NLS2003041, Emergency Plan Implementing Procedure, Cooper Nuclear Station, NRC Docket 50-298, DPR-46

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Emergency Plan Implementing Procedure, Cooper Nuclear Station, NRC Docket 50-298, DPR-46
ML030830357
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/18/2003
From: Hutton J
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2003041
Download: ML030830357 (34)
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Text

N Nebraska Public Power District Always there when you need us NLS2003041 March 18, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Emergency Plan Implementing Procedure Cooper Nuclear Station, NRC Docket 50-298, DPR-46 Pursuant to the requirements of 10 CFR 50, Appendix E, Section V, "Implementing Procedures,"

Nebraska Public Power District is transmitting the following Emergency Plan Implementing Procedure (EPIP):

EPIP 5.7.17 Revision 30 "Dose Assessment" Should you have any questions concerning this matter, please contact me at 402-825-5233.

Sincerely, Plant Manager

/nr Enclosure cc: Regional Administrator w/enclosure (2) NPG Distribution w/o enclosure USNRC - Region IV Senior Resident Inspector w/enclosure Records w/o enclosure USNRC COOPER NUCLEAR STATION P,045 P 0 Box 98 / Brownvulle, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www nppd corn

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2003041 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None 4-4-

4-I-

1-t i

+

4-I PROCEDURE0.42 1 REVISION 12 1 PAGE 14 OF 16

USE: REFERENCE CNS OPERATIONS MANUAL EFEC E: 3/

EPIP PROCEDURE 5.7.17 APPROVA: S/IQA APPROVAL: SORC/IQA DOSE ASSESSMENT OWNER:

DPRMN:E J. A. BEDNAR DEPARTMENT: EP

1. PU RPO SE ............................................................ 1
2. PRECAUTIONS AND LIMITATIONS ..................................... 2
3. REQUIREM ENTS ...................................................... 2
4. COMPUTER DOSE PROJECTION (CNS-DOSE) ............................ 3
5. HAND-CALCULATED DOSE PROJECTION (CENTERLINE) ................. 5
6. HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE) ............ 8
7. CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS©

..................................................................... 12

8. CORE DAMAGE ESTIMATE USING IN-CONTAINMENT HI-RANGE RADIATION M ONITORS .......................................................... 14 ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON CENTERLINE) ..................................... 15 ATTACHMENT 2 TRANSIT TIMES AND EFFECTIVE AGES OF NOBLE GASES AT RECEPTOR SITES ........................ 17 ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLINE) q ATTACHMENT 4 CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS .....................................

18 20 ATTACHMENT 5 METEOROLOGICAL AND RADIOLOGICAL DATA SOURCES FOR CNS-DOSE .................................... 21 ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE .................... 22 ATTACHMENT 7 CORE DAMAGE ESTIMATION ....................... 29 ATTACHMENT 8 INFORMATION SHEET ............................. 30

1. PURPOSE

[ ] 1.1 This procedure provides instructions for performing a dose projection using the CNS-DOSE Computer Program.

[] 1.2 This procedure provides a manual backup method for performing dose assessment.

[ ] 1.3 This procedure provides instructions for making a rapid gross estimation of core damage based on in-containment high range radiation monitor readings for primary containment LOCA events.

PROCEDURE 5.7.17 REVISION 30 PAGE 1 OF 32

[ ] 1.4 This procedure provides instructions for obtaining meteorological data from alternate sources if the primary sources are not available. The general order of preference will be PMIS, National Weather Service, and then the use of historically determined default values.

2. PRECAUTIONS AND LIMITATIONS

[ ] 2.1 Actual dose rates will vary as a function of:

[ ] 2.1.1 The total curies released.

[ ] 2.1.2 Release rate.

[ ] 2.1.3 The duration of the release.

[] 2.1.4 The isotopic mixture of the release.

[ ] 2.1.5 Meteorological conditions.

[ ] 2.2 Update and refine dose calculations upon significant changes in one or more of the above parameters.

[ ] 2.3 Should a release occur which necessitates rapid decision making concerning the recommendation of protective actions, the guidance contained in Procedure 5.7.20 should be followed.

[ ] 2.4 Attachment 7 should be used to estimate core damage only in cases where the high range in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accident sequences, a Reactor Coolant System (RCS) sample and Core Damage Assessment Program (CORDAM) must be used. The Post-Accident Sampling System (PASS) may be used, as required, to obtain the RCS sample.

[1 2.5 If the needed KAMAN monitor(s) is (are) inoperable, Release Rate Determinations shall be performed using Procedure 5.7.16.

3. REQUIREMENTS

[ ] 3.1 Ensure following equipment and materials are available, as needed:

[ ] 3.1.1 COMPUTERIZED DOSE PROJECTION (CNS-DOSE)

[ ] 3.1.1.1 Computer terminals.

[ ] 3.1.1.2 Computer printers.

I PROCEDURE 5.7.17 1 REVSION 30 1 PAGE 2 OF 32

I[I 3.1.2 MANUALLY CALCULATED DOSE PROJECTION

[ ] 3.1.2.1 Environs map.

[1 3.1.2.2 x/Q isopleths (off-centerline only).

] 3.1.2.3 Scientific calculator.

[ ] 3.2 A release of airborne radioactive material has or may occur.

[ ] NOTE 1 - When Meteorological or Radiological data needed to perform dose assessment is unavailable or "unhealthy", refer to Attachment 5 for alternate sources of data. Health "quality codes" are defined in Attachment 6.

[ ] NOTE 2 - If the user is not familiar with the use of PMIS, Attachment 6 provides an overview and instructions on access and selected use of PMIS.

4. COMPUTER DOSE PROJECTION (CNS-DOSE)

[ ] 4.1 To start the dose projection program on a PMIS terminal, enter the turn-on code "DOSE" on a terminal logged into either the Primary or Backup System.

[ ] 4.2 The dose projection program can also be run on a non-PMIS terminal.

However, this is reserved for personnel having access to an account on the computer and familiar with its use. To start the dose projection program on a non-PMIS terminal, on either PMIS computer, login to an account that has privileges to run PMIS software and run program

[NPPD.EXECUTE]NPDOSEZ.

[ ] 4.3 Each time the program is started or the "New Sample" option is selected, new data will be loaded into the program. Verify that Field 1 correctly indicates the origin of the release and the data displayed is "healthy" and correct.

Health "quality codes" are defined in Attachment 6:-Alternate sources of meteorological and radiological data needed to run CNS-DOSE or perform a hand-calculation are found in Attachment 5.

[ ] 4.4 Determine if SGT is in the effluent stream and if it is functional. Consult with Radiological, Operations, and Engineering personnel for this determination, if available.

[ ] 4.5 Estimate the duration of release (consult with Operations and/or Engineering for this time estimate) in hours. If the estimated duration of release cannot be determined, use the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default value.

