ML030410605
| ML030410605 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 01/31/2003 |
| From: | Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| EPIP059 | |
| Download: ML030410605 (146) | |
Text
PSEG Internal Use Only Page 1 of 1 SALEM GENERATING STATION SC.EP-EP.ZZ-0205 (Q) Rev. 03 TSC - POST ACCIDENT CORE DAMAGE ASSESSMENT USE CATEGORY: II REVISION
SUMMARY
Biennial Review Performed: Yes X No-__
- Deleted all references to the Post Accident Sampling System (P.A.S.S) and changed all explicit references to "P.A.S.S sample" to a more generic term such as "isotopic sample" or "sample."
- Replaced all references to EPIP202S/NC.EP-EP.0201(Q) with NC.EP-EP.ZZ 0201 (Q).
- Revised the position that approves Emergency Plan Implementing Procedures IMPLEMENTATION REQUIREMENTS:
vN' I 'JU 51 Implementation Date: ' r 1.
3 V -
h __
APPROVED: /-/? -73 EP Manager Date APPROVED:
Date Dt Dir6ctodr Operations
SC.EP-EP.ZZ-0205(Q)
TSC - POST ACCIDENT CORE DAMAGE ASSESSMENT TABLE OF CONTENTS 1.0 P URPO S E ................................................................................................ 3 2.0 PREREQ UISITES ................................................................................ 3 3.0 PRECAUTIONS AND LIMITATIONS .................................................. 4 4.0 EQUIPMENT REQUIRED ................................................................... 4 5.0 PROCEDURE ....................................................................................... 5 5.1 PERFORM CORE DAMAGE ASSESSMENT USING CURRENT PLANT STATUS AND DOSE EQUIVALENT IODINE (DEI) [CTE] .................... 5 5.2 PERFORM CORE DAMAGE ASSESSMENT BY ANALYZING AN ISOTOPIC SAMPLE .......................................................................................... 7
6.0 REFERENCES
.................................................................................. 18 APPENDIX 1 REFERENCES FOR TABLE I .......................................................... 19 ATTACHMENT 1 PLANT PARAMETER TRENDING ................................................... 21 ATTACHMENT 2 HIGH LEVEL CORE DAMAGE ASSESSMENT ................................ 22 ATTACH MENT 3 CLAD DAMAGE ESTIMATE (STEP 5.1.4) ........................................ 24 ATTACHMENT 4 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5) ....................................................................................... 29 ATTACHMENT 5 FIGURES FOR SECTION 5.1 ............................................................ 35 ATTACH MENT 6 CORE DAMAGE ASSESSMENT TRENDING .................................. 40 ATTACHMENT 7 WATER DENSITY RATIO (TEMPERATURE VS. P- ) .................. 41 PsTP ATTACHMENT 8 POWER CORRECTION FACTOR FOR CS-134 BASED ON AVERAGE POWER DURING OPERATION ...................................... 42 ATTACHMENT 9 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES ............................ 43 ATTACHMENT 10 PRESSURE AND TEMPERATURE-CORRECTION FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES ................ 49 Salem Common Page 1 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 11 TOTAL ACTIVITY RELEASED FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES ..................................... 53 ATTACHMENT 12 TOTAL ACTIVITY RELEASED FOR ALL SAMPLES COMBINED ...... 56 ATTACHMENT 13 POWER CORRECTIONS FACTORS FOR: KR-85M, KR-87, KR-88, XE-135, 1-132, 1-133, 1-135, TE-129, PR-144 .................................... 57 ATTACHMENT 14 POWER CORRECTIONS FACTORS FOR: XE-131M, XE-133, XE-133M, 1-131, TE-132, BA-140 ...................................................... 59 ATTACHMENT 15 POWER CORRECTIONS FACTORS FOR: SR-90, CS-134, CS-137 ... 61 ATTACHMENT 16 POWER CORRECTIONS FACTORS FOR: SR-89 ........................... 62 ATTACHMENT 17 ISOTOPIC INVENTORY AVAILABLE FOR RELEASE ..................... 64 ATTACHMENT 18 PERCENT INVENTORY RELEASED FOR EACH ISOTOPE ........... 65 ATTACHMENT 19 CORE DAMAGE ASSESSMENT (BASED ON INVENTORY) ........... 66 ATTACHMENT 20 FIGURES USED IN SECTION 5.2 .................................................... 68 ATTACHMENT 21 ISOTOPIC ACTIVITY RATIOS OF FUEL PELLET AND GAP ....... 80 ATTACHMENT 22 DOSE EQUIVALENT IODINE (DEI) .................................................. 81 ATTACHMENT 23 FINAL CORE DAMAGE ASSESSMENT BASED ON ISOTOPIC INVENTORIES AND NOBLE GAS & IODINE RATIOS ..................... 82 Salem Common Page 2 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 1.0 PURPOSE This procedure provides information for the assessment of the degree of core damage during an accident, as required per NC.EP-EP.ZZ-0201(Q), Attachment 11.
Specifically, the information contained in this procedure relates to:
"* Determination of the degree of damage to the fuel rod cladding that results in the release of the fission product inventory in the fuel gap space.
"* Determination of the degree of core overheating that results in the release of fission product inventory in the fuel pellets.
" Section 5.1 of this procedure may be utilized by the Core Thermal-Hydraulics Engineer (CTE) to perform a core damage assessment using current plant parameters and Dose Equivalent Iodine (DEI) readings. Section 5.1 can be utilized immediately after the identification of a plant transient condition.
" Section 5.2 of this procedure may be utilized by the Core Thermal Hydraulics Engineer to perform a core damage assessment using isotopic data. Section 5.2 can be utilized after isotopic data is made available, which normally occurs several hours after the identification of a plant transient condition.
2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 Implement this procedure:
"* At the discretion of the Core Thermal-Hydraulic Engineer (CTE)
" Upon staffing of the Emergency Response Facility Salem Common Page 3 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.
3.1.2 This procedure should be used whenever the following indications are present:
"* There are indicated core temperatures that trigger the use of Functional Restoration Guidelines, or
"* There are indicated containment radiation levels that trigger an alarm.
"* There has been an initiating event which may have resulted in fuel damage.
3.1.3 If additional support is needed for performing Fuel Damage Assessment, contact the Nuclear Fuels Manager.
3.2 Limitations 3.2.1 Only the core damage assessment methodology based on Dose Equivalent Iodine (DEI) can be used at any reactor power level. All other assessment methodologies should only be used after reactor trip or shutdown.
3.2.2 Clad damage of less than 1% is not considered to be a loss of the fuel cladding boundary.
3.2.3 The core damage assessment methodology does not account for fission product spiking.
3.2.4 The methodology used in Section 5.1 defines three types of core damage: no damage, cladding failure, and fuel over-heating; while the methodology utilizing isotopic data in Section 5.2 defines fuel melting as a fourth type of core damage. Fuel melt is not considered a separate core damage category in Section 5.1 because the diagnosis of core melting is not required to evaluate and implement in-plant recovery strategies. As a result, the diagnosis of a core over-temperature condition is adequate.
4.0 EQUIPMENT REQUIRED As provided in the Emergency Response Facility.
Salem Common Page 4 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.0 PROCEDURE NOTE:
Due to the multiple and, at times, unpredictable failure mechanism associated with core damage, this procedure has been developed to provide GUIDANCE for Core Damage Assessment. The sequence and extent of procedure performance should be based on the knowledge and experience of the Core Thermal-Hydraulics Engineer.
5.1 Perform Core Damage Assessment Using Current Plant Status and Dose Equivalent Iodine (DEI) [CTE]
(The methodology used in this section is found in Reference 1. The Salem-specific setpoints used in this methodology are discussed in References 4 and 7.)
5.1.1 RECORD in Attachment 1, "Plant Parameter Trending," the Unit, Date, and Time of Reactor Trip or Shutdown, if trip/shutdown has occurred.
5.1.2 OBTAIN the current status of each plant parameter specified in Attachment 1 and write it in Table 1, "Plant Parameter Trend," along with the time at which the plant parameters were recorded.
Note: A core damage estimate is not used explicitly in the Salem Emergency Classification Guidelines (SECG) to determine the appropriate Emergency Action Level (EAL) in an accident. However, it is important to recognize that several plant parameters which indicate potential core damage are also used to determine EALs., most notably those found in SECG Section 3.0 - Fission Product Barriers. These parameters are as follows and can be used to perform a qualitative assessment of damage to the fission product barriers.
EAL #1.1.1.a Reactor Coolant > 1 ýiCi/gm DEI for > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Unusual Event EAL #3.1.2 Reactor Coolant > 300 pCi/gm DEI Alert or Higher EAL #3.1.3.a 5 or More CETs > 700 °F Alert or Higher EAL #3.1.3.b 5 or More CETs > 1200 OF Alert or Higher EAL #3.1.4 RVLIS Full Range < 39% (Modes 1-4) Alert or Higher EAL #8.1.3.b RVLIS Full Range < 57% (Modes 5,6) Site Area Emerg.
EAL #3.1.5 Containment Radiation (R44A or R44B) > 300 RPhr Alert or Higher EAL #3.2.4 Containment Radiation (R44A or R44B) > 10 RPhr Alert or Higher EAL #3.3.5 Containment Radiation (R44A or R44B) > 2000 R/hr Site Area Emerg.
- Adapted from SECG - Salem Event Classification Guidelines.
Salem Common Page 5 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.1.3 IDENTIFY the possible status of the reactor core by using Attachment 2, "High Level Core Damage Assessment."
Note: A clean copy of Attachment 2, "High Level Core Damage Assessment" should be used each time this step is performed.
5.1.4 ASSESS fuel rod cladding damage.
5.1.4.1 COMPLETE Attachment 3, "Clad Damage Estimate," to assess fuel rod cladding damage.
Note: A clean copy of Attachment 3, "CladDamage Estimate,"should be used each time this step is performed.
5.1.5 ASSESS fuel pellet over-temperature damage.
5.1.5.1 COMPLETE Attachment 4, "Fuel-Pellet Over-Temperature Damage Estimate," to assess fuel pellet over-temperature damage.
Note: A clean copy of Attachment 4, "Fuel-PelletOver-Temperature Damage Estimate," should be used each time this step is performed.
I RECOMMENDATION:
Because steps 5.1.3, 5.1.4, and 5.1.5 may be performed at numerous times throughout the duration of an event, it is recommended that several copies of Attachments 2, 3, and 4 be made at the time this procedure is implemented.
Note that the core damage assessments performed in Attachments 3 and 4 are collected and trended in Attachment 6. Also, copies of Attachments 1 and 6 may be made as needed.
Salem Common Page 6 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2 Perform Core Damage Assessment By Analyzing An Isotopic Sample (See Reference 2 for a more detailed discussion of the methodology used in this section.)
5.2.1 PROVIDE recommendations to the Radiological Assessment Coordinator (RAC) to initiate post accident radionuclide samples according to the "Suggested Sampling Locations" in the table below.
Scenario Principal Sampling Locations Other Sampling Locations Small Break LOCA Reactor Power > 1% RCS Hot Leg, Containment RCS Pressurizer Atmosphere Reactor Power < 1% RCS Hot Leg RCS Pressurizer Large Break LOCA Containment Sump, Reactor Power > 1% Containment Atmosphere, RCS Hot Leg Containment Sump, Reactor Power < 1% Containment Atmosphere Steam Line Break RCS Hot Leg RCS Pressurizer, Containment Atmosphere Steam Generator Tube RCS Hot Leg, Secondary Containment Rupture System Atmosphere Indication of Significant Containment Sump, Containment Sump Containment Atmosphere Inventory Containment Building Containment Atmosphere, Radiation Monitor Alarm Containment Sump Safety Injection Actuated RCS Hot Leg RCS Pressurizer Indication of High Rad. RCS Hot Leg RCS Pressurizer Alarm in RCS I II "Suggested Sampling Locations" taken from Reference 2, page 48.
- Assume operating at that level for some appreciable time.
Salem Common Page 7 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.2 the isotopic data from the Chemistry Department.
"* The majority of isotopic samples will be taken from the following media: Reactor Coolant System (RCS), containment sump, and/or containment atmosphere.
"* More than one sample may be provided, each from different media.
5.2.3 If it is possible to analyze the isotopic data via the "Core Damage Assessment" Excel spreadsheet, GO TO Step 5.2.4.
If the Excel spreadsheet can NOT be utilized, GO TO Step 5.2.5 to perform a manual analysis of the data.
5.2.4 Isotopic Sample - Automatic Calculation of Isotopic Data via the "Core Damage Assessment" Excel Spreadsheet 5.2.4.1 OPEN the "Core Damage Assessment" Excel Spreadsheet, located on the laptop, as "Read Only."
The spreadsheet is installed on the Laptop Computer, kept in Drawer C2, along the wall in the "Admin Support" area of the TSC.
" The Excel spreadsheet is found under D:\Core Damage Assessment\coredam.xls. A shortcut to this directory exists on the desktop.
"* The spreadsheet is password protected with the word "coredamage".
5.2.4.2 SAVE the "Read Only" spreadsheet by clicking File and then Save As. When prompted, rename your copy of the "Core Damage Assessment" spreadsheet with today's date in MMDDYYYY.xls format.
Salem Common Page 8 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.4.3 INPUT the following information on the spreadsheet.
Note: Only input data into the green boxes on the spreadsheet.
Input Parameter Excel Spreadsheet Box Your Name F10 Plant F11 Date & Time of Reactor Shutdown / Trip F4, G4 Date & Time of RCS Sample F5, G5 Date & Time of Sump Sample F6, G6 Date & Time of Containment Atmosphere Sample F7, G7 5.2.4.4 CHECK Box C14 if the isotopic samples taken from the RCS or sump are in units of pCi/gm.
5.2.4.5 INPUT the pressure and temperature of the containment atmosphere, sump, and RCS in Boxes D19 - D30.
5.2.4.6 INPUT the pressure, temperature, and water density ratio (P/PSTP), if needed, of any samples taken from the containment atmosphere, sump, and RCS in Boxes G19- G31. See Attachment 7 to obtain the correct water density ratio.
NOTE If isotopic data is not obtained from all three media (RCS, sump, and containment atmosphere), the pressure, temperature, and p/psTp boxes for the unused media should contain dummy values. This practice will not impact the calculated results and will keep "Division By Zero" errors from appearing throughout the spreadsheet.
5.2.4.7 INPUT the isotopic data obtained from chemistry in the appropriate location of the spreadsheet.
Sample Box Numbers RCS H42 - H53 B57 - B64 Sump H74 - H85 B89 - B96 Containment H104 - H115 Atmosphere B1 19 - B126 Salem Common Page 9 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
Note:
For sample media and/or specific isotopes for which data was not obtained, fill in "O.OOE+00" in the appropriate box.
5.2.4.8 CHECK the appropriate box if the isotopic data has been previously decay corrected by Chemistry.
Sample Decay Corrected Data Check Box RCS E44 Sump E77 Containment Atmosphere E107 Note:
It is standard practice that all isotopic data received from the Chemistry Department will have been decay-corrected back to the time of reactor shutdown by the Chemistry Department.
5.2.4.9 DETERMINE all liquid volumes that contribute inventory to the RCS and/or sump.
5.2.4.9.1 CHECK the appropriate boxes under the "RCS" or "Sump" headings in boxes L12 - L20 or M12 - M20, respectively.
5.2.4.9.2 INPUT the correct liquid volumes (Boxes N12 - N19) and RWST water levels (Q20 and S20) if these are different from the default values. The default values are the liquid volume at 100% capacity. (Table 1, "Liquid Volumes Available to the RCS and Sump" of Section 5.2.5.3 contains the default values).
