ML20040F983
| ML20040F983 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/20/1982 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20040F984 | List: |
| References | |
| PROC-820120-01, NUDOCS 8202110036 | |
| Download: ML20040F983 (35) | |
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7 Date: January 20.1982 CALVERT CLIFFS NUCLEAR POWER PLANT
- r. ^.,
EMERGENCY RESPONSE PLAN IMPLEMENTATION PROCEDURES LIST OF EFFECTIVE PAGES __
ERPIP PAGE REV.
ERPIP PAGE REV.
C.1-3 2
C.2-2 2
C.1-4 6
C.2-3 6
C.1-5 2
C.2-4 6
C.1-6 6
C.2-5 6
C.1-7 2
C.2-6 2
C.1-8 2
C.3-1 2
C.1-9 2
C.3-2 2
C.1-10 6
C.3-3 6
i C.1-11 2
C.3-4 2
C.1-12 3
C.3-5 2
C.1-13 3
C.3-6 2
C.1-14 2
C.3-7 2
C.1-15 2
C.3-8 2
4 C.1-16 2
C.3-9 2
l C.1-17 2
C.3-10 2
C.1-18 2
C.3-11 2
C.1-19 2
C.3-12 2
l C.1-20 2
C.3-13 2
C.1-21 2
C.4-1 6
C.2-1 2
C.4-2 6
_.)
l l
s
Page: 19 of 19 Rev.:
7 Date: January 20,1982 CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN IMPLEMENTATION PROCEDURES LIST OF EFFECTIVE PAGES _
ERPIP PAGE REV.
ERPIP PAGE REV.
C.43 6
C.4-4 6
C.b5 6
C.4-6 '
6 C.4-7 6
i C.4-8 6
i I
l C.b9 6
C.4-10 6
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D.1-1 2
0.1-2 2
D.2-1 2
D.2-2 1
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ERPIP NO.: 4.1.3 / REV. 7 DATER January 20,1982 TITLE: TECHNICAL SUPPORT CENTER DIRECTOR CHECKLIST 1.0 RESPONSIBLE INDIVIDUAL The Technical Support Center Director (TSCD)is responsible to the Plant Superintendent to analyze the current and projected plant status and to provide technical support in the event of an accident.
2.0 CONDITIONS AND PREREOUISITES 2.1 Declaration of an Alert, Site Emergency or General Emergency.
2.2 As directed by the Site Emergency Coordinator.
3.0 ACTIONS AND LIMITATIONS Gn the Technical Support Center at CCNPP on the 55' elevation of the Log and Test Instrument Room.)
-NOTE-Checklists are to be used as determined by the TSCD. Spaces for initials and times are.to be utilized, as necessary, to clarify the status.
3.1 Upon declaration of an Alert, Site Emergency or General Emergency:
3.1.1 The TSCD reports to the TSC.
3.1.2 The TSCD alternates and TSC members report to the TSC after checking in with their Assembly Area Leader or the OSCD as appropriate.
e e
4.1.3-1
._..__z.__._._.__..
. _ __ _.1_. _._. q ERPIP NO.: 4.1.3 / REV. 5 DATE: November 11, 1981 j
3.2 Activate the Technical Support Center.
TSC Activated:
/
Initials Time 3.2.1 While the TSC is being activated establish communications as per ERPIP 4.2, Section 5.0.
3.2.2 Request support personnel from OSD as required.
3.3 Record all pertinent actions on EXHIBIT 5.2-A, EMERGENCY ACTIONS FORM.
3.4 Analyze mechanical, electrical, and instrument and control problems and determine alternate solutions.
3.5 Analyze thermohydraulic and thermodynamic problems and develop problem resolutions.
3.6 Assist in the development of Emergency Response Plan Implementation Procedures, Operating Procedures, etc., as necessary, f orconducting -
]
emergency operations.
1 3.7 Analyze conditions and de"elop guidance for the Site Emergency Coordinator and operations personnel on protection of the core.
3.3 Resolve questions concerning Operating 1.icense requirements with the designated NRC representative.
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._.6-
ERPIP NO. 4.3.2 / REV.2 DATE: September 1,1981 TITLE:
ONSITE GAMMA RADIATION AND MOBILE AIR SAMPLE SURVEYS 1.0 RESPONSIBLE IN_DIVIDU ALS Onsite Monitoring Team (ONMT) and Onsite Monitoring Team Leader (ONMTL) are responsible to the Radiation Protection Director (RPD) to:
1.1 Survey and record onsite airborne and liquid pathways radiological data at selected locations and the bay (if necessary).