I PROCEDURE 5.7.17 REVISION 30 PAGE 3 OF 32 J

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[ ] 4.6 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

[1 4.6.1 15,000 mrem/hr on SJAE monitor.

[] 4.6.2 Reactor Coolant Sample > 300 [iCi/gm Dose Equivalent 1-131.

[] 4.6.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[] 4.6.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[] 4.6.5 Main Steam Line Radiation Monitor Readings > 1200 mrem/hr.

[] 4.6.6 Reactor water level below 0" FZ (Fuel Zone).

I [] 4.7 DETERMINE IF RELEASE PATHWAY IS THROUGH REACTOR BUILDING

[1 4.7.1 If release bypasses Reactor Building (i.e., direct venting of drywell or a release from the Turbine Building), then enter N.

[] 4.7.2 If release is through Reactor Building, then enter Y.

[ ] 4.8 Make corrections or changes, as necessary.

- [ 4.9 Use the ENTER key to accept data and move to the next field.

[1 4.10 Press the RESULTS option to display the dose projections.

[ ]4.11 Select either the PRINT or HARD COPY option to make a hard copy of the results.

[ ] 4.12 Select the "New Sample" or "Edit" option to return to the previous display and obtain new data or make additional changes.

[1 4.13 Exit the program by entering "Q" or pressing the "CANC" key on PMIS terminals.

[] 4.14 Select the "Help" option for additional program operational information.

I PROCEDURE 5.7.17 1 REVSION 30 1 PAGE 4 OF 32 J

5. HAND-CALCULATED DOSE PROJECTION (CENTERLINE)

[ ] NOTE - This method reflects the methodology used in the CNS-DOSE Program. It gives only downwind dose values for plume centerline at distances of 1, 2, 5, and 10 miles from the site. For calculating doses at specific receptor locations, the method in Section 6 is used.

[ ] 5.1 Obtain release rate from effluent KAMAN monitor digital readout in VCilsec and record value in Block 1 on Attachment 3. If KAMAN is inoperable, complete the appropriate attachment of Procedure 5.7.16 and record the noble gas release rate value (liCi/sec) in Block 1 on Attachment 3.

[ ] NOTE - The answer to the question concerning the status of the Standby Gas Treatment System has a significant impact on the resultant dose projection calculation. The answer to this question is coordinated with Radiological, Operations, and Engineering personnel, if available.©

[ ] 5.2 Determine if SGT is in the effluent stream.

[ ] 5.2.1 If SGT is in the effluent stream, enter 0.01 in Block 2 of Attachment 3.

[ ] 5.2.2 If SGT is not in the effluent stream, enter 1 in Block 2 of Attachment 3.

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[ ] 5.3 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

[] 5.3.1 15,000 mrem/hr on SJAE monitor.

[] 5.3.2 Reactor Coolant Sample > 300 [iCi/gm Dose Equivalent 1-131.

[] 5.3.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[] 5.3.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[1 5.3.5 Main Steam Line Radiation Monitor Readings > 1200 mrem/hr.

[1 5.3.6 Reactor water level below 0" FZ (Fuel Zone).

PROCEDURE 5.7.17 1 REVISION 30 PAGE 5 OF 32

[ ] 5.3.7 If core is degraded, obtain the Iodine to Noble Gas ratio from Table 1 of Attachment 3 and enter that value in Block 3 of Attachment 3.

[ ] 5.3.8 If core is not degraded, enter 1.86E-7 in Block 3 of Attachment 3.

[ ] 5.4 Obtain the Noble Gas energy factor (MeV/dis) based on time since reactor shutdown in hours from Table 2 on Attachment 3 and enter this value in Block 4 on Attachment 3.

[ ] 5.5 Obtain the wind speed in miles per hour (mph) from PMIS and record the value in Block 5 of Attachment 3. If wind speed is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind speed at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory Federal TAB.

[ ] 5.5.1 If the release is from the ERP, use wind speed at the 100 meter level.

If 100 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 13 mph.

[] 5.5.2 If the release is from any other source, use the wind speed at the 10 meter level. Either MET tower 10 meter level is acceptable. If 10 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 8 mph.

[ ] 5.6 Determine the atmospheric stability class ("A" through "G") from PMIS and

- - record in Block 6 on Attachment 3. If the stability class cannot be obtained from PMIS and the National Weather Service cannot be contacted, use "D" as the default stability class.

[] 5.6.1 If using temperatures from the NWS to develop delta-T-based stability class, request the temperatures (10 meter (M) and 100 M) in degrees Centigrade. Determine degrees Centigrade (C) delta-T and the appropriate stability class using the following formula and table:

100 M 'C - 10 M 0C = delta-T 'C delta-T 0C < -1.7 -1.7 to -1.5 -1.5 to -1.3 -1.3 to -0.45 -0.45 to 1.3 1.3 to 3.6 > 3.6 Stability Class A B C D E F G I PROCEDURE 5.7.17 REVISION 30 1 PAGE 6 OF32 3

I [] 5.7 DETERMINE IF RELEASE PATHWAY IS THROUGH REACTOR BUILDING I [] 5.7.1 If release bypasses Reactor Building (for example, direct venting of drywell or a release from the Turbine Building), then enter 1 in Block 7 on Attachment 3.

[] 5.7.2 If release is through the Reactor Building, then enter 0.5 in Block 7 on Attachment 3.

[ ] 5.8 Obtain TEDE Noble Gas Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 8 on Attachment 3.

[ ] 5.9 Obtain TEDE Iodine Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 9 on Attachment 3.

[ ] 5.10 Obtain CDE Iodine Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 10 on Attachment 3.

[ ] 5.11 Compute TEDE "sub-calculation" value and record in Block 11 of Attachment 3.

[(Block 1)(Block 4)(Block 8)1 + [(Block 1)(Block 2)(Block 3)(Block 7)(Block 9)1 (Block 5)

[1 5.12 Using the appropriate release point (ERP or other) and stability class (Block 6), obtain the mixing factors (x/Qs) for distances 1, 2, 5, and 10 miles from Table 4 on Attachment 3 and record in Block 12 of Attachment 3.

[] 5.13 Compute the TEDE dose rate for each distance and record values in Block 13 Attachment 3.

(Block 11) x (Block 12)

[1 5.14 Estimate the duration of the release (consult with Operations and/or Engineering for this time estimate) in hours and record value in Block 14 on Attachment 3. If the estimated duration of release cannot be determined, use 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as a default value.

[ ] 5.15 Compute integrated TEDE doses for each distance and record values in Blocks 15 on Attachment 3.

(Block 13) x (Block 14)

I PROCEDURE 5.7.17 REVISION 30 1 PAGE 7 OF32

[ ] 5.16 Compute CDE "sub-calculation" value and record in Block 16 of Attachment 3.

