ML20045H736

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Rev 0 to Radiation Control Manual RP.305.40, RP Responder Instructions
ML20045H736
Person / Time
Site: Rancho Seco
Issue date: 07/01/1993
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20045H726 List:
References
RP.305.40, NUDOCS 9307210197
Download: ML20045H736 (20)


Text

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- MANUAL: RADIATION CONTROL

' MANUAL NUMBER: RP.305,40 t

REVISION:

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TITLE: RP R$SPONDER INSTRUCTIONS -

PAGE 1 OF 20 l

LEAD DEPARTMENT:

EFFECTIVE DATE:

RP/ EM/ EP/ NUCLEAR CHEMISTRY 07-01-93

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REVISION

SUMMARY

l NEW PROCEDURE

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MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 2 OF 20 l

1.0 PURPOSE Provide instructions for the implementation of the RP Responder program.

2.0 SCOPE This procedure gives guidance to qualified RP Responder personnel to perform:

1.

Entries into high radiation and contaminated areas for routine plant evolutions, inspections, and surveillances.

2.

Initial response actions for unexpected radiological situations that require immediate attention by onsite radiological personnel.

This program is being put into place under the auspices of having Operations personnel act as RP Responders in situations where RP personnel are not available.

NOTE To ensure the function of the RP Responder is maintained within the intent of the program, plant conditions shall be such that the possibility of leakage from plant systems that could create more severe or new contaminated or airborne areas is minimal. Routine evolutions that would increase the probability of changing radiological conditions shall be scheduled to ensure Chem / RP Decommissioning Technicians (RP Technicians) provide the necessary coverage and survey support.

The instructions contained in this procedure are for:

1.

Unexpected events that could occur on the back shift, weekends (Friday through Sunday), and holidays. Typical unexpected events are as follows:

A radiation monitor is declared out of service A liquid effluent diversion occurs

MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 3 OF 20 2.0 SCOPE.

(continued)

An individual is unable to exit from the controlled area or site due to an alarming contamination monitor.

An area is suspected to be contaminated that has not been previously posted, or a posted contaminated area is further contaminated.

There is a personnel contamination.

An unplanned event occurs where a high radiation area entry is required before an RP Technician can be called in.

Radiological support for Emergency Plan Response Team, Fire Brigade, or offsite fire suppression personnel is -

required before an RP Technician can be called in.

and/ or 2.

Those activities on the back shift, weekends, and holidays that have been evaluated to be within the scope of this program. They would typically be:

(1)

Operations activities that require surveillances, inspection and /or operation of plant equipment in high radiation or contamination areas that require radiological support for entry. Routine evolutions or the operation of plant equipment (i.e. radwaste processing) that may change radiological conditions shall be performed when RP Technician coverage is available.

(2)

Large area (masslin) contamination information surveys of the radiological controlled area (RCA) walkways. These information surveys are to provide "information only" evaluation of the control of contamination in the street clothes areas.

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MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 4 OF 20 2.0 SCOPE (continued)

Radiological support during normal working hours would be provided by Chem / RP Decommissioning Technicians and Chem / RP Technical Staff 1

personnel. RP Responder support is only for back shift, weekend, and holiday coverage.

RP Technicians and RP Supervision exceed the qualifications for RP Responders and may perform the activities that RP Responders are trained and qualified to perform.

In accordance with Permanently Defueled Technical Specifications (PDTS), an individual qualified in Radiation Protection practices and procedures shall be on site during fuel handling operations when fuel is in the Spent Fuel Pool (PDTS D6.2.2.c). This individual will be an ANSI qualified RP Technician. Providing coverage for fuel handling operations is not within the scope of the RP Responder program.