1.2 Report all survey results to the RFD at the ECC.
1.3 Recommend survey locaticns for continued onsite monitoring.
2.0 CONDITIONS AND LIMITATIONS 2.1 A.s directed by the RPD per ERPIP 4.1.5.
2.2 Suspicion or recognit'on of an uncontrolled release of radioactive material.
(A Radiological Event, ERPIP 3.6.)
2.3 Declaration of an' ALERT, SITE EMERGENCY or GENERAL EMERGENCY.
/
3.0 ACTIONS AND LIMITATIONS Action Initiator Time (When notified, assemble and activate the Onsite Monitoring Team (s)(ONMT) as directed by the Radiation Protection Director (RPD).
NOTE-Checklists are to be used as determined by the Onsite Monitoring Team Leader (ONMTL). Spaces for initials and times are to be utilized as necessary to help clarify the status.
- 3. l Request briefing of site conditions and the specific locations to be monitored.
Location (s):
/
Briefing Completed:
Imtials Time 3.2 When directed by the RPD to perform an onsite survey, one ONMT member should obtain an EMERGENCY MONITORING KIT (MOBILE) while another ONMT member locates and prepares the survey vehicle (if necessary).
/
4.3.2-1 s
' ^ '
- u-_L__
ERPIP NO.: 4.3.2 / REV. 7 DATE: January 20,1982
-NOTE-
)
Four-wheel drive vehicles or piant automobiles can be obtained at the South Guard House Parking Lot. EMERGENCY MONITORING KIT (MOBILE) can be obtained from the South GUARD HOUSE.
Vehicle Obtained:
/
(if necessary)
Initials Time Kit Obtained:
/
Initials Time 3.3 Perform a quick equipment and instrument check (use Table 5-1, Appendix B-
- -1) prior to initiating survey.
-Equipment & Instruments Checked:
/
Initials Time 3.4 -Establish communications with the ECC and the RPD using the radio-telephone.
Communications Established:
/
Initials Time
-NOTE-Confirm survey locations during this communication and, if changed,
~
-document on EXHIBIT 4.3.1-D, MONITORING TEAM ACTION FORM.
3.5 Proceed as directed by the RPD to the location where the first survey will be i
taken.
Arrived at Survey Location:
/
Initials Time
-NOTE-
- -Use EXHIBITS 4.3.2-A, PLANT M AP, and 4.3.2-B, SITE M AP, as a guide to the survey locations.
3.6 Monitor the area.
-NOTE-Record all data obtained from sections 3.6 and 3.7 on EXHIBITS 4.3.1-D, EXPOSURE RATE FORM, and 4.3.1-E, MONITORING TEAM SUkVEY FORM, as specified. All pertinent information not requested on these forms can'be
~
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recorded on the MONITORING TEAM ACTION FORM, EXHIBIT 4.3.1-C.
3.6.1 Using equipment shielded against Beta radiation, traverse the piume -
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in the crosswind direction, determine maximum exposure rate in j
mrem /h, and record that reading, time the reading was taken, and the 4.3.2-2 I
ERPIP NO. 4.3.2 / REV.2 DATE: September 1,1981 location.
Exposure Rate (mR/hh Time Reading Was Taken:
Location:
/
Initials Time 3.6.2 Place a particulate filter and a charcoal cartridge in the air sampler and collect a 50 liter sample at the location where the mR/h reading was the highest (found during the traverse).
Sample Initiated:
/
Initials Time 3.6.3 While collecting the sample, report the specific location and results of the gamma exposure rate survey to the RPD.
Exposure Rate Reported:
/
Initials Time 3.6.4. After collecting the air sample, record the time completed and place the charcoal cartridge and the particulate filter in separate plastic bags and mark them for later identification.
Actual Sample Size (cch Sample Completed:
/
Initials Time 3.6.5 Contact the RPD (by radio) to locate a low background area to be used for counting and proceed to that location. While en route, backflush the charcoal cartridge only with three cubic feet of uncontaminated air.
