mRem/Hr) 100cm2 K=1000 DPM)

.LUU bU bU 1b : UU RWP Activity 2U 3 DRESS REQUIREMENTS: NO DRESS REQUIREMENTS FULL PC'S FULL PC'S & PAPERS Face shield/Hood per HP (6)

PROTECTION: NONE NONE NONE 3 RESPIRATORY INTERMITTENT CONSTANT * , "

HP COVERAGE: INTERMITTENT AIR SAMPLES: NONE PER BRIEFING BZA -

DOSIMETRY Extremity TLD: NO NO NO Special Dosimetry:. - -. -s Other: CD '

• 0" W, " *. "

ENGINEERING CONTROLS HEPA: NO NO NO "

Shielding: NO Per NP Per HP Other: NO NO (5)

HOLD POINT: NO (1), (2), (3) (1),(2), (3) 1 OTHER REQUrIREMENTS: SEE SPECIAL INSTRUCTIONS SEE SPECIAL INSTRUCTIONS SEE SPECIAL INSTRUCTIONS Special Instructions for Worker:

........ I .......... I --..

(1). A radiological briefing by HP is required prior to entering the phase separator complex.

Explain work activities and locations in detail.

ROOMS 0 (2). ALARA blocking IAW NDAP 00-0626 required. ACCESS IS LIMITED TO THE PUMP AND WASTE SLUDGE PHASE SEP TANK (3). HP must be present for initial shiftly entry, for breach of system.

sep (4). Retreat to a low dose rate area whenever possible. Minimize time near the base of the waste sludge phase tank, piping and passage ways to the other phase sep tank rooms.

(5). Contain any water / sludge released during breach and direct to the nearest floor drain.

Bag used rags and parts separately from normal rad trash.

(6). Face Shield required when rinsing tank.

LADDER WHEN (7). NO ENTRY INTO THE RWCU PHASE SEP ROOMS IS PERMITTED ON THIS RWP. DO NOT PASS BEYOND THE WSPS TANK ACCESSING THE TANK WORK AREA WITHOUT SPECIFIC HP APPROVAL.

" Ensure hoses can be reaily disconnected to allow door closure when necessary.

Form NDAP-QA-0626-2, Rev. 0, Page I of 1 (file R6-1).

ALARA RWP Person Rem Estimate Worksheet TP: 2001-0037 Rev: 000 Alara Code A: DE DECONTAMINATION Work Code: 1 ROUTINE MAINTENANCE Alara Code B: FH FLUSHING/HYDROLAZING LOCATION :

Unit: Common Building Elevation Room RWASTE 646 R-030 WASTE SLUDGE PHASE SEPARATOR PHASE SEPARATOR PUMPS RWASTE 646 R-029 Job

Description:

fVSPS:GLEAN OUT/RINSE UT331- WASiESLUE ,.SEP PHASE LTANK; GLEAN BASKI:E 1:11KAI:NE: UN -M-t' tsI-Z. INtLUUr*

PUMP RM AND NON-CONTAMINATED AREA SUPPORT. I Dose Rate are in mRem/hr DDE = Person Hours X Est. Dose Rate TEDE = DDE + CEDE Dose is in Rem CEDE = (Person Hours X DAC X CF) / PF Person Est. Rate CF DDE Description Hours DAC PF CEDE TEDE dlpor I4 U 0 1  : UI - - Q l T. SupporE worR in non-WUJS on

14. UU U.UU U . %.m UU Z4:oo 3. U t) U.Ob'4 U.Ub4

. ISC. support in pump room.

h. *reacfl manway, rinse taInK, misc support in tanK oom and breach and clean pump strainer.

+/-*u*u'.'Lu u .ru Is O.*4i u .u u ....