5.2.4.10 INPUT the power history data in boxes M32 -M35, P32 - P35, S32 - S35.
"* List power history information in chronological order from the most recent reactor start-up to shutdown.
"* If isotopic data for Cs-1 34 exists, then use Attachment 8 to input the power correction factor in Box U56.
Salem Common Page 10 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.4.11 CHECK the applicable fuel burnup conditions.
Beginning of Cycle Box AA3 Middle of Cycle Box AA4 End of Cycle Box AA5 5.2.4.12 ASSESS the amount of core damage by examining the information found in Column AH, in the Noble Gas Ratio and Iodine Ratio tables of Columns AL and AO, and the Dose Equivalent Iodine (DEI) table of Columns AL and AN.
5.2.4.13 SUMMARIZE a final core damage assessment in Attachment 23.
5.2.4.14 REPORT findings.
5.2.4.14.1 Report core damage estimate to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201 (Q).
5.2.4.15 GO TO Step 5.1 to perform a core damage assessment based on current plant status, if needed.
5.2.5 P.A.S.S. Sample - Manual Calculation of Isotopic Data 5.2.5.1 DETERMINE if the sampling results need to be decay corrected. See Section 2.4.5.3 "Decay Correction" (Reference 2) for a more detailed discussion of this methodology.
5.2.5.1.1 If the results have NOT been decay-corrected by the Chemistry Department. GO TO Attachment 9 and decay-correct the isotopic data.
5.2.5.1.2 If the results have already been decay-corrected by the Chemistry Department. GO TO Step 5.2.5.2.
Note:
It is standard practice that all isotopic data received from the Chemistry Department will have been decay-corrected back to the time of reactor shutdown by the Chemistry Department.
Salem Common Page 11 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.2 DETERMINE if the sampling results need to be pressure and temperature-corrected. See Section 2.4.5.2 "Pressure and Temperature Adjustment" (Reference 2) for a more detailed discussion of this methodology.
5.2.5.2.1 The isotopic data does NOT need to be pressure and temperature-corrected if the following is true.
GO TO Step 5.2.5.3.
"* The RCS sample or sump sample is in units of pCi/gm.
" The RCS sample or sump sample is in units of pCi/cc and the temperature of the RCS or sump is less than 200 OF.
"* The pressure and temperature of the containment atmosphere sample at the time of analysis is the same as the conditions of the containment atmosphere.
5.2.5.2.2 The isotopic data DOES need to be pressure and temperature-corrected if the following is true. GO TO Attachment 10 and pressure/temperature correct the isotopic data.
" The RCS sample or sump sample is in units of pCi/cc and the temperature of the RCS or sump is greater than 200 OF.
" The pressure and temperature of the containment atmosphere sample at the time of analysis is different than the conditions of the containment atmosphere.
5.2.5.3 CALCULATE the total volume of the coolant inventory available to the RCS (if RCS sample) or sump (if sump sample).
5.2.5.3.1 ADD each of the volumes in Table 1 (on the next page) that contributes to the coolant inventory in either the RCS or sump.
5.2.5.3.2 WRITE the total volume of coolant inventory of the RCS or sump in Table 2.
Salem Common Page 12 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
Table 1: *Liquid Volumes Available to the RCS and Sump Coolant Volumes Liquid Volume (ft")
Reactor Vessel (To Top of Vessel) 4945 Reactor Vessel (To Hot/Cold Leg) 3300 Reactor Vessel (To Top of Fuel) 2500 All 4 Accumulators (1 = 850 ft") 3400 All 4 Steam Generators (Salem Unit 1) 3864 (1 SG= 966.1 ft3)
Unit 2) 4320 All 4 Steam Generators (Salem (1 SG= 1080 ft3)
All 4 Hot Legs (1 = 108 ftW) 432 All 4 Cold Legs (1 = 302 ft') 1208 Pressurizer (nominal) 1080 Pressurizer (solid) 1800 Pressurizer Surge Line 45
- The references for each value are found in Appendix I Table 2: Calculated Volumes of Coolant Inventory in RCS and Sump Volume of Coolant Inventory (ft3)
Sump RCS 5.2.5.4 CALCULATE the total mass of the coolant inventory (for any RCS/sump samples) and total volume of containment (for any containment atmosphere samples).
5.2.5.4.1 USE the following equation for an RCS or sump sample.
3 M=V x P x 1.0 g/cc x 28.3E3 cc/ft PSTP Where, M = mass of coolant inventory (gm)
P - water density ratio obtained from Attachment 7 PSTP V = volume of coolant inventory (ft3) from Table 2 Salem Common Page 13 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.4.2 USE the following equation for a containment atmosphere sample.
= (2.6E6 3 -SSV) x2.ECC/ft CV CV=(.6Eft 283E3 3X x
14.7 psia x(T2 +460 P2 32F + 460)
Where, SV = volume of coolant inventory in sump (ft3) in Table 2 T 2 , P 2 = temperature (OF) and pressure (psia) of the containment atmosphere at time of sample CV = corrected containment atmosphere volume (cc) 5.2.5.4.3 WRITE the calculated mass and/or volume in Table 3 below.
Table 3: Calculated RCS and Sump Masses and Containment Atmosphere Volume RCS Mass (g)
Sump Mass (g)
Containment Atmosphere Volume (cc) 5.2.5.5 CALCULATE the total activity released for each isotope from each sample medium.
5.2.5.5.1 RECORD the corrected specific activities from each sample on the appropriate page in Attachment 11. Make sure to transfer the corrected specific activities for each sample medium from the most recently used attachment (either Attachment 9 or 10). If neither Attachment 9 nor 10 was utilized, then transfer the isotopic activities from the Chemistry Data.
5.2.5.5.2 TRANSFER the coolant inventory total mass (for an RCS or sump sample) or volume (for a containment atmosphere sample) from Table 3 onto the appropriate page in Attachment 11.
Salem Common Page 14 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.5.3 COMPLETE the multiplication for each isotope as indicated in Attachment 11 for each sample analyzed.
5.2.5.6 CALCULATE the total amount of activity released.
"* If there is only one sample, GO TO Step 5.2.5.7.
", If there are several samples from different media, PERFORM the indicated additions to calculate the total amount of activity released for each isotope from all of the media in Attachment 12.
5.2.5.7 CALCULATE the noble gas ratios for the following isotopes.
Xe-1 31 m Kr-85m Xe-1 33m Kr-87 Xe-1 35 Kr-88 5.2.5.7.1 USING the total isotopic activities found in Attachment 12 (for several samples) or in Attachment 11 (for one sample), the noble gas ratios are found by dividing the above activities by the activity for Xe-1 33.
Gas Isotope Noble Gas Ratio = Total Activity of Noble I------------------------------------
Total Activity of Xe - 133 Salem Common Page 15 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.7.2 RECORD the calculated noble gas ratios in Table 4 below.
Table 4: Noble Gas Ratios Noble Gas Isotope Noble Gas Ratio
(/Xe-133)
Xe-1 31m Xe-1 33m Xe-1 35 Kr-85m Kr-87 Kr-88 5.2.5.8 CALCULATE the iodine ratios for the following isotopes.
1-132 1-133 1-135 5.2.5.8.1 USING the total isotopic activities found in Attachment 12 (for several samples) or in Attachment 11 (for one sample), the iodine ratios are found by dividing the above activities by the activity for 1-131.
Total Activity of Iodine Isotope Iodine Ratio=
Total Activity of 1-131 5.2.5.8.2 RECORD the calculated iodine ratios in Table 5.
Table 5: Iodine Ratios Iodine Isotope Iodine Ratio 12(/-131) 1-132 1-133 I-135 Salem Common Page 16 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.9 CALCULATE the Dose Equivalent Iodine (DEI), if not already provided by Chemistry.
5.2.5.9.1 USE the equation below to find the DEI in units of "CVcc or Ci/ gram. (The constants used in the equation below are from Reference 5.)
DEI = (1.00 x 1-131) + (0.0361 x 1-132) + (0.270 x 1-133) + (0.0169 x 1-134) + (0.0838 x 1-135) 5.2.5.10 RECORD the DEI in Table 6.
Table 6: Dose Equivalent Iodine (DEI)
L I ii 1i 5.2.5.11 OBTAIN the power history prior to shutdown.
5.2.5.12 CALCULATE the Power Correction Factor (PCF) for each isotope that is available for release utilizing the appropriate Attachment. See Section 2.3.1, "Power Correction Factor" (Reference 2) for a discussion of this methodology.
Attachment 13 Attachment 14 Attachment 15 Attachment 16 Kr-85m Xe-1 31m Sr-9U :Sr-89 Kr-87 Xe-1 33 Cs-1 34 Kr-88 Xe-1 33m Cs-1 37 Xe-1 35 1-131 1-132 Te-132 1-133 Ba-140 1-135 Te-129 Pr-144 5.2.5.13 CALCULATE the inventory available from each isotope that is available for release in Attachment 17.
5.2.5.14 CALCULATE Percent Inventory Released in Attachment 18.
5.2.5.15 EXECUTE an assessment of the core damage based on the percent inventories released in Attachment 19, using the figures found in Attachment 20.
Salem Common Page 17 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q) 5.2.5.16 EXECUTE an assessment of the core damage based on the Noble Gas and Iodine ratios calculated in Tables 4 and 5, using the table in Attachment 21.
5.2.6.17 EXECUTE an assessment of the core damage based on the Dose Equivalent Iodine (DEI), either provided from Chemistry or calculated in Table 6, using Attachment 22.
5.2.5.18 SUMMARIZE a final assessment of core damage based on the percent inventories released and the noble gas and iodine ratios in Attachment 23.
5.2.5.19 REPORT findings.
5.2.5.19.1 Report core damage estimate to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201 (Q).
5.2.5.20 GO TO Step 5.1 to perform a core damage assessment based on current plant status, if needed.
6.0 REFERENCES
6.1 WCAP-14696-A, Westinghouse Owners Group, Core Damage Assessment Guidance, Rev. 1, November 1999.
6.2 Westinghouse Owners Group Document, Post Accident Core Damage Assessment Methodology, Rev. 2, November 1984.
6.3 NC.EP-EP.ZZ-0201(Q), TSC-lntegrated Engineering Response, Rev. 2.
6.4 NFS Calc File DS1.6-0244, "Basis For Salem-Specific Values Used In SC.EP EP.ZZ-0205(Q) - TSC - PostAccident Core Damage Assessment," 07/26/1999.
6.5 EPRI Document TR-1 08779, "Fuel Integrity Monitoring & Failure Evaluation Handbook," Appendix B, August 1998.
6.6 NFS Calc File DS1.6-0098, "Verification of Emergency Action Levels for Event Classification Guide," 02/10/1995.
6.7 NFS Calc File DS1.6-0316, "Updated Basis For Salem-Specific Values Used In SC.EP-EP.ZZ-0205(Q) - TSC - Post Accident Core Damage Assessment,"
12/19/2000.
Salem Common Page 18 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
APPENDIX 1 Page 1 of 2 REFERENCES FOR TABLE 1 "Liquid Volumes Available to the RCS and Sump" Coolant Volumes 1 Reactor Vessel (To Top of Vessel) 4945 ft 3 Per Salem UFSAR, Table 5.2-3, "ReactorVessel Design Data," Rev 16, 3 01/31/1998, the total reactor vessel water volume with core and internals in place is 4945 ft .
- 2. Reactor Vessel (To Hot/Cold Leg) = 3300 ft 3 Per Salem UFSAR, Figure 5.1-1, "ReactorVessel Schematic," Rev 6, 02115/1987, the nozzles are at a height roughly two-thirds above the bottom of the vessel. Thus, 2Y3 x4945 ft 3 &3300 ft3 .
- 3. Reactor Vessel (To Top of Fuel) = 2500 ft 3 Per PSBP #117627, "ReactorGeneral Assembly Internals,"Rev 4, 07/05/1989 the top of the fuel (approximately at the upper core plate) is at a height roughly one half above the bottom of the vessel. Thus, 12 x 4945 ft 3 2500 ft 3 .
- 4. All 4 Accumulators = 3400 ft 3 Per Salem UFSAR, Table 6.2-3, "AccumulatorDesign Parameters,"Rev 6, 02115/1987, the minimum water volume for 1 accumulator at operating conditions is 850 ft3 . Thus, the volume of all 4 accumulators is 4 x 850 ft3 = 3400 ft3 .
3
- 5. All 4 Steam Generators (Salem Unit 1) = 3864 ft 3 All 4 Steam Generators (Salem Unit 2) = 4320 ft Per Salem UFSAR, Table 5.2-5a, "Steam GeneratorDesign Data (Model F)," Rev 18, 04/26/2000, the reactor coolant water volume in one steam generator is 966.1 ft3 . Thus, the volume of all 4 steam generators for Salem Unit 1 is 4 x 966.1 ft3 = 3864 ft 3.
Per Salem UFSAR, Table 5.2-5, "Steam GeneratorDesign Data (Model 51)," Rev 18, 04/26/2000, the reactor coolant water volume in one steam generator is 1080 ft3 . Thus, the volume of all 4 steam generators for Salem Unit 2 is 4 x 1080 ft3 = 4320 ft3 .
- 6. All 4 Hot Legs = 432 ft 3 Per NFS Calc File TO 1.6-093, "ConsolidatedDocumentation for the RETRAN02 Mod03 Model of Salem Units 1 and 2, 02129/1991, the volume of one hot leg is 109 ft3 . Thus, the volume of all 4 hot legs is 4 x 108 ft3 = 432 ft3.
- 7. All 4 Cold Legs and RCS Pumps = 1208 ft3 Per NFS Ca/c File TO 1.6-093, "ConsolidatedDocumentation for the RETRAN02 Mod03 Model of Salem Units 1 and 2, 02/29/1991, the volume of one pump suction volume is 143.76 ft 3, the volume of one pump is 56.0 ft 3, and the volume of one cold leg is 102.33 ft3 . The sum of these volumes is 143.76 ft3 + 56.0 ft3 + 102.33 ft3 = 302 ft3 . Thus, the volume of all 4 cold legs, pumps, and pump suction volumes is 4 x 302 ft3 = 1208 ft3 .
Salem Common Page 19 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
APPENDIX 1 (con't)
Page 2 of 2 REFERENCES FOR TABLE 1 "Liquid Volumes Available to the RCS and Sump" Coolant Volumes
- 8. Pressurizer (nominal) = 1080 ft3 Per Salem UFSAR, Table 5.2-4, "Pressurizerand PressurizerRelief Tank Design Data," Rev 16, 01/31/1998, the water volume of the pressurizer at full power is 1080 ft3 .
- 9. Pressurizer (solid) = 1800 ft3 Per Salem UFSAR, Table 5.2-4, "Pressurizerand PressurizerRelief Tank Design power is 1080 ft3 Data," Rev 16, 01/31/1998, the water volume of the pressurizer at full and the steam volume at full power is 720 ft3 . If the pressurizer was water solid, the amount of liquid would be 1080 ft3 + 720 ft3 = 1800 ft3 .
- 10. Pressurizer Surge Line = 45 ft3 Per NFS Calc File TO1. 6-093, "ConsolidatedDocumentation for the RETRAN02 Mod03 Model of Salem Units I and 2, 02/29/1991, the volume of the pressurizer surge line is 45 ft3 .
- 11. Refueling Water Storage Tank (RWST) = calculated by:
= (Initial RWST Level - Final RWST Level) x 1115 ft2 Per Salem UFSAR, Table 6.3-4, "Refueling Water Storage Tank Design Parameters,"
Rev 16, 01/31/1998, the tank capacity is 400,000 gallons, while the minimum volume is 364,500 gallons. The straight side height is given as 48 ft.
