B18805, Revised Emergency Plan Procedures

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Revised Emergency Plan Procedures
ML023450269
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 11/27/2002
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, NRC/FSME
References
B18805
Download: ML023450269 (67)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.

Dominion Millstone Po1,,ci Siution Ropc.c,-,

Road NOV 2 7 2002 Watcrfordf, CT 06.385 Docket Nos. 50-245 50-336 50-423 B18805 RE: 10 CFR 50, Appendix E 10 CFR 50.47(b)(5)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Power Station, Unit Nos. 1, 2 and 3 Revised Emergqency Plan Procedures The purpose of this Jetter is to inforrp the Nuclear Regulatory Commission that the following Emergency Plan Procedures.have, been implemented:

"* MP-26-EPI-FAP11, "Core Damage Assessment," Major Revision 1, Minor Revision 2, transmitted via Attachment 1;

"* MP-26-EPI-FAP11-001, "Core Damage Estimate:

Core Exit Temperatures," Major Revision 0, Minor Revision 1, transmitted via ;

"* MP-26-EPI-FAP11-002, "Core Damage Estimate:

Core Uncovery Times," Major Revision 0,

Minor Revision 1, transmitted via ;

"* MP-26-EPI-FAP1 1-004, "Core Damage Estimate:

Main Steam Line Radiation Monitors," Major Revision 0, Minor Revision 1, transmitted via Attachment 4;

"* MP-26-EPI-FAP1 1-005, "Core Damage Estimate:

Containment Hydrogen," Major Revision 0, Minor Revision 1, transmitted via ;

"* MP-26-EPI-FAP11-006, "Core Damage Estimate: Ratio Comparison/

Abnormal Isotopes," Major Revision 0, Minor Revision 1, transmitted via Attachment 6;

"* MP-26-EPI-FAP1 1-007, "Core Damage Estimate: Isotopic Concentrations,"

Major Revision 0, Minor Revision 1, transmitted via Attachment 7;

"* MP-26-EPI-FAP11-009, "Unit 2 Reactor Coolant and Liquid Waste Sample Worksheet," Major Revision 0, Minor Revision 2, transmitted via Attachment 8; and

"* MP-26-EPI-FAP11-011, "Unit 3 Reactor Coolant and Liquid Waste Sample Worksheet," Major Revision 0, Minor Revision 2, transmitted via Attachment 9.

U.S. Nuclear Regulatory Commission B18805/Page 2 There are no regulatory commitments contained within this letter.

If you should have any questions concerning this submittal, please contact Mr. David W. Dodson at (860) 447-1791, ext. 2346.

Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

J. Ala idc*e' Site e President - Millstone Attachments (9) cc:

H. J. Miller, Region I Administrator (2 copies)

R. J. Conte, Chief, Operational Safety Branch, Region I cc:

w/o attachment J. B. Hickman, NRC Project Manager, Millstone Unit No. 1 J. R. Wray, NRC Inspector, Region I, Millstone Unit No. 1 R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 V. Nerses, NRC Senior Project Manager, Millstone Unit No. 3 Millstone Senior Resident Inspector

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1, "Core Damage Assessment" Major Revision 1, Minor Revision 2

08/20102 S08/20/02 Approval Date Procedure Action Request 09/03/02 Effective Date SPG 021024-134150 Document No.:

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El El El MP-26-EPI-FAP1 1-001, rOOO-01 MP-26-EPI-FAP11-002, rOO-01 MP-26-EPI-FAP1 1-004, rO0O-01 MP-26-EPI-FAP1 1-005, rO0O-01 MP-26-EPI-FAP1 1-006, r000-01 MP-26-EPI-FAP1 1-007, rOOO-01 MP-26-EPI-FAP1 1-009, rOOO-02 MP-26-EPI-FAP11-011, rOOO-02 MP-05-DC-FAPO1.1-005 Rev. 000 Paze 2 of I

Functional Administrative Procedure AMll Millstone Station Core Damage Assessment MP-26-EPI-FAP11 Rev. 001-02 Approval Date:

Effective Date:

10 1Ial 10; ID I

TABLE OF CONTENTS 1.PU R PO SE...................................................................................................................................

3

1. 1 O bjective...............................................................................................................................

3 1.2 A pplicability.........................................................................................................................

3 1.3 Supporting Documents...................................................................................................

3 1.4 D iscussion............................................................................................................................

3

2. IN STRU CTIO N S........................................................................................................................

5 2.1 Core Damage Assessment..............................................................................................

5 2.2 Plant Parameter Evaluation Method.................................................................................

6 2.3 System Activity Evaluation Method.................................................................................

8 2.4 Sample Location Determination.....................................................................................

10

3.

SUMMARY

OF CHANGES....................................................................................................

11 3.1 R evision 001-01.................................................................................................................

11 3.2 R evision 001.......................................................................................................................

11 ATTACHMENTS AND FORMS Definitions and Abbreviations......................................................................

12 Responsibilities.............................................................................................

13 Common Conditions of Core Damage.......................................................

14 Isotopes in Core Fission Products.................................................................

15 Isotopes in Core Fission Products.................................................................

16 Indicators of Core Damage..........................................................................

17 Indicators of Core Damage..........................................................................

18 Indicators of Core Damage..........................................................................

19 MP-26-EPI-FAP 11-001, "Core Damage Estimate: Core Exit Temperatures" MP-26-EPI-FAP1 1-002, "Core Damage Estimate: Core Uncovery Time" MP-26-EPI-FAP1 1-003, "Core Damage Estimate: Containment Radiation Monitors" MP-26-EPI-FAP1 1-004, "Core Damage Estimate: Main Steam Line Radiation Monitors" MP-26-EPI-FAP1 1-005, "Core Damage Estimate: Containment Hydrogen" MP-26-EPI-FAP1 1-006, "Core Damage Estimate: Ratio Comparison/Abnormal Isotopes" MP-26-EPI-FAP1 1-007, "Core Damage Estimate: Isotopic Concentrations" MP-26-EPI-FAP 11-008, "Core Damage Estimate: Summary Analysis" MP-26-EPI-FAP1 1-009, "Unit 2 Reactor Coolant and Liquid Waste Sample Worksheet" MP-26-EPI-FAPI 1-010, "Unit 2 Vent and Containment Air Sample Worksheet" MP-26-EPI-FAP1 1-011, "Unit 3 Reactor Coolant and Liquid Waste Sample Worksheet" MP-26-EPI-FAPI 1-012, "Unit 3 Vent and Containment Air Sample Worksheet" MP-26-EPI-FAP1I Rev. 001-02 2 of 19

S

1.

PURPOSE 1.1 Objective This procedure provides sampling and analysis guidance and instructions for estimating core damage under accident conditions.

1.2 Applicability This procedure is applicable when the following occurs:

An emergency has been declared and the SERO has been activated There are indications of core damage Events require the estimation of the type and amount of core damage 1.3 Supporting Documents 1.3.1 CP 2804L, "Unit 2 Rx Coolant and Liquid Waste PASS" I )

1.3.2 CP 2804M, "Unit 2 Vent and Containment Air PASS" 1.3.3 CP 3804K, "PASS RCS/RSS Sample" 1.3.4 CP 3804L, "PASS Containment Air Sample" 1.3.5 CP 3804M, "PASS Ventilation Samples" 1.4 Discussion Core Damage estimates are used to provide the following:

9 Confirm whether fuel barriers are breached Determine the potential quality (type) or quantity (%) of source term available for release in support of projected offsite doses 0

Support the determination of radiological protection actions that should be considered for long term recovery activities Satisfy inquiries from local and federal government agencies and provide evidence that the utility understands the plant conditions MP-26-EPI-FAPI I Rev. 001-02 3 of 19

An overall estimation of the extent of core damage can be made when information accumulated from all available sources and methods is evaluated. The NRC defines the overall condition of the core using a matrix of 10 categories as shown below:

NRC Criteria for Determining Condition of Core Degree of Degradation Minor Intermediate Major

(<10%)

(10%-50%)

(>50%)

No Fuel Damage 1

1 1

Cladding Failure 2

3 4

Fuel Overheat 5

6 7

Fuel Melt 8

9 10 The NRC recognizes four general classifications with three degrees of core damage within each (excepting the "No Fuel Damage" classification). It is important to recognize that different methodologies may provide indications that point to several degrees if not several classifications, simultaneously.

- End of Section 1 -

MP-26-EPI-FAPI 1 Rev. 001-02 4 of 19 V

I

2.

INSTRUCTIONS 2.1 Core Damage Assessment 2.1.1 IF current core conditions are appropriate for the plant parameter methods, Go To Section 2.2.

NOTE System activity results are not usually available in the early stages of an emergency. Assessment involving isotopic ratio comparisons and the presence of abnormal isotopes are valid as soon as a sample can be taken following an accident, but provide only an indication of the type of core damage.

Concentration evaluations will normally provide the most accurate assessment, but require a stable steady state condition to be valid. Methods include:

  • Isotopic Ratio Comparison
  • Presence of Abnormal Isotopes
  • Isotopic Concentration 2.1.2 IF current plant conditions produce a representative reactor coolant or containment sample, Go To Section 2.3.

2.1.3 IF samples are needed for operational or source term adjustment, Go To Section 2.4.

- End of Section 2.1 -

MP-26-EPI-FAPI 1 Rev. 001-02 5 of 19 NOTE

1. The magnitude and type of event, transport mechanism, and time after shutdown will be influencing factors on the method(s) used to determine the extent of core damage.
2. Plant operating parameters are usually the first type of information available for core damage evaluation. Generally, they can only provide a low confidence numerical value, but do help to determine the type of core damage resulting from the accident. Methods include:

"* Core Exit Temperatures

"* Core Uncovery Time

"* Containment Radiation

"* Main Steam Line Radiation

"* Containment Hydrogen

2.2 Plant Parameter Evaluation Method 2.2.1 IF necessary, contact the Accident Management Team in the TSC for assistance with core temperatures or uncovery times.

2.2.2 Obtain plant parameters from the following, as applicable:

Off-Site Facilities Information System (OFIS)

Technical Information Coordinator Control Room Data Coordinator 2.2.3 WHEN plant data becomes available, perform the following, as applicable:

NOTE Containment radiation, main steam line radiation, and containment hydrogen methods assume a significant reactor coolant leak (LOCA) has occurred into containment.