U..*44 Total Hrs: 60: 00 Total DDE: 0.335 Total CEDE: 0.003 Total TEDE: 0.338 ALARA Goal TEDE: 0.300 Total DAC Hrs.: 1.20 Effective mRem/Hr: 5.6 HP-AL-400-3, Rev. 5, Page I of 1

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000 Date: 02/21/2001 Pre Job Attendance Required: No Job

Description:

WSPS: CLEAN OUT / RINSE 0T331 -WASTE SLUDGE PHASE SEPARATOR TANK, AND CLEAN BASKET STRAINER ON PUMP 0P332. INCLUDES PUMP ROOM AND NON CONTAMINATED AREA SUPPORT.

Also covers RWPs: N/A JOB LOCATION:

Unit: 0 Building: RW Elevation: 646' Completed By: David A. Gallagher I Charles W. Madara Outage: No Health Physics Specialist ALARA APPLICABLE A. PERSON-REM ESTIMATE:

Z] 1. Do the workers have sufficient available exposure to complete the job?

Estimated: 60 Person-hrs Estimated: 0.335 Person-Rem Alara Goal TEDE: 0.300 Person-Rem Work group supervision shall ensure workers have sufficient available exposure to complete assigned tasks.

APPLICABLE B. WORK PLANNING/SCHEDULING:

S 1. Is work properly scheduled accounting for downpowers, hydrogen injection reductions, outages, work windows, etc.?

Waste Sludge Phase Separator work is power and hydrogen injection rate independent.

Z 2. Is the work sequence optimized?

Yes. - See "Work Flow".

Z 3. Has the optimum work crew size been determined?

The size of the work crew will vary depending on the task being performed. Normally 2 HPs, 3 Effluents, and a contractor to pump sludge from tank as it is being rinsed.

FORM HP-AL-400-1, Rev. 7, Page 1 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000

• *~U u APPLICABLE B. WORK PLANNING/SCHEDULNL:

CREW SIZE 7 Z 4. Are the workers experienced or familiar with the work?

Workers performing these tasks have previously performed the same or similar tasks.

E 5. Can mock up or other training be utilized?

N/A

6. Has the Job History File been reviewed? Should one be created?

Yes. - JHF # 27

7. Can SSES/lndustry experience be gained from previously performed similar jobs?

Yes. - RWP 1999-0064 for installing a pipe patch on this section of pipe was reviewed to incorporate previous experience.

Also, RWP 2000-0064 was reviewed.

8. Are photos, drawings, video tapes etc. available of installed equipment or actual work being performed, to aid in work briefing?

HP photo library contains pictures of affected area, as does the JHF.

9. Are all required support groups identified or notified?

Operations, Maintenance, HP, and Effluents are aware of activities as outlined on approved schedule.

Z] 10. Can waste generation be minimized? Will special waste be generated? Has Effluents Management been notified?

Effluents Management will process waste in the WSPS prior to work starting.

D 11. Are funnelslhoses required to drain the system/component to an appropriate floor drain?

No.

FORM HP-AL-400-1, Rev. 7, Page 2 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000 APPLICABLE C. EXTERNAL EXPOSURE REDUCTION CONTROLS:

S 1. Can work be delayed until short lived isotopes have decayed?

(e.g. schedule work during outageslisolating systems prior to work, etc.)

Tank will be emptied of contents thus decay is not necessary.

Z 2. Have ALARA blocking and Protective Tagging requirements been identified?

ALARA blocking will be applied in accordance with NDAP-QA-0626 and NDAP-QA-0323.

Z 3. Can communication devices, headsets or cameras be used to improve efficiency?

Radios will be used for communications between the tank room, Operations, and the vendor during rinse and pump down evolutions. Cameras and communications equipment are available for use if the need is identified.

4. Are all necessary materials, tools, parts, etc. available?

Parts, tools, equipment, and material are available for this work.

5. Are all required support services available?

(lighting, power, air, water, drains, etc.)

Yes.

Z 6. Can equipment/parts be stagedlsetup or fabricated in an accessible low dose rate area? (outside radiation or contaminated areas)

Hoses will be made-up and tested prior to work in the tank room.