3.0 REFERENCES

/ COMMITMENT DOCUMENTS 3.1 References 3.1.1 10 CFR 19; Notices, Instructions and Reports to Workers; Inspections and Investigations 3.1.2 10 CFR 20, Standards for Protection Against Radiation 3.1.3 ANSI / ANS-N18.1-1971; American National Standard for Selection and Training of Nuclear Plant Personnel 3.1.4 Radiation Control Manual 3.1.5 Radiation Detection Instruments Manual 3.1.6 Chemistry Department Procedures 3.1.7 Rancho Seco Emergency Plan and Implementing Procedures 3.1.8 RP Responder OJT Check Sheet i

I MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION: t0

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. TITLE: RP RESPONDER INSTRUCTIONS PAGE 5 OF 20 3.2 Commitment Documents a

j 3.2.1 ANI / MAELU criteria as required '

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i 4.0 DEFINITIONS

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5.0 PREREQUISITES

.i 5.1 Operations Personnel:

5.1.1 Satisfactory completion of the required classroom training for RP-Responders.

5.1.2 Satisfactory completion of the RP Responder OJT check sheet.

5.1.3 Satisfactory completion of final oral examination and/ or walk through.

i 6.0 QUALIFICATIONS / INITIAL TRAINING / RE-TRAINING a

6.1 Responsibilities 6.1.1 RP/ EM/ EP/ Chem Manaaer 6.1.1.1 Responsible for program description, initial training and retraining :

with Operations Group concurrence.

6.1.1.2 Providing OJT Trainers and Evaluators 6.1.1.3 Conducting walk-throughs and oral examinations 6.1.1.4 Conducting on-shift task evaluation schedule as determined necessary to maintain task based training qualifications.

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MANUAL NUMBER: RP.305.40 MANUAL: RADIATION CONTROL REVISION:

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6.1 Responsibilities (continued) 1 6.1.2 Operation / Security Manaaer Maintain instructions in the Operations Daily Work Plan and/ or the Shift 6.1.2.1 Routine Book to ensure:

Radiation Protection support is requested from RP -

1.

Supervision when work, that potentially involves changing radiological conditions is scheduled outside of normal working hours, or The Emergency Response Organization (ERO) Radiological 2.

Assessment Coordinator (RAC) is called upon identification of an off-normal radiological event (i.e. fire in the radiological controlled area (RCA), personnel contamination, Emergency Plan event, liquid radwaste spill, etc.).

6.2

_ Initial Traininq initial RP Responder training will be conducted as classroom training to support a task based training program. A written examination will be 6.2.1 given at the completion of the classroom initial training portion of the R Responder training program.

Task qualification will be determined by Trainer and Evaluator reviews documented on a RP Responder OJT Check sheet maintained by 6.2.2 the Radiation Protection Group.

Qualified Trainer / Evaluator lists will be maintained by the RP Group.

6.2.2.1 Final qualification will be determined by an oral examination and/ or 6.2.3 walk-through conducted by second level RP Supervision.

The Task Evaluation Sheet (attachment 1 to the RP Responder OJT check sheet) will be used to evaluate the performance level for each task.

6.2.3.1 Task evaluations may be repeated several times to ensure proficiency in each task.

s MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40.

REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 7 OF 20 l

6.3 Retrainina 6.3.1 Retraining will be the responsibility of the Radiation Protection Group and will be included in the Radiation Protection Group Training Program.

6.3.2 RP Responders will be included in the Radiation Protection Group training matrix for procedure revisions and procedure training.

6.3.3 Group Briefings, reading assignments and classroom training that is determined to be relevant to RP Responders will be given to Qualified RP Responders. Industry events training will be provided as determined to be applicable to the RP Responder qualification.

l 6.3.4 Task evaluation and drill schedules will be maintained to provide opportunities for RP Responders to be involved in scheduled Emergency a

Plan Drills and other drill activities and scenarios as determined to be necessary. RP Responder drill activities and task evaluation schedules will be determined by the RP and Operations Supervision.

7.0 PRECAUTIONS 7.1 The designated Emergency Plan Emergency Response Organization (ERO) Radiological Assessment Coordinator (RAC) shall conduct an evaluation to determine if additional RP support is necessary whenever non-routine RP Responder actions are to be performed or are considered.