Evaluate all methods using the DAMAGE computer application.

Refer To and complete the following forms, as applicable:

0 EPI-FAP1 1-001, "Core Damage Estimate: Core Exit Temperatures" 0

EPI-FAP 11-002, "Core Damage Estimate: Core Uncovery Time" 0

EPI-FAP1 1-003, "Core Damage Estimate: Containment Radiation Monitors" 0

EPI-FAPI 1-004, "Core Damage Estimate: Main Steam Line Radiation Monitors" EPI-FAP1 1-005, "Core Damage Estimate: Containment Hydrogen" MP-26-EPI-FAP1I Rev. 001-02 6 of 19

NOTE The following attachments are provided as additional information for use in estimating core damage:

  • Attachment 3, "Common Conditions of Core Damage"
  • Attachment 4, "Isotopes in Core Fission Products"
  • Attachment 5, "Indicators of Core Damage" 2.2.4 Record the overall damage estimation by performing one of the following:

Print the DAMAGE application summary report.

Refer To and complete EPI-FAP 11-008, "Core Damage Estimate:

Summary Analysis."

2.2.5 IF additional information becomes available OR is revised throughout the course of the accident, provide an overall estimation of the extent of core damage to the ADEOF.

- End of Section 2.2 -

MP-26-EPI-FAP 11 Rev. 001-02 7 of 19

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2.3 System Activity Evaluation Method 2.3.1 Determine the most representative sample points (location of the activity released from the core) based on current system conditions as shown in Table 1.

Table 1 Sampling Point Determination Criteria Sampling Points Limitations Unit 2 Unit 3 Loop 1 Hot Leg Loop 1 or 3 Hot Break should not be upstream of the Leg sample point Liquid Waste Liquid Waste Not used for core damage estimates Containment Sump via:

Containment Sump System in operation and sump

"* HPSI Pumps via Containment recirculation actuation signal in effect

" LPSI Pumps Spray System prior to sampling

"* Containment Spray Pumps Containment Air Containment Air Accident must involve a release into containment Vent Air Vent Air Not used for core damage estimates WRGM Air SLCRS Air Not used for core damage estimates 2.3.2 Contact the MRCA to discuss the following:

In-plant radiological conditions Priority for obtaining samples Sampling sequence if multiple locations are available 2.3.3 Inform the ADTS of the selected sample points.

2.3.4 Request the ADTS assemble a sample team for core damage assessment purposes.

I MP-26-EPI-FAP1I Rev. 001-02 8 of 19 V

2.3.5 WHEN sample results become available, perform the following, as applicable:

Evaluate all methods using the DAMAGE computer application.

Refer To and complete the following forms, as applicable:

EPI-FAPI 1-006, "Core Damage Estimate: Ratio Comparison/Abnormal Isotopes" EPI-FAPI 1-007, "Core Damage Estimate: Isotopic Concentrations" 0

2.3.6 Record the overall damage estimation by performing one of the following:

Print the DAMAGE application summary report.

Refer To and complete EPI-FAP 11-008, "Core Damage Estimate:

Summary Analysis."

2.3.7 IF additional information becomes available OR is revised throughout the course of the accident, provide an overall estimation of the extent of core damage to the ADEOF.

- End of Section 2.3 -

MP-26-EPI-FAPI 1 Rev. 001-02 9 of 19 NOTE The following attachments are provided as additional information for use in estimating core damage:

"* Attachment 3, "Common Conditions of Core Damage"

"* Attachment 4, "Isotopes in Core Fission Products"

"* Attachment 5, " Indicators of Core Damage" r

2.4 Sample Location Determination 2.4.1 Discuss sample preparations with the MRCA.

2.4.2 Determine sampling and analysis requirements using one of the following forms, as applicable:

0 EPI-FAPI 1-009, "Unit 2 RX Coolant and Liquid Waste Sample Worksheet" EPI-FAPI 1-010, "Unit 2 Vent and Containment Air Sample Worksheet" 0

EPI-FAPI 1-011, "Unit 3 RX Coolant and Liquid Waste Sample Worksheet" 0

EPI-FAPI 1-012, "Unit 3 Vent and Containment Air Sample Worksheet" 2.4.3 Fax completed forms to the ADTS for review.

2.4.4 IF required, request additional Chemistry Technician support from the MOR.

- End of Section 2.4 -

MP-26-EPI-FAPI 1 Rev. 001-02 10 of 19 V

3.

SUMMARY

OF CHANGES 3.1 Revision 001-02 3.1.1 Biennial Review was performed (CR-02-11018) 3.1.2 Incorporated minor editorial corrections to procedure and the following forms:

MP-26-EPI-FAPI 1-001, r000-01 MP-26-EPI-FAP1 1-002, rOOO-01 MP-26-EPI-FAP1 1-004, rOOO-01 MP-26-EPI-FAP1 1-005, rOOO-01 MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, r000-01 MP-26-EPI-FAPI 1-009, rOOO-02 MP-26-EPI-FAP1 1-011, rOOO-02 3.2 Revision 001-01 3.2.1 Deleted reference to 3-hour time requirement for a PASS sample from Section 1.4.

3.2.2 Deleted Note box in Section 3 discussing 3-hour time requirement and ADTS responsibility for initiating sampling.

3.2.3 Deleted words "normal" and "PASS" from step 2.4.1.

3.2.4 Deleted PASS definition and acronym from Attachment 1.

3.2.5 Deleted responsibilities for PASS from Attachment 2.

3.3 Revision 001 3.3.1 Added Wide Range Gas Monitor Air and Supplemental Leak Collection and Release System Air to the sampling points in Table 1.

3.3.2 Added the definition of Wide Range Gas Monitor to Attachment 1.

3.3.3 Changed Primary Vent Stack to Wide Range Gas Monitor in MP-26-EPI-FAP1I1 010, "Unit 2 Vent and Containment Air Sample Worksheet."

3.3.4 Deleted reference to Primary Vent Stack in MP-26-EPI-FAP 11-012.

3.3.5 Performed Writer's Guide modifications for compliance with the administrative format contained in MM-05.

- End of Section 3 MP-26-EPI-FAPI 1 Rev. 001-02 11 of 19 Definitions and Abbreviations (Sheet I of 1)

Definitions None Abbreviations ADEOF - Assistant Director EOF ADTS - Assistant Director Technical Support Center AMRDA - Assistant Manager of Radiological Dose Assessment DSEO - Director of Station Emergency Operations ESF - Engineered Safety Features MOSC - Manager of Operational Support Center MRCA - Manager of Radiological Consequence Assessment MRDA - Manager of Radiological Dose Assessment RSS - Recirculation Spray System SERO - Station Emergency Response Organization SLCRS - Supplementary Leak Collection and Release System TSC - Technical Support Center WRGM - Wide Range Gas Monitor MP-26-EPI-FAPI 1 Rev. 001-02 12 of 19 Responsibilities (Sheet I of 1)

1. The Manager of Radiological Dose Assessment or the Assistant Manager of Radiological Dose Assessment specify sampling and analysis requirements.
2. The Assistant Manager of Radiological Dose Assessment is responsible for performing the calculations and evaluations required for determining core damage estimates.

MP-26-EPI-FAPII Rev. 001-02 13 of 19

!I Common Conditions of Core Damage (Sheet I of 1)

The types of damage sustained, as well as their severity, depend upon fission rate, power, and temperature of the reactor. During an accident, clad damage would occur first, followed by fuel overheating, and finally fuel melt as conditions become more severe.

Common conditions of core damage are shown below:

The presence of specific isotopes within the core fission product inventory are indicative of the type(s) of core damage that exist. Although each type of core damage exhibits the presence of certain isotopes, the isotopes related to each damage type build up as accident severity increases. Thus, when determining the type of core damage, the presence and amounts of some isotopes and the absence of others is usually a good indicator.

Most of the noble gases will be detected in containment air samples unless the accident does not involve a break inside the containment.

MP-26-EPI-FAPI I Rev. 001-02 14 of 19 Indicators of Core Damage Damage Type Conditions Clad Damage An increasing potential for inadequate core cooling exists Loose part indication is observed No significant overheating has been observed at this point Fuel Overheat The fuel is suspected to be at least partially uncovered for a period of time greater than a few minutes Loss of inventory in the pressurizer is observed Hot leg temperatures are increasing Voiding in the core is detected Ex-core count rate is increasing (occurs when uncovered core is no longer shielded by water)

High in-core thermocouple readings are observed Fuel clad oxidation is detected by excess hydrogen in the containment (>10%)

Fuel Melt The core has been uncovered for an appreciable period of time In-core thermocouples are off-scale In-core and ex-core instrumentation display erratic readings V

I l

Isotopes in Core Fission Products (Sheet I of 2)

Fission products are grouped with respect to their relative volatility. The categories of isotopes as shown below, are grouped in order of decreasing volatility:

Isotopes in Core Fission Products Group Fission Product Type Group Fission Product Type I

Noble Gases (Xe, Kr)

V Alkaline Earths (Sr, Br)

II Halogens (I, Br)

VI Noble Metals (Ru, Rh, Pd, Mo, Tc) 111 Alkali Metals (Cs, Rb)

VII Rare Earths and Actinides (Y, La, Ce)

IV Tellurium (Te, Se, Sb)

Vill Refractory Oxides of Zr and Nb Isotopes with longer half-lives will serve as a better basis for analysis in long-term sampling. Note that any sample taken soon after shutdown will be difficult to analyze due to the large amount of short-lived isotopes in the sample. There may be many isotopes with similar peaks which makes it difficult to distinguish one from another. Some isotopes may have peaks near the annihilation radiation level (511 KeV). Also, Compton edges could lead to difficulties in the sample analysis. Therefore, it is recommended that confirming peaks are used in the isotopic analysis. Any other quantifying techniques, such as iodine cartridge analysis, if available for analysis in long-term sampling, are recommended.