(Block 1)(Block 2)(Block 3)(Block 7)(Block 10)

(Block 5)

[ ] 5.17 Compute the CDE dose rate for each distance and record values in Block 17 on Attachment 3.

(Block 16) x (Block 12)

[ ] 5.18 Compute the CDE dose for each distance and record values in Block 18 on Attachment 3.

(Block 17) x (Block 14)

[ ] 5.19 Refer to Procedure 5.7.1 to determine if an emergency should be declared due to radiological effluent (dose rate or integrated dose to a member of the public) calculated at or beyond 1 mile.

[ ] 5.20 Refer to Procedure 5.7.20 to determine if any protective action recommendations should be made to off-site authorities.

[ ] 5.21 Recalculate dose projections whenever conditions change significantly.

[1 5.22 Record name, time, and date at the bottom of Attachment 3.

6. HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

[ ]6.1 Obtain release rate from effluent KAMAN monitor digital readout in [ICilsec and record value in Block 1 on Attachment 1. If KAMAN is inoperable, complete appropriate attachment of Procedure 5.7.16 and record the noble gas release rate value ([iCilsec) in Block 1 on Attachment 1.

[ ] NOTE - The answer to the question concerning the status of the Standby Gas Treatment System has a significant impact on the resultant dose projection calculation. The answer to this question is coordinated with Radiological, Operations, and Engineering personnel, if available.

[ ] 6.2 Determine if SGT is in the effluent path.

[ ] 6.2.1 If SGT is in effluent path, enter 0.01 in Block 2 on Attachment 1.

[ ] 6.2.2 If SGT is not in effluent path, enter 1 in Block 2 on Attachment 1.

I PROCEDURE 5.7.17 REVISION 30 1 PAGE 8 OF 32 J

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[ ] 6.3 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

[] 6.3.1 15,000 mrem/hr on SJAE monitor.

[] 6.3.2 Reactor Coolant Sample > 300 [tCi/gm Dose Equivalent 1-131.

[] 6.3.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[] 6.3.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[] 6.3.5 Main Steam Line Radiation Monitor Readings Ž 1200 mrem/hr.

[] 6.3.6 Reactor water level below 0" FZ (Fuel Zone).

[] 6.3.7 If core is degraded, obtain the Iodine to Noble Gas ratio from Table 1 of Attachment 1 and enter that value in Block 3 on Attachment 1.

[] 6.3.8 If core is not degraded, enter 1.86E-07 in Block 3 on Attachment 1.

[ ] 6.4 Determine the energy factor (MeV/dis) based on time since reactor shutdown in hours and Table 2 on Attachment 1, and enter value in Block 4 on Attachment 1.

[ ] 6.5 Obtain the wind speed in miles per hour (mph) from PMIS and record the value in Block 5 on Attachment 1. If wind speed is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind speed at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory Federal TAB.

[ ] 6.5.1 If the release is from the ERP, use wind speed at the 100 meter level.

If 100 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 13 mph.

I PROCEDURE 5.7.17 1 REVISION 30 1 PAGE 9 OF 32 ]

[] 6.5.2 If the release is from any other source, use the wind speed at the 10 meter level. Either MET tower 10 meter level is acceptable. If 10 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use "K> the historical default wind speed value of 8 mph.

[ ] 6.6 Determine the wind direction (from) in degrees from PMIS and record in Block 6 on Attachment 1. If wind direction is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind direction at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory - Federal TAB.

[ ] 6.7 Determine the atmospheric stability class ("A" through "G") from PMIS and record in Block 7 on Attachment 1. If the stability class cannot be obtained from the PMIS and the NWS cannot be contacted, use "D" as the default stability class.

[] 6.7.1 If using temperatures from the NWS to develop delta-T-based stability class, request the temperatures (10 meter (M) and 100 M) in degrees Centigrade. Determine degrees Centigrade (C) delta-T and the appropriate stability class using the following formula and table:

100 M °C - 10 M°C = delta-T°C delta-T °C <-1.7 -1.7 to -1.5 -1.5 to -1.3 -1.3 to -0.45 -0.45 to 1.3 1.3 to 3.6 > 3.6 Stability Class A B C D E F G I [] 6.8 DETERMINE IF RELEASE PATHWAY IS THROUGH REACTOR BUILDING

[ ] 6.8.1 If the release bypasses Reactor Building (for example direct venting of the drywell or a release from the Turbine Building), then enter 1 in Block 8 on Attachment i. -

[ ] 6.8.2 If the release is through Reactor Building, then enter 0.5 in Block 8 on Attachment 1.

[ ] 6.9 Obtain TEDE Noble Gas Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 9 on Attachment 1.

[ ] 6.10 Obtain TEDE Iodine Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 10 on Attachment 1.

[ ] 6.11 Obtain CDE Iodine Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 11 on Attachment 1.

I PROCEDURE 5.7.17 1 REVISION 30 1 PAGE 10 OF 32 j

[] 6.12 Obtain the mixing factor (X/Q) for the receptor point or location.

[ ] 6.12.1 Record location or receptor point ID at the top of Attachment 1.

[ ] 6.12.2 Obtain the proper x/Q isopleth overlay based on stability class and release point.

[ ] 6.12.2.1 Overlays are available in the TSC or EOF for both elevated and ground level releases for each stability class.

Use ground level isopleths for all releases which are not from the ERP.

[ ] 6.12.3 Place the isopleth overlay on an Emergency Planning Zone map scaled to 1" per mile. The preferred map is the "Cooper Nuclear Station 20 Mile Plume Exposure" map with sectors, radii, and wind direction labeled. One is posted in the TSC and EOF.

[ ] 6.12.4 Orient the isopleth overlay so the centerline of the isopleth is over the wind direction radius, the open end of the isopleth is downwind, and the asterisk is over CNS.

[ ] 6.12.5 Lightly mark the desired receptor location on the isopleth with a pencil.

[ ] NOTE - All x/Qs have negative exponents.

[ ] 6.12.6 Using the legend in the lower right hand corner of the isopleth overlay, linearly interpolating as necessary, determine a x]Q value for the receptor site.

[ ] 6.12.7 Record the x]Q value in Block 12 on Attachment 1.

1 6.13 Compute TEDE dose rate (REM/hr) and record in Block 13 on Attachment 1.

[(Block 1)(Block 4)(Block 9)1+[(Block 1)(Block 2)(Block 3)(Block 8)(Block 10)1 x (Block 12)

(Block 5)

] 6.14 Estimate the duration of the release (consult with Operations and/or Engineering for this time estimate) in hours and record the value in Block 14 on Attachment 1. If the estimated duration of release cannot be determined, use 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as a default value.

[ ] 6.15 Compute the integrated TEDE dose (REM) and record in Block 15 on Attachment 1.