3 400,000 gallons = 53,472 ft 3 364,500 gallons = 48,726 ft The "100%" value is assumed to be the minimum allowable RWST volume of 48,726 ft3 . This occurs at a RWST level of 53,472 ft 3 x 48 ft = 43.7 ft. The total volume of water entering the Reactor Coolant System (RCS) from the RWST is found below.
Total RWST Volume Entering RCS = (Initial RWST Level - Final RWST Level) x r48,726 ft3 y43.7 ft)
Total RWST Volume 2 Entering RCS = (Initial RWST Level - Final RWST Level) x 1115 ft Salem Common Page 20 of 82 Rev. 03
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ATTACHMENT 1 Page 1 of 1 PLANT PARAMETER TRENDING Unit: Date:
Time of Reactor Trip or Shutdown:
Table 1: Plant Parameter Trend
- Plant Reading at Reading at Reading at Reading at Reading at Parameter Time = Time = Time - Time = Time
- 1. DEI liCi/gr oa pCi/gr or iCi/gr or gCi/gr or ltCi/gr or (if known) PtCu/cC ACu/cc u/c
/cc ACu/cc l.Cu/cc
- 2. Hottest CET Temperature oF °F oF TF
- 3. Number of CETs > 1200*F
- 4. Number of CETs > 1400°F
- 5. Number of CETs > 2000OF
- 7. R44 A Reading Rad/hr Rad/hi Rad/hr Rad/hr Rad/h Rad/hr Rad/hi Rad/hr Rad/hi Rad/h
- 8. RCS Pressure psig psig psig psig psig
- 9. Tat at the above RCS Pressure [#8.] °F T oF °F oF
- 10. Containment H2 Level volume % volume % volume % volume % volume %
- 11. RVLIS Reading % % o% %__ _
- 12. Hot Leg RTD 0 0 -F °F F oF Temperature F
- 13. SRM Reading cts/sec cts/sec cts/sec cts/sec cts/sec CET Core Exit Thermocouple DEI Dose Equivalent Iodine H2 Hydrogen RCS Reactor Coolant System RTD Resistance Temperature Detector RVLIS Reactor Vessel Level Indication System SRM Source Range Monitor Tsar Saturated Temperature Salem Common Page 21 of 82 Rev. 03
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ATTACHMENT 2 Page 1 of 2 HIGH LEVEL CORE DAMAGE ASSESSMENT Hiah Level Core Damage Assessment STEP 1: DETERMINE the time elapsed between Reactor Shutdown and the time at which the plant parameters in Table 1 of Attachment 1, "Plant Parameter Trending," were obtained and RECORD in Table 2.
Note: If a Reactor Trip or Shutdown has not occurred, WRITE "Not Applicable," and assess only the DEI, if known, in Table 3.
STEP 2: DETERMINE the correct values of <CRMI> by using Figure 1, "Containment Radiation Level Vs. Time For RCS Release," in Attachment 5, "Figures For Section 5.1," and <CRM2> by using Figure 2, "Containment Radiation Level Vs.
Time For 1 % Fuel Pellet Over-Temperature Release," in Attachment 5, "Figures For Section 5.1," and RECORD in Tables 2 and 3.
Table 2: Values of Containment Radiation Level Setpoints <CRMI> and <CRM2>
- 14. Time After Rx #15. <CRMI> #16. <CRM2>
Shutdown (hrs) hrs R/hr R/hr NOTE:
The value of <CRM1> is the postulated containment radiation level corresponding to normal reactor coolant system activity with an iodine spike, while <CRM2> is the postulated containment radiation level corresponding to a 1% fuel pellet over-temperature fission product release at specific times after reactor shutdown. The actual containment radiation monitor (R-44) reading is compared to <CRM3> and <CRM4> for the purpose of discriminating between fuel rod gap activity from cladding damage and the onset of fission product releases from the fuel pellet due to high fuel pellet temperatures.
Salem Common Page 22 of 82 Rev. 03
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ATTACHMENT 2 (Con't.)
Page 2 of 2 HIGH LEVEL CORE DAMAGE ASSESSMENT High Level Core Damage Assessment (Continued)
STEP 3: IDENTIFY the possible status of the reactor core by using Table 3, "Fuel Rod Fission Product Status."
Table 3: Fuel Rod Fission Product Status Plant Status Fuel Rod Fission Product Status Core Exit Thermocouples LESS THAN 700 OF AND No Core Damage Containment Radiation LESS THAN <Fr,.,i- Rad/hr Continue to Monitor Plant AND #15 Parameters Dose Equivalent Iodine (DEI) [if known] LESS THAN Go To Step 5.1.2 1 pCi/gm or 1 pCi/cc Core Exit Thermocouples LESS THAN 2000 OF AND Containment Radiation LESS THAN <c.,- Rad/hr Possible Fuel Rod
- 16 Clad Damage Go To Step 5.1.4 OR and Attachment 3 Dose Equivalent Iodine (DEI) [if known] GREATER THAN 1 ýtCl/gm or 1 itCl/cc Core Exit Thermocouples GREATER THAN 2000 OF Possible Fuel Pellet OR I IOver-temperature Damage Containment Radiation GREATER THAN <r,-- Rad/hr Go To Step 5.1.5 and Attachment 4 Values for #15 <CRMI> and #16 <CRM2> are obtained from Table 2 on Page 22.
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ATTACHMENT 3 Page 1 of 5 CLAD DAMAGE ESTIMATE (STEP 5.1.4)
A. Estimate Fuel Rod Clad Damage Based on Containment Radiation (CR) Levels STEP 1: DETERMINE the correct value of <CRM3> by using Figure 3, "Containment Radiation Level Vs. Time For 100% Clad Damage Release," in Attachment 5, "Figures For Section 5.1," and RECORD in Table 4.
Table 4: Values of Containment Radiation Level Setpoint <CRM3>
- 14. Time After Rx #17. <CRM3>
Shutdown hrs R/hr STEP 2: ESTIMATE clad damage by using the following equation.
Current Containment Radiation Level Clad DamageC (%) = Predicted Containment i Radiation Level at 100% Clad Damage x 100 Clad DamagecR (%) = x 100
- 17 Salem Common Page 24 of 82 Rev. 03
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ATTACHMENT 3 (Con't)
Page 2 of 5 CLAD DAMAGE ESTIMATE (STEP 5.1.4)
B. Estimate Fuel Rod Clad Damage Based on Core Exit Thermocouple (CET)
Readings STEP 3: ESTIMATE clad damage by using one of the following two (2) equations.
o ForRCS Pressure > 1600 psig, Clad Dam agecET (%) = Number of CETs > 1400OF x 100 Total Number of Operable CETs Clad DamagecET (%) = x 100 %
- 19 OR SFor RCS Pressure < 1600 psig, Clad DamagecET(%) =x Number of CETs > 1200°F 100 Total Number of Operable CETs Clad DamagecET (%) :1 x 100 =
- 19 Salem Common Page 25 of 82 Rev. 03
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ATTACHMENT 3 (Con't)
Page 3 of 5 CLAD DAMAGE ESTIMATE (STEP 5.1.4)
C. Estimate Fuel Rod Clad Damage Based on Dose Equivalent Iodine (DEI)
Readings STEP 4: ESTIMATE clad damage by using Figure 5, "Clad Damage Vs. Dose Equivalent Iodine, " in Attachment 5, "Figures For Section 5.1."
DElis:
Clad DamageDE (%) =%
- 20 Note: Figure5, "CladDamage Vs. Dose Equivalent Iodine," was createdfrom data found in Reference 6. Due to the very rough correlationbetween DEl and Clad Damage, the relatively small difference between the DEI in units of pCi/cc and units ofpCi/gm does not substantiallyimpact the estimated clad damage.
Salem Common Page 26 of 82 Rev. 03
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ATTACHMENT 3 (Con't)
Page 4 of 5 CLAD DAMAGE ESTIMATE (STEP 5.1.4)
D. Estimate Reasonableness of Clad Damage Estimates.
STEP 5: COMPARE current plant parameters to expected response by completing Table 5, "Current Vs. Expected Value Comparison Table," below.
Table 5: Current Vs. Expected Value Comparison Table Expected Response Containment H2 Level YES INO ?
Is < 0.5 volume %?
RVLIS Reading Is 44% < < 57%
Hot Leg RTD Temperature Is T... < < 650°F
- 9 #12 Source Range Monitor (SRM) Reading Is > 20,000 cps ?
- 13 Clad Damage Estimates
- 18 #19 Is x100 <50%
8 "Is the absolute value of f(% Clad DamagecR - % Clad DamagecET) /
% Clad Damagecpj x 100 < 50% ?"
Salem Common Page 27 of 82 Rev. 03
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ATTACHMENT 3 (Con't)
Page 5 of 5 CLAD DAMAGE ESTIMATE (STEP 5.1.4)
D. Estimate Reasonableness of Clad Damage Estimates (Continued)
STEP 6: For any "NO" responses in Table 5, DETERMINE if the deviation can be explained from the accident progression.
v/
Iniection of water to the RCS Bleed paths from the RCS Direct radiation to the containment radiation monitors Fuel bumup Fission product retention in the RCS Fission product removal from containment Conservatisms in the predictive model Other:
E. Trend and Report Findings STEP 7: RECORD estimated fuel pellet over-temperature damage in ATTACHMENT 6, "Core Damage Assessment Trending."
STEP 8: REPORT findings using guidance below.
- 1. If clad damage estimates have increased by more than 1% in the past 30 minutes or if estimates exceed 2% clad damage, report possible degradation of fission product barrier to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201 (Q).
- 2. Report core damage estimate to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201(Q)
STEP 9: RETURN to 5.1.2 or 5.2 and PERFORM another core damage assessment, as needed.
Salem Common Page 28 of 82 Rev. 03
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ATTACHMENT 4 Page 1 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
A. Estimate Fuel Pellet Over-Temperature Damage Based on Containment Radiation (CR) Levels STEP 1: DETERMINE the correct value of <CRM4> by using Figure 4, "Containment Radiation Level Vs. Time For 100% Fuel Over-Temperature Release," in Attachment 5, "Figures For Section 5.1," and RECORD in Table 6 below.
Table 6: Values of Containment Radiation Level Setpoint <CRM4>
- 14. Time After Rx #21. <CRM4>
Shutdown hrs R/hr STEP 2: ESTIMATE fuel pellet over-temperature damage by using the following equation.
Current Containment Radiation Level Predicted Containment Radiation Level at 100% Over - tempDamage
- 7 Fuel Pellet Over-temperature DamageCR (%) =
Salem Common Page 29 of 82 Rev. 03
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ATTACHMENT 4 (Con't)
Page 2 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
B. Estimate Fuel Pellet Over-Temperature Damage Based on Core Exit Thermocouple (CET) Readings STEP 3: ESTIMATE fuel pellet over-temperature damage by using the following equation.
Number of CETs > 2000 °F Over - Temp. DamageCET (%) -- x 100 Total Number of Operable CETs Over-Temperature DamageCET (%) =%
I#23 Salem Common Page 30 of 82 Rev. 03
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ATTACHMENT 4 (Con't)
Page 3 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
C. Estimate Fuel Pellet Over-Temperature Damage Based on Containment Hydrogen Level STEP: 4 DETERMINE the expected Containment H 2 Concentration at 100% Fuel Pellet Over-Temperature by using Table 7 below.
Table 7: Expected Containment Hydrogen Concentration At Various Conditions RCS Pressure Water Injection Predicted Containment psig to the RCS Hydrogen Concentration
No 25 volume%
RCS Pressure > 1050 psig Yes 75 volume %
No- 2 v.o..lu e %
The Expected Containment Hydrogen Concentration is %
STEP 5: ESTIMATE fuel pellet over-temperature damage by using the following equation.
zI10 Over-Temperature DamageHYDROGEN (%) = X 100 =
- 24 Salem Common Page 31 of 82 Rev. 03
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ATTACHMENT 4 (Con't)
Page 4 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
D. Estimate Reasonableness of Fuel Pellet Over-Temperature Damage Estimates.
STEP 6: COMPARE current plant parameters to expected response by completing Table 8 below.
Table 8: Current Vs. Expected Value Comparison Table Expected Response YES / NO ?
RVLIS Reading Is < 44%
- 11 Hot Leg RTD Temperature Is > 650°F
- 12 Source Range Monitor (SRM) Reading Is > 20,000 cps ?
- 13 Fuel Pellet Over-Temperature Damage Estimates
- 22 #23 Is x100 <50%
- 22 "Is the absolute value of[(% Over-Temp. DamagecR - % Over-Temp.
DamagecEm)/ % Over-Temp. Damagecpj x 100 < 50% ?"
(IaDle 1 Is continuea on the next page)
Salem Common Page 32 of 82 Rev. 03
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ATTACHMENT 4 (Con't)
Page 5 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
D. Estimate Reasonableness of Fuel Pellet Over-Temperature Damage Estimates (Continued).
Table 8 (Con't): Current Vs. Expected Value Comparison Table Expected Response YES I NO ?
Fuel Pellet Over-Temperature Damage Estimates Is % < 25%
- 22#25 "Is the absolute value of [(% Over-Temp. DamagecR - % Over-Temp.
DamageHYDROGEN) < 25% ?"
Fuel Pellet Over-Temperature Damage Estimates Is i % < 25%
- 23 #251 "is the absolute value of[(% Over-Temp. DamageCET- % Over-Temp.
DamageHYDROGEN) < 25% ?"
Salem Common Page 33 of 82 Rev. 03
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ATTACHMENT 4 (Con't)
Page 6 of 6 FUEL PELLET OVER-TEMPERATURE DAMAGE ESTIMATE (STEP 5.1.5)
D. Estimate Reasonableness of Clad Damage Estimates (Continued)
STEP 7: For any "NO" responses in Table 8, DETERMINE if the deviation can be explained from the accident progression.
F-Injection of water to the RCS Bleed paths from the RCS Direct radiation to the containment radiation monitors Hydrogen burn in containment or operation of hydrogen igniters Fuel burnup Fission product retention in the RCS Fission product removal from containment Conservatisms in the predictive model Other: i E. Trend and Report Findings STEP 8: RECORD estimated fuel pellet over-temperature damage in ATTACHMENT 6, "Core Damage Assessment Trending."
STEP 9: REPORT findings using guidance below.
- 1. If clad damage estimates have increased by more than 1% in the past 30 minutes or if estimates exceed 2% clad damage, report possible degradation of fission product barrier to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201 (Q).
- 2. Report core damage estimate to appropriate emergency response personnel as identified in NC.EP-EP.ZZ-0201(Q)
STEP 10: RETURN to 5.1.2 or 5.2 and PERFORM another core damage assessment, as needed.
Salem Common Page 34 of 82 Rev. 03
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ATTACHMENT 5 Page 1 of 5 FIGURES FOR SECTION 5.1 FIGURE 1: <CRM1>
"CONTAINMENT RADIATION LEVEL VS. TIME FOR RCS RELEASE" (Adapted from Figure 1 of Reference 1) 10 V
4J 0 1 (Ir 0
U 0
C) 0.1 0 5 10 15 20 25 30 35 40 45 50 Time Since Shutdown (hours)
Salem Common Page 35 of 82 Rev. 03
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ATTACHMENT 5 (Con't)
Page 2 of 5 FIGURES FOR SECTION 5.1 FIGURE 2: <CRM2>
"CONTAINMENT RADIATION LEVEL VS. TIME FOR 1% FUEL PELLET OVER-TEMPERATURE RELEASE" (Adapted from Figure 2 of Reference 1) 10,000 1,000 M 02 35 4--45 -50 U)
- 1 0
100 E
0m 0
C O
0, 4.