MP-26-EPI-FAP 11 Rev. 001-02 15 of 19 Ip Isotopes in Core Fission Products (Sheet 2 of 2)

The isotopes as shown below, reflect a best choice in terms of measurement and effect from in-growth of daughter products. It is important to recognize that halogens, and to some degree other particulate radioisotopes, may not be a good measure of the extent of core damage when identified as part of a gaseous sample.

lI*otone*~ Indicative of Core Damage Core Damage State Nuclide Group Half-Life (hrs)

Clad Failure Kr-85m I

4.48E+00

_ Kr-87 I

1.27E+00 Kr-88 I

2.84E+00 Xe-131 m 2.86E+02 Xe-1 33 1

1.26E+02 Xe-133m I

5.25E+01 Xe-135 1I 9.09E+00 1-131 I

1.93E+02 1-132 II 2.30E+00 1-133 II 2.08E+01 1-135 II 6.61 E+00 Rb-88 III 2.97E-01 Fuel Overheat Cs-1 34 I11 1.81 E+04 Cs-1 37 III 2.63E+05 Te-129 IV 1.16E+00 Te-132 IV 7.82E+01 Fuel Meltdown Sr-89 V

1.21 E+03 Sr-90 V

2.55E+05 Ba-140 V

3.06E+02 La-1 40 VIi 4.03E+01 La-142 VII 1.54E+00 Pr-144 VII 2.88E-01 Combination Xe-135m I

4.32E+00 (Related Parent Nuclides)

Sb-1 29 IV 8.06E+02 Te-129m IV 2.55E-01 Ba-1 42 V

1.77E-01 Ce-144 VII 6.82E+03 MP-26-EPI-FAP1 1 Rev. 001-02 16 of 19 I

Indicators of Core Damage (Sheet I of 3)

The following are indicators of core damage:

Clad Damage The presence of noble gases and iodines in reactor coolant or containment air without the presence of other fission products is a fair indication of clad damage and perhaps some degree of fuel overheat.

lodines may be detected in both reactor coolant and containment air, depending upon the accident scenario and upon the physical and chemical form of the radioactive release.

Fuel Overheat Damage No significant quantity of cesiums (i.e., greater than 30 percent of the inventory) should be found if core temperatures remain below 23000 F or if the core has not been at least partially uncovered for an appreciable amount of time. Therefore, the presence of a significant amount of cesium is indicative of a fuel overheat condition. The amount of hydrogen in the containment air and reactor coolant samples can serve as confirmation. It should also be noted that just as in the case of iodines, the cesiums from both containment air and reactor coolant samples should be taken together.

Over 50 percent of the core inventory of noble gases, iodines, and cesiums may be released from extensively damaged fuel clad (i.e., fuel overheating) even if fuel temperatures remain below the melting point.

As the fuel temperature increases and fuel melting is suspected to have occurred, the possibility of finding significant quantities of other core solids (e.g., groups IV through VIII) above the baseline increases. However, these fission products will not be found in reactor coolant samples unless the core has been covered and a recirculation mode has been established. Many of the fission products and most of the actinides which occur as refractory oxides are released only in relatively small amounts even at elevated temperatures. However, if damaged fuel pellets are rewetted, some of the more refractory radioactive material will be leached out.

Fuel Melt Damage Significant releases of tellurium, ruthenium, and more refractory materials will occur only if the temperature approaches the fuel melting point (52000 F).

However, the presence of ruthenium and tellurium does not prove melting, but their absence in long-term sampling analysis is a good indication that fuel meltdown has not occurred.

MP-26-EPI-FAPI I Rev. 001-02 17 of 19 Indicators of Core Damage (Sheet 2 of 3)

Assuming equilibrium conditions have been reached, a fixed inventory of radioisotopes exists within the fuel pellet. The relative ratios of the isotopes which have reached equilibrium can be considered a constant value. The distribution of isotopes in the fuel gap are not in the same proportion as in the fuel pellet. This is due to the differing diffusion rates of the isotopes from the fuel pellet to the fuel gap. During an accident, the ratios of isotopic activities obtained from samples can be compared to the expected ratios for a gap and melt type mix.

The following methods and indications can be used to estimate the amount or type of core damage under accident conditions:

Core Parameters: An indirect method which is immediately available and is used to indicate the potential for core damage. Indications are provided by core exit thermocouples and the time of core uncovery and are applicable for all types of accidents. This method does not provide numerical estimations, but rather can be used to determine the type of damage.

Containment Radiation: An indirect method which is used to determine the amount of core damage. Indications are provided by containment high range or main steam line radiation monitors. This method is only applicable for a loss of coolant accident and is based upon an end-of-life source term and static nuclide ratio assumptions.

Containment Hydrogen: An indirect method which is used to determine the amount of fuel melt. This method assumes all the hydrogen generated by the metal-water reaction is released into containment (LOCA).

System Activity - Isotopic Ratio Comparison: A direct method which is used to help establish the type of core damage (clad failure or fuel melt). This method is applicable under all types of accidents and is valid any time following an accident although accuracy will decrease over time.

System Activity - Presence of Abnormal Isotopes: A direct method which is used to indicate some degree of fuel melt by the presence of unusually high concentrations of any of the less volatile fission products.

System Activity - Isotopic Concentration Evaluation: A direct method which can yield numeric estimations. This method is applicable for all types of accidents and requires the sampled system(s) to be in a steady state which usually prevents its use until the plant is in a stable shutdown condition.

MP-26-EPI-FAPII Rev. 001-02 18 of 19 Indicators of Core Damage (Sheet 3 of 3)

Precise damage estimates are based upon accounting for all of the radioactivity released from the core. Methods which provide a numerical estimation of the extent of core damage should be evaluated to ensure all activity has been accounted for. If reactor coolant and containment air samples are available, then the total activity should be determined from the sum of both types of samples.

Iodine should not be used as the sole means of determining an estimate of core damage since it is difficult to determine the extent to which iodine will plate-out on containment walls, other surfaces, and piping. Spiking due to power excursions can also lead to inaccurate results in the iodine analysis.

No single method should be relied upon for a definitive damage estimation. All available data and sound engineering principles should be used to compile the best overall estimation.

MP-26-EPI-FAPI I Rev. 001-02 19 of 19 K

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1-001, "Core Damage Estimate: Core Exit Temperatures" Maior Revision 0, Minor Revision 1

  • 08/20/02 09/03/02 OE/20102 Approval Date Procedure Action Request 09/03E02 Effective Date SPG 021024-134150 Traininnr I*l None f-I Nuclear Training El Briefing U Famillanzatlonl 0 SQR Review and Approval n-SORC Review and Approval rl Department Head Review and Approval Approval Disapproval El WA WA (1) Department Head Sign/Date (1) Department Head Approval Sign In (2) SOAC Meeting Number f(2) Dea4t Head Aro al Sign (3) SORG Approval Sign Approval Date:

/01 ?21/OZ--

Effective Date:

10/301fOZ.

MP-05-DC-FAPOI.1-005 Rev. 000 Page I of Document No.:

MP-26-EPI-FAP1 1 Writer.

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whi*e.

001 02

Title:

Core Damage Assessment For New Documents Document is QA E]

DH

Title:

o Revision

[ Minor Revision

[] Cleanup Revision Eg Biennial Review o Cancel 0 Void (Do Not Use) 0 Expire 0 Superceded By:

Comments:

0 Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sig2 Date Department Biennial Review A,q Id7

'i u

Irj RCD

/ 0f29?/02-A.lPO Environmental Screen See attached form Li censing Basis e.

Ys[ro w

o OZ/z AP (50.59 Screen Req El&

1 Ye 4o Tech Independent q4

,C,,,.

Validation None El Field -Use El Simulated Periormance -

[E Table Top and

[E Comparison MP-05-DC-SAPOI-004 Use MP-0-DC-SAPO1-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member

Procedure Action Request Continuation Page Document No.:

MP-26-EPI-FAP1 I Writer:

M. Maryeski Rev. No.

Minor Rev.

I CA I

int: Mark WhiM 001 02

Title:

Core Damage Assessment V*Comments

[0 Validation Comments Reviews 111 Print I -

t -------

I Sign Date Department III 11 MP-26-EPI-FAP11-001, rOOO-01 MP-26-EPI-FAP1 1-002, rOO-O1 MP-26-EPI-FAP1 1-004, rOOO-01 MP-26-EPI-FAP1 1-005, rOOO-01 MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP11-007, rOOO-01 MP-26-EPI-FAP1 1-009, rOOO-02 MP-26-EPI-FAP11-011, rOOO-02 MP-05-DC-FAPOI.1-005 Rev. 000 Page 2of r

n-

ol L30?A Effective Date Approval Date Core Damage Estimate:

Core Exit Temperatures Affected Unit:

L) Unit 2 LI Unit 3 Assessment Steps:

1. Record the core exit thermocouple reading that is most representative of the overall core exit temperature (0 F).

[ i]

2. Evaluate the assumptions and limitations of the indication using the following guidance:

"* The core exit thermocouple do not measure core temperature directly, they measure the temperature of the water as it exits the core.

The core exit thermocouple readings are generally several hundred degrees below the actual core temperatures, especially during transient heat-up conditions.

"* The maximum temperature core exit thermocouples can reliably measure is about 2000* F.

"* There can be flow blockages in the core that would cause localized overheating that may not be represented by the core exit thermocouple.

3.

Record the estimate from the AMT that is most representative of the nominal core temperature (' F).

I

4.

Record the core state which is best described by the temperature ranges provided in the table below.

Performed By:

Name:

Date:

Time:

MP-26-EPI-FAPI1-001 Rev. 000-01 Pane I of 1 1 ZI I

54000) F 5

The uranium oxide (U02) fuel pellet itself melts....................................................................

Fuel has Melted 4800* F All volatile fission products are released from the fuel core....................................................

Fuel has Melted 42000 F Possible formation of an uncoolable core................................................................................

Fuel has Melted 3600" F Fuel pellets dissolve into melted components.........................................................................

Fuel has Melted 3000" F Rapid release of noble gases, halogens, and cesium from the fuel.....................................

Fuel is Overheated 24000 F Very rapid H20-Zr reaction. H2 is released........................................................................

Fuel Cladding Fails 1800( F Fission products are released into the fuel pin gap......................................................

Possible Clad Ruptures 1200' F Normal operating or slightly elevated temperatures.......................................................

No Damage Expected 6000F V1 I

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1-002, "Core Damage Estimate: Core Uncovery Times" Major Revision 0, Minor Revision 1

08/20/02 Approval Date Procedure Action Request 09103102 Effective Date SPG 021024-134150 Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski Rev. No.

Minor Rev.