The RP Responder shall call the designated ERO RAC to obtain this evaluation. Certain incidents require RP support to complete all the regulatory and procedure requirements.

q 7.2 The RP Responder training program defines the scope of activities an j

operator is allowed to perform as an RP Responder. Also, the q

training program defines the radiological safety precautions that an operator must consider when hel she performs RP Responder functions or responds to adverse radiological conditions. In this way, caution will -

be exercised when an operator performs functions which require the operation of plant equipment and the performance of radiological controls or coverage. The RP Responder training program gives.

reasonable assurance that the required separation of responsibilities is maintained.

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MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 8 OF 20 l

7.0 PRECAUTIONS (continued) 7.3 Plant Conditions shall be such that the possibility of leakage from plant systems that could create more severe or new contaminated or airborne areas would be very minimal. r autine evolutions that increase the probability of changing radiolo6. cal conditions shall be scheduled when Chem / RP Decommissioning Technicians can provide the necessary coverage and survey support.

7.4 All personnel involved in this program are to be aware of the different responsibilities under 10 CFR 19,10 CFR 20, the Permanently Defueled Technical Specifications, Emergency Plan, Fire Protection Plan, ODCM, and Security Plan. In summary, although an RP Responder may be working under Operations Supervision, that individual still has the prerogative to:

7.4.1 Contact upper management if there are concems about the Radiation Protection Program.

7.4.2 Request an NRC investigation without concern about reprisals.

7.4.3 Not follow directives that knowingly violate sections of the regulations concerning Radiation Protection.

7.5 In accordance with Permanently Defueled Technical Specifications (PDTS), an individual qualified in Radiation Protection practices and procedures shall be on site during fuel handling operations when fuel is in the Spent Fuel Pool (PDTS D6.2.2.c) i

MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 -

I REVISION:.._ 0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 9 OF 20 -

- 8.0 PROCEDURE Index 8.1 Instrumentation Checkout and Source Checks 8.1.1 Dose Rate Meter 8.1.2 Count Rate Meters 8.1.3 PCM-18, Personnel Contamination Monitors 8.1.4 Site Portal Monitors 8.2 Controlled Area Coverage 8.2.1 High Radiation Area Entries.

8.2.2 Emergency Team / Fire Brigade / Off-Site Fire Suppression

.i Personnel Coverage 8.2.3 Emergency Plan Actions 8.2.4 Hot Particle Area Coverage 8.2.5 Radiation Area Posting 8.2.6 Contaminated Area Posting 8.2.7 Airborne Area Posting 8.2.8 Posting Supplies 8.3 Personnel Monitoring 8.3.1 Controlled Area Egress 8.3.2_ Portal Monitors (Site Exit) 8.3.3. Hot Particle Zone Monitoring 8.4 Walkway Contamination Information Surveys 8.4.1 Information Survey Requirements 8.4.2 Counting Techniques 8.4.3 Documentation of Results 8.4.4 Notification of RP Supervision 8.5 Personnel Contaminations 8.5.1 Hot Particle Contaminations 8.5.2 Non-Hot Particle Contaminations

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8.5.3 Clothing Contaminations 8.5.4 Personnel Decontamination Documentation 8.5.5 Contaminated / Injured Personnel i

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MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 10 OF 20 8.0 PROCEDURE Index (continued) 8.6 Dosimetry 8.6.1 Abnormal Dosimelry Report 8.6.2 Emergency Dosimetry 8.7 Effluents Monitor Alarm Response 8.8 Out of Service Effluent Monitors Actions 8.8.1 Auxiliary Building, Auxiliary Building Grade Level Vent, and Reactor Building Stack particulate samples 8.8.2 IOS Building Vent particulate samples S.8.3 Plant Effluent samples 8.1 Instrumentation Source Checks 8.1.1 Dose rate meters (RO-2) shall be checked out and source checked in accordance with RP. ?11.II.01, section 1.0 through 6.2.