1

-- 7. Can the component be removed to a low dose rate area for work?

No.

8. Can radioactive materials contributing to background or general area dose rates be removed from the work area or placed in shielded drums, lead pigs or water buckets?

The contents of the Waste Sludge Phase Sep will be transferred to a HIC prior to the start of the tank rinsing evolution.

FORM HP-AL-400-1, Rev. 7, Page 3 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000 APPLICABLE C. EXTERNAL EXPOSURE REDUCTION CONTROLS:

F-1 9. Can remote handling tools or robotics be used to increase worker distance from the source, decrease the time in the area and/or limit extremity dose?

N/A

10. Can system(s)Iequipment be filled with water to reduce dose !rates?

No. - The system must be drained to accomplish the rinse.

Z* 11. Can the system(s)/equipment be drained and/or flushed to reduce dose rates and/or minimize airborne contamination?

Flushing of the inside of the Phase Sep is the task at hand.

F--] 12. Can temporary shielding be used to lower whole body and/or skin dose rate?

Not Required TSR #

APPUCABLE D. INTERNAL EXPOSURE REDUCTION CONTROLS:

(RADIOLOGICAL RESPIRATORYPROTECTION CONSIDERATIONS)

1. Will activity be performed in a contaminatedlairborne area or create a contaminatedlairbome area? (If yes, see Attachment E, Respiratory Protection/ALARA review.)

Room is currently contaminated. Levels of contamination were in the 10k to 15k range when work last completed in the room. The rinsing operation keeps tank internals wet Airborne radioactivity has been shown to remain < 0.3 DAC when working in these conditions.

2. Can alternative tools be utilized that would minimize the generation of airborne contamination? (e.g. bandsaw in lieu of an air grinder)

The only task is to rinse down the tank internals.

FORM HP-AL-400-1, Rev. 7, Page 4 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 C©OLY Rev.: 000 APPLICABLE D. INTERNAL EXPOSURE REDUCTION CONTROLS:

Z 3. Can the system, area or component be decontaminated prior to work?

Area decon, if required, will be accomplished after the tank is emptied and dose rates are lessened.

4. Can containment devices (e.g. glove box, tent, etc.) be utilized to isolate the component andlor area?

No.

5. Can wetting or fixing agents be utilized to contain or minimize the generation of airborne contamination?

Wetting of the tank internals will be performed as part of the task. Wetting of the tank room floor will only be required if tank room general contamination levels are >50k.

E 6. Can a HEPA ventilation unit be utilized to reduce or minimize the potential for airborne contamination from entering the breathing zone and/or reduce general area airborne levels?

N/A

- 7. Can changes be made to the work process to minimize airborne generation?

N/A

8. Can early warning Air Monitors be used?

No. - dose rates are too high for proper operation of an AMS-3.

(INDUSTRIAL SAFETY RESPIRATORY PROTECTION CONSIDERATIONS)

9. Heat stress?

N/A

10. Confined space entry?

N/A FORM HP-AL-400-1, Rev. 7, Page 5 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 ci ED Rev.: 000 APPLICABLE D. INTERNAL EXPOSURE REDUCTION CONTROLS:

11. IDLH atmosphere?

N/A

- 12. Asbestos work?

N/A

- 13. Physical constraints?

N/A

14. Visual impairments?

N/A

15. Other?

N/A

16. Is the use of respiratory protection justified? No.

Basis:

Historical data indicates that work of this nature will not result in an airborne radioactivity area.

APPLICABLE E. HEALTH PHYSICS OPERA TIONAL CONCERNS

1. Hot Spots identified?

Hot spots are subject to change as rinsing/flushing progresses. The HP Technician providing job coverage will brief the workers on radiological conditions including the location of Hot Spots.

2. Low dose rate areas available and marked?

Lower dose rate areas may vary as work progresses. The HP Technician providing job coverage will brief the workers as to the location of low dose rate waiting areas.