I int: Mark Whi-f_

001 02

Title:

Core Damage Assessment For New Documents Document is QA Ii DH

Title:

El Revision I

Minor Revision

[] Cleanup Revision

[ Biennial Review

[J Cancel El Void (Do Not Use) 0 Expire 0 Superceded By:

Comments:

[I Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sigý Date Department Biennial Review

/,got

/*

..4L-

/

/

t7 El__

RCD A

//.A/O

, oA/PO Environmental Screen See attached form Licensing Basis 150.59 Screen Ree. fl Yes [9'No)

/IPO Tech Independent Aj A1.

  • /1, fie' Validation None

[]

Field - Use Simulated Perormance-E] Table Top and El Comparison MP-05-DC-SAPO1-004 Use MP-05-DC-SAP01-O04 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member Training:

ID None

[j Nuclear Training

[] Briefing

[I Familiarization 0

SOR Review and Approval Fl SORC Review and Approval nl Department Head Review and Approval Approval Disapproval LI WA WA lellZO *-

(1) Department Head Sign/Date (1) Department Head Approval Sign (2) SORC Meeting Number

'(2) De>a nt Head A rodal Sign 1 (3) SORC Approval Sign I

Approval Date:

/o0/_9 z0..

Effective Date:

O/:30/o.z.

MP-05-DC-FAPOI.1-005 Rev. 000 Page I Of_._

49.

444

Procedure Action Request Continuation Page Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whi+?.

01 02

Title:

Core Damage Assessment E(Comments LI Validation Comments Reviews Print Sign Date Department I]

E]

E]

MP-26-EPI-FAP1 1-001, r000-01 MP-26-EPI-FAP1 1-002, r000-01 vl' MP-26-EPI-FAPI11-004, r000-01 MP-26-EPI-FAPI11-005, r000-01 MP-26-EPI-FAP1 1-006, r000-01 MP-26-EPI-FAP1 1-007, r000-01 MP-26-EPI-FAP1 1-009, r000-02 MP-26-EPI-FAP1 1-011, r000-02 MP-05-DC-FAPOI.1-005 Rev. 000 Page 2 of

  • 1

1i01Ak;c\\-~

Approval Date 10130 Effective Date Core Uncovery Times Core Damage Estimate:

Affected Unit:

LI Unit 2 L] Unit 3 Assessment Steps:

1. Evaluate plant indications to determine whether core uncovery has occurred using the following guidance:

"* Primary indication of core uncovery is a RVLIS Full Range value < 39% (31/2 feet, or only the lower 1/3 of the core is covered).

"* An unexpected increase in the source range count rate can also be used to indicate core uncovery.

SA loss of water results in an increase in the gamma radiation at the source range detector.

SUpon core uncovery, the source range count rate will begin to increase as shielding (i.e. water) is removed from the region between the core and the source range detector outside the reactor vessel.

"* A source range count rate that is one decade above the normal count rate can also be used as a possible indication of core uncovery.

S...

2.

Record the estimate of the time that is most representative of the period that the core was uncovered (Hours).

I I

......... I..

3.

Record the core state which is best described by the time ranges provided in the table below.

1II1 0

T = 0 Core Uncovered 0 to 1/4 hr Minimal uncovery time.

No Damage Expected S.......

...t......../........... *..

...m..,u.c~ *.i.........

.......................*.D.. g............

.x.x*............

Rapid H2 generation.

'A to N hr' Release of fuel pin (gap) fission products.

Fuel Cladding Fails S....L..............................

.Local

.fuel-m elt Possible uncoolable core.

1/2 to 11/2 hrs Possible slump of molten core.

Fuel is Overheated S...........

unar...................

u f

Melt through vessel.

I to 3+ hrs Maximum rate of core melt and H2 generation.

Fuel has Melted Maximum in-vessel (melt) fission product release.

Performed By:

Name:

Date:

Time:

I TMI experienced cladding failure at 34 minutes after core uncovery.

MP-26-EPI-FAPI 1-002 Rev. 000-01 Paee I of I r

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1-004, "Core Damage Estimate: Main Steam Line Radiation Monitors" Maior Revision 0, Minor Revision 1

08/20/02 08/20/02 Approval Date Procedure Action Request I Document No.:

MP-26-EPI-FAP1 1 Writer.

M. Maryeski I

int: Mark Whi*e.

0903/02 Effective Date RPG 021024-134150 SG01041341N.50inr -1v 0e0. No.

minor 02v.

01 1

02

Title:

Core Damage Assessment For New Documents Document is QA El DH

Title:

o0 Revision I

Minor Revision 0 Cleanup Revision

[ Biennial Review 0 Cancel I] Void (Do Not Use) 01 Expire El Superceded By.

Comments:

[0 Administrative Correction FLS:.

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sigr)

Date Department Biennial Review L

fr r/

El Environmental Screen See attached form

... * ~

r -

Ucensing Basis t=fn =;Q.Rrr=cn R:ch:n fl YAs R(No*

i2fl. 

AIPO Techindependent

[I Validation None

[]

Field-Use

[] Simulated Periormance -

[D Table Top and El comparison MP-05-DC-SAPO1-004 Use MP-05-DC-SAPO1-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member Training:

ED None

[] Nuclear Training E] Briefing

[I Familiarization 0

SOR Review and Approval F-SORC Review and Approval

-l Department Head Review and Approval Approval Disapproval El NA N/A

?

=

lolz..z- (1) Department Head Sign/Date (1) Department Head Approval Sign 7

g(2)

SORC Meeting Number

-'(2) Delpa nt Head ro al Sign

_ (3) SORC Approval Sign Approval Date:

/0/ Z9/O7 Effective Date:

/O/31ooz-.

MP-05-DC-FAPO1.1-005 Rev. 000 PaeI of 10/21/0-Z

Procedure Action Request Continuation Page Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski I Rev. No. I Minor Rev.

int: Mark Whi4fP.

001 02 "itle:

Core Damage Assessment I"Comments 5 Validation Comments Review.s Print Sign Date Department El MP-26-EPI-FAP11 -001, rOOO-01 MP-26-EPI-FAP1 1-004, r000-01'~

MP-26-EPI-FAP1 1-004, rOOO-01 MP-26-EPI-FAPI 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, rOOO-01 MP-26-EPI-FAP1 1-009, rOOO-02 MP-26-EPI-FAP1 1-011, rOOO-02 MP-05-DC-FAPOI.1-005 Rev. 000 IPage 2 of 3-12

I O\\9R%.0, Approval Date Core Damage Estimate:

Effec~tive bate Main Steam Line Radiation Monitors

6.

Multiply the monitor reading by the selected dose rate to concentration conversion to obtain an estimate of the containment Noble Gas concentration (pCi/cc).

Step 4 x Step 5 = I I

MP-26-EPI-FAPI 1-004 Rev. 000-01 Pane I of 2 V

LOCA ONLY Affected Unit:

U Unit 2 UL Unit 3 Assessment Steps:

1. Record number of hours between the time that the monitor reading was taken and the reactor trip (or shutdown) occurred.

[1]

2.

Record the main steam line monitor reading in R/hr (Unit 3's monitor must be removed from it's shield).

[Unit 2] 4299C (R/hr) or [Unit 3] RE-76f77 (uCi/cc) Iy j

3.

Determine and record the MSL to containment monitor conversion factor for the appropriate period after shutdown.

Hours Past S/D Unit 2 Unit 3 0

3680 105 1/2 4290 103 2

4340 113 4

4350 121 12 4620 157 48 4610 218 11 1

>72 4640 241 S...........................................................................................

4. Multiply the monitor reading by the selected conversion factor to obtain an estimate of the containment monitor reading (R/hr).

Step 2 x Step3=

3II S..................................................

5.

Determine and record the dose rate to concentration conversion (PtCi/cc per R/hr) for the appropriate period after shutdown.

Hours Past S/D Unit 2 Unit 3 0

0.023 0.010 1/2 0.028 0.019 2

0.040 0.028 4

0.055 0.038 12 0.097 0.068 48 0.200 0.140 72 0.230 0.160

Assessment Steps:

7.

Multiply the Noble Gas concentration by the appropriate volumetric conversion factor (Ci - cc/pCi) below to obtain an estimate of the total curies of Noble Gas in containment (Ci).

Step 6 x [Unit 2] 5.687E+4 =

[Unit 31 6.513E+4 =Lliiiiil 513.............................

8.

Determine and record the estimate of the total core inventory of Noble Gas in curies (Ci).

Hours Past S/D 0

'/2 2

4 12 48 72 Unit 2 9.13E+08 5.40E+08 4.40E+08 3.83E+08 2.81E+08 1.51E+08

1. 17E+08 Unit 3 1.15E+09 6.82E+08 5.566E+08 4.84E+08 3.55E+08 1.911E+08 1.48E+08
9.

Divide the total curies of Noble Gas in containment by the core Noble Gas inventory to obtain an estimate of the fraction of the core Noble Gas inventor, released.

I Step 7 + Step 8 = I S........................................................................................................................

10. Multiply the fraction of the core Noble Gas inventory released by 100 to obtain an esumate oi me 70 rnuUIc,Ja, J1lv~-5,Ly e

aS containment.

Se 0

11. Divide the % Noble Gas inventory released by the damage fraction below to obtain the %

damage estimates (round to the nearest % and record results >100% as 100%).

Clad Overheat Melt Step 10 + (3%) x 100 Step 10 + (50%) x 100 Step 10 - (100%) x 100 IZ L

IZIZI]

Performed By:

Date:

Time:

MP-26-EPI-FAP1 1-004 Rev. 000-01 Page 2 of 2 II IZI z.IZ Name:

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP 11-005, "Core Damage Estimate: Containment Hydrogen" Maior Revision 0, Minor Revision 1

09/03/02 Effective Date Procedure Action Request SPG 021024-134150 Document No.:

MP-26-EPI-FAP11 Writer:

M. Maryeski Rev. No.

Minor Rev.

Iint:

Mark Whi-te_

001 02

Title:

Core Damage Assessment For New Documents Document is QA E]

DH

Title:

0] Revision 0 Minor Revision

[1 Cleanup Revision 0 Biennial Review

[0 Cancel E] Void (Do Not Use) 0 Expire 0 Superceded By:

Comments:

[] Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sign Date Department Biennial Review

[

j/4.

