ML19224B559

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Health Physics Procedures 1630.2,Revision 2:reactor Bldg Entry
ML19224B559
Person / Time
Site: Crane Constellation icon.png
Issue date: 11/06/1978
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
1630.2, TM-0413, TM-413, NUDOCS 7906150311
Download: ML19224B559 (15)
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1630.2 Revision 0 08/29/77 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1630.2 REACTOR BUILDING ENTRY (UNIT 2 ONLY) 1.0 PURPOSE The purpose of this procedure is to list the requirements necessary to enter the Reactor Building during Reactor shutdown, power operation or an emergency.

2.0 DISCUSSION To ensure personnel safety during a Reactor Building entry, several tests must be made of the Reactor Building atmosphere.

The biological hazards that exist inside the Reactor Building are radiation, oxygen deficient atmosphere and explosive gases.

2.1 Radiological Hazards--Airborne radioactivity comes from leaks mainly around the reactor coolant pump seals.

Penetrating radiation (gamma and neutron 1 comes mainly from the reactor, and from the main coolant piping.

(. Neutrons only when reactcr is critical.).

2.2 0xygen Deficient Atmosphere--Cue to the fact that the Reactor Buiiding is sealed and normally not purged during operation, i.t is possible that an oxygen deficient atmosphere might exist.

2.3 Explosive Gas--The explosive gas is hydecgen coming from leaks in the primary ccolant system.

3.0 REFERENCES

3.1 Three Mile Island Operating Procedure 2102-d.1, " Reactor Building Purging & 'lenting."

3.2 TMI Radiation Protection Manual 3.3 1622 - Releasing Radioactive Gasecus Waste z 1 !i

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1630.2

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Revision 0 08/29/77 3.4 1963 - Gas Analysis using a Gas Chromatograph 3.5 1662 - Radiation Dose Rate Surveys a.6 1605 - Portable Air Sampling for Radioactive Particulates 3.7 1606 - Air Sanpling for Radioactive Iodine 3.8 16C7 - Air Sampling for Radioactive Gas 3.9 1608 - Air Sampling for Tritium 3.10 1609 - Surface Contamination Surveys 3.11 1613 - Radiation Work Permits 3.12 1632 - Radiation Shutdown Survey 3.13 2311-5 Containment Integrity.

4.0 EQUIPMENT 4.1 0xygen Explosive Gas Meter, MSA Model 250, or equivalent.

4.2 Eberline Rad Owl Ion Chamber Instrument er appropriate doserate instrument.

4.3 Air Sampler 4.4 Self-contained Breathing Apparatus 4.5 Tritium Sampler 4.6 Personnel Dosimetry 4.7 Syringe 4.8 Appropriate Protective Clothing 4.9 Gas Sampling Flask 4.10 Neutron Instrument 'Eberline Model PNR-a}/(Eberline Model PNC-4)_

4.11 Gas Partitioner 5.0 OPERATING INSTRUCTICNS ENTRY WHEN REACTOR IS AT PCWER Oo SHUT ECWN and Containment Integrity is established.

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1630.2 Revision 0 08/29/77 5.1 Before Reactor Building entry, insure that the following steps Fave

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been accomplished.

5.1.1 Samples of the Reactor Building have been collected and analyzed for radioactivity, explosive qualities and oxygen content. or 5.1.2 Readings taken from the RMS and recorded on form 1630.2-1 with the oxygen levels and explosive levels to be determined upon en t ry.

NOTE:

Entry into the building may be made, in the event of an emergency, without first conducting an air quality survey if proper respiratory equipment is worn and, da soon as possible, the air quality is determined.

Perform Section 2 of Form 1630.2-1.

5.1.3 0xygen levels greater than 19.5% in the Reactor Building as read on an Oxygen Explosive Gas Meter, or Gas Partitioner, as per 1963, are acceptable.

5.1.4 Hydcogen levels less than 2.5% in the Reactor Building as read on an Oxygen Explosive Gas Meter, or Gas Partitioner, as per 1963, are acceptable.

5.2 Submit Form HPP 1630.2-1, with Step 1 complete, to the Shi.f t Foreman /

C, Supervisor and Radiation Protection Supervisor / Foreman for signatures and approval for entry.