10 I
0 5 10 15 20 25 30 35 40 45 5 Timne Since Shutdown (hours)
(hours) i RCS Pressure > 1600 psig w/o Spray TimeShutdown Since SRCS Pressure > 1600 psig w/ Spray
-- t RCS Pressure < 1600 psig w/o Spray -- RCS Pressure < 1600 psig w/ Spray Salem Common Page 36 of 82 Rev. 03
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ATTACHMENT 5 (Con't)
Page 3 of 5 FIGURES FOR SECTION 5.1 FIGURE 3: <CRM3>
"CONTAINMENT RADIATION LEVEL VS. TIME FOR 100% CLAD DAMAGE RELEASE" (Adapted from Figure 3 of Reference 1) 100,000
~~10,000 ca
~,1,000 0
Q E
o 100 0.
10 0 5 10 15 20 25 30 35 40 45 50 Tine Since Shutdown (hours)
-.- RCS Pressure > 1600 psig w/o Spray . RCS Pressure > 1600 psig w/ Spray SRCS Pressure < 1600 psig w/o Spray 9
.- RCS Pressure < 1600 psig w/ Spray Salem Common Page 37 of 82 Rev. 03
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ATTACHMENT 5 (Con't)
Page 4 of 5 FIGURES FOR SECTION 5.1 FIGURE 4: <CRM4>
"CONTAINMENT RADIATION LEVEL VS. TIME FOR 100% FUEL OVER-TEMPERATURE RELEASE" (Adapted from Figure 4 of Reference 1) 1,000,000 100,000 0
S10,000 ' ,.
S10,000 N!
10 I F 100 I I t t J I i i I i , -,, , L , ; ; W I 0 5 10 15 20 25 30 35 40 45 50 Time Since Shutdown (hours)
.RCS Pressure > 1600 psig w/o Spray . RCS Pressure > 1600 psig w/ Spray
.... RCS Pressure < 1600 psig w/o Spray -. 9 RCS Pressure < 1600 psig w/ Spray Salem Common Page 38 of 82 Rev. 03
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ATTACHMENT 5 (Con't)
Page 5 of 5 FIGURES FOR SECTION 5.1 FIGURE 5: "CLAD DAMAGE VS. DOSE EQUIVALENT IODINE (DEI)"
100 95 90 85 80 DEI % Damage 75 1. 0.01 300. 2.8 70 2143. 20.
65 10715 100.
60 y = 0.009332x + 0.000478 E) 55 From DSI1. 6-0098 (Ref 6.6) 50 EI 0t 45 -j I I
40 - -I I
35 30
___ -- I 25 20 15
__j i 10 5
0 1 10 100 1000 10000 100000 DEI (,Ci/cc or pCi/gram)
Salem Common Page 39 of 82 Rev. 03
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ATTACHMENT 6 Page 1 of 1 CORE DAMAGE ASSESSMENT TRENDING Time Estimated Clad Estimated Fuel Damage Over-Temperature Damage
.4- 4 i i Salem Common Page 40 of 82 Rev. 03
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ATTACHMENT 7 Page 1 of I WATER DENSITY RATIO (TEMPERATURE VS. P)
PSTP (Figure 2-10 of Reference 2) 800 700 600 U- 500 0)
.=400 E
E300 200 100 0
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 p
PSTP Salem Common Page 41 of 82 Rev. 03
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ATTACHMENT 8 Page 1 of 1 POWER CORRECTION FACTOR FOR CS-134 BASED ON AVERAGE POWER DURING OPERATION (Figure 2-1 of Reference 2) 1 0.9 S**- 90% Power 0.8 L.
0 0.7 U.
L) r., 75% Power 0.6 0
0.5 U
IL a) 0.4 I,.
0.3 n) 0.2 5- o.P 0.1 0 S I I I I ', ________________________________
0 200 400 600 800 1000 Cycle Operation (Calendar Days)
Salem Common Page 42 of 82 Rev. 03
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ATTACHMENT 9 Page 1 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES As previously stated in Step 5.2.5.1, the Chemistry Department normally delivers the isotopic data decay-corrected as standard practice. Ifthe isotopic data is not decay-corrected, two methods are used to accomplish this. See Section 2.4.5.3 "Decay Correction" (Reference
- 2) for a more detailed discussion of this methodology.
Method 1 For the following isotopes, parent-daughter relationships need not be accounted for.
1-131 Kr-85m Cs-1 34 Sr-89 1-133 Kr-87 Cs-1 37 Sr-90 1-135 Kr-88 Te-1 32 Ba-140 Use the following equation and table to calculate the decay-corrected specific activities for each sample and list them in the appropriate "Decay-Corrected Activities" page at the end of this attachment Note: 1 cc = 1 ml A0= A e-At where:
A = measured specific activity, (pCi/gm) or (ýtCi/cc) ki = decay constant of isotope i, (sec"1) t = time elapsed from reactor shutdown to time of sampling (sec)
A0 = specific activity at shutdown, (pCi/gm) or (pCi/cc)
Constants Required for Method 1 ISOTOPE T 1 /2 k (sec 1 )
1-131 8.05 d 9.966E-7 1-133 20.3 h 9.485E-6 1-135 6.68 h 2.882E-5 Kr-85m 4.4 h 4.376E-5 Kr-87 76 m 1.520E-4 Kr-88 2.8 h 6.876E-5 Cs-134 2y 1.098E-8 Cs-1 37 30 y 7.322E-10 Te-132 77.7 h 2.478E-6 Sr-89 52.7 d 1.522E-7 Sr-90 28 y 7.845E-10 Ba-140 12.8 d 6.268E-7 (Adapted from Table 2-1 of Reference 2)
Salem Common Page 43 of 82 Rev. 03
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ATTACHMENT 9 (Con't.)
Page 2 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Method 2 For the following isotopes, parent-daughter relationships do need to be taken into consideration.
1-132 Xe-133 Pr-144 Xe-1 31 m Xe-1 35 Xe-1 33m Te-1 29 Use the following equations and tables to calculate the decay-corrected specific activities for each sample and list them in the appropriate "Decay-Corrected Activities" page at the end of this attachment.
- 1. Calculate the hypothetical daughter concentration (QB) at the time of the sample analysis assuming 100 percent release of the parent and daughter source inventory.
QB(t) = =k B XAB .QA e- BtQoe QoA(e -^- _ e )+Qoe -ABt A'B -- )A Where, QA0 = 100% source inventory (Ci) of parent (Ref. 2, Table 2-2 or 2-8)
QB° = 100% source inventory (Ci) of daughter (Ref. 2, Table 2-2 or 2-8)
QB(t) = hypothetical daughter activity (Ci) at sample time k = if parent has 2 daughters, k is the branching factor (Ref. 2, Table 2-7) kA= parent decay constant (sec-1 )
,B = daughter decay constant (sec-)
t = time period from shutdown to time of sample (sec)
- 2. Determine the contribution of only the decay of the initial inventory of the daughter to the hypothetical daughter activity at sample time.
Fr = Q- "e-ABt Q8 (t)
Where:
Fr = fraction of daughter activity at sample time due to the decay of only the daughter initial activity Salem Common Page 44 of 82 Rev. 03
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ATTACHMENT 9 (Con't.)
Page 3 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES
- 3. Calculate the amount of the measured sample specific activity associated with the decay of the daughter that was released.
MB =MxFr Where:
M = measured specific activity (ptCi/gm) or (ýiCi/cc)
MB = parent-daughter compensated activity (ýLCi/gm) or (p.Ci/cc)
- 4. Decay correct the specific activity to reactor shutdown and list it in the appropriate "Decay-Corrected Activities" page at the end of this attachment.
M0 MB B eABt Where, Ms° = decay corrected specific activity Constants Required for Method 2:
Daughter T 1/ 2 k (sec1 ) Parent T1 /2 (sec) X (sec 1 )
1-132 2.26 h 8.520E-05 Te-132 77.7 h 2.478E-06 Xe-131m 11.8 d 6.799E-07 1-131 8.05 d 9.966E-07 Xe-1 33m 2.26 d 3.550E-06 1-133 20.3 h 9.485E-06 Xe-1 33 5.27 d 1.522E-06 1-133 20.3 h 9.485E-06 Xe-1 35 9.14 h 2.107E-05 1-135 6.68 h 2.882E-05 Te-129 68.7 m 1.682E-04 Sb-129 4.3 h 4.478E-05 Pr-144 17.27 m 6.689E-04 Ce-1 44 284 d 2.825E-08 (Adapted from Table 2-7 of Reference 2)
Daughter Parent 100% Daughter 100% Parent K Inventory Inventory 0
QB (Ci) QA0 (Ci) 1-132 Te-132 1.4E8 1.4E8 1.0 Xe-131 m 1-131 6.3E5 9.8E7 0.008 Xe-133m 1-133 2.8E7 2.0E8 0.024 Xe-1 33 1-133 2.0E8 2.0E8 0.976 Xe-135 1-135 3.7E7 1.8E8 0.700 Te-129 Sb-129 3.3E7 3.2E7 0.827 Pr-144 Ce-144 1.2E8 1.1E8 1.0 (Adapted from Tables 2-2, 2-7, and 2-8 of Reference 2)
Salem Common Page 45 of 82 Rev. 03
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ATTACHMENT 9 (Con't.)
Page 4 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Decay Corrected Activities - RCS Sample 1-131 =
1-132 =
1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-1 31m =
Xe-133m =
Xe-1 33 =
Xe-135 =
Cs-134 =
Cs-137 =
Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 46 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 9 (Con't.)
Page 5 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Decay Corrected Activities - Sump Sample 1-131 =
1-132 =
1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-1 31m =
Xe-1 33m =
Xe-133 =
Xe-135 =
Cs-134 =
Cs-137 =
Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 47 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 9 (Con't.)
Page 6 of 6 DECAY-CORRECTION OF ISOTOPIC DATA FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Decay Corrected Activities - Con't Atmosphere Sample 1-131 =
1-132 =
1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-131m =
Xe-133m =
Xe-133 =
Xe-135 =
Cs-134 =
Cs-137 Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 48 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 10 Page 1 of 4 PRESSURE AND TEMPERATURE-CORRECTION FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES RCS and Sump Samples Use the following equation to pressure- and temperature-correct the activities of the RCS or sump sample and list them in the appropriate "Pressure/Temperature/Decay-Corrected Activities" page at the end of this attachment. See Section 2.4.5.2 "Pressure and Temperature Adjustment" (Reference 2) for a more detailed discussion of this methodology.
ApP-= A. x PSTP Where, A0 = decay-corrected specific activity APTC = decay-pressure-temperature corrected specific activity P - water density ratio at RCS or sump temperature taken from Attachment 6.
PSTP Containment Atmosphere Sample Use the following equation to pressure- and temperature-correct the activities of the containment atmosphere sample and list them in the appropriate "PressurefTemperature Decay-Corrected Activities" page at the end of this attachment.
XT, +460 APTC =A(pT2P2 ApTC~P +460)
Where, T1 , P1 = measured sample temperature (OF) and pressure (psia)
T 2 , P 2 = containment atmosphere temperature (OF) and pressure (psia)
A0 = decay-corrected specific activity APTC = decay-pressure-temperature corrected specific activity Salem Common Page 49 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 10 Page 2 of 4 PRESSURE AND TEMPERATURE-CORRECTION FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Pressure/Temperature/Decay Corrected Activities (RCS SampIe) 1-131 =
1-132 1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-1 31m =
Xe-1 33m =
Xe-133 =
Xe-1 35 =
Cs-134 =
Cs-137 =
Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 50 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 10 Page 3 of 4 PRESSURE AND TEMPERATURE-CORRECTION FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Pressure/Temperature/Decay Corrected Activities (Sump Sample) 1-131 =
1-132 =
1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-131m =
Xe-1 33m =
Xe-1 33 =
Xe-1 35 =
Cs-134 =
Cs-137 =
Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 51 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 10 Page 4 of 4 PRESSURE AND TEMPERATURE-CORRECTION FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES PressurelTemperaturelDecay Corrected Activities (Containment Atmosphere Sample) 1-131 =
1-132 =
1-133 =
1-135 =
Kr-85m =
Kr-87 =
Kr-88 =
Xe-1 31m =
Xe-1 33m =
Xe-133 =
Xe-135 =
Cs-134 =
Cs-137 =
Te-129 =
Te-132 =
Sr-89 =
Sr-90 =
Ba-140 =
Pr-144 =
Additional Isotopes For Core Damage Assessment Salem Common Page 52 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 11 Page 1 of 3 TOTAL ACTIVITY RELEASED FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES RCS Sample Corrected Specific Total RCS Isotope Activity RCS Mass Activity (pCi/g) (grams) (PCi) 1-131 x 1-132 x 1-133 x 1-135 x Kr-85m x Kr-87 x Kr-88 x Xe-131m x Xe-1 33m x Xe-1 33 x Xe-1 35 x Cs-1 34 x Cs-1 37 x Te-129 x Te-132 x Sr-89 x Sr-90 x Ba-140 x Pr-144 x x
x x
x x
x x
Salem Common Page 53 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 11 (Con't.)
Page 2 of 3 TOTAL ACTIVITY RELEASED FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Sump Sample Corrected Specific Total Sump Isotope Activity Sump Mass Activity (pCi/g) (grams) (PCi) 1-131 x 1-132 x 1-133 x 1-135 x Kr-85m x Kr-87 x Kr-88 x Xe-1 31 m x Xe-1 33m x Xe-1 33 x Xe-1 35 x Cs-1 34 x Cs-1 37 x Te-129 x Te-132 x Sr-89 x Sr-90 x Ba-140 x Pr-144 x x
x x
x x
x x
Salem Common Page 54 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 11 (Con't.)
Page 3 of 3 TOTAL ACTIVITY RELEASED FOR RCS, SUMP, AND CONTAINMENT ATMOSPHERE SAMPLES Containment Atmosphere Sample Corrected Specific Sample Medium Total Con't.
Isotope Activity Mass or Volume Atmos. Activity (pCi/cc) (cc's) (Pci) 1-131 x 1-132 x 1-133 x 1-135 x Kr-85m x x
x Kr-87 X Kr-88 X X
Xe-1 31 m x xX Xe-1 33m xx Xe-1 33 x
Xe-1 35 x
Cs-1 34 x x
Cs-1 37 x
Te-129 x
Te-132 x
Sr-89 x
Sr-90 x xX Ba-140 Pr-144 x x
x x
x X
X x
Salem Common Page 55 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 12 Page 1 of 1 TOTAL ACTIVITY RELEASED FOR ALL SAMPLES COMBINED Total RCS Total Sump Total Con't Total Isotope Activity Activity Atmos. Activity (pCi) (pCi) (pCi) (pCi)
+
1-131 +
+ +
1-132
+ +
1-133
+ +
1-135
+ +
Kr-85m
+ +
Kr-87
+ +
Kr-88
+
Xe-1 31 m +
Xe-1 33m +
+
m mm+m Xe-1 33 + - m-
- m m- -m
+
- - -- - - -m-Xe-1 35 -- - - -
+
- - - -+
+
Cs-1 34 - - - - - - - - - - - -
+
-- - - - - - - -+
+
- m- -m - m-
- - -mm Te-129 -- - - -
+
- - - -+
Te-132 -m - - m- - -mm - - -m
+
-- - - - - - - -+
+
Sr-89 m mm+m
-- - - - - - - -+
+
Sr-90 +
- -m m m -m m m -m - m- - - mm- - - m
+
Ba-140 -- - - - - - - -+
+ +
Pr-144 -- - - - - - - - -+
-I m m m m
+ +
+ +
m m+m m
+
+
+
Salem Common Page 56 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 13 Page 1 of 2 POWER CORRECTIONS FACTORS FOR:
KR-85M, KR-87, KR-88, XE-135, 1-132, 1-133,1-135, TE-129, PR-144 A. Has prior 4 days power varied more than +/- 10% Rated Thermal Power?