8.1.1.1 Pre-operational checks are conducted in accordance with RP.311.II.01, section 6.1 and 6.2.

8.1.1.2 Source check of the dose rate meter is performed in accordance with RP.311.VI.02, section 6.2.

8.1.1.3 If any abnormal indications are observed during the. battery check or i

source check, the dose rate meter (RO-2) shall nqt be used. The dose rate meter (RO-2) shall be tagged with a radiac repair tag and placed in the Radiac Repair Area (Auxiliary Building, +40).

CAUTION Under no circumstances shall a dose rate meter (RO-2) be used that does not meet all the requirements of the pre-operational and source checks.

8.1.1.4 Instrument calibration due date and beta factor shall be indicated on the RO-2 checked out. Calibration due date shall be current.

8.1.1.5 Instrument source checks shall be completed on a daily basis prior to use.

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TITLE: RP RESPONDER INSTRUCTIONS PAGE - 11 OF 20 3

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~ 8.1 Instrumentation Source Checks 1

(continued) 8.1.2 Count rate meters (friskers) shall be checked out and source checked in accordance with RP.311.1.01, section 1.0 to 6.2 (RM-14) or RP.311.1.02, section 1.0 to 6.2 (Ludlum 177).

8.1.2.1 Pre-operational checks are performed in accordance with RP.311.1.01, section 6.1 (RM-14) and RP.311.l.02, section 6.1 (Ludlum 177).

8.1.2.2 Source checks for portable friskers (RM-14 and Ludlum 177) are performed in accordance with RP.311.VI.02, section 6.3.-

i 8.1.2.3 Instrument calibration due date shall be indicated on the count rate meter checked out. Calibration due date shall be current.

CAUTION Under no circumstances shall a count rate instrument (RM-14 or -

Ludlum-177) be used that does not meet all the requirements of, the pre-operational and source checks.

5 8.1.2.4 Instrument source checks shall be completed on a daily basis prior to use.

8.1.3.

PCM-1B, Personnel Contamination Monitor Source Check 8.1.3.1 PCM-1B source check is performed in accordance with RP.311 VI.02,-

i section 6.4.

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8.1.3.2 Source check for the PCM-1B is performed on a daily frequency.

8.1.3.3 Results of the PCM-1B source check are recorded on the PCM-1B Daily.

Source Check Loa. RAD-144, whether the instrument passed or failed the source check.

8.1.4.

Gamma-10 Portal Monitor (Site Exit) i 8.1.4.1 Portal Monitor source checks are performed in accordance with RP.311.VI.02, section 6.5 q

8.1.4.2 Source check for the Gamma-10 Portal Monitor is performed on a daily _

frequency.

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e MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 12 OF 20 8.1 Instrumentation Source Checks (continued) 8.1.4.3 Results of the Portal Monitor source check should be recorded on RAD-188, Portal Monitor Source Check Loo.

8.2 Controlled Area Coveraae 8.2.1 RP Responders providing coverage for entry into high radiation or contamination areas shall ensure that all personnel have the required dosimetry and comply with the requirements of the RWP used for the entry.

8.2.2 RP Responder coverage for Emergency Response Team, Fire Brigade, and/ or off-site fire suppression personnel shall be performed in accordance with the standing RWP that is used for these activities.

Certain emergency situations (i.e., a fire, personnel injury in a radiological controlled area, or other Emergency Plan scenario) may require entry without the normal access control sign-in. The requirements of the applicable RWP must be followed for all situations. The radiological conditions described in the RWP must be current and applicable for all entries.

8.2.3 The radiological conditions that are present for the Emergency Team, Fire Brigade, and/ or off-site fire suppression personnel entries can be initially evaluated and documented within the scope of the RP Responder program. Final evaluation and recording of external and internal doses will be conducted by ANSI qualified RP Technicians. Free release surveys of potentially contaminated equipment will be done by ANSI qualified RP Technicians.