(Block 13) x (Block 14)

I PROCEDURE 5.7.17 REVISION 30 1 PAGE 11 OF 32 j

[ ] 6.16 Compute CDE dose rate (REM/hr) and record in Block 16 on Attachment 1.

(Block 1)(Block 2)(Block 3)(Block 8)(Block 11) x (Block 12) 5)

(Block

[ ] 6.17 Compute CDE dose (REM) and record in Block 17 on Attachment 1.

(Block 14) x (Block 16)

[ ] 6.18 Record name, time, and date at the bottom of Attachment 1.

7. CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS©

[ ] NOTE 1 - This section describes the methodology to be used to correlate CNS-DOSE results (estimated gross iodine concentrations) with gross iodine concentrations sampled in the field.

[ ] NOTE 2 - This section is to be used by dose assessment personnel in the EOF once field teams have been dispatched and sample results become available.

[ ] NOTE 3 - Initial dose projections (computer and hand-calculated) are based upon assumed radionuclide concentrations until actual concentrations have been measured. Off-site sample results are used to determine a dose correction factor which may be applied to adjust the CNS-DOSE Program.

[] 7.1 FIELD TEAM SAMPLE TO CNS-DOSE COMPARISON

[] 7.1.1 Radiological Assessment Supervisor shall:

[ ] NOTE 1 - Prior to comparing field team air sample results, ensure that the time of the field team air sample and the time of "CNS-DOSE" dose assessment are comparable.

[ ] NOTE 2 - If the field team air sample is reported from a distance other than 1, 2, 5, or 10 miles, use the appropriate stability class/release point isopleth to determine what CNS-DOSE predicted iodine air sample results would be at that distance prior to performing the field team sample comparison.

[ ] 7.1.1.1 Compare the field team iodine air sample concentrations with the predicted CNS-Dose iodine air sample concentrations using the decision tree in Step 7.1.2.

[ ] 7.1.1.2 Radiological Control Manager shall review the field team corrected dose assessment results and communicate any change in PARs or Classification to the Emergency Director.

PROCEDURE 5.7.17 1 REVISION 30 -PAGE12 OF 32

[] 7.1.2

] 7.2 APPLYING FIELD TEAM CORRECTION TO CNS-DOSE

[ ] 7.2.1 Apply the correction to CNS-Dose using the "Field Adjust" OPTION of CNS-DOSE.

[I 7.2.1.1 At the MAIN CNS-DOSE screen, select option "Field Adjust".

I PROCEDURE 5.7.17 REVISION 30 R 1 PAGE 13 OF 32 ]

[] 7.2.1.2 Enter the radius distance from CNS in miles at the prompt (1, 2, 5, and 10 are the only options).

[] 7.2.1.3 Enter the gross iodine concentration (in [iCi/cc) obtained from the field at the prompt.

[] 7.2.1.4 After obtaining new Results from CNS-DOSE, compare new PARs to any PARs previously transmitted to off-site authorities.

8. CORE DAMAGE ESTIMATE USING IN-CONTAINMENT HI-RANGE RADIATION MONITORS

[ ] NOTE 1 - Attachment 7 is only used for core damage estimates where the in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accident sequences, a Reactor Coolant System (RCS) sample and Core Damage Assessment Program (CORDAM) must be used. The Post-Accident Sampling System (PASS) may be used, as required, to obtain the RCS sample.

[ ] NOTE 2 - The release from the core may bypass the containment, be retained in the primary system, or not be uniformly mixed. Therefore, a low containment radiation reading does not guarantee a lack of core damage. The levels of damage indicated by the value in Attachment 7 are considered minimum levels unless there are inconsistent monitor readings.

[] NOTE 3 - Inconsistent monitor readings may be due to the uneven mixing in containment (e.g., steam rising to the top of the dome). It may take hours for uniform mixing.

[ ] 8.1 The Chem/RP Coordinator or designee shall perform following steps to determine an estimate of core damage, if decisions must be made which are based on core conditions and PASS results are not available.

[] 8.1.1 Obtain highest in-containment hi-range radiation monitor reading from RMA-RM-40A(B), DRYWELL RAD MONITOR, and record in Block 1 on Attachment 7.

[ ] 8.1.2 Complete the calculations on Attachment 7.

[] 8.1.3 Report results to the TSC Director.

PROCEDURE 5.7.17 REVISION 30 PAGE 14 OF 32

C ( (

ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

Location or Receptor ID:

(1) Noble Gas Release (2) Release Path (3) Iodine/Noble Gas (4) Energy Factor (5) Wind Speed (mph) (6) Wind (7) Stability (8) Release through Rate from KAMAN or through SBGT? Ratio Direction Class Reactor Building?

5.7.16 (jiCi/Sec) No = 1; Yes = 0.5 Yes = 0 01; No = 1 (from Table 1) (from Table 2) ERP = 13; Other = 8 (° from) Default = D For Columns 5, 6, and 7, use PMIS, NWS, or Defaults.

Mixing Factor Conversion Factors (from Table 3) (from Isopleths)

TEDE Noble Gas (9) (12)

TEDE Iodine (10)

CDE Iodine (11)

TEDE Dose Rate (13): (REM/hr) Duration (Hours) TEDE Dose (REM)

Default = 4 hrs (Block 13) x (Block 14) f(Block 1)(Block 4)(Block 9)1+f(Block 1)(Block 2)(Block 3)(Block 8)(Block 10)1 x (Block 12) (14) (15)

(Block 5)

CDE Dose Rate (16): (REM/hr) ODE Dose (REM)

(Block 14) x (Block 16)

[(Block 1)(Block 2)(Block 3)(Block 8)(Block 11)1 x (Block 12) (17)

(Block 5)

Name/Time/Date:

PROCEDURE 5.7.17 REVISION 30 PAGE 15 OF 32

ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

TABLE 1 - IODINE TO NOBLE GAS RATIO VS. TABLE 2 - ENERGY FACTORS TIME SINCE SHUTDOWN TIME SINCE IODINE/NOBLE GAS RATIO TIME SINCE ENERGY SHUTDOWN NON-DEGRADED DEGRADED SHUTDOWN FACTOR (hrs) CORE CORE (hrs) (MeV/dis) t<1 1.86 E-7 2.71 E-1 t<1 0.75 1< t <2 1.86 E-7 3.57 E-1 1:< t < 2 0.60 2<t <4 1.86 E-7 3.41 E-1 2 <t<4 0.40 4 < t < 10 1.86 E-7 2.81 E-1 4 < t < 10 0.25 10*g t < 30 1.86 E-7 2.30 E-1 10 < t < 30 0.15 30 < t < 100 1.86 E-7 1.65 E-1 30:5 t < 100 0.09 100 < t 1.86 E-7 1.40 E-1 100 < t 0.07 TABLE 3 - DOSE CONVERSION FACTORS

-__ _ NON-DEGRADED CORE DEGRADED CORE TEDE Noble Gas 1.48 E-3 9.19 E-4 TEDE Iodine 8.77 E-2 2.98 E-2 CDE Iodine 2.04 E 0 4.96 E-1 I PROCEDURE 5.7.17 REVISION 30 1 PAGE 16 OF 32 j

ATTACHMENT 2 TRANSIT TIMES AND EFFECTIVE AGES OF NOBLE GASES AT RECEPTOR SITES I

1. Effective Age is defined as time elapsed (hrs) since shutdown. For off-site locations, the effective age of the isotopic mixture may be obtained through summarizing following components:

[] 1.1 The effective age at the time of release onset.