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
4 Days (%)
PCF = Average Power For Prior 100 where, PCF = Power Correction Factor YES: Go to Part B.
B. Is the total operating history greater than 4 times the half life of the isotope of interest?
(See table of half-lives and decay constants at end of this attachment).
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
p(1_ e-"i )e-9° P-*
PCF 1001 where, tj= Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj= Average power (%) during operating period (tj) j= The number of times that power has varied more than +
10% in the previous 4 days X= Decay constant (days 1 )
t= Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Salem Common Page 57 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 13(Con't.)
Page 2 of 2 POWER CORRECTIONS FACTORS FOR:
KR-85M, KR-87, KR-88, XE-135, 1-132, 1-133, 1-135, TE-129, PR-144 YES: Calculate the power correction factor using the following equation and record it in Attachment 17.
- pj (1 - e-* e*
PCF 100(1.0) where, tj = Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj= Average power (%) during operating period (tj) j= The number of times that power has varied more than +/-
10% in the previous 4 days Ak= Decay constant (days 1) t= Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Half-Lives and Decay Constants for Isotopes Isotope Half-Life Decay (Days) Constant (Days 1) 1-131 8.05 8.61E-2 1-132 9.42E-2 7.36 1-133 8.46E-1 8.19E-1 1-135 2.78E-1 2.49 Kr-85m 1.83E-1 3.79 Kr-87 5.28E-2 1.31 El Kr-88 1.17E-1 5.92 Xe-131m 1.18E1 5.87E-2 Xe-133m 2.26 3.07E-1 Xe-133 5.27 1.32E-1 Xe-135 3.81E-1 1.82 Cs-134 7.30E2 9.50E-4 Cs-137 1.10E4 6.30E-5 Te-129 4.77E-2 1.45E1 Te-132 3.24 2.14E-1 Sr-89 5.27E1 1.32E-2 Sr-90 1.02E4 6.80E-5 Ba-140 1.28E1 5.42E-2 Pr-144 1.20E-2 5.78E1 Salem Common Page 58 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 14 Page 1 of 2 POWER CORRECTIONS FACTORS FOR:
XE-131M, XE-133, XE-133M, 1-131, TE-132, BA-140 A. Has prior 30 days power varied more than +/- 10% Rated Thermal Power?
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
(%)
PCF = Average Power For Prior 30 Days 100 where, PCF = Power Correction Factor YES: Go to Part B.
B. Is the total operating history greater than 4 times the half life of the isotope of interest?
(See table of half-lives and decay constants at end of this attachment).
NO- Calculate the power correction factor using the following equation and record it in Attachment 17.
p(1j - e-21i )e-%° Pj 0 PCF = 1X T~i 100(1_ eAZt, where, tj= Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj= Average power (%) during operating period (tj) j= The number of times that power has varied more than +/- 10% in the previous 30 days A= Decay constant (days-1) t= Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Salem Common Page 59 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 14 (Con't.)
Page 2 of 2 POWER CORRECTIONS FACTORS FOR:
XE-131M, XE-133, XE-133M, 1-131, TE-132, BA-140 YES: Calculate the power correction factor using the following equation and record it in Attachment 17.
"pi (1 _e-m, )e-%tj PCF = 1 100(1.0) where, tj= Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj = Average power (%) during operating period (tj) j= The number of times that power has varied more than +/- 10% in the previous 30 days A= Decay constant (days-1 )
t= Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Half-Lives and Decay Constants for Isotopes Isotope Half-Life Decay (Days) Constant (Days"1 )
1-131 8.05 8.61E-2 1-132 9.42E-2 7.36 1-133 8.46E-1 8.19E-1 1-135 2.78E-1 2.49 Kr-85m 1.83E-1 3.79 Kr-87 5.28E-2 1.31 El Kr-88 1.17E-1 5.92 Xe-131m 1.18E1 5.87E-2 Xe-1 33m 2.26 3.07E-1 Xe-133 5.27 1.32E-1 Xe-135 3.81E-1 1.82 Cs-1 34 7.30E2 9.50E-4 Cs-137 1.10E4 6.30E-5 Te-129 4.77E-2 1.45E1 Te-132 3.24 2.14E-1 Sr-89 5.27E1 1.32E-2 Sr-90 1.02E4 6.80E-5 Ba-140 1.28E1 5.42E-2 Pr-144 1.20E-2 5.78E1 Salem Common Page 60 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 15 Page 1 of 1 POWER CORRECTIONS FACTORS FOR:
SR-90, CS-134, CS-137 A. Is Cs-134 the isotope of interest?
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
Date PCF =Actual Number of "Effective Full Power Days" in Cycle To Expected Number of "Effective Full Power Days" in Cycle To Date where, PCF = Power Correction Factor YES: Use Attachment 8 to obtain the Power Correction Factor and record it in Attachment 17.
Salem Common Page 61 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 16 Page 1 of 2 POWER CORRECTIONS FACTORS FOR:
SR-89 A. Has prior 1 year power varied more than +/- 10% Rated Thermal Power?
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
(%)
PCF = Average Power For Prior 100 Days 100 where, PCF = Power Correction Factor YES: Go to Part B.
B. Is the total operating history greater than 4 times the half life of the isotope of interest?
(See table of half-lives and decay constants at end of this attachment).
NO: Calculate the power correction factor using the following equation and record it in Attachment 17.
>, Pj( _ e-PCF = 1 100(1 - e_
where, tj= Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj= Average power (%) during operating period (ti) j= The number of times that power has varied more than +/- 10% in the previous 1 year A= Decay constant (days-1) t= Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Salem Common Page 62 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 16 Page 2 of 2 POWER CORRECTIONS FACTORS FOR:
SR-89 YES: Calculate the power correction factor using the following equation and list it in Attachment 17.
PCFL1P1 (1-e xj 100(1.0) where t, = Operating period in days at power (Pj) where power does not vary more than +/- 10% from the time averaged power (Pj)
Pj = Average power (%) during operating period (ti) j = The number of times that power has varied more than +/- 10% in the previous 1 year Xk = Decay constant (days-1 )
to = Time between end of period "j" and time of reactor shutdown in days PCF = Power Correction Factor Half-Lives and Decay Constants for Isotopes Isotope Half-Life Decay (Days) Constant (Days 1) 1-131 8.05 8.61E-2 1-132 9.42E-2 7.36 1-133 8.46E-1 8.19E-1 1-135 2.78E-1 2.49 Kr-85m 1.83E-1 3.79 Kr-87 5.28E-2 1.31 E1 Kr-88 1.17E-1 5.92 Xe-131m 1.18E1 5.87E-2 Xe-1 33m 2.26 3.07E-1 Xe-133 5.27 1.32E-1 Xe-135 3.81E-1 1.82 Cs-134 7.30E2 9.50E-4 Cs-137 1.10E4 6.30E-5 Te-129 4.77E-2 1.45E1 Te-132 3.24 2.14E-1 Sr-89 5.27E1 1.32E-2 Sr-90 1.02E4 6.80E-5 Ba-140 1.28E1 5.42E-2 Pr-144 1.20E-2 5.78E1 Salem Common Page 63 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 17 Page 1 of I ISOTOPIC INVENTORY AVAILABLE FOR RELEASE Source Inventory Power Inventory Isotope Table 2-2, Ref. 2 Correction Available For (Ci) Factor Release (Ci) 1-131 9.8E7 x 1-132 1.4E8 x 1-133 2.0E8 x 1-135 1.8E8 x Kr-85m 2.2E7 x Kr-87 4.0E7 x Kr-88 5.7E7 x Xe-1 31m 6.3E5 x Xe-1 33m 2.8E7 x Xe-1 33 2.0E8 x Xe-1 35 3.7E7 x Cs-1 34 2.3E7 x Cs-137 1.1E7 x Te-129 3.3E7 x Te-132 1.4E8 x Sr-89 7.9E7 x Sr-90 7.2E6 x Ba-140 1.7E8 x Pr-1 44 1.2E8 x x
x x
x x
x x
Salem Common Page 64 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 18 Page 1 of 1 PERCENT INVENTORY RELEASED FOR EACH ISOTOPE A. Copy the "Total Activity" from Attachment 11 (for one sample medium) or Attachment 12 (for several sample media) and the "Inventory Available for Release" from Attachment 17 into the table below.
B. Calculate the "Percent Inventory Released" using the following equation and list it in the table below.
Total Activity x ( )lE6 pCiI)
% Inventory Released = x 100 Inventory Avaliable For Release Total Inventory Isotope Activity Available For % Inventory (pCi) Release (Ci) Released (Attachment 11/12) (Attachment 17) 1-131 1-132 1-133 1-135 Kr-85m Kr-87 Kr-88 Xe-131m Xe-1 33m Xe-1 33 Xe-1 35 Cs-1 34 Cs-1 37 Te-129 Te-132 Sr-89 Sr-90 Ba-140 Pr-144 Salem Common Page 65 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 19 Page 1 of 2 CORE DAMAGE ASSESSMENT (BASED ON INVENTORY)
Take each percent inventory released from Attachment 18 and compare it to the appropriate figures in Attachment 20. Record the extent and type of damage in the following table. The figures are taken from Reference 2.
Clad Damage Isotope Percent Inventory Estimated Clad Damage Released 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Kr-87 Fuel Pellet Over-temperature Estimates Isotope Percent Inventory Estimated Clad Damage Released 1-131 1-132 1-133 1-135 Xe-1 31m Xe-1 33 Xe-1 33m Xe-135 Kr-85m Kr-87 Kr-88 Cs-1 34 Cs-1 37 Te-129 Te-132 Salem Common Page 66 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 19 Page 2 of 2 CORE DAMAGE ASSESSMENT (BASED ON INVENTORY)
Fuel Pellet Over-temperature Estimates Isotope Percent Inventory Estimated Clad Damage Released Ba-1 40 Sr-89 Sr-90 Fuel Melt Estimates Isotope Percent Inventory Estimated Clad Released Damage 1-131 1-132 1-133 1-135 Xe-1 31 m Xe-1 33 Xe-1 33m Xe-135 Kr-85m Kr-87 Kr-88 Cs-1 34 Cs-1 37 Te-129 Te-132 Ba-1 40 Sr-89 Sr-90 Pr-144 Salem Common Page 67 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 Page 1 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE 1-131 I
0.1 a)
W 0.01
_I, (U
0 0.001 0
L) 0.0001 0.00001 0.1 I 10 100 Clad Damage (%)
Salem Common Page 68 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 2 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE 1-132 0.1
________ - I- - ________ - - t "I i 0
0.01 U) nu -".4--- *-LowBurnu O
om.
00 0.001 76 0
U 0.0001
___I -- Average IN
--High Burnup
!1 0_9 0.00001 0.1 I 10 100 Clad Damage (%)
Salem Common Page 69 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 3 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRAT1ON VS. INDICATION OF CLAD DAMAGE 1-133 1
I 0.1 U,
F 01 0
Cu 0 0 0 0 a)
___e 0.01 a) z 0 -I 0.001 a) - --- - !
- i{
a)
L.
00 , IA -! -- Low I"
" Burnup 0 0.0001 0 * ---- Average
.* * --- High
- Burnup 0.00001 0.1 1 10 100 Clad Damage (%)
Salem Common Page 70 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 4 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE 1-135 1
0.1 0
0.01
'I (0
0 0.001 0
0.0001 0.00001 0.1 1 10 100 Clad Damage (%)
Salem Common Page 71 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 5 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE XE-131M I
I I1 I 1 1 I Low Burnup
-Average "0
-High Burnup 0.1 1' -_I 0
0.01 0 7 17P
____ fzh 0.001 0.1 1 10 100 Clad Damage (%)
Salem Common Page 72 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 6 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE XE-1 33 I
0.1 a) 0.01 0.001 0.1 1 10 100 Clad Damage (%)
Salem Common Page 73 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 7 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF CLAD DAMAGE KR-87 0.1 II I } I I i
-- *Low Burnup 1 11 I 1T1
-- Average 0.01 - -High Burnup "C) ! _W11 W
(n 0.001
___,_ I _
_ _ _ O
_ _ _ 00 0 0.0001 ____0 01~LL 0 __
_---ii]I
__0
- t- - - _____________i1i 0.00001 0.1 1 10 100 Clad Damage (%)
Salem Common Page 74 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 8 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF FUEL PELLET OVER-TEMPERATURE DAMAGE XE, KR, I, or CS 100 1 I1 j I a) 10 0 ,00
-i 01ýý1
_____ _____ 77 * - High urnu 0 _________1__ _ _ _ _
, - - *Low Burnup
.10_____________________________
____________________~1000 I1 0
0.
I 10 100 Fuel Overtemperature Damage (%)
Salem Common Page 75 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 9 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF FUEL PELLET OVER-TEMPERATURE DAMAGE BA or SR 1
4.-
__________ ' - -1 ---
0.1 Cu "0
0 -- Low Burnup 0 P0.001 _____ _ -- Average
,I -- v rgBurnup
-High
'i -Hg Bru 0.0001 1 10 100 Fuel Overtemperature Damage (%)
Salem Common Page 76 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 10 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF FUEL MELT DAMAGE XE, KR, I, CS, or TE 100 10 0) 0 0
1 _____- ___' -- - . Low Burnup z yz:z Average
-High Burnup 1.... ...L.
0.1 __ _ __ _ _ _ _ _ I ___I - I 1 10 100 Fuel Melt Damage (%)
Salem Common Page 77 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 11 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF FUEL MELT DAMAGE BA or SR 100 0
0 10 0) 7a)
Cu 1
0 0
0.1 0.01 1 10 100 Fuel Melt Damage (%)
Salem Common Page 78 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 20 (Con't)
Page 12 of 12 FIGURES USED IN SECTION 5.2 ISOTOPIC CONCENTRATION VS. INDICATION OF FUEL MELT DAMAGE PR 100 10 I -___
0.10-0 00 O 0.01"*
- verag
- 0) 10 0.001 0.01 oFe Fue Mlt Mel Daam -averg A verage Salem Common Page 79 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 21 Page 1 of 1 ISOTOPIC ACTIVITY RATIOS OF FUEL PELLET AND GAP Nuclide Fuel Pellet Activity Ratio Gap Activity Ratio Kr-85m 0.11 0.022 Kr-87 0.22 0.022 Kr-88 0.29 0.045 Xe-1 31 m 0.004 0.004 Xe-1 33 1.0 1.0 Xe-1 33m 0.14 0.096 Xe-1 35 0.19 0.051 1-131 1.0 1.0 1-132 1.5 0.17 1-133 2.1 0.71 1-135 1.9 0.39
- Adapted from "Isotopic Activity Ratios of Fuel Pellet and Gap" Table 2-6 of Reference 2 Noble Gas Isotope Inventory Noble Gas Ratio Xe - 133 Inventory Iodine Isotope Inventory Iodine Ratio =
I - 131 Inventory If Calculated Ratio is: Postulated Damage Less Than the Gap Activity Ratio None Greater Than the Gap Activity Ratio and Clad Damage Less Than the Fuel Pellet Activity Ratio Greater Than the Fuel Pellet Activity Ratio Fuel Pellet Over-temperature Note:
The use of these ratios for post accident damage assessment is restricted to an attempt to differentiate between fuel pellet over-temperature conditions and fuel cladding failure conditions only.
Salem Common Page 80 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 22 Page 1 of 1 DOSE EQUIVALENT IODINE (DEI)
CLAD DAMAGE VS. DEI 100 90 80 70 0
60 E 50 0) 40 I N 30 20 10
-0__00 0
1 10 100 1000 10000 100000 DEI (ý Cilcc or P Ci/gm)
Note:
This figure was created from data found in Reference 6. Due to the very rough correlation between DEI and Clad Damage, the relatively small difference between the DEl in units of ipCi/cc and units of ýtCi/gm does not substantially impact the estimated clad damage.