4 "/[

//

El El RCD N

/0/ 2q/0oL A/,00 Environmental Screen See attached form Licensing Basis (50.59 Screen Req. rYes [9'No)

AA___

___-wJ__

Tech Independent A Al OM Validation None El Field -Use O

S Simulated Pe ormance -

E] Table Top and El Comparison MP-05-DC-SAP01-004 Use MP-05-DC-SAPOI-00 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member Training:

g None E] Nuclear Training

[] Briefing

[] Familiarization F3 SOR Review and Approval n-SORC Review and Approval

-- Department Head Review and Approval

Approval, Disapproval El NtA N/A iIola?/0 Z.

(1) Department Head Sign/Date (1) Department Head Approval Sign

(

iSgr ate gn/l*2)e e(2) SORC Meeting Number T(2) Dep A~t Head A ro al Sign 1 (3) SORC Approval Sign Approval Date:

/o Z91/02.

Effective Date:

10130(o0-.

MP-05-DC-FAPOI.1-005 Rev. 000 Page I of 08/20/02 Approval Date

I Procedure Action Request Continuation Page 9' Comments 0I Validation Comments Reviews Print Sign Date Department El El MP-26-EPI-FAP1 1-002, rOOO-01 MP-26-EPI-FAP1 1-004, rOQO-Ol MP-26-EPI-FAP1 1-005, rOOO-O1 ~

MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, rO0O-01 MP-26-EPI-FAPI 1-009, rOOO-02 MP-26-EPI-FAP1 1-011, rOOO-02 MP-05-DC-FAPO0.1-005 Rev. 000 Page 2 of

Approval Date Core Damage Estimate:

j 1) A010 -,

]iffective Date Containment Hydrogen LOCA ONLY Affected Unit:

I-Unit 2 LI Unit 3 Assessment Steps:

1. Record the highest OFIS dry containment Hydrogen concentration (%).

[Unit 2] AE8152/8154 or [Unit 3] SSP-A58ALB n.t 2 /

.1.5..

°.r.......................................:8....I

2.

Evaluate the methods assumptions and limitations using the following guidance:

"* This method is not valid and should not be used for accidents which do not involve a LOCA.

"* All hydrogen generated by the reaction is released to containment.

"* Perfect mixing conditions exist in containment with ideal gas behavior.

"* No depletion of hydrogen occurs (such as containment leakage or combustion).

3.

Record the amount of Zirc-Water reaction from the hydrogen concentration graph below.

I j

% Hydrogen Concentration in Dry Air 12 0

o_

_----0Uit 2

Unit3

  • 4 0

0 5

10 15 20 25 30 35 40

% Zr-Water Reaction

4.

Record the core state which is best described by the % Zr-Water reaction provided in the table below.

Zr-Water Reaction Damage State

......5.............

<..5%......................N o.,a n.g.e..x. te..................................

S..................... 5=.6.i

....................... Pu.e*!h-a-s..C.a..

M.

-e.nI.E

-t -J.........................................

10-20%

Fuel has Melted

> 20%

1Vessel Melt Through Possible LZZ110 Performed By:

Name:

Date:

Time:

MP-26-EPI-FAPI 1-005 Rev. 000-01 Page 1 of I V

l

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP11-006, "Core Damage Estimate:

Ratio Comparison/Abnormal Isotopes" Major Revision 0. Minor Revision 1

08/20/02 Approval Date Procedure Action Request 09/03/02 Effective Date SPG 021024-134150 Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whi**

7 001 02

Title:

Core Damage Assessment For New Documents Document is QA El DH

Title:

o Revision CD Minor Revision Q Cleanup Revision ID Biennial Review

[o Cancel D Void (Do Not Use) 0 Expire 0 Superceded By:

Comments:

0 Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print SIg2 Date Department Biennial Review f]

,eqjiL ea/

4.

7-

//

(

fr E]

'ICD 0

A

/o/~q/oZ-A.1,0

-Environmental Screen N

See attached form Licensing Basis I

10/OZ?

AJPO (50.59 Screen Req. [I Yes [9No)

_'_-___r__

Tech Independent

[

Aif.

  • G Z Validation None

[]

Field -Use El Simulated Peor-mance-El Table Top and El Comparison MP-05-DC-SAPO1-004 Use MP-05-DC-SAPO1-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member ID None

[] Nuclear Training

[I Briefing

[] Familiarization E] SOR Review and Approval n-SORC Review and Approval

-' Department Head Review and Approval Approval Disapproval El WA WA

!0mliw (1) Department Head Sign/Date (1) Department Head Approval Sign 7

(2) SORC Meeting Number

'f(.2) Dea

  • t Head rodal Sign 1 (3) SORC Approval Sign Approval Date:

/0o "9 0Z _

Effective Date:

10(30/OZ MP-05-DC-FAPOI.1-005 Rev. 000 Page I of Training:

Procedure SDocument No.:

MP-26-EPI-FAP1 1 Action Request Continuation Page Writer~ M. Maryeski

  • in MarkvB.o Wh....

SRev. No.

Minor Rev.

001 02 Core Damage Assessment iIwM r

Wh...-

MP-05-DC-FAPOI.1-005 Rev. 000 Pa~e 2of "

I

Title:

M'Comments 0l Validation Comments Reviews Print Sign Date Department El E]

MP-26-EPI-FAP1 1-001, r000-01 MP-26-EPI-FAP1 1-002, r000-01 MP-26-EPI-FAPI11-004, r000-01 S MP-26-EPI-FAP11-005, r000-01 MP-26-EPI-FAP1 1-006, r000-01 MP-26-EPI-FAP11-007, r000-011 MP-26-EPI-FAP1 1-009, r000-02 MP-26-EPI-FAP11-011, r000-02 Page 2 of

Io210QlO "

Approval Date Core Damage Estimate:

v) 1-3010 V' Effective Date Ratio Comparison/Abnormal Isotopes Affected Unit:

LI1 Unit 2 ElI Unit 3 Assessment Steps:

1. Record number of hours between the time that the sample was taken and the reactor trip (or shutdown) occurred.
2. Obtain sample information and decay correct the activity from the time of reactor shutdown to the time of sample as follows:

ASHUTDOWN = ASAMPLE X ext Where:

Asmrr.w, Decay corrected activity of the sample in pCi/ml or cc.

A.,,,

Measured sample concentration in pCi/ml or cc.

x Decay constant in hours" (see table below).

t Time interval between reactor shutdown and sample measurement in hours (from Step 1).

Isotope ASAMPLE xo t

uXt AsemowN Xe-133 5.50E-03 Kr-85m 1.55E-01 Kr-87 5.45E-01 Kr-88 2.44E-01 Xe-131m 2.42E-03 Xe-133m 1.32E-02 Xe-135 7.62E-02 1-131 3.59E-03 1-132 3.01E-01 1-133 3.33E-02 1-135 1.05E-01 MP-26-EPI-FAPI 1-006 Rev. 000-01 Paee I of 3 I

Evaluation Steps:

............................................ I.....

3. Calculate and record the ratios for the nuclides and evaluate the results as follows:

Noble Gas Ratio = Noble Gas Isotope - A(shutdown)

Xe-133 A(shutdown)

Iodine Ratio = Iodine Isotope - A(shutdown) 1-131 - A(shutdown)

"* If the ratio of the sample is greater than the ratio for fuel melt, check the fuel box.

"* If the ratio of the sample is less than the ratio for a gap release, check the gap box.

"* If the ratio is between the values evaluate the ratio as follows:

RatiOMELT RatioSAMLE RatioSAPLE Ratio SIf the above relationship is true, check the fuel box.

SIf the above relationship is not true, check the gap box.

Fuel Ratio (melt)

I I

II Sample Ratio Gap Ratio (clad)

Xe-133 1.0 1.0 1.0 Kr-85m 0.11 U

0.022 Q

Kr-87 0.22 Q

0.022 Q

Kr-88 0.29 Q

0.045 Q

Xe-131m 0.04 Q

0.004 Q

Xe-133m 0.14 U

0.096 U

Xe-135 0.19 3

0.051 U

1-131 1.0 1.0 1.0 1-132 1.5 Ul 0.17 U

1-133 2.1 U

0.71 E

1-135 1.9 U3 0.39 Q

4. Determine and record the overall damage state by identifying the column that contains the most checked boxes.

Ratio Assessment:

L Undetermined U3 Clad Failure U Fuel Melt MP-26-EPI-FAPI 1-006 Rev. 000-01 PaRe 2 of 3 Isotope 0

V I

I Evaluation Steps:

5. Check any of the isotopes listed below which were identified within the sample.

Alkaline Earths LI Sr L1 Ba Noble Metals LIoRu UeRh 1U Pd LI Mo U Tc Rare Earths UlY LI La LI Ce LI Nd LI Pr LI Eu LI Pm LI Sm L Np 1U Pu Refractories LI Zr LI Nb Unusually high concentrations of any of the less volatile fission products are indicative of some degree of fuel melt. These fission products may include soluble or insoluble isotopes of the above elements.

6. Based on the evaluation of the ratio analysis and the presence of abnormal isotopes, determine an overall damage estimation for this method.

Overall Assessment:

LI Undetermined L) Clad Failure

'- Fuel Melt Performed By:

Date:

Time:

MP-26-EPI-FAPI 1-006 Rev. 000-01 Page 3 of 3 Name:

V I

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1-007, "Core Damage Estimate: Isotopic Concentrations" Major Revision 0, Minor Revision 1

08/20/02 09/03/02 08/20/02 Approval Date Procedure Action Request Effective Date R P( 021024-134150 Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski Rev. No.

Minor Rev.

I int: Mark Whi-It 001 02

Title:

Core Damage Assessment For New Documents Document is QA E]

DH

Title:

o Revision 0 Minor Revision 0 Cleanup Revision 09 Biennial Review o Cancel 0 Void (Do Not Use) 0 Expire

[3 Superceded By:

Comments:

[] Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sigý Date Department Biennial Review

]

$/*/L-.

/

1'.i RCD

/0/29/02.