[ ] 1.2 The transit time from the release point to the receptor site (refer to Section 2 below).

2. CALCULATION OF TRANSIT TIME FROM THE RELEASE POINT TO THE RECEPTOR LOCATION

[] 2.1 Estimate the downwind distance (miles) to the receptor location.

[] 2.2 Divide the distance in miles by the 100m meter level wind speed (mph) to determine the plume transit time. __

(1) RECEPTOR SITE (2) 100 METER LEVEL (3) PLUME TRANSIT DOWNWIND DISTANCE WIND SPEED TIME (hrs)

(miles) (mph) (1) -÷-(2)

4. 4.

I.

4.

3. DETERMINATION OF EFFECTIVE AGES AT RECEPTOR SITES (3) EFFECTIVE AGE OF (1) EFFECTIVE AGE OF (2) TRANSIT TIME FROM ISOTOPIC MIXTURE AT MIXTURE AT TIME RELEASE POINT TO RECEPTOR LOCATION OF RELEASE ONSET RECEPTOR LOCATION (hrs)

(hrs) (hrs) (1) + (2)

Name/Time/Date: I  !

I PROCEDURE 5.7.17 REVISION 30 PAGE 17 OF 32 I

( C ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLINE)

(1) Noble Gas Release Rate (2) Release Path (3) Iodine/Noble Gas (4) Energy Factor (5) Wind Speed (mph) (6) Stability (7) Release through from KAMAN or through SBGT? Ratio (MeV/dis) Class Reactor Building?

5.7.16 (VCi/Sec) No = 1; Yes 0.5 Yes = 0.01; No 1 (from Table 1) (from Table 2) Defaults ERP = 13; Other = 8 Default = D For Columns 5 and b, use PMIS, NWS, or Defaults.

Conversion Factors (from Table 3) TEDE Sub-Calculation (11):

TEDE Noble Gas (8)

[(Block 1)(Block 4)(Block 8)1+[(Block 1)(Block 2)(Block 3)(Block 7)(Block 9)A (Block 5)

CDE Iodine (10)

TEDE RATE (REM/hr) Duration (hours) TEDE Dose (REM)

Mixing Factors (from Table 4) (Block 11 x tlock 12) Default = 4 hrs (Block 13 x Block 14) 1 Mile (12) 1 Mile (131 (14) 1 Mile (15) 2 Mile (12) 2 Mile (13) 2 Mile (15) 5 Mile (12) 5 Mile (13) 5 Mile (15) 10 Mile (12) 10 Mile' (13) 10 Mile (15)

CDE Rate (REM/hr) CDE Dose (REM)

CDE Sub-Calculation (16): (Block 16 x Block 12) (Block 14 x Block 17) 1 Mile (17) 1 Mile (18)

[(Block 1)(Block 2)(Block 3)(Block 7)(Block 10)A 2 Mile (17) 2 Mile (18)

(Block 5) 5 Mile (17) 5 Mile (18) 10 Mile (17) 10 Mile (18)

Name/Time/Date: I PROCEDURE 5.7.17 REVISION 30 PAGE 18 OF 32

ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLI TABLE 1 - IODINE TO NOBLE GAS RATIO VS. TABLE 2 - ENERGY TIME SINCE SHUTDOWN FACTORS IODINE/NOBLE GAS RATIO TIME SINCE ENERGY TIME SINCE NON-DEGRADED DEGRADED SHUTDOWN FACTOR 3HUTDOWN (hrs) CORE CORE (hrs) (MeV/dis) t<1 1.86 E-7 2.71 E-1 t<1 0.75 1*!t<2 1.86 E-7 3.57 E-1 1:5t<2 0.60 2:<t<4 1.86 E-7 3.41 E-1 2*- t<4 0.40 4*< t< 10 1.86 E-7 2.81 E-1 4 < t < 10 0.25 10*< t < 30 1.86 E-7 2.30 E-1 10*< t < 30 0.15 30 < t < 100 1.86 E-7 1.65 E-1 30 _<t < 100 0.09 100 < t 1.86 E-7 1.40 E-1 100

  • t 0.07 TABLE 3 - DOSE CONVERSION FACTORS NON-DEGRADED CORE DEGRADED CORE TEDE Noble Gas 1.48 E-3 9.19 E-4 TEDE Iodine 8.77 E-2 2.98 E-2 CDE Iodine 2.04 E 0 4.96 E-1 TABLE 4 - PLUME CENTERLINR-XIQ'S (MIXING FACTORS)

RELEASE STABILITY

-POINT CLASS A-1 - B 7-

-C-- -i*

1 MILE 2.87E-6 6.04E-6 1.17E-5 8.35E-6 1.03E-6 2.35E-11 1.31E-23 ERP 2 MILE 7.94E-7 1.78E-6 4.55E-6 8.21E-6 4.98E-6 8.12E-8 5.62E-13 (ELEVATED) 5 MILE 1.50E-7 3.42E-7 1.18E-6 3.77E-6 4.66E-6 1.09E-6 5.67E-9 10 MILE 4.51E-8 1.03E-7 4.58E-7 1.82E-6 3.13E-6 1.44E-6 4.OOE-8 OTHER 1 MILE 3.01E-6 6.90E-6 1.73E-5 5.10E-5 1.09E-4 3.07E-4 7.67E-4 THAN ERP 2 MILE 8.03E-7 1.84E-6 5.15E-6 1.78E-5 3.86E-5 1.09E-4 2.71E-4 (GROUND 5 MILE 1.50E-7 3.44E-7 1.21E-6 4.98E-6 1.25E-5 3.52E-5 8.81E-5 LEVEL) 10 MILE 4.51E-8 1.03E-7 4.63E-7 2.07E-6 6.43E-6 1.81E-5 4.52E-5 PROCEDURE 5.7.17 1 REVISION 30 1 PAGE 19 OF 32 j

I ATTACHMENT 4 CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS

1. CORRECTION FACTOR DETERMINATIONS USING OFF-SITE SAMPLING DATA (3) FIELD GROSS (4) CNS-DOSE (5)

(2) IODINE IODINE CORRECTION (1) SAMPLE SAMPLE CONCENTRATION CONCENTRATION FACTOR (CF)

LOCATION TIME ([iCi/cc) (1iCi/cc) (3) (4) 9 4- 9 9 4. 9 9 1. I I t I Name/Time/Date: I I

3. Route completed form to Emergency Preparedness Department.

I PROCEDURE 5.7.17 1 REVISION 30 1 PAGE 20 OF 32 ]

ATTACHMENT 5 METEOROLOGICAL AND RADIOLOGICAL DATA SOURCES FOR CNS-DOSE NOTE 1 - When the normal source of meteorological data (PMIS MET screen) is not available or is "unhealthy", attempt to obtain the data by PMIS point ID. If PMIS is not available, call the National Weather Service (NWS) in Valley, NE to obtain the data. The telephone number is contained in the Emergency Telephone Directory - Federal TAB. If the NWS cannot be contacted, use default values.