5.3 Personnel Criteria 5.3.1 Routine entry to the Reacto-Building, when at power, or initial entry to the Ruactor Builuing af ter shutdown for purposes of surveying and.asting will require a minimum of two (2) persons. One of the two (2) must be a Radiation-Chemistry Tech /Jr., Auxiliary operator or an alternate that is r,r 1 n j (-))

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1630.2 Revision 2 11/06/78 qualified by previous H.P. Training as determined by the Radiation Protection Supervisor / Foreman.

NOTE:

For special entries Radiation Protection personnel entering the Reactor Building to perform a survey for completica of an RWP do not requirc an RWP when authorized by the Radiation Protection Supervisor /

Fo reman.

Radiation Protection personnel may accompany other individuals into the Reactor Building without a completed RWP.

The Radiation Protection personnel will provide the level of safety and control normally provided by the RWP.

Immediately after exiting the area an RWP will be completed.

Routine entry into the Reactor Building, when at power, for purposes of a general inspection will require an RWP.

5.3.2 The approval of the Shif t Supervisor, Radiation Protection Supervisor, and Unit Superintendent must be obtained if maintenance or operations inspections must be L;rformed w' thin the secondary shielo, on top of the "D: Rings, or in the rea' :or head area when the reacter pcwer is greater than 15. Rcactor power must not be increased until such work is ccmpleted or the situation is Ee-evaluated and further approval is obtaiaed from the e

Radiation Protection Supervisor, Shift Supervisor, and Unit /Str Mn Superintendent.

NOTE:

Standing approval to enter the "D" Rings to perform routine survey No. 48 has been given by the Radiation Protection Supervisor and the Unit Superintender'.

Notification of the Shif t Supervisor 4.0

1630.2

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Revision 1 12/27/77 will be required, however, for each entry of this nature.

5.3.3 Protective clothing requirements for entry for purposes of surveying and testing will be specified by '.he Radiation Protection Supervisor / Foreman.

NOTE:

If HPR-227 alarms, Control Room Personnel will notify personnel to exit the Reactor Building immediately.

5.3.4 Equipment requirements for initial entry for purposes of surveying and testing wi!1 consist of a portable radiation survey meter, sampling eauipment necessary to perform the required atmospheric surveying and appropriate respiratory equipment, if required.

5.4 Notify the Control Roca prior to entry into Reactor Building.

5.5 When making entry into the Reactor Building, insure that Containment Integrity is maintained as follows:

5.5.1 Before attempting to enter access lock observe the red indicating lights above the handwheel.

If the opposite door is in use these lights will be lit indicating that a mechanical interlock will prevent opening the exterior door.

5.5.

Observe differential pressure across door on local DPI.

Rotate handwheel very slowly in the opan direction.

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interlock should stop rotation at 29' until D.P. is less than 1 PSID.

CAUTION: Do not continue rotation if DP is greater than 1 PSID.

CAUTION: Always stay clear of the doors as a higher pressure on the exterior can cause the door to swing open and motion of the door is NOT controlled by the handwheel.

2} O klbb 5.0

1630.2 Revision 1 12/27/77,

Continue rotating handwheel in open direction uritil door is 5.5.3 unlatched and the mechanical stop is felt.

5.5.4 Open exterior door and enter air lock.

5.5.5 Close door.

Do fot bang door against seals.

5.5.6 Rotate handwheel at exterior door in close direction to latch

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door closed.

Turn handwheel until mechanical stop is felt and indicating lights at interior door go out.

5.5.7 Check seal on interlock system.

If seal is broken, and containment integrity is required, notify the Shift Foreman and perform section 7.1.

5.5.8 Proceed to interior door.

Repeat steps 5.5.2 and 5.5.3 to unlatch interior door.

5.5.9 Open iaterior door and enter Reactor Building.

5.5.10 Close interior door.

Do Not bang door against seals.

5.5.11 Rotate handwheel in close direction to latch door closed.

Turn handwheel until mechanical stop is felt and indicating lights at exterior door as viewed through sight glasses, go out.

WARN _I!jG Insure interior door is closed so that entrance can be made through the air lock.