FORM HP-AL-400-1, Rev. 7, Page 6 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000 PD Y APPLICABLE E. HEALTH PHYSICS OPERATIONAL CONCERNS

- 3. Hot Particle Zones established where necessary?

N/A

4. Special requirements for protective clothing?

(e.g. facial PC's, face shields, etc.)

Face shield and hood are required for Effluents worker while rinsing tank and may be required for other activities based on HP survey results.

- 5. Stay times required (Dose rate/Heat Stress)?

MAX Stay Time:

N/A APPLICABLE F. DOSIMETRY AND RADIOLOGICAL MONITORING (REFERENCEHP-TP-222)

1. Relocation of permanent whole body TLD?

Not expected to be required. The job coverage HP Technician shall evaluate conditions and if relocation is required, have workers relocate as appropriate and make an RWP Remarks Log entry to document the relocation.

- 2. Multiple whole body TLD's/Dosimeters?

No.

3. Telemetry or real time airborne monitoring system to monitor personnel exposures?

N/A L- 4. Extremity:

a) Monitoring?

b) Tracking?

N/A FORM HP-AL-400-1, Rev. 7, Page 7 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 C©LPY Rev.: 000 APPLICABLE F. DOSIMETRY AND RADIOLOGICAL MONITORING (REFERENCE HP-TP-222)

Z 5. Pocket Alarming Dosimeter?

Required.

6. Has HP Instruments or Dosimetry been notified for support needs?

N/A

[- 7. Other.

N/A Anticipated Dose RatesIDACS:

Whole Body: to 1000 mR/hr Skin: as WB Extremity: as WB Neutron: 0 Est. DAC Hours: 1.2 G. ADDITIONAL COMMENTSIINSTRUCTIONS

1. Water hoses should be taped together and fastened to a long pole to allow for easy rinsing of the tank internals.

2. The vent pipe on the top of the tank is normally a source of radiation, ensure dose rates are established on the vent pipe if entry to the top of the tank is required.

FORM HP-AL-400-1, Rev. 7, Page 8 of 9

ALARA PRE JOB REVIEW RWP Number: 20010037 Rev.: 000 cioPY H. WORK FLOW (SYNOPSIS OF WORK) Include items required such as and notifications evolutions with potential time requirements forfor theairborne, tents, notifications.

Tank Room Work

1. If not already done, perform a survey of the work area. Install a rope barricade just north of the ladder which piovides access to the tank top. Post this barricade - High Radiation Area - Keep Out. This will require constant coverage to prevent access to a >1 R/hr area (the entrance to "B" RWCU Phase Sep).

2. If general area contamination levels in the WSPS tank room are >150k ensure that the floor is wetted down immediately prior to the start of work.

3. Brief the Effluents work crew.

4. Effluents shall open hatch on top of the tank and have the System Engineer (or designee) examine the tank internal prior to rinse down. Take pictures of the tank internal, if reasonable.

5. If needed, Effluents rinse inner walls and top of tank to remove radioactive material.

6. Inspect the tank internal and if satisfactory, reinstall the hatch cover.

7. If general area contamination levels in the WSPS tank room are >50k, and dose rates are reasonable, decon room floor (and piping if necessary). Target should be < 50K.

8. When all work has been completed, remove tools and equipment.

9. The WSPS strainer should be cleaned when it best fits the work flow for the above evolution.

Pump Room Work (clean basket strainer for 0P332)

1. Pin spring can hanger. Drain pump inlet and outlet.

2. Remove strainer.

3. Perform gross cleaning of strainer in bucket of water. Send strainer to decon shop if more decon is necessary.

4. Install cleaned strainer (or new strainer as necessary).

5. Unpin spring can hanger. Refill pump and piping for ISLI.

FORM HP-AL-400-1, Rev. 7, Page 9 of 9

BETA & GAMMA AIR SAMPLE ANALYSIS FORM RWP Number(s): -j-- co.,_

Area: Ail/ k~L to ws'ts AA/6-Unit B uild ing~ */evuo , o I 'F rt Description of Work C- I c-j4.u T-C,¢ 1/06 *Cal Due Date: I/- el -0o AS Model _AS _C