NOTE 2 - If the user is not familiar with the use of PMIS, Attachment 6 provides an overview and instructions on access and selected use of PMIS.

NOTE 3 - The Turn-On-Code "VALUE" is used to display single point values and qualities.

NOTE 4 - The Turn-On-Code "MET" is used to display most meteorological point values and stability classes.

PMIS POINT ID DESCRIPTION MET001 100M LVL SIGMA THETA (15 MIN AVE)

MET004 100M LVL TEMPERATURE MET005 DELTA TEMPERATURE (10OM-10M)

MET006 100M LVL WIND DIR. (15 MIN AVE)

MET007 100M LVL WIND SPEED (15 MIN AVE)

MET009 60M LVL SIGMA THETA (15 MIN AVE)

MET012 60M LVL TEMPERATURE MET013 DELTA TEMPERATURE (100M-60M)

MET014 60M LVL WIND DIR. (15 MIN AVE)

MET015 60M LVL WIND SPEED (15 MIN AVE)

MET017 10M LVL SIGMA THETA (15 MIN AVE)

MET020 10M LVL TEMPERATURE MET021 DELTA TEMPERATURE (60M-10M)

MET023 10M LVL WIND DIR. (15 MIN AVE)

MET024 10M LVL WIND SPEED (15 MIN AVE)

MET027 -.. PRECIPITATION (15 MIN PERIOD)

MET028 10M TWR SIGMA THETA (15 MIN AVE)

MET029 10M TWR TEMPERATURE MET030 10M TWR WIND DIR. (15 MIN AVE)

MET031 10M TWR WIND SPEED (15 MIN AVE)

N8000 RX BLDG EFFLUENT FLOW AVE N8001 TURB BLDG EFF HI RAD MON AVE N8002 TURB BLDG EFF NORM RAD MON AVE N8003 TURB BLDG FLOW AVE N8004 AOG & RW EFF HI RAD MON AVE N8005 AOG & RW EFF NORM RAD MON AVE N8006 RX BLDG EFF RAD MON AVE N8007 AOG & RW BLDG EFF FLOW AVE N8010 ERP HI RAD MON AVE N8011 ERP NORMAL RAD MON AVE N8012 ERP FLOW AVE N8013 SGT FLOW TO ERP AVE I PROCEDURE 5.7.17 1 REVISION 30 1 PAGE 21 OF 32 j

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE 1.PLANT MANAGEMENT INFORMATION SYSTEM (PMIS) 1.1 The PMIS System (PMIS) is a set of programs and hardware provided by NPPD that make use of VMS functions and additional peripherals (Data Concentrators) which provides access to plant parameters.

2. PMIS COMPUTERS 2.1 PMIS computers share a common set of peripherals (disk drives, tape drives, terminals, etc.) and software.
3. VMS OPERATING SYSTEM 3.1 The VMS Operating System (VMS) is the host operating system for the PMIS computers. It is a set of programs that interface with the computer hardware and peripherals, and allows the computers to recognize and process commands.
4. PMIS MODES 4.1 PMIS has three operational modes, Primary, Primary/Backup, and Backup, and will operate on either computer in one of the three modes. A computer with PMIS operating in either the Primary or Primary/Backup Mode is

___ referred to as the Primary System and the one with PMIS operating in the Backup Mode is referred to as the Backup System.

4.2 The Primary and Primary/Backup Modes provide full PMIS capabilities,

- consisting (in part) of data acquisition and conversion, data display, data archiving, alarm processing, self monitoring, and many other functions that perform specialized calculations and displays.

4.3 The Backup Mode monitors the Primary System, transfers information necessary to keep the Backup System files and tables up-to-date, and automatically changes to the Primary Mode when a loss of the Primary System is detected (referred to as a FAILOVER). Although many functions are available on the Backup System, their use is discouraged because the lack of real-time data results in the display of inaccurate information (CNS-DOSE is an exception).

5. PMIS ACCESS 5.1 Access to PMIS is gained through various video display terminals, printer/plotters, and printers, including color graphic Information Display Terminals (IDTs) dedicated exclusively for PMIS access in the Control Room, TSC, and EOF.

PROCEDURE 5.7.17 REVISION 30 PAGE 22 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE 5.2 The IDTs and printers are selectively connected to either computer through a switching device controlled by PMIS. At system start or during a FAILOVER, all terminals and printers are switched to the Primary System. However, the SWITCH position may be changed at any time after that.

6. SCREEN FORMAT 6.1 When a terminal is under control of PMIS (instead of VMS), the screen display will be in a standard format consisting of four areas, OCA, GGDA, SSA, and FKA.

6.2 The OCA (Operator Communication Area) consists of the top two (one and two lines on the screen. This area is generally used to prompt-for and receive user inputs and display advisory and warning messages. In addition, some displays that require only one or two lines of screen use the OCA for display. Also (though technically not part of the OCA), the current date and time (updated once a second) is displayed at the right side of the screen on lines 1 and 2.

6.3 The GGDA (General and Graphic Display Area) consists of lines 4 through 47 and is used for most displays. In addition, some displays (chiefly functions requiring significant editing) also prompt-for and receive user inputs in the GGDA.

6.4 The SSA (SPDS Status Area) consists of lines 45 through 48 and contain four boxes that represent (by color code) the status of the SPDS (Safety Parameter Display System), which is a software system that monitors selected plant

"-Farame-ters and determines overall plant shfetW-t-6tus.

6.5 The FKA (Function Key Area) consists of the bottom two (50 and 51) lines of the screen. The FKA is used to indicate which of the definable function keys are enabled. It also indicates which mode PMIS is in, the Plant Mode, and whether or not a PMIS "event" has occurred.

7. SCREEN-COPY FUNCTION 7.1 The screen-copy function, which is activated by pressing the HARD COPY key, provides full screen reproduction in color on a printer located in the same general area as the terminal.
8. PRINTER 8.1 The printers are connected to a specific computer and are generally accessed when a "...PRINT..." option is selected and a "logical name" is entered.