3.6.6 Set up the MS-2 and SPA-3 sample counting equipment.
3.6.7 Verify that control adjustments are per instructions in the Emergency Kit, then run a two minute background count and record results. -
Background Counts (cpmh Background Recorded:
/
Initials Time 3.6.3 Set the detector directly on the inlet side of the charcoal cartridge, E
count for two minutes and record the results.
2
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' 21' - E 7 'E Gross Counts ( pmh Cartridge Counted and Recorded:
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Initials Time 3.6.9 Determine the charcoal activity by the following formula and record l
l 4.3.2-3 l
ERPIP NO. 4.3.2 / REV. 7 ~
DATE: January 20,1982 resuits:
Charcoal Activity (uCi/cc.) =
~
Gross Counts - Background counts (Counting Minutes) (Actual Sampie Volume (cc))(2.22E6)(Efficiency)
Use the efficiency listed on the scaler.
microcuries/cc
=
3.6.10 Record the standard procedures utilized, any exceptions taken, specific instruments used and corrections for flow rates applied.
Specific Location:
Standard Procedures Used:
Exception to Procedures:
Instruments Used:
(Serial No. or ID No.):
Corrections Applied for Flow Rates:
Recorded:
/
Initials Time 3.6.11 Report the specific survey location and charcoal activity (Steps 3.6 3
& 3.6.9) to the RPD.
.)
Results Reportedr
/
Initials Time 1
3.6.12 Ask RPD if a silver zeolite cartridge air sample should be collected.
If directed by RPD to do so, Repeat steps, 3.6.1 through 3.6.10 using a silver colite instead of charcoal cartridge. Report the specific
~~
survey location and silver zeolite activity to the RPD.
Results Reported:
/
Initials Time 3.7 Perform additional surveys as directed by the RPD as follows:
-NOTE-l Based on field exposure rate measurements, take air samples starting as near to the center of the plume as possible.
l 3.7.1 Repeat Step 3.6 using charcoal cartridges unless directed otherwise by the RPD (3 or 4 passes scross the plume should be optimum).
Record data on EXHIBITS 4.3.1-D and E.
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4.3.2 4 L._.
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ERPIP NO. 4.3.2 / REV. 7 DATE: January 20,1982 Surveys Completed:
/
initials Time 3.7.2 Compute the average exposure rate for all passes made in or near the same location and recorded:
E Exoosure Rates (mrem /h) = Average Exposure Rate:
I No. of Exposure Rates Summed Survey Data Reported:
/
Initials Time
-NOTE-Label sample plastic bags (charcoal or silver zeolite cartridge and particulate filter) for tim e, date, location, time sample collection began / stopped and initial for later identification.
3.3 Assist in ccordination and augmentation of the State and Local effort, as directed by the RPD.
State and Local Agencies Assisted:
(
f Initials Time 3.9 Request further instructions from RPD and record on EXHIBIT 4.3.1-C Further Instructions Requested:
/
Initials Time
-CAUTION-IF RELIEVED BY A NEW ONMT MEMBER, FULLY BRIEF THE NEW MEMBER ON THE STATUS OF THE SURVEYS.
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ERPIP NO.: 4.3.3 / REV. 7 DATE: January 20,1982
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TITLE:
LIQUID EFFLUENT ACTIVTTY SAMPLING AND ANALYSIS 1.0 RESPONSIBLE INDIVILU AL 1.1 The Liquid Release Monitoring Team Members are responsible to collect liquid effluent samples from Circulating Water Systems, obtain analyses, then report results to the RPD.
1.2 The RPD is responsible to the SEC to assure that appropriate precautionary actions are taken if liquid effluent activity levels exceed specific limits.
2.0 CONDITIONS AND PREREQUISITES 2.1 As directed by the RPD or SEC.
2.2 Upon indication of an off-normal release of radioactive liquid to the Circulating Water System.
3.0 ACTIONS AND LIMITATIONS
/
Action Initiator Time
-NOTE-(
Use EXHIBIT 4.3.1-C, MONITORING TEAM ACTION FORM, to document results, as necessary.
3.1 The Liquid Release Monitoring Team shall:
3.1.1 Obtain the equipment necessary to take two Circ Water samples from the Rad-Chem Lab or mobile backup lab (trailer).
3.1.2 Proceed to the grating above the Circ Water disenarge duct, remove the grating, and collect a 500 cc dip sample of Circ Water.