8.2.3.1 Air sampling (low volume grab samples) will be collected when Emergency Response Team, Fire Brigade, and/ or off-site fire l

suppression personnel enter areas which have the potential for airborne activity. Radiological support for response to a fire in a radioactive material storage area is an example of situations of potential airborne activity. Air samples collected during these types of evolutions shall be analyzed by Chem / RP group personnel.

MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 13 OF 20 8.2 Controlled Area Coveraae (continued) 8.2.4 Entries shall not be made into areas where the radiological conditions have not been evaluated. An RWP that applies to the activity being performed must be available(i.e. section 8.2.2). Entries into areas where the radiological conditions have not been evaluated shall not be made unless an evaluation of the conditions is made by ensuring the following actions are completed.

8.2.4.1 Radiation Protection Supervision is contacted.

8.2.4.2 A radiological evaluation is made of the work area, and

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8.2.4.3 Appropriate protective measures are taken as specified by qualified RP personnel.

8.2.5 RP Responder coverage for response teams following Emergency Plan activation shall be in accordance with EPIP-5305.

8.2.5.1 Emergency Exposure Guidelines, EPIP 5360, shall be implemented as required.

8.2.5.2 Off-site support personnel, (i.e. Ambulance and Fire Suppression personnel), shall be issued dosimetry in accordance with EPIP-5220.

8.2.6 RP Responder coverage for entries into Hot Particle areas shall be in accordance with RP.305.7, section 6.8. Normally, entries into Hot particle I

areas are scheduled when Chem / RP Decommissioning Technicians are available.

8.2.7 Posting of radiation, contamination, and airborne areas by RP Responders shall be in accordance with RP.305.7.

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8.2.8 Suspected contamination areas shall be posted in accordance with the

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appropriate " Contaminated Area" posting at the boundary of the contamination. RP Supervision shall be contacted to ensure the i

necessary surveys to verify and evaluate the contaminated area (s) are

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conducted.

I 8.2.9 Suspected airborne areas shall be posted with a " Airborne Area" posting.

RP Supervision shall be contacted to conduct the necessary surveys to verify and evaluate the airborne area. See 8.2.2.1 for information regarding potential airborne activity areas.

MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 14 OF 20 8.2 Controlled Area Coveraae (continued)

NOTE To ensure the function of the RP Responder is maintained within the intent of the program, plant conditions shall be such that the possibility of leakage from plant systems that could create more severe or new contaminated or airborne areas is minimal. Routine evolutions that may change radiological conditions shall be scheduled to allow Chem / RP Decommissioning Technicians to provide the necessary coverage and survey support.

8.2.10 Posting materials and barrier supplies are located at several locations in the radiological controlled area. The Emergency Plan RP locker in the Technical Support Center (TSC) contains additional posting supplies.

8.3 Personnel Monitorina 8.3.1 Workers exiting the Controlled Area do so in accordance with RP.305.98.

Response actions for a frisking station (access control or step off pads located in controlled area) alarm are located in RP.305.98, sections 6.4.1 and 6.4.2.3.

8.3.2 Personnel exiting the site are required to monitor themselves with the installed portal monitors. Alarms that occur at the restricted area exit are to be responded to in accordance with RP.305.9B, section 6.5.

8.3.3 Workers exiting a Hot Particle Zone are to be surveyed in accordance with RP.305.9E, section 6.3.

8.4 Walkway Contamination Information Surveys 8.4.1 Contamination information surveys shall be conducted on a daily frequency in the radiological controlled area (RCA) walkways and stairwells which are in the designated street clothes area of the RCA.

This information survey shall be limited to the Auxiliary Building walkways and stairwells. Contamination information surveys shall be conducted in the Spent Fuel Building if entries are made into this area.