A/PO Environmental Screen See attached form Licensing Basis 00210 AIDC)

(50.59 Screen Req. [3Yesl39NO)

PA.LA4CI~

Tech independent

______A411 Validation 0

None []

Field-Use

[]

Simulated Pe ormance-

[]Table Top and []

Comparison MP-05-DC-SAP01-O04 Use MP-05-DC-SAP01-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member 0 None 0 Nuclear Training El Briefing

[] Familiarization

[D SQR Review and Approval fn SORC Review and Approval n-Department Head Review and Approval Approval Disapproval [NiA WA (1) Department Head Sign/Date (1) Department Head Approval Sign

( Rf ggnate 7

(2) SORC Meeting Number

'(2) De it HeadA AlroVal Sign

_f_2)________HeadA____1_(3)

SORC Approval Sign Approval Date:

/01 Z9/0_2..

Effective Date:

/Ofoz..

MP-05-DC-FAPOI.1-005 Rev. 000 Page I of Training:

09103(02

Procedure Action Request Continuation Page I

V MP-05-DC-FAPOI.1-005 Rev. 000 Page 2 of F

Document No.:

MP-26-EPI-FAP11 Writer.

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whik P 001 02 STitle:

Core Damage Assessment E(Comments El Validation Comments Reviews Print Sign Date Department El 0_ El 0_

El El MP-26-EPI-FAP1 1-001, r000-01 MP-26-EPI-FAP1 1-002, r000-01 MP-26-EPI-FAP1 1-004, rOOO-01

-MP-26-EPI-FAP1 1-005, rOOO-01 MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, rOOO-01 Ve*

MP-26-EPI-FAP11-009, rOOO-02 MP-26-EPI-FAP1 1-011, rOOO-02 I

I

AIproval Date Effective bate Core Damage Estimate:

Isotopic Concentrations Affected Unit:

LU Unit 2 L) Unit 3 Assessment Steps:

1. Select and record (on the applicable core fraction worksheet) the isotopes to be used for the core damage estimate from the sample analysis results.
  • . Base isotope selection on the type and severity of accident and the temperature/condition of the core.
  • Refer to EPI-FAP 11 Section 1.4 for additional selection guidance for the isotopes.
  • 'Other' isotopes can be obtained from the Fission Product Inventories at Shutdown list.

S.....................................................................................................................

2. Perform the worksheet calculations to obtain the core release fractions for the isotopes selected.

a) Decay correct the isotopic activities from time of sample back to time of shutdown.

b) Obtain and record the baseline parameters for the appropriate sample location(s).

c) If assessing an RCS sample, determine the density correction and RCS volume.

d) If assessing a containment sample, determine the Pressure/Temperature correction.

~..........-.

~

3. Transfer the core fraction results from the unit core fraction worksheet to the damage estimate worksheet.

a) Calculate the damage values.

b) If more that one isotope was used in the assessment, determine a best estimate from the results obtained.

4. Record the results for the best estimate for the three possible types of core damage (record results >100% as 100%).

Clad Overheat Melt Performed By:

Name:

Date:

Time:

MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 1 oft9

RCS Baseline Data:

(complete for RCS samples only)

1. Record number of hours between the time that the RCS sample was taken and the reactor trip (or shutdown) occurred.

I

[

2.

Record reactor coolant temperature (OF average) at the time the sample

-[

was taken.

..~....

3.

Record pressurizer pressure (psig) at the time the sample was taken.

I y]

4.

Determine and record whether Emergency Core Cooling Systems were used prior to sampling.

U Yes L3I No

5.

Determine and record RCS volume at the time of sample:

"* If ECCS (Step 2) was not used, RCS volume =

[Unit 2] 2.85E+8 (cc)

[Unit 3] 3.31E+8 (cc)

"* If ECCS (Step 2) was used, determine the total using the RCS Volume Worksheet.

1 1

1 Containment Baseline Data:

(complete for Containment samples only)

1. Record number of hours between the time that the containment sample I

I I was taken and the reactor trip (or shutdown) occurred.

2.

Record containment temperature (OF) at the time the sample was taken.

... ~.

3.

Record containment pressure (psig) at the time the sample was taken.

Attach completed worksheet to the corresponding damage estimate calculation package.

MP-26-EPI-FAPI 1-007 Rev. 000-01 Paze 2 of 9 r

RCS Volume Worksheet:

1. Determine the fraction of Refueling Water Storage Tank (RWST) used:

[% Initial (

)- % at Sample (.

)] + 100 =

2.

Multiply the % tank volume used by the tank volume below:

Step 1 x [Unit 2] 4.75E+5 (gal)

[Unit 3] 1.20E+6 (gal) i I

3. Calculate and record the RWST volume added (cc) from the equation below:

Step 2 x 3785 (cc/gal) =

4.

Determine and record the number of SI Tanks [Unit 2] or Accumulator Tanks [Unit 3] have been added:

Unit 2: if uncertain about how many SITs have been used, assume 4 provided RCS pressure < 250 psig.

Unit 3: if uncertain about how many isolation valves have been opened, assume 4 jj provided RCS pressure < 600 psig.

5.

Multiply the number of tanks used by the tank volume below:

Step 4 x [Unit 2] 3.22E+7 (cc)

[Unit 3] 2.69E+6 (cc) jj[

6. Determine the fraction of Boric Acid Storage Tank (BAST) used:

[Unit 2 only]

[ % Initial (

) - % at Sample (Q J] - 100 =

I

7.

Calculate and record the BAST volume added (cc) from the equation below:

Step 6 x 6000 (gal) x 3785 (cc/gal) =

[

8.

Calculate the total (cc) added to the RCS by the time of sample:

Step 3 + Step 5 + [Unit 2 only] Step7=

7

9.

Sum the addition volume and the normal RCS volume below and record the results:

Step 8 + [Unit 2] 2.85E+8 (cc)

[Unit 3] 3.31E+8 (cc)

Attach completed worksheet to the corresponding damage estimate calculation package.

MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 3 of 9 f

Unit 2 Core Fraction Worksheet Date:

Time:

Worksheet Completed by:

Print Name REACTOR COOLANT Activity PCVml Density RCS*

Decay Corr.

Volume CONTAINMENT AIR I

Activity Density CONT PCi/cc Decay Corr.

Volume X

X X 5.4E10 *=

Total Core Inv Core PIJ

~

PIJ Fraction x

x 5.41 0)1.94E13 Kr-87 X

X X

)-+ (

X X

X5.4E10) =

+

3.24E13 =

Kr-88 X

X X

+

X X

X 5.4E10

=

486E13 =

Xe-131m X

X X

+

X X

X S.4E10)=

+

4.75E1l

=

Xe-133 X

X X

+(

X X

X5.4E10)=

1.49E14 =

Xe-133m X

X X

+

X X

X5.4E10) =

+ 5.8E12

=

Xe-135

(

X X

X

) +

X X

X5.4E10) =

+ 2.00E13 =

1-131 x,

X-!

X

)

  • X X5.4E10). =

+ 7.29E1 3 =

1-132

(

X X

X

)+(

X X

X5.4E10) =

+

1.03E14 =

1,-13 X

X X

+

X X

X5.4E10

=

+ 1.38E14 =

C1-134

(

X X

X

)+(

X X

X5.4E10)=

+ 1.43E14 =

Cs-134 X

X X

)+

X X

X5.4E10) =

+

1.45E13 =

S129

(

X X

X

)+(

X X

X5.4E10) =

2.43E13 =

Te-132 (Xý

ý X

X

) + (

XX XS.4E,0) =

+1.03E1 4 =

Ba-140 (x

XX X

) +(

X 5.4E10) =+

1.30E1 4 =

La-142

(

X X

X XX X 5.4E10) =+1.3 4=

Ce-144 X

ý.

X)+

Xr 11 X5.4E10) =

+9.45E13

=

Other X

X X

+

X X

X5.4E10) =

+

XXX

+

x X

X XS.E10) =+=

Kr-85m

exp (,155xT hrs)**

Kr-85m

exp (.155xT hrs)

PT CORRECTION Kr-87

exp (.547xT hrs)

Rx Coolant Density Kr-87

exp (.547xT hrs)

Cont. P Cant. Temp Kr-88

exp (.244xT hrs)

Temp IF

Corr, Kr-88
exp (.244xT hrs)

PSIG 100P 200 300.-

Transfer Fcon, to the Xe-135

exp (.076xT hrs) 100 1.0 Xe-135
exp (.076xT hrs) 0 0.96 0.82 0.71 damage estimate 1-132
exp (.301xT hrs) 325 0.9 1-132
exp (.301xT hrs) 2 1.1 0.93 0.81 worksheet.

1-135

exp (.1O3xT hrs) 475 0.8 1-135
exp (.O3xT hrs) 5 1.3 1.1 0.95 Sb-129
exp (.158xT hrs) 580 0.7 Sb-129
exp (.158xT hrs) 10 1.6 1.4 1.2 La-142
exp (.500xT hrs) 650 0.6 La-142
exp (.500xT hrs) 20 2.3 1.9 1.7 T - Rx shutdown to time of sample 690 015 T = Rx shutdown to time of sampl 40 3.6 3.0 2.6
  • Use the RCS Volume Worksheet to determine appropriate reactor coolant inventory volume. **exp (.155 x T hrs) = e*+155T MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 4 of 9

(

Kr-85m

(

X X

X

Unit 3 Core Fraction Worksheet Date:

REACTOR COOLANT Time:

Worksheet Completed by:

Print Name CONTAINMENT AIR Density RCS*

Decav Corr.

Volume Activity Kr-85m

(

X X

X

)+(

X X

X6.5E10) =

r 2.-'E13.