PROCEDURE 5.7.17 REVISION 30 PAGE 23 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

9. LOGICAL NAME 9.1 Printers and terminals are usually referenced by "logical names", in the format of TTOO, TT01, etc. (IDTs), and LAOO, LA01, etc. (printers). The "logical name" for a device can usually be found on a tag on the device.
10. RESET FUNCTION 10.1 This function, which is activated by pressing the RESET key (PC keyboard) or CONTROL-RESET keys (IDT keyboard), clears the screen, sounds the bell, and resets internal parameters to the default settings, producing the same effect as a re-boot or turning power off and on.
11. IDE FIELD 11.1 User input to PMIS Programs is through an open IDE (Interactive Data Entry) field on the terminal. An open IDE field is denoted by a yellow box that appears in the OCA or GGDA area. Anything typed on the keyboard will be echoed in the box. Erasing or back-spacing is accomplished with the DEL key.

All entries into an IDE field must be terminated by pressing the ENTER key unless the field is overfilled or a function key is pressed (the terminal automatically adds a carriage return character in those cases).

12. TURN-ON-CODE 12.1 The Turn-On-Code (TOC) is the mechanism by which commands are issued to PMIS. Thi§ is a one to eight character code which is iritetpreted by PMIS and a corresponding command is issued.
13. PMIS DATABASE .....

13.1 All plant parameters (or additional data based on plant or PMIS parameters) that are processed by PMIS SYSTEM are defined in the PMIS DATABASE, which is a file that specifies the origin of the data, the frequency at which it is processed, the type of processing to be performed, etc. Each parameter is referred to as a "point" and is identified by a one to eight character name or POINT-ID (PID).

14. PMIS DATA PROCESSING 14.1 Some PMIS points are processed by scanning plant sensors (through the Data Concentrator) while others are calculated based on the values of previously processed points or PMIS parameters. All points values are then assigned a quality code stored in the Current Value Table (CVT).

PROCEDURE 5.7.17 REVISION 30 PAGE 24 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE 14.2 Data in the CVT is considered to be "real-time" and representative of current plant and system conditions.

14.3 At regular intervals (and other special circumstances) point values are also stored in an Archive File, which provides - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of on-line historical information.

15. PMIS DATA ACCESS 15.1 All point values in the CVT and Archive File are accessed by the POINT-ID.
16. QUALITY CODES 16.1 The Quality Code, assigned when point values are assigned, represents the general status and "health" of the point, and determines how it is used by PMIS Programs. The following is a list of PMIS quality codes and related information.

CODE DESCRIPTION COLOR HEALTH UNK Value unknown - not yet processed White Bad DEL Processing has been disabled Magenta Bad INVL Data concentrator error Magenta Bad RDER Data concentrator error Magenta Bad OIC Data concentrator error Magenta Bad BAD Outside instrument range Magenta Bad STAG Point failed stagnation check Magenta Bad UDEF Undefined (spare) Magenta Bad REDU Fails redundant point check Magenta Bad HALM Above high-alarm limit Red Good LALM Below low alarm limit Red Good HWRN Above high warning limit Yellow Good LWRN Below low warning limit Yellow Good ALM State/Change-of-State alarm Red Good SUB Value has been substituted Blue Good DALM Alarm checking has been disabled Green Good NCAL Value cannot be calculated White Good INHB Alarm inhibited by cut-out point Green Good GOOD Passes all other checks Green Good 16.2 Not listed above is quality code OSUB (Operator Substituted), which is treated the same as SUB, and indicates that the value was substituted within that program. OSUB is not used in the CVT.

PROCEDURE 5.7.17 REVISION 30 PAGE 25 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

17. PMIS LOGIN 17.1 If the current date and time is displayed in the OCA and is being updated about once a second:

17.1.1 If"ENTER PASSWORD..." is displayed on line 2, press the ENTER key.

17.1.2 If"SELECT FUNC. KEY OR TURN ON CODE..." and an open IDE field is displayed on line 2, the IDT is logged into PMIS. No further action is necessary.

17.1.3 If a display is operating, press the CANC key.

17.1.4 If terminal does not respond or does not meet any of the above criteria, press the XOFF key once. The terminal should be automatically reset (screen clears and the bell sounds) after about 30 seconds, and either the "ENTER PASSWORD..." or

"...TURN-ON-CODE..." prompt should be displayed. Refer to the applicable previous step for more instruction.

17.2 If the current date and time is NOT displayed or is displayed but is not being updated:

17.2.1 Press the RESET key (PC keyboard) or CONTROL-RESET keys (IDT keyboard), wait at least 10 seconds, and press the ENTER key. If the date and timne appear and began updating, refer to the previous (date and time updating) step.

17.2.2 If a "$" is-displaiyed at the left of the screen, enter "LO" and press the ENTER key. After the "...LOGGED OFF..." message is displayed, press the ENTER key again.

17.2.3 After "Username:" is displayed, enter "PMIS" and press the ENTER key. A welcome message followed by "PMIS LOGGED OUT..." will be displayed. Do not press any keys for 5 minutes or until the PMIS login display appears. When the "ENTER PASSWORD..." prompt is issued, refer to the previous (date and time updating) step and login to PMIS.

17.3 If neither of the above criteria is met or the specified sequence of events does not occur, contact the Nuclear Information Services (NIS) Department for assistance.

I PROCEDURE 5.7.17 I REVISION 30 IIPG2O3 PAGE 26 OF 321 IL PRCDR .. 7I RVSO 0

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

18. ACTIVATING A TURN-ON-CODE 18.1 If a display is currently operating in the area of the screen that the desired TOC requires, press the CANC key.

18.2 When "SELECT FUNC. KEY OR TURN ON CODE..." is displayed followed by an open IDE field, enter one of following:

18.2.1 A TOC (i.e., "GROUP" -- activates the Group Display Program; the program will then prompt the user to select a menu option).

18.2.2 A TOC followed by a space and optional text (i.e., "PLOT ARMI" -

activates the Real-Time Plot Program and plots the group "ARMI" without further user input; note that optional text is recognized by only selected TOCs).

18.2.3 Press one of the programmable function keys on the right hand key pad or top row of function keys (i.e., blue "GROUP DISP" key -

functions the same as the first example).

18.3 Refer to the FKA for the function keys that are enabled and their descriptions.

Use other options as provided by each program.

18.4 To exit a program, use the specified exit option (if provided) or press the CANC function key.

19. DETERMINING TO WHICH SYSTEMKATERMINAL IS CONNECTED The PMIS System to which a terminal is connected is indicated by the "CONSOLE =..." on the bottom line of the FKA as follows:

CONSOLE = PRIMARY -- Connected to the Primary System operating in the Primary Mode.