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MANUAL: RADIATION CONTROL

' MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 15 OF 20 8.4 Walkway Contamination Information Surveys (continued) 8.4.2 Walkway and stairwell information surveys shall be conducted using the large area survey (masslin) technique.

8.4.3 Masslin used for the information surveys shall be counted using a RM-14 or Ludlum-144 frisker with a HP-260 probe, Background levels shall be determined prior to counting the masslin.

8.4.4 The contamination limit for this type of contamination information survey is 100 counts per minute (CPM) above the background cpm reading ( i.e.

survey reading - background reading = contamination level ). This reading corresponds to a contamination limit of 750 dpm per ft 2 2

8.4.5 If contamination levels greater than the 750 dpm per ft limit are detected the following actions should be taken:

8.4.5.1 Access to the suspected contaminated area should be restricted to minimize the spread of contamination. Operations Supervision should be notified that this action has been taken.

8.4.5.2 The suspected contaminated area should be re-entered and re-surveyed (information only) using the appropriate protective clothing (minimum requirement would be shoe covers).

8.4.5.3 If the re-survey (information only) results indicate that the contamination is still present, the area should be posted as a contaminated area. RP Supervision should be notified to determine if additional action is 1

required.

J 8.4.6 Results of all information surveys performed shall be documented in the appropriate Control Room or RP log book with the date, time, information survey location (s), information survey results, and the RP Responder performing the information survey.

MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 16 OF 20 8.5 Personnel Contaminations 8.5.1 Hot Particle Contaminations shall be responded to in accordance with the instructions given in RP.305.9D, section 6.2.

NOTE A Hot Particle is defined as a highly radioactive, discrete, small particle of either irradiated fuel fragments or neutron activated corrosion and wear products. Activity greater than 5000' corrected counts per minute (ccpm) at 0.5 inches with an RM-14 equipped with an HP-260 probe is the activity level that determines if the contamination is considered to be a hot particle contamination.

8.5.1.1 Skin dose calculations are completed in accordance with RP.305.9D, section 6.1 and 6.2. Dose assessment shall be completed as soon as possible to determine if administrative or regulatory dose limits have been exceeded.

8.5.2 Non-hot particle skin contaminations (i.e. facial or noble gas) are responded to in accordance with RP.305.9D, section 6.1 and sections 6.3 through 6.12.

8.5.3 Response to clothing contaminations shall be in accordance with RP.305.9E, section 6.13.

8.5.4 Documentation for all contaminations shall be completed as described in each applicable section of RP.305.9D. Initial dose calculations shall be documented as soon as possible.

8.5.5 Contaminated / injured personnel shall be responded to in accordance j

with EPIP-5330. Additional RP support shall be requested as required by the Emergency Plan Implementing Procedures.

8.5.6 RP Supervision shall be contacted to discuss all personnel contaminations as soon as possible to verify the exposure calculations and ensure all necessary actions have been completed.

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MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

0 TITLE: RP RESPONDER INSTRUCTIONS PAGE 17 OF 20 8.6 Dosimetry 8.6.1 An Abnormal Dosimetry Report (RAD-167) shall be completed whenever any of the following conditions of RP.312.1.13, section 4.1 occur:

(1)

Lost Dosimetry.

(2)

Off scale pocket dosimeter.

(3)

Abnormal pocket dosimeter readings.

(4)

Damaged dosimetry.

(5)

Radiological Controlled area entries with improper dosimetry.

(6)

When deemed necessary by RP Supervision.