5.5.12 Proceed immediately to the opposite airlock and insure it is open so that 2 entrances exist for emergencies.

5.6 Exiting the Reactor Building.

5.6.1 Before attempting to enter access lock observe the red indicating lights above the handwheel.

If the opposite door is in use

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these lights will be lit indicating that a mechanical interlock will prevent opening the interior door.

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1630.2 Revision 1 12/27/77 5.6.2 Observe differential pressure across door on local CPI.

Rotate handwheel very slowly in the open direction.

A mechanical interlock should stop rotation at 29 until D.P. is less than 1 PSID.

CAUTION Do Not continue rotation is D.P. is greater than 1 PSID.

CAUTION Always stay clear of the doors as a higher pres ure on the exterior can cause the door to swing open anc motion of the door is NOT controlled by the handwheel.

5.6.3 Continue rotating handwheel in open direction until door is unlatched and the mechanical stop is felt.

5.6.4 Open interior door and enter airlock 5.6.5 Close door.

Do not bang door against seals.

5.6.6 Rotate handwheel at interior door in close direction to latch door closed.

Turn handwheel until mechanical stop is felt and indicating lights at exterior door go out.

5.6.7 Check seal on interlock system.

If seal is broken and containment integrity is required, notify the Shif t Foreman and perform section 7.1.

5.6.8 Proceed to exterior door.

Repeat steps 5.6.3 and 5.6.4 to unlatch. exterior door.

5.6.9 Open exterior door and exit airlock.

5.6.10 Close exterior door.

Do Not bang door against seals.

5.6.11 Rotate handwheel in close direction to latch door closed.

Turn handwheel until mechanical stop is felt and indicating lights at interior door as viewed through sight glassas, go out.

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1630.2 Revision 1 12/27/77 5.6.12 insure surveillance test on airlock (s) per 2311-5 is performed if required per Tech. Spec. 4.6.1.3.

5.7 The surveying and testing will consist of radiation, contamination, and air surveys for the following conditions:

5.7.1 For Initial Entry at shutdown conditions follow steps 5.7.1 through 5.7.4.

5.7.2 Routine Inspection at Power will consist of radiation surveys in the area of the inspection.

5.7.1 The radiation survey will be conducted as per 1602, " Radiation Dose Rate Surveys", and/or 1632.2, " Radiation Shutdown Survey".

NOTE:

All areas over 100 mrem /hr. will be roped of f and posted.

5.7.2 The contamination survey will be conducted as per 1609, " Surface Contamination Surveys", in areas specified by the Radiation Protection Supervisor / Foreman.

5.7.3 The air surveys will be conducted as per 1605, " Portable Air Sampling for Radioactive particulates",1606 " Air Sampling for Radioactive Iodine"; 1607, " Air Sampling for Radioactive Gas"; and 1608, " Air Sampling for Tritium", in areas specified by the Radiation Portection Supervisor / Foreman.

NOTE:

If the air surveys indicate that the atmosphere is not hazardous for occupancy of personnel, further surveying and testing of the Reacter Building may proceed without the_use of respiratory devices.

5.7.4 The additional air testing, if specified by the Radiation Protection Supervisor / Foreman, will be accomplished by sampling with a portable oxygen / explosive gas meter, or utilizing the gas partitioner as per 1963.

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Revision 1 12/27/77 5.7.4.1 Record results as mentioned in Step 2 of Form 1630-1 and submit to the Shift Foreman / Supervisor and Radiation Protection Supervisor /Forenan for approval.

NOTE:

If oxygen and explosive gas samples were taken at HPR 227 prior to entry, steps 5.7.4 and 5.7.4.1 need not be completed.

5.8 At this point, the Radiation Protection Department will complete a Radiation Work Permit (See 1613) and Form 1630.2-1, " Reactor Building Entry Survey Log", and submit tc the Shif t Foreman / Supervisor and Radiation Protection Supervisor / Foreman for approval.

Form 1630.2-I will be filed in the H.P. Lab.

5.9 A log of Reactor Building entries and exits will be maintained at the entrance of the Reactor Building Personnel Access Hatch.

This log book will be used during reactor critical and not critical Reactor Building entries.

When the reactor is critical the Control Rocm also maintains a log of Reactor Building entries and exits therefore during this time notify the Control Room Operator when entries and exits are made.