CONSOLE = PRIM/BAC -- Connected to the Primary System operating in the Primary/Backup Mode.

CONSOLE = BACKUP -- Connected to the Backup System.

CONSOLE = UNKNOWN -- PMIS is in a transition or unknown state.

I PROCEDURE 5.7.17 REVISION 30 PAGE 27 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

20. SWITCHING A DEVICE TO THE OTHER SYSTEM 20.1 On a terminal located in the same area as the device to be switched and connected to either PMIS System, activate the TOC "SWITCH".

20.2 A list of all devices that can be switched from that terminal will be displayed.

Included will be their logical names, description, and the CPU to which the device is connected.

20.3 To switch a device, press function key F1 and then enter the logical name at the prompt.

20.4 If the device is an IDT, it will be logged off PMIS.

20.5 If the device being switched is a terminal other than the one running SWITCH, both are connected to the same system and a TOC is currently active, a message will be displayed to that effect, and the user will be asked if it is to be switched anyway. If the answer is not YES, the device is not switched.

I PROCEDURE 5.7.17 REVISION 30 PAGE 28 OF 32

ATTACHMENT 7 CORE DAMAGE ESTIMATION NOTE - This attachment is only used for core damage estimates where the in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accidents sequences, utilize the Post-Accident Sampling System (PASS) and Core Damage Assessment Program (CORDAM).

(1) HIGHEST DRYWELL (3) CORE (5) PERCENT RAD MONITOR (2) 100% MELT (4) PERCENT CLAD READING CORE MELT FRACTION CORE MELT FAILURE (RMA-RM-40A,B) FACTOR (1) - (2) (3) x 100 (4) x 10 2.44E+6 Report the results of the core damage estimate (Blocks 4 and 5) to the TSC Director.

Name/Time/Date: / /

I PROCEDURE 5.7.17 REVISION 30 1 PAGE 29 OF 32 j

ATTACHMENT 8 INFORMATION SHEET

1. DISCUSSION 1.1 This procedure covers dose projection. Dose projection represents calculation of an accumulated dose at some time in the future if current conditions continue.

1.2 The CNS-DOSE Computer Program is a software application operated on the PMIS computers. It makes use of current meteorological and radiological data from PMIS and manually entered data to perform dose projection for the area surrounding CNS. CNS-DOSE is the primary method of dose projection.

1.2.1 The PMIS Computer System consists of two computers operating in a Primary and Backup Mode. Historical data may be obtained from either system; however, current data may be obtained only from the Primary System.

1.2.2 Personal unfamiliar with the operation of PMIS should reference procedures governing the operation of PMIS or refer to Attachment 6.

1.3 The manual dose projection methods in this procedure are intended to be used when CNS-DOSE is unavailable. Where possible, data used is from the same source as that used by the computer programs. The hand calculations are divided into two sections. Section 5 is intended to be used by the on-shift personnel for centerline dose projections. Section 6 is intended for dose assessment personnel in projecting non-centerline values.

1.4 The correlation methodology as described in Section 8 provides EOF dose assessment personnel with a means of correlating field team iodine concentration data with CNS-DOSE projected iodine concentration. Such a correlation is necessary to determine if initial Protective Action Recommendations (PARs) were adequate to protect the health and safety of the public.

1.5 Containment radiation level provides a measure of core damage, because it is an indication of the inventory of airborne fission products (i.e., noble gases, a fraction of the halogens, and a much smaller fraction of the particulates) released from the fuel to the containment (refer to NEDO-22215, Pages 1 and 2; NEDC 02-009).

I PROCEDURE 5.7.17 REVISION 30 PAGE 30 OF 32

ATTACHMENT 8 INFORMATION SHEET

2. REFERENCES 2.1 CODES AND STANDARDS 2.1.1 NRC Regulatory Guide 1.109, Revision 1, October 1977, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Iodine Inhalation Dose Factors.

2.1.2 NRC Regulatory Guide 1.111, July 1977, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.

2.1.3 NRC Regulatory Guide 1.145, August 1979, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants.

2.1.4 Health Physics Journal, November 1981, Noble Gas Dose Rate Conversion Factors.

2.1.5 ICRP 59, Working Breathing Rate.

2.1.6 EPA 400-R-92-001, May 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

2.2 DRAWINGS (MAPS) 2.2.1 NPPD Drawing CNS-MI-102, Atmospheric Dispersion Model (EPM2)

Special Receptor Points, 10 Mile Radius.

2.2.2 NPPD Drawing CNS-MI-03, Preselected Radiological Sampling and Monitoring Points in the Vicinity of Cooper Nuclear Station, 10 Mile Radius.

2.2.3 NPPD Drawing 2.2 (P3-A-45), Revision 1, Cooper Nuclear Station Site and Property Boundary, 1 Mile Radius.

2.2.4 Cooper Nuclear Station 50 Mile Emergency Planning Zone, Revision 2, 50 Mile Radius.

PROCEDURE 5.7.17 REVISION 30 PAGE 31 OF 32

ATTACHMENT 8 INFORMATION SHEET 2.3 VENDOR MANUALS 2.3.1 CNS Number 0984, PMIS Operator's Manual - SAIC Document 502-85500107-72.

2.4 PROCEDURES 2.4.1 Emergency Plan Implementing Procedure 5.7.1, Emergency Classification.

2.4.2 Emergency Plan Implementing Procedure 5.7.16, Release Rate Determination.

2.4.3 Emergency Plan Implementing Procedure 5.7.20, Protective Action Recommendations.

2.5 MISCELLANEOUS 2.5.8 Engineering Evaluation EE 02-056, Elimination of Meteorological Instrumentation System Strip Chart Recorder References.

2.5.1 General Electric Corporation, NEDO-22215, Procedures for the Determination of the Extent of Core Damage Under Accident Conditions.

2.5.2 NEDC 02-004, Estimation of the Steam Jet Air Ejector Radiation Monitor, RMP-RM-150A(B), Readings Following a 1% Fuel Clad release (Degraded Core) in the Reactor Coolant System.

2.5.3 NEDC 02-009, Estimation of Primary Containment High Range Monitor, RMA-RM-40A(B), Readings Following 1% Clad Failure in the RCS under Non-LOCA Conditions.

2.5.4 NEDO-31400, Safety Evaluation for Eliminating the BWR MSIV Closure Function and Scram Function for the MSL Rad Monitors.

2.5.5 NRC Inspection Report 89-35.

2.5.6 © NRC Inspection Report 91-12, Emergency Preparedness Annual Inspection Report. Affects Section 7 and NOTE prior to Step 5.2.

2.5.7 NRC Inspection Report 92-14, Emergency Preparedness Annual Inspection Report.

PROCEDURE 5.7.17 REVISION 30 PAGE 32 OF 32

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