8.6.1.1 Completion of the required documentation shall be in accordance with RP.312.1.13.

8.6.1.2 RP Supervision shall be contacted as soon as possible to determine if any additional actions shall be initiated.

8.6.2 Emergency Dosimetry for offsite support personnel (Ambulance and Fire Suppression personnel) shall be issued in accordance with EPIP-5220.

j 8.7 Effluents Monitor Alarm Response 8.7.1 Response to gaseous and liquid effluent monitor Alarms shall be in accordance with CHM-5109 section 1.0 through 6.1. Effluent monitor alarm response is only for a valid high alarm on the following monitors:

(1)

R15044:

Reactor Building Stack (RBS)' monitor (2)

R15045:

Auxiliary Building Stack (ABS) monitor (3)

R15546A:

Auxiliary Building Grade Level Vent (ABGLV) i monitor (4)

R15017A Plant Effluent nonitor (5)

R15106 IOS Building gaseous monitor (particulate channel) 8.7.2 Response to a high alarm for R15044, R15045, and R15546A is in accordance with CHM-5109, section 6.2.

8.7.3 Response to a high alarm for R15017A is in accordance with CHM-5109, section 6.3

1 MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

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TITLE: RP RESPONDER INSTRUCTIONS PAGE 18 OF 20 8.7 Effluents Monitor Alarm Response (continued}

8.7.4 Response to a high alarm on R15106 is in accordance with CHM-5109, section 6.5.

8.8 Out of Service Gaseous and Liould Effluent Monitors 8.8.1 RP Responder responsibilities will be to immediately notify RP Supervision and ensure that (1) the alternate samples have been collected for out of service gaseous effluent monitors, and (2) the plant effluent grab sample is collected for a liquid effluent monitor alarm and/ or plant effluent divert.

NOTE Time constraints for initiating alternate sampling must be met for all gaseous effluent monitoring points. Particulate sampling shall be initiated within one hour of the monitor being declared out of service. Gaseous sampling is required to be taken within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of the monitor being declared out of service by qualified Chem / RP group personnel. See CAP-009, section 6.4.1.4 for particulate sampling requirements.

0.8.2 Auxiliary Building Stack (ABS), Auxillary Building Grade Level i

Vent (ABGLV), and Reactor Building Stack alternate samples for the particulate monitors shall be completed in accordance with CAP-009, section 6.4.1.

NOTE Air sampling equipment shall be available for use at the alternate sampling point locations. Contact RP Supervision if sampling equipment is unavailable.

8.8.2.1 Sample collection for ABS, ABGLV, and RBD is in accordance with CHM-1000, sections 5.4 and 6.6.

1 MANUAL: RADIATION CONTROL MANUAL NUMBER: RP.305.40 REVISION:

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TITLE: RP RESPONDER INSTRUCTIONS PAGE 19 'OF 20 l

8.8 Out of Service Gaseous and Liauld Effluent Monitors:

(continued) 8.8.2.2 Air sampling documentation for Auxiliary Building Stack, Auxiliary Building Grade Level Vent, and Reactor Building Stack samples shall be recorded on form CHM-088, A_ir Sample Data Sheet.

8.8.3 IOS Building Vent alternate samples should be collected in accordance with CHM-1000, section 6.6 NOTE Continuous particulate monitoring of the IOS Building Vent is required only if the ventilation system is operating. See CAP-002 (ODCM), Attachment 16.

8.8.3.1 Air sampling documentation for 10" Building Vent samples shall be recorded on form CHM-088, Air Samole Data Sheet.

8.8.4 Plant Efflu'ent samples are to be collected in accordance with' CHM-1005, section 6.7.16. Sampling is required due io an alarm on R15017A/

R150178 or if the plant effluent diverts.

8.8.4.1 Time restraints on sample collection and documentation required are found in CHM-5109. Samples should be collected as soon as possible to determine if release limits have been exceeded. See CHM-5109, section 1.0 through 6.1, and section 6.3 for instructions for sampling the plant effluent in response to an effluent alarm or divert.

9.0 RECORDS The following individual / packaged documents and related -

correspondence completed as a result of the performance of this procedure are records. They shall be transmitted to Records Management in accordance with RSAP-0601, " Nuclear Records Management".

9.1 RP Responder OJT Check sheet 9.2 Task Evaluation Sheet L

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10.0 ENCLOSURES NONE i

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