3.1.3 Record the date, time, and specific location where the sample was obtained.
Date:
Sample Time:
Sample Point:
Discharge Data Recorded:
- - /- - - - - -
Initials
-Fime-I 3.1.4 Proceed to the Cire Water Room and collect a 500cc sample from a Circ Water intake vent e
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s ERPIP NO.: 4.3.3 / P EV. 3 DATE: October 2,1981 3.1.5 Record the date, time, and specific location where the sample was j
obtained.
Date:
Sample Time:
Sampie Point:
Intake Data Recorded:
/
Initials Time 3.1.6 Proceed to the Rad Che n Lab and have equal portions of each sampie analyzed in accordance with RCP 1-1007 for Tritium and RCP 1-1001 for Gross Beta.
Analyses Requested:
/
Initials Time 3.1.7 Record the results of each analysis and report this information to the R FD.
Intake Activity Discharge Activity Tritium uCi/cc Tritium uCi/cc Gross Beta uCi/cc Gross Beta uCi/cc Results Recorded and. Reported m ~
D to RFD:
/
Initials Time
- t
-NO TE-If aalyses and calculations indicate a gross discharge activity > 5 x 10-5 uC1/cc an Alert Condition should be declared and extensive monitoring in the Bay initiated. Analyses for specific isotopes must be made, dose calculations per Regulatory Guide 1.109, and comparisons made to EAL and PAG dose rate and dose criteria.
3.1.3 Repeat steps 3.1.1 through 3.1.7 at a frequency determined by the R PD.
l l
4.3.3-2
ERPIP NO.: 4.3.4 / REV. 7 DATE: January 20,1981 i
TITLE:
PERSONNEL CONTAMINATION MONITORING 1.0 RESPONSIBLE INDIVIDUAL Emergency Radiation Team members are responsible to the RPD to perform personnel monitoring during emergencies for the purpose of minimizing personnel exposure and preventing unnecessary spread of contamination. Members of the Emergency Security Tean: may assist if requested by the RPD and directed by the ESTL.
2.0 CONDITIONS AND PREREQUISITES When directed by the RPD.
.u.
3.0 ACTIONS AND LIMITATIONS
-NOTE-Use EXHIBIT 4.3.1-C, MONITORING TEAM ACTION FORM, to document results, as necessary 3.1 General -
Normal self-monitoring of personnel will be performed at access control points.
3.1.1 Radiation monitoring personnel shall supervise and assist with personnel monitoring as required.
-NOTE-If contamination is detected on inplant personnel, dress the affected person (s)in appropriate protective clothing and have them proceed to the nearest (safe) decontamination station.
3.1.2 If radiation levels cause the background count on the personnel monitoring instruments to increase greater than 0.2 mrem /h:
3.1.2.1 Move the self-monitoring equipment and control point to a lower radiation level area.
Controi Point Moved:
/
Initials Time 3.1.2.2 Report location of new control peint to the SEC. :
3.
4.3.4-1 l-
_ 1
_,l ERPIP NO.: 4.3.4 / REV. 2 DATE: September 1,1981 L
New Location Reported:
/
r]- l Initiais Time 3.1.2.3 Continue to assist monitoring of personnel.
3.1.3 Onsite contaminated personnel shall be treated per ERPIP 4.5.5.
3.1.4 Onsite iniured. contaminated personnel shall be treated per ERPIP 3.5 immediately and ERPIPS 4.6.2, 4.6.3 and 4.6.4, as necessary.
3.2 Controlled Area Moniuring and Assembly Area Monitoring 3.2.1 If personnel monitoring was NOT performed at a control point, (because of radiation levels or other safety hazard), Assembly Area Monitoring Team members will monitor personnel using portable equipment at the assembly areas when requested by Assembly Area Leaders or personnel not monitored.
Monitoring Continued in Assembly Area:
/
Initiais Time r
3.2.2 If, during evacuation, Assembly Areas are utilized for accountability and/or cover, Assembly Area Monitoring. Team. members.(and.the.ECC.
Monitoring Team, if required) will monitor Assembly Areas.
Assembly Areas Monitored:
/
Initials Time 3.3 Gate House Monitoring ALL personnel exiting the protected area will be directed by the Gate and Access Monitoring Team through the portal monitors, if the monitors are operable.
-NOTE-If contamination is detected on inplant personnel, dress the aff ected person (s) in appropriate protective clothing and have them proceed to the nearest (safe) decontamination station.