5.10 The Control Room must ensure that the access hatch seals are leak tested and the Containment inspected, if applicable, per 2311-5.

6.0 EMERGENCY L'NSCHEDULED ENTRANCE INTO REACTOR SUILDING This section refers to emergency entry into the Reactor Building.

6.1 Personnel initially entering Reactor Building during an emergency must wear a full set of protective clothing, a self-contained breathing apparatus, carry a high range Ion Chamber, neutron instrument, and appropriate dosimetry.

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1630.2 Revision 1 12/27/77 Personnel requirements --A minimum of two (2) persons.

6.2 6.3 Radiation limits are 2.5 REM per person (not to exceed 5 (N-18) for the emergency, with the concurrence of the Radiation Protection Su pe rvi sor/ Foreman.

6.4 Af ter exit, a " Reactor Building Emergency Entrance Log," (Form 1630.2-2) report must be submitted to the Station Superintendent stating the following information:

6.4.1 Why the entry was made.

6.4.2 Who entered.

6.4.3 What work or action was completed.

6.4.4 What radiation exposures were received.

7.0 REACTOR BUILDING AIRLOCK INTERLCCK CPERATION 7.1 Restoring interlock.

7.1.1 Obtain seal to seal interlock cabinet.

7.1.2 Enter airlock per section 5.5.

7.1.3 Insure both doors are closed.

NOTE:

Reference figures 1 & 2 for detailed drawing of interlock system.

7.1.4 Remove clamp knob (#48) and open cover (d52).

7.1.5 Press down on camyoke (149) until it is parallel with shaft as e.-

7 in Fig. I and interlock disks are together.

7.1.6 Close cover (#52) screw in clamp kncb (#48) and apply seal.

7.1.7 Notify Shif t Foreman that interlock is in force, and seal is applied.

7.2 Violating the interlock system 7.2.1 Cbtain Shif t Supervisor / Foreman approval prior to violating interlock.

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1630.2 Revision 1 12/27/77 7.2.1 Enter airlock per section 5.5.

fl0TE:

See Figures 1 & 2 for detailed drawing of interlock system.

7.2.2 Break seal and remove clamp knotr (#48).

7.2.3 Open hinged cover (#52) and pull or push on cam yoke (#49) until yoke is perpendicular to the shaft.

Upper interlocking disk (#50) 2hould slide toward clamp yoke violating interlock as in Fig. 2.

7.2.4 Close cover and start clamp knob (#48) into hol'e.

Do not turn in fully and do not apply seal.

7.2.5 Notify Shif t Supervisor / Foreman that interlock is violated.

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1630.2 Revision I 12/27/77 REACTOR BUILDING ENTRY SURVEY LOG Date Start Time Rad./ Chem. Technician /Jr.

1.

HPR-227 Monitor Readings,

HPR-227 Lab Analysis

' Limit

-10, Particulate c/m uci/cc uCi/cc

<3 X 10 Gaseous c/m

__uci/cc uCi/cc

-9*

Iodine c/m/m uci/cc

__uCi/cc

<9 x 10 02 Reading at HPR227

% on Gas Partioner

>l9.5%

Explosive Gas at HPR227

% on Gas Partioner

<2.5% LEL

-6 Tritium 3 uCi/cc

<5.0 X 10 H

uCi/cc Check appropriate box:

o Reactor Building purge pricr to entry.

O Iodines & Particulates < MPC Reviewed Above Information Shif t Foreman / Supervisor Radiation Protection Supervisor / Foreman 2.

Readings Inside Reactor Building Portable 0 Meter 2

02 Gas Partioner e '

Portable Explosive Gas."eter Explosive Gas I, Gas Partioner Reviewed above information and authorization is granted for entry into Reactor Building without respirator, but with protective clothing.

Shif t Foreman / Supervisor Radiation Protection Supervisor / Foreman

  • Respiratory Protection, protection clothing and radiat:en areas will be indicated on a Radaition Work Permit.

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1630.2 Revision 1 12/27/77 REACTOR BUILDING EMERGENCY ENTRANCE LOG Date s

Time Entry Time Exit Time Why Entry was made Personnel Involved Name Exposure Received Work and/or action completed

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Supervisor of Operations Date Unit Superintendent Date 9

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