Salem Common Page 81 of 82 Rev. 03
SC.EP-EP.ZZ-0205(Q)
ATTACHMENT 23 Page 1 of 1 FINAL CORE DAMAGE ASSESSMENT BASED ON ISOTOPIC INVENTORIES AND NOBLE GAS & IODINE RATIOS Salem Common Page 82 of 82 Rev. 03
PSEG Internal Use Only PSEG NUCLEAR LLC Page 1 of 1 NC.EP-EP.ZZ-0203 (Q) Rev. 04 ADMINISTRATIVE SUPPORT/COMMUNICATION TEAM RESPONSE - TSC USE CATEGORY: II REVISION
SUMMARY
- Biennial Review Yes X No Attachment 1 and 4 revised to have more detailed steps.
Added a new attachment containing guidelines for classification and PAR upgrades titled, Attachment 6, Classification Guidelines.
Added a new step (5.1.6) directing implementation of the newly developed Attachment 6, Classification Guidelines.
Added a new step for the Emergency Preparedness Advisor (EPA) to designate Ops Advisor to obtain OSC Priorities. This responsibility has been removed from the Admin staff member supporting the EDO, to the Ops Advsior.
IMPLEMENTATION REQUIREMENTS Effective Date /K- .5/-Zi,:
C03;Y -4'-
K i APPROVED: En P r E meronyPel]aens s Manager n b-'7-c_
Date APPROVED: "//D7 3
/Date
NC.EP-EP.ZZ-0203(Q)
ADMINISTRATIVE SUPPORT/COMMUNICATION TEAM RESPONSE - TSC TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS .................................................................... 1 1.0 P U R P O S E ................................................................................................. .. 2 2.0 P R E R EQ UIS IT ES ........................................................................................ 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure ....... 2 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 2 3.1 Emergency Staffing/Relief ..................................................................... 2 4.0 EQ UIPM ENT REQ UIRED ........................................................................... 2 5 .0 P R O C E D U R E ........................................................................................... . . 2 5.1 Administrative Support Supervisor and Emergency Preparedness Advisor (TSC1/TSC2 until arrival of the ADMSS/EPA) Duties ............... 2 6 .0 R E C O R D S .................................................................................................. . . 3 6.1 The Administrative Support Supervisor Should Ensure The Following ...... 3 7 .0 R E F E R E NC E S ........................................................................................... .. 3 7 .1 R e fe re n ce s .......................................................................................... . . 3 7.2 C ross R eferences ................................................................................ ..3 ATTACHMENTS ATTACHMENT 1- ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST... 4 ATTACHMENT 2- EMERGENCY PREPAREDNESS ADVISOR (EPA) CHECKLIST ..... 9 ATTACHMENT 3- EMERGENCY RESPONSE TEAM - TELECOPY LOG ..................... 11 ATTACHMENT 4- ONSITE SHIFT RELIEF SCHEDULE MANNING CHART ................ 12 ATTACHMENT 5- EDO CLERK GUIDELINES .............................................................. 16 ATTACHMENT 6- CLASSIFICATION GUIDELINES ...................................................... 17 Nuclear Common Page 1 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q) 1.0 PURPOSE To provide direction for the emergency actions of the Administrative Support Supervisor (ADMSS), Administrative Support Team, Emergency Preparedness Advisor (EPA), and Communications Team in the Technical Support Center (TSC).
2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 An emergency has been declared at Salem or Hope Creek Nuclear Generating Station and the TSC is required to be staffed or activated.
2.1.2 Precautionary staffing has been initiated due to management decision.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Emergency StaffingIRelief:
3.1.1 It is expected the two duty TSC Communicators will implement this procedure until the arrival of the ADMSS or EPA. Upon arrival, the ADMSS and EPA are expected to continue with implementation of this procedure.
3.1.2 The Administrative Support Supervisor (ADMSS) in the Technical Support Center (TSC) should coordinate the assessment and completion of minimum staffing of the Emergency Response Facilities (ERFs) with the Administrative Support Manager (ASM) in the Emergency Operations Facility (EOF).
3.1.3 After completion of initial staffing, the ADMSS and ASM should begin to assess and arrange relief staffing in order to continue 24-hour minimum staffing of ERFs.
4.0 EQUIPMENT REQUIRED As provided in the Emergency Response Facility.
5.0 PROCEDURE 5.1 Administrative Support Supervisor and Emergency Preparedness Advisor (TSCI/TSC2 until arrival of the ADMSS/EPA) Duties 5.1.1 INFORM Emergency Duty Officer of arrival and when prepared to assume functional duties.
5.1.2 DIRECT staff to verify operation of the following:
A. Telephone lines, telecopiers, and reprographic equipment are in working condition.
Nuclear Common Page 2 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
B. Check SPDS time and change clocks in the facility as appropriate (clock instructions are hanging near the wall clock), inform the EDO this has been done.
5.1.3 COORDINATE with the ASM in the EOF bringing in additional support personnel needed to staff (TSC/OSC).
5.1.4 ADMSS to IMPLEMENT Attachment 1 of this procedure.
5.1.5 EPA to IMPLEMENT Attachment 2 of this procedure.
5.1.6 IMPLEMENT Attachment 6, Classification Guidelines, anytime conditions requiring Event Classification or PAR Upgrades surface.
6.0 RECORDS 6.1 The Administrative Support Supervisor Should Ensure The Following 6.1.1 All written communications and documentation produced during an emergency are important for recording actions taken and reconstruction of events and should not be discarded.
6.1.2 The ADMSS should ensure that TSC Administrative Support Team captures and controls all material received and generated throughout the emergency including all logbooks and original data forms. Attachment 3, Emergency Response Team - Telecopy Log, should be used for all data sent or received over the emergency telecopier network.
6.1.3 All attachments, forms, appendices, and logs are to be retained in accordance with NAP-1 and sent to the Emergency Preparedness Manager, who will ensure all materials are retained.
7.0 REFERENCES
7.1 References 7.1.1 PSEG Nuclear Emergency Plan 7.2 Cross-References 7.2.1 Emergency Response Callout/Personnel Recall EPIP 204H(C) 7.2.2 Emergency Response Callout/Personnel Recall EPIP 204S(C)
Nuclear Common Page 3 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT I Page 1 of 5 ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST 1.0 Prior to Activation of the Facility: Initials DESIGNATE responsibilities to the Administrative Support Team upon arrival to assist with the following items:
"o Faxing/logging/copying/distribution "o Assist in updating status boards "o Emergency Duty Officer's clerk (initiate and maintain EDO's log book).
PROVIDE a copy of Attachment 5 "EDO Clerk Guidelines" of this procedure to designated person.
NOTE:
Reference RED staffing checklist (found in telecopier transmittal book on Admin desk) to be aware of what procedures/attachments will be asked for upon arrival of other ERO members.
VERIFY computer/phone equipment in the facility are working properly by testing or asking the groups in the facility. Contact the EOF Admin Support Manager to report any computer/phone equipment malfunctions. The EOF IT Support Supervisor will take appropriate action for resolution.
- RUN test copy through copy machine. Contact the designated extension on copier machine label to report any problems.
- TRANSMIT fax test sheet to insure proper operation of equipment (fax test sheets are located in the telecopier transmittal book on Admin desk).
NOTE:
RECEIVING telecopier machine should indicate 0% memory. If a "memory jam" occurs, turn machine ON/OFF to clear the memory, if this is done, verify receiving faxes for current date/data prior to logging in and making copies.
Nuclear Common Page 4 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT I Page 2 of 5 ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST Initials CHECK telecopier machine for incoming faxes. Utilize Attachment 3 for all forms received and transmitted via fax machine. The sequential log number shall be recorded on Attachment 3. ENSURE the incoming faxes received get:
Indicate "X"if received ......... "X"iftransmitted
" STAMPED IN Ar" I'll Sample of the stamp: RECV'D TRANS. ___ _ - Sequential log #
TIME DOC#
DATE INITIALS A___ Admin Staff Initials "o LOGGED IN Time/Date documented on all forms "o COPIES MADE and distribute to in-baskets in the facility (estimated 10 copies)
VERIFY time on SPDS machines and CHANGE wall clock time, if necessary (instructions are below, more detailed instructions on hanging near the wall clock).
NOTE:
Electronic wall clocks only apply to SALEM TSC and the EOF.
II 0 II fI I I i ii HR. MIN. SEC. RUN TIME AUTO 12 STD. SFT MTE DAY YEAR HOLD DATE DEL. 24 ALT. DIG SET BUTTON LOCATIONS SET TIME: # ACCESS WITH PLASTIC SET ROD THRU FRONT LENS Press RUN/HOLD button to stop clock, the colons will then extinguish indicating the clock is in HOLD. Press HR., MIN. Buttons to display the desired time. It is recommended the selected time be 1 or 2 minutes in advance of current time to allow for complete programming and then synchronization. In the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> mode the PM indicator lamp located in upper left corner of display will be off during AM hours. Using a watch or standard of known accuracy press the RUN button to start the time function. The U.S. Atomic Clock can be accessed via telephone by dialing (202)762-1401.
Nuclear Common Page 5 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 1 Page 3 of 5 ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST Initials
- COORDINATE with the ASM in the EOF if personnel need to be called in for INITIAL MANNING of the facilities. IF the EOF needs assistance doing this, then:
"o Retrieve the BROWN 204S/H confidential envelop (located in the working copy file drawers).
"o Unseal the envelop. Envelop contains 4 items:
"* Small white sealed envelop with call out instructions - YOU WILL NOT NEED TO PERFORM THIS
"* Admin/Bargaining ERO list - also includes X team ERO personnel with home/pager/office numbers
"* ERO Listing by TEAMS with home/pager/office numbers
"* Instructions and additional list of ERO members (not including X team) with home/pager/office numbers o Veif ERO title needed and proceed to make your calls requesting them to report.
NOTE:
You may also check the incoming fax machine designated specifically for the call-out system (located in the Admin Supervisor's area). This print out will tell you who the call-out system contacted and their responses.
2.0 Post Activation of Facility
- REPORT out on the following information during BRIEFINGS:
"o Food/Lodging/Transportation Arrangements (EOF would have this information, or via Phone Book, EP Phone Directory if TSC has to make the arrangements)
"o 24-Hour Shift Relief Roster Developed/Reviewed (Once EOF faxes back the shift relief roster - have EDO review the list).
"o External Assistance Requested (any request would be given to the EOF to call in)
"o Status of Additionally Needed Support Personnel (any additional request would be given to the EOF to call-in)
Nuclear Common Page 6 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 1 Page 4 of 5 ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST Initials INITIATE THE FOLLOWING ACTIONS REGARDING SHIFT RELIEF:
"o REQUEST the following information from the EDO:
"* TIME for shift relief
"* VERIFY any special routing/access instructions Radiological Assessment Coordinator (RAC) can assist with this information.
"o INITIATE completing Attachment 4 of this procedure with the current ERO names.
"o CONTACT the EOF Admin Support Manager (ASM) via (NETS: 5008) and request implementation of "Shift Relief Callout" as per instructions in EPEP 0701. PROVIDE the following information to the EOF ASM:
- Time of shift relief
- Any special routing/access instructions
EOF may request assistance in implementation of Shift Relief Callout (EPEP 0701).
" DETERMINE the needs for food, lodging, equipment, and transportation.
COORDINATE these needs with the ASM in the EOF when it is activated.
IF catering services are not available during emergencies/severe weather conditions THEN DISTRIBUTE emergency food packets located in the food bin lockers, as needed (this could also include the following facilities: OSC/Control Point/Control Room. Arrangements for distribution of food packets will be coordinated with the ADMSS in the TSC). Locker keys are located in key box holders above Security's desk inside the TSCs:
Salem: Food storage bins are located in the TSC kitchen area.
Hope Creek: Food storage bins are located by the TSC entry door.
" IF additional supplies/equipment are needed for support of station emergency response team, and Emergency Duty Officer THEN COORDINATE with the Admin Support Staff - Purchasing in the EOF. Admin Support Staff - Purchasing has access to vendor lists and will initiate purchase of any items needed during the emergency.
Nuclear Common Page 7 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 1 Page 5 of 5 ADMINISTRATIVE SUPPORT SUPERVISOR (ADMSS) CHECKLIST NOTE:
Other resource information available includes: EP Emergency Phone Directory, commercial phone books, and internet.
EVENT TERMINATION/CLOSEOUT Initials RESTORE the Facility to its original state in. Refer to NC.EP-DG.ZZ-0002(Z)
Maintenance of Emergency Response Facilities.
FORWARD all completed forms, logs to the Emergency Preparedness Manager. ATTACH any referenced and completed EPEPs and appendices.
MAINTAIN 5 file copies of each procedure and attachments in the working procedures file drawers.
Nuclear Common Page 8 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 2 Page l of 2 EMERGENCY PREPAREDNESS ADVISOR (EPA) CHECKLIST Prior to Activation of Facility:
Initials
- 1. VERIFY or have TSC Communicators VERIFY communication capabilities with other Emergency Response Facilities using NETS, ESSX, and DID systems. EPA
- 2. VERIFY or have TSC Communicators VERIFY operability of telecopiers (may COORDINATE with Admin Support Team). EPA
- 3. OBTAIN anticipated ECG Communicator Attachments located in work file drawer. EPA
- 4. OBTAIN a turnover briefing from Control Room Communicators to include the following information:
"*Current ECG attachment being implemented.
"*Status of notifications being made.
"*Due time for next station Status Checklist (SSCL).
SSCLs are due every 30 minutes.
"*Request copy of Initial Contact Message Form (ICMF),
if necessary.
"*Note any special communication problems, number changes, or contacts.
"*Further note any relevant operational status.
"*Give Communicator your name, phone extension and advise that you will notify him when your facility is activated to assume Communicator duties.
"*Status of the NRC Data Sheet.
"*Status of NRC notification. EPA
- 5. DESIGNATE Communicator 1 for voice notification duties and Communicator 2 for form preparation/ coordination and status board maintenance. IF a third Communicator is available, ASSIGN to NRC-ENS telephone duty. EPA
- 6. DESIGNATE Ops Advisor to UPDATE OSC priority board (located in the TSC) every 30 minutes and INFORM EDO when priority board is updated. EPA Nuclear Common Page 9 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 2 Page 2 of 2 EMERGENCY PREPAREDNESS ADVISOR (EPA) CHECKLIST Post Activation of Facility:
InitialIs
- 1. ASSUME all emergency communications functions when Facility is declared activated. EPA
- 2. IMPLEMENT Event classification Guide Attachments only as directed by the Emergency Duty Officer (EDO). EPA
- 3. MONITOR all Telecopier activity. Ensure all data forms are initialed or signed off. EPA
- 4. ESTABLISH timetable for telecopier transmissions of critical data forms ensuring deadlines are met. EPA
- 5. ENSURE all notifications and procedural requirements are completed accurately and on time. EPA
- 6. MONITOR status boards ensuring accuracy and timely updates.
- 8. REVIEW Communicator ECG attachments ensuring completeness and accuracy. EPA Event Termination/Closeout:
- 1. ASSIST in restoration of facility to its original state. Refer to NC.EP-DG.ZZ-0002. EPA
- 2. FORWARD all completed EPEPs, forms, and attachments to the EP Manager. EPA Nuclear Common Page 10 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 3 Page 1 of I EMERGENCY RESPONSE TEAM - TELECOPY LOG STATION/UNIT: PAGE OF DATE:
No.* Time Rec'd (R) Subject Initials Sent (S) (Refer to Legend) 4 *4 4.
4 .4 4. t 4 4 4 4 4 4 4. 4
+ .4 4. 4
+ *4 4.
o:o Assign a sequential number to all documents except for test transmittals.