/4) HIP#

Date/Time Counted: "_ -- ' 1" OJc' Beta Counter HP #

Counted by I HP Technician

.7-Sample Volumi Gross Beta ParticulateActivity 3.;-C' / Time: ogii-f Gross Counts: / [ J-A/S Start Date:

A/S Stop Date: Time: ___/_ (1) CountTime: _ S_-04 _ _

Total Minutes: c0 Gross CPM:  : 3 7_. LPM Background CPM: _ -__--

Flow Rate:

Total Volume: Liters Net CPM: _

Counter Efficiency: /1., 0 (2) Beta Activity: ' 2c-i> pCi cc Is Particulate Filter Beta-to-Gamma Ratio z: 10? beta ac-fi*iity ) YES NO (Circle one) gamma actiiy (3) Gamma Isotopic I D: Part - DET ID: HP-__Acquisitio ate/Time /

(Complete this section A ion Date/Tie I Iodine - DE- ID: HP- me ONLY ifGamma Analysis is performed.) Gas - DET ID: HP- cquisition Date/Time I Gamma Analysis: " L/ ,4 Total Tracking DAC's: DAC (Complete this section if Grand Total Fractional DAC on the Gamma Printout is a 0.3 DAC.) Total Posting DAC's: DAC (4) See Paga 2 of this form for required a ns.

If Page 1 of Gamma printout contains Uhid entified peaks k 25 counts, complete Form HP-TP-720-4.

If Page 3 of Gamma printout contains Nonstochastic nuclides, complete Form HP-TP-720-4.

If Particulate Filter Beta-to-Gamma Ratio is zŽ 10 after the second count, complete Form HP-TP-720-7.

jtf t) 17 Reviewed: L Health Physics Supervision uate Date FORM HP-TP-720-1, Rev. 15, Page I of 2, Duplex (File R6-2)

ENLARGEMENT SUSq SES - AREA SURVEY MAP RxPWR ,A)I/.

RADWASTE BUILDING Elfev. 646' 1 PHASE SEPARATOR PUMPS R-29 RWP# c5/ - oo.?? DATE: 23 'c TIME-.- - -0 _J SURVEY BY: _. /--,r Q RAD. INST. tZ'- HP # 5a Z- AIR SAMPLER 141L4-- HP #/1 ACT. 2 ( jC/cc CONTAMINATION INST. xý m - HP #Z S-12 EFF. t'O  % BKGD. ,-.

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Health Physics / Date SMEAR.LOCATIONS CIRCLED. RAD READINGS IN mR/hr.. UNDERUNE - CONTACT RAD READINGS W = S.O.P.

-..RAD TAPE -X-X- = RAD TAPE & ROPE X XXX - RAD ROPE @ = A/S LOCA71ON N S= eec. outlet &ko t,r tc des,*/v d , &e . -e/ e CAL BRATION D UEDATE INSTRUMENT SOURCE -,, CAITO/DEDT CHECKED SAT.,.:-

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PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO EP.PS.126.101 0 05/01/01 206000 4.1 Appi To JPM Number Rev No. Date NUREG 1123 Sys. No. K/A Task

Title:

Make Initial Notifications to Off-site Agencies and Emergency Personnel per EP-PS-126.

Completed By: Reviews Phil Ballard 0614/01 Writer Date Instructor/Writer Date Approval:

Requesting Supv./C.A. Head Date Nuclear Tr, ining Supv. Dhtet

• -- Date of Performance:

20 Min.

Allowed Time (Min) Time Taken (Min)

JPM Performed By:

Last First M.I. Employee #/S.S. #

Performance Evaluation: ) Satisfactory ( ) Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2, (9/93)

Page 1 of I File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE RO EP.PS.126.101

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-001, Operations Shift Policies.