=

+2.45E1 3 =

Kr-87 X

X X

X X

X 6.5E10) =

+

4.09E13

=

Kr-88 X

X

+(

X X

X6.5E10_ =

6.14E13 =

Xe-131m x

X X

+(

XX X6.5E10)

+

6.OOEl1

=

Xe-1 33

(

X X

+

x i

x X 6.5E10)=

+

1.88E14 =

X+

6.67E12

=

Xe-135 X

X X

)+(

X X

X6.5E10) =

+ 2.53E13 =

1-131 x

x

+(

XX X6.5E10

=

+ 9.21E14 =

1-132 X

X X

+

X X

X6.5E10) =

+

1.30E14 =

1-133 X

X X

+,X X6.5E10)=

+

1,88E14 =

1-135

(

X X

X

)

X 6.5E10) =

1.74E14 =

Cs-134 X

ý

ýX X

+

X X

6.5E10).=

1.83E13 =

CS-i 37 xx Cs-13 (

X X

X

+(

X X6.5E10) =

-1.13E13=

SIP1129 x

X X

+

)(

X X

X6.5E10) =+

3.07E1 3 =

Te-132

(

X'

+

)(

X

'X X 6.5E10) =

+1.30E14

=

Be-140

  • XX)(XXX6.5E10)

=

+1.64E14

=

La-142

(

X X

X

+

X X

X6.5E10)=

1.43E14 =

Ce-144 XX X

+

X X

X6.5E10)=

+

1.19E14 =

Other X

X X

+ (

X X 6.5E10)= =

X X

X

+

X X 6.5E10) =

+

=

Kr-85m

exp (.155xT hrs)**

Kr-85m

exp (A155xT hrs)

PT CORRECTION Kr-87

exp (.547xT hrs)

Rx Coolant Density Kr-87

exp (.547xT hrs)

Cont. P Cont, Temp Kr-88

exp (.244xT hrs)

Temp F Corr Kr-88

exp (.244xT hrs)

PSIG 1000 2000 300*

Transfer Fcomr to the Xe-135

exp (.076xT hrs) 100 1.0 Xe-135
exp (.076xT hrs) 0 0,96 0.82 0.71 damage estimate 1-132
exp (.301xT hrs) 325 0.9 1-132
exp (.301xT hrs) 2 1.1 0.93 0.81 worksheet.

1-135

exp (.103xT hrs) 475 0.8 1-135
exp (.103xT hrs) 5 1,3 1.1 0.95 Sb-129
exp (.158xT hrs) 580 0.7 Sb-1 29
exp (.1 58xT hrs) 10 1.6 1.4 1.2 La-142
exp (.500xT hrs) 650 0.6 La-142
exp (.5OOxT hrs) 20 2.3 1.9 1.7 T - Rx shutdown to time of sample 690 0.5 T - Rx shutdown to time of sample 40 3.6 3.0 2.6
    • exp (.155 x T hrs) = e+.lsST MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 5 of 9 Density CONT Dr-a/

(.nrr VnlI iilllma Total Core Inv Core Activity UCVi/m

(

Damage Estimate Worksheet Date:

Time:

Worksheet Completed by:

Isotope Kr-85m Kr-87 Kr-88 Xe-31 m Xe-133 Xe-133m Xe-i 35 1-131 1-132 1-133 1-135 Cs-134 Cs-i 37 Sb-129 Te-132 Ba-140 La-142 Ce-144 Other Fuel Cladding FR Gap Rel Frac Frac Release

+.03 =

X100=

+.03 =

X100=

+

.03 =

X 100 =

+.03 =

X 100 =

+.03 =

X100=

+.03 =

X100=

+.03 =

X 100 =

+.02 =

X100=

+.02 =

X100=

+.02 =

X100=

+.02 =

X100=

+.05

f Xl00

+.05 =

XlO0=

.0001 =

X 100 =

+.0001 =

X 100 =

+

=

X 100 =

+

=

X100=

X 100=

+.

100 =

Fuel Overheat FR OH Rel Frac Frac Release

+.50 =

X 100 =

+.50 =

X100=

.50 =

X100=

.50 =

X100=

+

.50

=

X100=

+

.50

=

X100=

+

.50

=

X 100 =

+.50

=

X100=

+.50

=

X 100=

+.50

=

X100=

+.50

=

X 100 =

+.50

=

X100=

+.50

=

X100=

+.02

=

X100=

+

.10 =

X100=

+.01

=

X 100=

S X 100=

+

X 100=

S X 100=

MP-26-EPI-FAP1 1-007 Rev. 000-01 Page 6 of 9 Print Name Fuel Melt FR Melt Rel Frac Frac Release 1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100=

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100=

+

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100 =

+

1.0

=

X 100 =

.20

=

X 100 =

+

.30

=

X 100 =

+

.20

=

X 100 =

+

.0001 =

X100=

.0001 =

X100=

X 100=

S X 100=

+

=

X 100=

¢

Fission Product Inventories at Shutdown Unit 2 tuCi Unit 3 uCi 1.05E+14 1.33E+14 4.91E+13 6.20E+13 8.37E+13 1.06E+14 8.91E+13 1.13E+14 1.05E+14 1.33E+14 1.1IE+14 1.40E+14 1.19E+14 1.50E+14 1.13E+ 14 1.43E+14 P

Isotope Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Kr-91 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Xe-139 Xe-140 Xe-141 Br-84 Br-85 Br-86 Br-87 Br-88 Br-89 Br-90 1-131 1-132 1-133 1-134 1-135 1-136 1-137 1-138 1-139 1-140 Se-84 Se-85 Se-86 Se-87 Rb-88 Rb-89 Rb-90 Rb-91 Sr-89 Sr-91 Sr-92 Sr-93 MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 7 of 9 1

Unit 2 pCi 8.09E+12 1.94E+13 7.83E+ I1 3.24E+ 13 4.86E+13 5.94E+13 6.75E+13 5.13E+13 4.75E+ I1 5.28E+12 1.49E+14 2.62E+ 13 2.OOE+13 1.32E+14 1.27E+14 1.05E+14 7.02E+13 2.70E+13 1.46E+13 1.81E+13 2.67E+ 13 3.24E+13 4.05E+13 4.05E+13 4.05E+13 7.29E+13 1.02E+14 1.49E+14 1.59E+14 1.38E+14 7.56E+13 9.18E+ 13 5.67E+13 2.97E+13 1.27E+13 1.43E+13 1.70E+13 2.05E+13 1.78E+13 4.86E+13 6.21E+13 8.10E+13 8.1OE+13 6.48E+13 8.10E+13 8.9]E+13 1.03E+14 Isotope Sr-94 Y-91m Y-91 Y-92 Y-93 Y-94 Y-95 Y-96 Y-99 Unit 3 mCi 1.26E+13 2.45E+13 9.89E+ 1I 4.09E+13 6.14E+13 7.50E+13 8.53E+13 6.48E+13 6.OOE+1 1 6.67E+12 1.88E+14 3.31E+13 2-53E+13 1.67E+14 1.60E+14 1.33E+14 8.87E+13 3.41E+13 1.84E+13 2.29E+13 3.37E+13 4.09E+13 5.12E+13 5.12E+13 5.12E+-13 9.21E+13 1.30E+14 1.88E+14 2.01E+14 1.74E+14 9.55E+ 13 1.16E+14 7.16E+13 3.75E+13 1.60E+13 1.81E+13 2.15E+13 2.59E+13 2.25E+13 6.14E+13 7.84E+13 1.02E+14 1.02E+14 8.19E+13 1.02E+14 1.12E+14 1.30E+14 Zr-95 Zr-97 Zr-98 Zr-99 Zr-loo Nb-95m Nb-95 Nb-97m Nb-97 Nb-98m Nb-99m Nb-99 Nb-100m Nb-100 Mo-99 Mo-101 Mo-102 Mo-103m Mo-103 Mo-104 Tc-99m Tc-100 TC-101 Tc-102m Tc-103 Tc-104 TC-105 Tc-107 Tc-108 Ru-103 Ru-105 Ru-106 Ru-107 Ru-108 Ru-109 Rh-103m Rh-104 Rh-105m 2.97E+13 1.22E+14 1.24E+14 1.22E+14 1.1IE+14 8.64E+13 2.51E+12 1.22E+14 1.23E+14 1.24E+14 1.24E+14 4.59E+13 1.22E+14 7.02E+13 7.02E+13 1.38E+14 1.24E+14 1.16E+ 14 2.54E+13 9.99E+13 8.10E+13 1.22E+14 1.24E+13 1.24E+14 1.19E+14 1.19E+14 9.45E+13 6.21E+13 2.67E+13 1.89E+13 1.19E+14 6.48E+13 4.32E+13 4.05E+13 3.24E+13 1.97E+13 1.16E+14 4.86E+13 1.38E+13 3.75E+13 1.54E+14 1.57E+14 1.54E+14 1.40E+14 1.09E+14 3.17E+12 1.54E+14 1.55E+14 1.57E+14 1.57E+14 5.80E+13 1.54E+14 8.87E+13 8.87E+13 1.74E+14 1.57E+14 1.47E+14 3.21E+13 1.26E+14 1.02E+14 1.54E+14 1 -57E+ 13 1.57E+14 1.50E+14 1.50E+14 1.19E+14 7.85E+13 3.37E+ 13 2.39E+ 13 1.50E+14 8.19E+13 5.46E+13 5.12E+13 4.09E+ 13 2.49E+13 1.47E+14 6.14E+13 1.74E+ 13 I

Unit 2 mCi Unit 3 mCi 1.35E+14 1.30E+14 1.24E+14 1.05E+14 8.64E+13 5.13E+13 1.35E+14 1.24E+14 1.13E+14 1.08E+14 9.45E+13 1.24E+14 1.11E+14 9.45E+13 7.56E+13 5.94E+13 4.05E+13 2.35E+13 9.45E+12 1.08E+14 9.45E+13 7.56E+13 6.21E+13 4.59E+13 3.78E+13 2.46E+13 4.86E+13 2.70E+13 1.35E+13 1.76E+13 4.05E+13 1.46E+13 2.40E+13 1.30E+13 1.71E+14 1.64E+14 1.57E+14 1.33E+14 1.09E+14 6.48E+13 1.71E+14 1.57E+14 1.43E+14 1.36E+14 1.19E+14 1.57E+14 1.40E+14 1.19E+14 9.55E+13 7.50E+13 5.12E+13 2.97E+13 1.19E+13 1.36E+14 1.19E+14 9.55E+13 7.85E+13 5.80E+13 4.78E+13 3.11E+13 6.14E+13 3.41E+13 1.71E+13 2.22E+13 5.12E+13 1.84E+13 3.03E+13 1.64E+13 MP-26-EPI-FAPl 1-007 Rev. 000-01 Rh-105 Rh-106 Rh-107 Rh-108 Rh-109 6.48E+13 4.59E+ 13 4.32E+13 3.51E+13 2.13E+ 13 8.19E+13 5.80E+13 5.46E+ 13 4.43E+13 2.69ER+13 Ba-139 Ba-140 Ba-141 Ba-142 Ba-143 Ba-144 2.87E+13 Pd-109 Sn-130 Sn-131 Sn-132 Sb-127 Sb-128m Sb-129 Sb-130 Sb-131 Sb-132m Sb-132 Sb-133 Sb-134 Sb-135 Te-127 Te-129 Te-131m Te-131 Te-132 Te-133m Te-133 Te-134 Te-135 Te-136 Cs-134 Cs-137 Cs-138 Cs-139 Cs-140 Cs-141 Cs-142 Cs-143 2.27E+ 13 2.46E+13 2.19E+13 1.89E+13 7.56E+12 1.11E+13 2.43E+13 3.51E+13 5.94E+13 3.78E+13 6.21E+13 6.75E+13 3.51E+13 1.11E+13 9.72E+12 2.32E+13 1.16E+ 13 6.48E+13 1.03E+14 8.64E+13 6.48E+13 1.32E+14 6.75E+13 2.70E+13 1.45E+ 13 8.95E+12 1.35E+14 1.32E+14 1.22E+14 9.18E+13 5.67E+13 2.70E+13 3.11 E+ 13 2.77E+13 2.39E+13 9.59E+12 1.40E+ 13 3.07E+13 4.43E+13 7.50E+13 4.78E+13 7.85E+13 8.53E+13 4.43E+13 1.40E+13 1.23E+12 2.93E+13 1.47E+ 13 8.19E+13 1.30E+14 1.09E+14 8.19E+ 13 1.67E+14 8.53E+13 3.41E+13 1.83E+13 1.13E+13 1.71E+14 1.67E+14 1.54E+14