LEGEND:
ARR = Activity Report Roster DADS = Dose Assessment Data Sheet ERFR = Integrated ERF Roster ICMF = Initial Contact Message Form MEES = Major Equip. & Elec Status NRCD = NRC Data Sheet (2 pgs.)
OPS = Operational Status Board PDL = Plant Display Locations (2 pgs.)
RADS = Radiological Assessment Data Sheet RE = Reduction in Event SRS = Shift Relief Schedule (2 pgs.) SSCL = Station Status Checklist (2 pgs.)
Nuclear Common Page 11 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 4 Page 1 of 4 ONSITE SHIFT RELIEF SCHEDULE MANNING CHART Date:
Technical Support Center (TSC)
TSC Admin Support Supervisor to complete this form and fax to EOF (NETS: 5035).
POSITION TITLE SHIFT #1 SHIFT #2
(-: to : (: to :_j (Current shift) (Relief shift)
A-03 EDO E-01 RAC E-02 RP SUPERVISOR OFFSITE E-03 RP TECH F-01 TSS F-02 TSTL F-05 CONTROLS ENG F-06A CORE THERMAL ENGR.
F-03 ELECTRICAL ENGR F-04 MECHANICAL ENGR F-07 EPA F-08 CM1 F-08 CM2 F08B OPERATIONS ADVISOR 1-01 SECURITY LIAISON J-03 ADMIN SUPPORT SUPV J-04 ADMIN STAFF J-04 ADMIN STAFF J-04 ADMIN STAFF J-04a ADMIN STAFF (TDR CLERK)
Nuclear Common Page 12 of 17 Rev. 04
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ATTACHMENT 4 Page 2 of 4 ONSITE SHIFT RELIEF SCHEDULE MANNING CHART Date:
Operations Support Center (OSC)
TSC Admin Support Supervisor to contact OSC Clerk for the current shift names. Direct OSC Clerk to use EPEP 202 Attachment 6 to accomplish this task, and relay information to TSC Admin Support Supervisor Salem OSC Clerk DID Line 856-339-2588 ...... Hope Creek OSC Clerk DID Line 856-339-3155 NOTE: When calling a DID line from a NETS phone, dial: 4-2588, 4-3155)
POSITION TITLE SHIFT #1 SHIFT #2
(-: to : (: to :)
(Current shift) (Relief shift)
C-01 OSC COORDINATOR C-10 OSC CLERK C-04A SHIFT SUP SUPERVISOR C-05A RAD WASTE OPERATOR B-05 EO B-05 EO B-05 EO C-04B MECH SUPV C-04C CONTROLS SUPV C-05E I&C TECH C-05E I&C TECH C-05D ELEC TECH C-05D ELEC TECH C-05B MACHINIST C-08 PLANNER E-02 RP SUPV EXP CONT C-06 SITE PROT SUPERVISOR Nuclear Common Page 13 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 4 Page 3 of 4 ONSITE SHIFT RELIEF SCHEDULE MANNING CHART Date:
Operations Support Center (OSC) - Continued POSITION TITLE SHIFT #1 SHIFT #2 (L : to : ) (_: to :
(Current shift) (Relief shift)
C-06A FIRE BRIGADE C-06A FIRE BRIGADE C-06A FIRE BRIGADE C-06A FIRE BRIGADE C-06A FIRE BRIGADE EXTRA POSITIONS THAT WERE CALLED-IN FOR THE OSC Position Title Shift #1 Shift #2 Date:
Control Room Staff TSC Admin Support Supervisor to contact OSC Clerk to obtain names of Control Room personnel currently on shift. Direct the OSC Clerk to walk to the Work Control where a wall chart is hanging that lists CR personnel who are on shift, and relay back to TSC Admin Support Supervisor.
Salem OSC Clerk DID Line 856-339-2588 ...... Hope Creek OSC Clerk DID Line 856-339-3155 POSITION TITLE SHIFT #1 SHIFT #2
( : to : ( : to :)
(Current shift) (Relief shift)
A-04 OS B-04 CR CM1 B-04 CR CM2 B-02 CRS B-01 NSTA B-03 NCO B-03 NCO Nuclear Common Page 14 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 4 Page 4 of 4 ONSITE SHIFT RELIEF SCHEDULE MANNING CHART Date:
Control Point Staff (CP)
TSC Admin Support Supervisor to contact Chemistry Supervisor at the CP for the current shift names and fax to the EOF (NETS: 5035)
Salem CP NETS: 5312 .................................................... Hope Creek CP NETS: 5230 POSITION TITLE SHIFT #1 SHIFT #2 L : -to -: )(_: to :)
(Current shift) (Relief shift)
E-02 RP SUPERVISOR IN PLANT E-03/04 RP TECH E-03/04 RPTECH E-03/04 RP TECH E-03/04 RP TECH E-03/04 RP TECH E-03/04 RP TECH E-03/04 RP TECH E-05 CHEM SUPERVISOR E-06 CHEM TECH E-06 CHEM TECH Nuclear Common Page 15 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 5 Page 1 of I EDO CLERK GUIDELINES The following guidelines provide suggested tasks that the EDO Clerk should perform if agreed upon with the EDO.
GUIDELINES:
"* MAINTAIN EDO logbook. ENTER key information as announced or as directed by the EDO.
Ensure the EDO reviews the log periodically.
"* TRACK EDO facility briefings and PROVIDE the EDO with a 5-minute warning before the next scheduled briefing (usually every 30 - 45 minutes).
"* MAINTAIN the facility activation section of the Emergency Status Information Board.
"* ANSWER unattended phones of the EDO, TSS, or RAC. TAKE message or INTERRUPT personnel if the caller says the information is urgent.
" OBTAIN procedures for the EDO/TSS/RAC as requested from the working file cabinet.
Procedures the EDO/TSS/RAC will need initially are:
EDO: NC.EP-EP.ZZ-102(Q) "Emergency Coordinator Response" Salem / Hope Creek ECG Attachments - 2, 3, 4, 5, 9 TSS: NC.EP-EP.ZZ-020 1(Q) "TSC-Integrated Engineering Response" RAC: NC.EP-EP.ZZ-0302(Q) "Radiological Assessment Coordinator Response"
"* ENSURE EDO/-SS/RAC have administrative supplies.
"* ADJUST volume of plant page desk speaker (SALEM ONLY) to maximum.
Nuclear Common Page 16 of 17 Rev. 04
NC.EP-EP.ZZ-0203(Q)
ATTACHMENT 6 Page 1 of I CLASSIFICATION GUIDELINES NOTE:
A hand held electronic countdown timer is kept on the EPA desk. Depress the appropriate hour/minute buttons to set the countdown. The timer can be reset at any time by pressing and holding down the reset button.
- 1. START a 10-15 minute countdown timer to alert the team of the approaching expiration of the allotted 15-minute assessment time window. This is performed upon initial recognition of changing plant conditions that could warrant official event classification escalation or PAR upgrade decisions.
- 2. RESET the timer upon event classification/PAR upgrade decision and START a 10-12 minute countdown timer for Communicator notifications (allows 3-minutes to get the agencies on the line.
- 3. ASSIST the EDO in the following guidelines provided below for event classification/escalation or PAR change decisions:
GUIDELINES
" When plant conditions change, make event classification the #1 priority for your entire facility; particularly your facility leads.
" Keep yourself and your teammates focused on event classification and big picture indications.
"* Manage/minimize distractions (phones, people chatting, etc.).
"* Manage the clock - make use of the allotted 15-minute classification assessment time.
"* Use other facilities for backup/consensus decision-making.
"* For a General Emergency, don't let PAR development detract from event classification time. PAR's are done after an event is classified as a General Emergency.
"* Utilize input from all of your facility teammates and other facilities.
"* Avoid drill mentality (UE, Alert, SAE, GE progression).
Nuclear Common Page 17 of 17 Rev. 04
PSEG Internal Use Only PSEG NUCLEAR LLC Page 1 of 1 NC.EP-EP.ZZ-0202 (Q) Rev. 05 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION AND OPERATIONS USE CATEGORY: II REVISION
SUMMARY
Revised Attachments 2, 3, and 6 to add a space to indicate Station and Unit number.
Added step 5.2.12 to ensure the radio is manned at all times, preferably by a fire operator.
IMPLEMENTATION REQUIREMENTS Effective Date /- ./- 2'"V PSE&G CONTROL COPY # _____
APPROVED: ,oj/ I EP Manager 'Datd APPROVED:
Director - Operations All"ý10 Dalt4 "
NC.EP-EP.ZZ-0202(Q)
OPERATIONS SUPPORT CENTER (OSC) ACTIVATION AND OPERATIONS TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E .................................................................................................. .. 2 2.0 PR ER EQ UIS ITES ........................................................................................ 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure... 2 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 2 3.1 Precautions and Limitations To Be Followed Prior To Implementing ..... 2 4.0 EQUIPMENT REQUIRED ........................................................................... 2 5.0 P R O C E D UR E ............................................................................................. 3 5.1 Preparation for Activation ................................................................... 3 5.2 Post Activation of the OSC ................................................................ 5 5 .3 R esto ration ...................................................................................... ..6 6 .0 R E C O R D S .................................................................................................. ..6 7.0 R E FE R E NC E S ............................................................................................. 6 7.1 R eferences .................................................................................... .. 6 7.2 C ross References .............................................................................. 6 ATTACHMENTS ATTACHMENT 1 - BOMB SEARCH OPERATIONS ........................................................ 7 ATTACHMENT 2 - ACCOUNTABILITY INSTRUCTIONS - OSC ................................... 10 ATTACHMENT 3 - OSCC TURNOVER LOG ................................................................. 13 ATTACHMENT 4 - PLANNER DUTIES .......................................................................... 14 ATTACHMENT 5- OPS/MECH/ELECT/I&C/FIRE PROTECTION DUTIES ................... 15 ATTACHMENT 6 - OSC SIGN IN ROSTER/ACCOUNTABILITY FORM ....................... 19 ATTACHMENT 7a -OSC SETUP - Hope Creek ............................................................. 21 ATTACHMENT 7b - OSC SETUP - Salem ..................................................................... 24 ATTACHMENT 8 - TEAM LEADER BRIEFING SHEET ................................................ 27 ATTACHMENT 9 - ASSEMBLY/ACCOUNTABILITY INSTRUCTIONS FOR HIGH NOISE AREAS - OSC (Salem Only) .......................................................... 28 Nuclear Common Page 1 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q) 1.0 PURPOSE This procedure provides guidance to emergency response personnel for administration of Operations Support Center (OSC) activation and operations during an emergency at Hope Creek or Salem Nuclear Generating Stations.
2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 Implement this procedure:
"* At the request of the Operations Superintendent (OS) or the Emergency Duty Officer (EDO).
"* Upon staffing of your Emergency Response Facility.
2.1.2 Steps within a section may be completed in any order.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations To Be Followed Prior To Implementing This Procedure:
3.1.1 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks if more than one person may implement this procedure.
3.1.2 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.
3.1.3 Attachment 6 page 2 of 2 should only be completed if the card readers for the accountability system fail.
4.0 EQUIPMENT REQUIRED As provided in the Emergency Response Facility.
Nuclear Common Page 2 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q) 5.0 PROCEDURE NOTE OSC Coordinator responsibility is filled by Name Date Time 5.1 Preparation for Activation 5.1.1 NOTIFY the following OSC support personnel to report to the OSC:
- a. Shift Electrician
- b. Shift I&C Technician
- c. Radwaste Operator
- d. Equipment Operators
- e. CALL the Fire Protection Supervisor (ext. 2800) or use the plant page, and direct the Fire Brigade to the OSC.
NOTE The Fire Brigade normally brings equipment to the station that has declared the emergency. Advise the Fire Protection Supervisor of conditions that would not permit leaving equipment in any location 5.1.2 DESIGNATE at least two individuals to set up the OSC lAW Attachment 7, OSC SETUP IF Hope Creek THEN implement Attachment 7a, OSC Setup, Hope Creek.
IF Salem THEN implement Attachment 7b, OSC Setup, Salem Nuclear Common Page 3 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q) 5.1.3 REPORT to the Control Room (CR) and obtain the following information from the Operations Superintendent (OS):
- a. Update of emergency status.
- b. Plant conditions including any known radiological problems.
- c. Status of personnel dispatched into the plant by the CR staff.
- d. (Salem Only) Discuss Auxiliary Building Ventilation System Status and ensure that One Supply and Two Exhaust Fans are operating properly. If less than the normal compliment of fans is in service, then request the OS prioritize actions lAW Attachment 2 of the Operating Procedure. Ensure design based auxiliary building temperatures are maintained. The aux.
building ventilation system needs to be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following an accident initiation.
5.1.4 ENSURE OSC clock time is approximately the same as the CRJSPDS time.
5.1.5 IMPLEMENT the following steps in any order:
"* IMPLEMENT Attachment 2 - Accountability Instructions, when Accountability is called.
"* DIRECT one individual to ensure all OSC personnel sign in on the Attachment 6, OSC Sign In Roster. DO NOT have control room personnel sign in at this time on Attachment 6
"* ASSEMBLE available OSC personnel and brief them on the status of the emergency.
"* DIRECT non-supervisory OSC personnel who are not assisting in set up of the OSC to assemble in the OSC Ready Room.
"* DIRECT the Radiation Protection Supervisor-Exposure Control (RPS-EXP) or Shift Radiation Protection Technician to implement NC.EP-EP.ZZ-0304(Q), OSC - Radiation Protection Response.
5.1.6 ACTIVATE the OSC as follows:
"* INFORM the OS and OSC personnel that the OSC is activated, at (time) on (date) / I
"* MAKE the following page announcement (Announce Twice):
"The OSC is now activated. All Plant Activities should be coordinated thru the OSC."
Nuclear Common Page 4 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
NOTE Each individual's annual limit will automatically be raised to 4500 mRem upon the declaration of an Alert or higher emergency classification provided a completed NRC FORM 4 is on record.
NOTE The following steps should be completed simultaneously 5.2 Post Activation of the OSC DIRECT an OSC Supervisor or OSC staff member to periodically brief the OSC READY ROOM on plant conditions and update the EMERGENCY INFORMATION OPS READY ROOM status board in the OSC Ready Room.
5.2.1 WHEN Accountability is called, THEN:
- a. IMPLEMENT Attachment 2, ACCOUNTABILITY INSTRUCTIONS.
- b. (SALEM ONLY) IF requested THEN IMPLEMENT Attachment 9, Assembly/Accountability Instructions for High Noise Areas - OSC (Salem Only).
5.2.2 IF directed to perform bomb search activities, THEN IMPLEMENT Attachment 1, BOMB SEARCH Operations.
5.2.3 IF loss of habitability occurs for:
"* The OSC Ready Room, THEN direct personnel to the Technical Support Center (TSC) or other location as directed by the OS/EDO.
"* The OSC, THEN direct OSC personnel to the TSC or other location as directed by the OS/EDO.
5.2.4 DIRECT Ops, Mechanical, I&C, Fire Protection, and Electrical Supervisors to implement Attachment 5, OPS/MECH/ELECT/I&C/FIRE PROTECTION DUTIES.
Nuclear Common Page 5 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q) 5.2.5 DIRECT the Planner to implement Attachment 4, PLANNER DUTIES.
5.2.6 DIRECT the OSC Clerk to:
- a. MAINTAIN the OSC Coordinator's Log.
- b. PROVIDE the log to the OSC Coordinator for periodic review.
- c. MAINTAIN the OSC Team Status Board and Priority Status Board.