B. All applicable safety precautions shall be taken in accordance with established PP&L safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

11. REFERENCES A. EP-PS-126-001 Ill. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Reactivity Manipulation(s):

None IV. TASK CONDITIONS A. A Unit 1 reactor scram occurred and all control rods are NOT fully inserted into the reactor core.

B. The US has entered EO-100-113, Level/Power Control.

C. The SS declared an ALERT at 1200 due to the failure of RPS to shutdown the reactor.

D. The TSC is NOT activated.

E. The completed EMERGENCY NOTIFICATION REPORT is provided as Attachment A.

F. You are the PCO on Unit 2.

G. The SS has determined that a Site Evacuation and accountability is NOT required.

H. The SS has determined that there are NO routing instructions for personnel responding.

I. The Centrex Telephone Network (CTN) "191" capability is NOT functioning.

V. INITIATING CUE Make the required notifications per EP-PS-126 and complete the required documentation per EP-PS-126. (Note: Actions are to be simulated)

(

PERFORMANCE CHECKLIST Page 3 of 5 Appl. To/JPM No.: RO EP.PS126.101 Student Name:

1. Obtain a controlled copy of EP-PS-126. Obtains a controlled copy of EP-PS-126.

Note: Because the CTN "191" capability is NOT functioning, the student is required to use the narrative procedure (Tab 4)

Reference:

in addition to the CONTROL ROOM COMMMUNICATOR Tab 1 (CONTROL ROOM FLOWCHART (Tab 1) to obtain the backup phone numbers. COMMUNICATOR FLOWCHART) and/or Tab 4 (narrative procedure).

Obtains a EMERGENCY NOTIFICATION LOG SHEET (Tab 5).

2. Warn plant personnel of the Emergency Declaration. Press the activate button on the PA phone handle and announce the following:

"Attention all personnel,a Alert has been declared at SSES."

Repeats the announcement.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1

r

/t PERFORMANCE CHECKLIST Page 4 of 5 AppI. To/JPM No.: RO EP.PS126.101 Student Name:______________

Step I Action I Standard Eval [ Comments

• 3. Request activation of the Nuclear Emergency Contact the ASCC to activate the Response Organization (NERO). NERO by either:

" Press "Hotline" Button Evaluator:

• Dial 8-254-3115 (Primary)

When the Alternate Security Control Center

• Dial 8-254-3000 (Backup)

(ASCC) is called:

• Answer the call as the ASCC and acknowledge Request activation of NERO.

that activation of the NERO is requested for an Inform ASCC to indicate Alert (B).

Alert and that there are NO routing instructions. Provide routing instructions as NONE.

Notify off-site agencies (PEMA - Pennsylvania Within 15 minutes of accepting the task

• 4. Emergency Management Agency, LCEMA - to make notifications, notify PEMA, Luzerne County Emergency Management LCEMA, and CCDPS as follows:

Agency, and CCDPS- Columbia County Department Public Safety). NOTE: CTN "191" is inoperable.

If 4191 is called, inform student the phone line is "dead."

Evaluator: PEMA: Dial 4960, 4961, or 8-1-717-When PEMA is called: Acknowledge report. 651-2001 and report alert.

LCEMA: Dial 8-353-4906/4907/4908, When LCEMA is called: Acknowledge report. or 8-1-800-821-3715, and report alert.

CCDPS: Dial 8-353-4955/4956, or 8 When CCDPS is called: Acknowledge report. 570-389-5734 and report alert.

NOTE: Completion of the EMERGENCY Enter agency contact, time of

-NOTIFICATION LOG SHEET (Tab 5) is NOT notification, and initial for ENR FROM required to satisfy the Critical Task. transmittal on the EMERGENCY NOTIFICATION LOG SHEET (Tab 5).