1. 16E+14 7.16E+13 3.41E+13 La-140 La-141 La-142 La-143 La-144 Ce-141 Ce-143 Ce-144 Ce-145 Ce-146 Ce-147 Ce-148 Pr-142 Pr-143 Pr-144 Pr-145 Pr-146 Pr-147 Pr-148 Pr-149 Nd-147 Nd-149 Nd-151 Pm-147 Pro-149 Pmr-151 Sm-153 Eu-156 Unit 2 mCi Unit 3 ptCi isotope Isotope

Release Fractions for Various Types of Core Damage Core Condition Fuel Cladding Fission Product Core Inventory Temperature*

Release Fraction Core Intact

<!ý 6000 F Normal Activity N/A Gap Release 13000 F - 21000 F Xe, Kr 0.03 (cladding failure) 1 0.02 CS 0.05 Te, Sb 0.0001 Fuel Overheat 20000 F - 32000 F Xe, Kr 0.5 (grain boundary) 1, CS 0.5 Te 0.1 Sb 0.02 Ba 0.01 Mo 0.01 Sr 0.001 Ru 0.0001 Core Meltdown

>35000 F Xe, Kr 1.0 I, Cs 1.0 Sb 0.2 Te 0.3 Ba 0.2 Mo 0.07 Sr 0.1 Ru 0.001 La 0.0001 Y

0.0001 Ce 0.0001 Np 0.0001

  • Above 13000 F, release rates will approximately double with every 2000 F increase in temperature.

MP-26-EPI-FAPI 1-007 Rev. 000-01 Page 9 of 9 I

S

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP1 1-009, "Unit 2 Reactor Coolant and Liquid Waste Sample Worksheet" Major Revision 0, Minor Revision 2

08/20102 09/03/02 08/20/02 Approval Date Procedure Action Request 09/03/02 Effective Date SPG 021024-134150 Document No.:

MP-26-EPI-FAP1 1 I Writer:

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whi-It 001 02

Title:

Core Damage Assessment For New Documents Document is QA El DH

Title:

[] Revision ID Minor Revision

[] Cleanup Revision 0g Biennial Review o Cancel 0 Void (Do Not Use) 03 Expire 0 Superceded By; Comments:

[l Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print sin Date Department Biennial Review

  1. i t$

14I7

/V2V~t fVj)

El 1CD

/0Io,'0/O, A/PC Environmental Screen See attached form Licensing Basis Io iq/oz__V-C)

(50.59 Screen Req. nYes [No)

W -A. D xomw k"J Tech Independent 41,eL.I4r/;iiII Validation None

[E Field-Use El Simulated Per-(rmance]-

E Table Top and El comparison MP-05-DC-SAPO1-004 Use MP-05-DC-SAPO1-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member Training:

0 None

[I Nuclear Training

[] Briefing

[] Familiarization SQR Review and Approval n-SORC Review and Aplrovai fl Department Head Review and Approval App Disapproval El WA WA loilaq*--

(1) Department Head Sign/Date (1) Department Head Approval Sign V R~~~

ig ate Sn (2) SORC Meeting Number

'(2) Deopalnt Head Ao

-al Sign 1 (3) SORC Approval Sign Approval Date:

/o0Z.?/OZ.

Effective Date:

/O13o/oz.

MP-05-DC-FAPOI.1-005 Rev. 000 Page 1 of

Procedure Action Request Continuation Page I Document No.:

MP-26-EPI-FAP1 1 Writer:

M. Maryeski int: Mark Whi4'P Rev. No.

Minor Rev.

001 02 Core Damage Assessment E(Comments 5 Validation Comments Reviews Print Sign Date Department EJ El

_~

~ El MP-26-EPI-FAP1 1 -001, rOOO-01 MP-26-EPI-FAPI 1-002, rOOO-01 MP-26-EPI-FAPI 1-004, rOOO-01 MP-26-EPI-FAP1 1-005, rOOO-01 MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, rOOO-01 MP-26-EPI-FAP1 1-009, rOOO-02 MP-26-EPI-FAP1 1 -011, rOOO-02 MP-05-DC-FAPOI.1-005 Rev. 000 PaRe 2 of I

j r) 1,lo c),

A--I-

'l Approval'Date Effecti'e Date Unit 2 Reactor Coolant and Liquid Waste Sample Worksheet TABLE 1 RM-8240/8241 Reading >_300 R/hr

(>5% Clad Damage)

RM-8240/8241 Reading >_5 R/hr without RCS Release into CTMT

(>5% Clad Damage)

Is the fuel damage as indicated in Table 1 ?

HPS Containment Spray LPSI Containment Spray RCS Hot Leg Normal RCS Sample Appropriate indicator circled TABLE 2 I

Boron LI Liquid isotopic Appropriate sample analysis checked Choose the Effluent Return Path:

Radwaste or VCT Completed by:

Date:

Time:

(MRDAIAMRDA)

MP-26-EPI-FAPI 1-009 Rev. 000-02 Page I of 1 1

I

Docket Nos. 50-245 50-336 50-423 B18805 Millstone Power Station, Unit Nos. 1, 2 and 3 Emergency Procedures Implementing (EPI) Functional Administrative Procedure (FAP)

MP-26-EPI-FAP11-011, "Unit 3 Reactor Coolant and Liquid Waste Sample Worksheet" Major Revision 0, Minor Revision 2

08/20/02 09/03/02 Approval Date Effective Date Procedure Action Request SPG 021024-134150 Document No.:

MP-26-EPI-FAP11 Writer:

M. Maryeski Rev. No.

Minor Rev.

int: Mark Whi-001 02

Title:

Core Damage Assessment For New Documents Document is QA E]

DH

Title:

ol Revision 0R Minor Revision 0 Cleanup Revision 0 Biennial Review o Cancel 0 Void (Do Not Use)

[

Expire U Superceded By:.

Comments:

0 Administrative Correction FLS:

Performed Biennial Review (CR-02-11018). Incorporated minor editoral corrections includes forms on attached page 2.

Reviews Print Sig2 Date Department Biennial Review L*/';u t.*

j E]

1CD,0

/029/O A/P Environmental Screen See attached form Licensing Basis AQ]kj'7>-lO /z1/0z A*/O (50.59 Screen Req. [I Yes [R'No)

~.ff LOJV4_____

Tech independent IN A tAA86'&/.j 9

Validation E3 None

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Field -Use,

Simulated Per(ormance -

El Table Top and El Comparison MP-05-OC-SAPO1-O04 Use MP-05-DC-SAPOI-004 Walk-through (minimum of two)

Print Sign Date Dept Coordinator Member Training:

ID None

[I Nuclear Training E] Briefing

[I Familiarization

[D SQR Review and Approval F-SORC Review and Approval fl" Department Head Review and Approval Approval Disapproval El WA WA

/a/0h (1) Department Head Sign/Date (1) Department Head Approval Sign

(.

Rj Ignig ate

/( 7 &

(2) SORC Meeting Number 0(2) Delm&nt Head ro al Sign 1(3) SORC Approval Sign Approval Date:

/o1 Z-9/OZ.

Effective Date:

iOI3o/o?_

MP-05-DC-FAPOI.1-005 Rev. 000 Page I of

Procedure l Document No.:

MP-26-EPI-FAP1 1 Action Request Continuation Page Writer:

M. Maryeski int-Mark Whi*'P I

I Rev. No. I Minor Rev.

001 02 I

M k

I 1

Title:

Core Damage Assessment i

MP-05-DC-FAPO1.1-005 Rev. 000 Paee 2 of P?

I I

VComments 5 Validation Comments Reviews Print Sign Date Department IJ El__

MP-26-EPI-FAP1 1-002, rOOO-01 MP-26-EPI-FAP1 1-002, rOOO-01 MP-26-EPI-FAP 11-005, rOOO-01 MP-26-EPI-FAP1 1-006, rOOO-01 MP-26-EPI-FAP1 1-007, rOOO-01 MP-26-EPI-FAP 11-009, rOOO-02 MP-26-EPI-FAPI1 -011, r000-02

toIo1kA 10,x Effective Date Approval Date Unit 3 Reactor Coolant and Liquid Waste Sample Worksheet TABLE I RM-04AI05A Reading >_50O R/hr

(>5% Clad Damage)

RM-04N05A Reading >5 R/hr without RCS Release into CTMT

(>5% Clad Damage)

Appropriate indicator circled Is the fuel damage as indicated in Table 1?

iABLE2 Completed by:

LI Degas liquid isotopic LI Pressurized 2.Oml grab sample

[]

Depressurized 2.0 ml grab sample Appropriate sample analysis checked Choose the Purge/Flush Path:

CTMT Drain Sump or VCT Date:

Time:

(MRDA/AMRDA)

MP-26-EPI-FAPI 1-011 Rev. 000-02 Page I of I

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