3.4 Perimeter Control Point Monitoring 3.4.1 Personnel will be subject to monitoring at the perimeter control point by the Gate and Access Monitoring Team if prior personnel monitoring was not performed due to emergency evacuation conditions.
b 4.3.4-2 3
.-e
ERPIP NO.: 4.4.7.2 / REV. 7 DATE: January 20,1982 TITLE:
POST ACCIDENT CONTAINMENT ATMOSPHERE SAMPLING AND ANALYSIS NOTE -
The procedure originally issued with this manual was not workable. During the interim pericd while a new procedure is being written for approval, the post accident containment atmosphere sampling and analysis will be k
performed using RCP l-504 (Post Accident Sampling of Containment Atmosphere). The interim procedure is available in the emergency trailors and the CCNPP Chemistry Lab.
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ERPIP NO.: 4.6.1/ REV. 2 DATE: Septembcr 1,1981
('
TITLE:
EMERGENCY PERSONNEL RADIATION EXPOSURES 1.0 R ESPONSIBLE INDIVIDU AL The Site Emergency Coordinator and /or Team Leaders are responsible to inform personnel entering a known or potential radiation area of possible health eff ects.
2.0 CONDITIONS AND PREREQUISITES Prior to personnel entering a known or potentially high radiation area (greater than 10R/h).
NOTE-This procedure is required for initial and periodic refresher training courses for Emergency Team members.
2.1 GUIDELINES FOR CONTROL OF PERSONNEL RADIATION EXPOSURE 2.1.1 DURING EMERGENCY PHASE Although an emergency situation transcends the normaLrequirements for limiting exposures to ionizing radiation, guideline levels are established for exposures that may be acceptable in emergencies. The maximum k
whole body dose received by any worker should not exceed established regulatory limits. Every reasonable effort will be used to ensure that an emergency is handled in such a manner that no worker exceeds these limits, including, where recommended by ERPIP 4.5.4.1, the administering of radioprotective drugs. The acceptability of higher exposures is restricted to emergency situations where some clear and definite advantage can be gained by such worker exposure. Attempts to rescue victims in a radiological accident should be regarded in the same context as any other emergency action involving the rescue of victims, regardless of the type of hazard involved. It is compatible with the risk i
concept to accept exposures leading to doses considerably in excess of those appropriate for normal occupational use when recovery from an accident or major operational difficulty is necessary. Saving of life, i
measures to circumvent substantial exposures to population groups, or preservation of valuable installations may all be sufficient cause for j
accepting above normal exposures. These higher dose limits cannot be specified; however, they should be commensurate with the significance
- 4. 6.1-1 o%
~-
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e
ERPIP 'NO.: 4.6.1/ REV. 7 DATE: January 20,1982
'3 of the objective and held to the lowest practicable level. As discussed below, all planned exposures should follow the guidelines set forth in National Council on Radiation Protection Report No. 39 (paragraphs 257-259) and International Commission on Radiation Protection Publication No. 26 (paragraphs 113,114 and 171), which deal with planned occupational exposure under emergency conditions.
Decision-making is based on conditions at the time of an emergency and should always consider the probable effects of an exposure prior to allowing any individual to be expoself to radiation levels exceeding the established occupational limits. The probable high radiation exposure effects are:
Up to 25 rad in 1 day - no physiological changes are likely to be observed.
25 to 100 rad - no impairment likely but some physiological changes, including possible temporary blood changes, may occur. Medical observations would be required after exposure.
100 to 400 rad - some physical impairment possible such as nausea and
)
vomiting. Some lethal exposure possible.
In applying these guidelines, the objective should be to maintain exposures as low as reasonably achievable and to avoid exposure that is unnecessary. Every effort should be used to maintain exposures within the lowest level possible commensurate with the emergency actions required.
2.1.1.1 The following subsections describe the criteria to be considered for lifesaving and facility protection actions.
l 2.1.1.1.1 Lifesaving Actions
- l When there is reasonable expectation that an individual is alive within the affected area, the course of action to be pursued is determined by the Site Emergency Coordinator.
1.
The amount of the planned exposure shall be determined by the SEC. He should evaluate the situation and establish the exposure limit for the rescue mission accordingly. Judgment should be based upon:
.j i
4.6.1-2
_.