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1

(

PERFORMANCE CHECKLIST Page 5 of 5 Appl. To/JPM No.: RO EP.PS126.101 Student Name:

Step Action Standard Eval Comments

5. Notify the Transmission Power Dispatcher. Activate the TPD "hotline" or dial 8-220-5090 or dial 8-220-5091.

Evaluator:

When TPD is called: Acknowledge report. Report the emergency.

• 6. Notify the NRC. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of accepting the task to notify the NRC as follows:

Evaluator:

When NRC is called: Acknowledge report. Pickup the ENS phone to activate auto dial or dial 301-816-5100 or 310-951-0550 or dial 301-415-0550 and report an alert.

NOTE: Completion of the EMERGENCY NOTIFICATION LOG SHEET (Tab 5) is NOT required to satisfy the Critical Task.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1

TASK CONDITIONS A. A Unit 1 reactor scram occurred and all control rods are NOT fully inserted into the reactor core.

B. The US has entered EO-100-113, Level/Power Control.

C. The SS declared an ALERT at 1200 due to the failure of RPS to shutdown the reactor.

D. The TSC is NOT activated.

E. The completed EMERGENCY NOTIFICATION REPORT is provided as Attachment A.

F. You are the PCO on Unit 2.

G. The SS has determined that a Site Evacuation and accountability is NOT required.

H. The SS has determined that there are NO routing instructions for personnel responding.

I. The Centrex Telephone Network (CTN) "191" capability is NOT functioning.

INITIATING CUE Make the required notifications per EP-PS-126 and complete the required documentation per EP-PS-126. (Note: Actions are to be simulated)

Page 2 of 3

TASK CONDITIONS A. A Unit 1 reactor scram occurred and all control rods are NOT fully inserted into the reactor core.

B. The US has entered EO-100-1 13, Level/Power Control.

C. The SS declared an ALERT at 1200 due to the failure of RPS to shutdown the reactor.

D. The TSC is NOT activated.

E. The completed EMERGENCY NOTIFICATION REPORT is provided as Attachment A.

F. You are the PCO on Unit 2.

G. The SS has determined that a Site Evacuation and accountability is NOT required.

H. The SS has determined that there are NO routing instructions for personnel responding.

I. The Centrex Telephone Network (CTN) "191" capability is NOT functioning.

INITIATING CUE Make the required notifications per EP-PS-126 and complete the required documentation per EP-PS-126. (Note: Actions are to be simulated)

Page 1 of 3

Attachment A Control # 01 EMERGENCY NOTIFICATION REPORT U This is a Drill 0 This is NOT a Drill 1 This is: Shift Supervisor Bob Knoll at Susquehanna Steam Electric Station.

My phone number is: 570-542-3904 the time is 1200

2. EMERGENCY CLASSIFICATION:

O Unusual Event El Site Area Emergency

• Alert 0l General Emergency El The Event has been Terminated UNIT: 1 TIME: 1200 DATE: 8/14/01 THIS REPRESENTS AN U Initial Declaration }

El Escalation } INCLASSIFICATION STATUS El No Change }

3. BRIEF NON-TECHNICAL DESCRIPTION OF THE EVENT:

An automatic reactor scram occurred and all control rods did NOT fully insert into the reactor core. Reactor power is currently at 8%.

4. THERE IS E NO }

El AN AIRBORNE } NON-ROUTINE RADIOLOGICAL RELEASE IN PROGRESS Q A LIQUID }

5. WHEN GENERAL EMERGENCY IS THE INITIAL EVENT, PROVIDE PROTECTIVE ACTION RECOMMENDATIONS BELOW:

NOT APPLICABLE.

6. Wind Direction is From: Not Applicable Wind Speed is: Not Applicable (Data is obtained from lo meter meteorological tower>)

• This is a Drill El This is NOT a Drill Approved: Bob Knoll TIME: 1200 DATE: 8/14/01 EP-AD-000-310, Revision 2, Page 1 of 1, File R36-9 Page 3 of 3