5.2.7 ASSEMBLE available OSC personnel and brief on the emergency.
5.2.8 DIRECT the OSC Clerk report to the TSC, if conditions degrade where respirators are needed for OSC personnel.
5.2.9 ENSURE the OSC priorities and activities are periodically discussed with the OS.
5.2.10 BRIEF the oncoming OSC Coordinator and conduct the turnover lAW Attachment 3, OSCC TURNOVER LOG.
5.2.11 IF additional personnel are needed, (e.g. Duty Storekeeper) contact the ADMSS in the TSC.
5.2.12 IF available, have a fire operator man the radio; otherwise ensure the radio is manned at all times.
5.3 Restoration ENSURE the OSC is restored to a ready status.
6.0 RECORDS Return completed procedure, attachments, and or forms to the EP Manager.
7.0 REFERENCES
7.1 References None 7.2 Cross References PSEG Nuclear Emergency Plan Nuclear Common Page 6 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT I Page 1 of 3 BOMB SEARCH OPERATIONS 1.0 BOMB SEARCH OPERATIONS 1.1 Perform the following for bomb search operations, as directed by the OS/EDO:
1.1.1 The OSC Coordinator should:
CAUTION Portable radios and portable phones shall not be used during a bomb search. Radio transmissions may cause an explosive device to detonate.
A. MAKE the following page announcement TWICE:
"Attention all personnel, terminate use of all portable radios phones until further notice."
B. CALL the Salem OS and request they make the proceeding page announcement.
C. CALL PSEG Security Supervisor (ext. 2222) and request that a Security Team Leader or Security Technical Analyst reports to the OSC.
D. OBTAIN a briefing from the OS concerning the requested bomb search to include, as a minimum:
- Nature of the bomb threat
- Specific areas mentioned in the threat
- Current bomb search activities
- Restrictions due to radiological concerns
- Copy of a completed Bomb Threat Checklist and Report Form if available.
E. DIRECT the Security Team Leader or Security Technical Analyst, assigned to the OSC, to recommend bomb search areas priorities, in accordance with Security Contingency Procedures.
Nuclear Common Page 7 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 1 Page 2 of 3 F. MODIFY bomb search priorities recommended by the Security Team Leader or Security Technical Analyst as required due to plant operational and/or radiological conditions.
- 0. Assemble bomb search teams that should consist of a Plant Operator as the Team Leader and a Security Force Member (SFM).
- Fire Protection Operators may be utilized if Plant Operators are not available
H. BRIEF the bomb search teams, in conjunction with the Security Team Leader or Security Technical Analyst and the SRPT/RPS - EXP.
OFFER the team leader a copy of Attachment 8, TEAM LEADER BRIEFING SHEET.
J. BRIEF each bomb search team to include discussion of the following:
- Information known from the bomb threat.
- Assigned search area(s) for each team.
- Operational and Radiological concerns such as exposure limits, dosimetry, protective clothing, etc.
- Abort conditions.
- OSC phone call back numbers for team communications.
- Instruct each team member to look for physical evidence of suspected sabotage in addition to the location of destructive device(s).
- 1. Mechanical (valve alignment, piping, loose ducts, structures, normal running equipment checks).
- 2. Electrical (checks for any breakers in an off-normal position, open cabinets, open conduit, etc.).
- 3. Physical Barriers (blocked open doors, misplaced contamination/high radiation areas, etc.).
- 4. Suspicious looking articles (lunch boxes, tool boxes, packing crates, etc.).
- 5. Abnormal log readings/indications for the area.
K. Using the plant page or hard wire phone, inform the OSC Coordinator immediately upon locating a potential bomb or sabotaged area.
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NC.EP-EP.ZZ-0202(Q)
ATTACHMENT I Page 3 of 3 L. IF a bomb is discovered, THEN:
- a. ENSURE that all personnel in the vicinity of the bomb are relocated to a safe area and direct the bomb search team to secure access to the area.
- b. CONTACT the OS, the OSC coordinator, the OSC Security Force Supervisor and EDO to take appropriate actions.
M. RECALL, debrief and deactivate the Bomb Search Team when:
- a. Completion of search with negative results is reported.
- b. Termination of the bomb threat.
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NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 2 Page 1 of 3 ACCOUNTABILITY INSTRUCTIONS - OSC 1.0 ACCOUNTABILITY INSTRUCTIONS 1.1 Upon Hearing the Page Announcement to Implement Accountability, the OSC Coordinator Shall:
Initials 1.1.1 ENSURE OSC and Control Room personnel are listed on the Attachment 6, OSC SIGN IN ROSTER (only obtain control room sign-in if back up Accountability method is being used.)
OSCC NOTE Personnel who have carded into the Control Room Security Area are not required to pass their photobadges through the OSC accountability station cardreader. This is because Control Room personnel are accounted for automatically by the access door cardreaders into the Control Room.
1.1.2 Upon hearing the page announcement, "All ACCOUNTABILITY STATIONS IMPLEMENT ACCOUNTABILITY":
A. DIRECT all personnel who are not within the Control Room Security Area to pass their photobadges through the special accountability cardreader located just outside the OSC.
OSCC B. DIRECT all OSC teams in the field to verbally accounted for by using an ACCOUNTABILITY EXEMPTION FORM, page 3 of this Attachment.
OSCC 1.1.3 MAINTAIN current status of all OSC personnel. This should include name, assignment, time dispatched.
OSCC Nuclear Common Page 10 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT-2 Page 2 of 3 1.1.4 Upon hearing the page announcement, "All ACCOUNTABILITY STATIONS COMPLETE YOUR 30 MINUTE ACCOUNTABILITY,"
A. ENSURE that any personnel arriving at the OSC since the initial call for accountability also have passed their photobadges through the OSC accountability cardreader.
OSCC B. ENSURE the badge numbers of personnel listed on page 3 of this attachment (Accountability Exception Form) are called to security at extension 2222. If unable to contact security on 2222, contact the security liaison at NETS 5214 (Hope Creek) or NETS 5217 (Salem)
OSCC 1.1.5 IF personnel arrive at the OSC after 30 minutes have elapsed, THEN:
A. NOTIFY security of the badge numbers of the personnel that have reported to the OSC using ext. 2222.
OSCC B. DIRECT those personnel to:
- 1. PASS their photobadge through the accountability cardreader.
OSCC
- 2. SIGN Attachment 6, OSC SIGN IN ROSTER if not already signed in OSCC 1.1.6 IF directed, THEN form search teams for unaccounted for personnel.
OSCC 1.1.7 MAINTAIN continuous accountability until the emergency is terminated.
OSCC 2.0 AUTOMATED ACCOUNTABILITY SYSTEM MALFUNCTION:
2.1 Perform the Following Should the Automated Accountability System Malfunction:
2.1.1 PROVIDE a copy of Attachment 6, OSC SIGN IN ROSTER Sheet(s), to the Security Force Member dispatched to the OSC.
OSCC Nuclear Common Page 11 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 2 Page 3 of 3 ACCOUNTABILITY EXEMPTION FORM OSC I-1 Hope Creek
-- Salem Unit 1 E]- Salem Unit 2 NAME (print) BADGE LAST FIRST NUMBER
-f 4-
- 4 t I 1- 4
+ 4 1-1 4 a _______________________________ L _________________________________
NOTE Call Security at extension 2222 and provide the badge numbers of the personnel listed above. The personnel listed above have been accounted for verbally. These personnel are involved in actions to mitigate emergency events. If unable to contact security at extension 2222, contact the TSC security liaison at NETS 5214 (Hope Creek) or NETS 5217 (Salem).
Signature (OSC Coordinator or OS) Time Date Nuclear Common Page 12 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 3 Page 1 of I OSCC TURNOVER LOG F-DHope Creek F-1Salem Unit 1 Salem Unit 2 Date:
- 1. [UE] [A] [SAE] [GE] was declared @ hrs. on / /
Due to:
- 2. The present classification, [A] [SAE] [GE] was declared @
hrs. on / /
Due to:
- 3. The Emergency Coordinator (EC) is in the [EOF] [TSC] [CR] name
- 4. The Oncoming and Offgoing OSCC should:
Initials On /Off A. DISCUSS current conditions. Include any problems encountered or anticipated, and any ongoing, or expected actions.
B. REVIEW all applicable documentation including procedures, logs, etc., ensuring they are completed, correct and signed. /
C. DISCUSS the OSC's priorities, personnel requirements and any equipment or material needs.
D. DISCUSS any Radiological, Safety, or Environmental concerns.
E. ENSURE that OSC teams in the field are recalled or relieved on the job as necessary.
F. NOTIFY the OS of the change in command in the OSC.
Update plant status and priorities as applicable.
(ONCOMING)
G. HOLD a briefing with the OSC staff to ensure a smooth transition between the oncoming and off-going OSC personnel. (ONCOMING)
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NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 4 Page 1 of 1 PLANNER DUTIES NOTE:
When the OSCC is activated, the Work Control Office becomes an extension of the OSC.
1.0 Planner Duties 1.1 Perform the Following, as Appropriate:
1.1.1 LOG on to SAP in Work Control on any available computer with LAN capabilities.
1.1.2 SELECT a Personnel Computer in Work Control to run the parts program, if necessary 1.1.3 TRACK any items issued and document for post-emergency review 1.1.4 PROVIDE current status of repairs in progress.
1.1.5 INITIATE Work Order/Notification packages as necessary for jobs originating in the OSC.
- IF time is not available, AND at the discretion of the OSCC, THEN use a paper work request and follow up with a Work Order/Notification as soon as possible.
1.1.6 PROVIDE guidance as to procedures, tools, and time that past repairs required.
1.1.7 As requested, obtain spare parts, materials, tools, etc.
1.1.8 ASSIST the other OSC staff members as directed by the OSCC including answering phones, page announcements and OSC ready room updates.
1.1.9 COLLECT all work orders and paper work for review and documentation after the emergency has been terminated.
Nuclear Common Page 14 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q ATTACHMENT 5 Page 1 of 4 OPSIMECHIELECT/I&C/FIRE PROTECTION DUTIES 1.0 OSC DUTIES 1.1 Perform the Following Duties, as Appropriate:
1.1.1 PROVIDE corrective action recommendations based on your expertise to the OSCC for accident mitigating activities.
1.1.2 MONITOR Oxygen content in the OSC and Control Room every hour.
1.1.3 MONITOR Fire Protection System Status and ensure compensatory measures (fire watch) are maintained in accordance with plant conditions.
NOTE
- 1. An individual, in lieu of a team, may be dispatched by the OSCC. The individual should be in contact with the OSC or the Control Point, via some type of audio communications (page, radio, or telephone), and should check in every 15 minutes with the OSC or the Control Point.
A. An individual shall not be used under the following circumstances:
"* An individual's exposure could be expected to exceed 1000 mRem.
"* The task would require entry into a "Harsh Environment Area" (i.e., a steam atmosphere, a heat stress area, unknown, etc.)
"* Acts of sabotage or suspected sabotage.
- 2. Prompt team dispatch is of the utmost importance. If necessary, a radiological briefing may be conducted on the way to the job.
1.1.4 ASSEMBLE teams and provide team briefings and debriefings in your areas of expertise.
"* ENSURE that all OSC teams are made up of at least two people unless a task meets the criteria from the note above.
"* ENSURE that teams dispatched from the Control Point are tracked using the OSC Team Status Board.
"* ASSEMBLE the Team and designate a Team Leader.
"* IF adverse radiological conditions exist, THEN a Radiation Protection Technician (RPT) should be included on the team.
"* IF a Personnel Injury/Medical Response incident occurs, THEN a Fire Brigade Member should be included on the team.
Nuclear Common Page 15 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q ATTACHMENT 5 Page 2 of 4
" OFFER Attachment 8, Team Leader Briefing Sheet, to each team leader.
" ENSURE all Teams obtain a briefing lAW, Team Briefing Guidelines of this Attachment.
CAUTION Portable radios are not to be keyed in the vicinity of the Control Room or Relay Room areas.
Any portable radio and cellular phone transmissions are prohibited during bomb search operations.
"* IF a Team is dispatched, THEN ENSURE the OSC Team Status Board is updated.
"* MONITOR and support dispatched teams (Point of Contact).
"* RECALL the Team IF:
- 1. The mission or objective is accomplished.
- 2. Directed by OS (higher priority, etc.).
- 3. Plant conditions degrade to where an individual's exposure to unanticipated changes in radiological conditions:
"* May exceed authorized exposure limit.
"* Life threatening environmental conditions are encountered.
"* WHEN the team returns, CONDUCT a general debriefing.
"* COLLECT all procedures, attachments, etc. and retain to forward to the Manager CA/EP/IT.
"* RELEASE team to RPT/RPS - EXP for a radiological debriefing.
" COORDINATE with the RAC for the transportation of injured person or personnel receiving Emergency Exposures of > 5 REM to the appropriate medical facilities, if necessary.
"* Deactivate the team and ensure the OSC Team Status Board is updated.
Nuclear Common Page 16 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q ATTACHMENT 5 Page 3 of 4 1.1.5 INTERFACE with the TSC Engineers for their support when needed by:
"* REQUEST the OSCC to contact the OS for technical support, as needed.
" WHEN TSC Technical support is requested, THEN OBTAIN a copy of the Technical Support Tracking Form from the OSCC for implementing mitigating actions recommended by the engineering staff, which are not addressed in a procedure.
"* ENSURE the Technical Support Tracking Form is approved for implementation by the OS.
NOTE The Work Control Office becomes an extension of the OSC when the OSC is activated 1.1.6 ASSIST the OSC Planner in Work Request/Notification generation lAW the appropriate NAPs.
"* Initiate tagging requests in Work Control.
"* Request the Operations Supervisor assist in tag request generation.
1.1.7 If acts of sabotage are expected, team safety must be the number one priority. Contact security in the TSC to determine what areas are safe for personnel dispatch. If any area is considered unsafe by security, discuss delaying team dispatch until the area is cleared by security.
Nuclear Common Page 17 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q ATTACHMENT 5 Page 4 of 4 TEAM BRIEFING GUIDELINES A. Mission Details 1. Designate a team leader
- 2. Explain purpose of mission
- 3. Define work to be performed
- 4. State expected results
- 5. Team identifier (team #)
B. Safety 1. Ensure required safety gear is used
- 2. Equipment C/T for work
- 3. Review Environmental Concerns:
N Heat stress
"* Oxygen deficient atmosphere
"* Toxic/caustic chemical concerns
- 4. Fire hazards C. Communications 1. Establish preferred method E Portable radios 0 Phones (Dimension) 0 Other (sound pwrd phones, etc.)
- 2. Point of contact
- 3. Check in time cycle
- 4. Estimated job completion time D. Equipment 1. Required tools
- 2. Test equipment
- 3. Procedures (current copy[s] as required)
- 4. Availability/location of spare parts
- 5. Authorization for "cannibalization" of other equipment for parts E. Radiological 1. Discuss expected dose rates
- 2. Establish stay times
- 3. Establish abort conditions criteria
- 4. Identify desired routes
- 5. Review rwp with the team including dress out criteria
- 6. Review exposure limits
- 7. Obtain high rad. key if required
- 8. Ensure the control point is notified.
F. Debrief 1. Team is expected to debrief the assigning supervisor when the job is complete or the team is recalled.
Nuclear Common Page 18 of 28 Rev. 05
t-ACHMENT 6
,ge I of 2 OSC SIGN IN ROSTER/ACCOUNTABILITY FORM z Hope Creek __
Salem Unit 1 Salem Unit 2 0
0 POSITION NAME BADGE # POSITION NAME BADGE #
0 OSC CLERK R.P. SUPPORT R. P. SUPPORT OPS SUPV FIRE PROT. SUPV.
OPERATOR FIRE BRIG. MBR.
OPERATOR FIRE BRIG. MBR OPERATOR FIRE BRIG. MBR OPERATOR FIRE BRIG. MBR OPERATOR FIRE BRIG. MBR 0
00 OPERATOR FIRE BRIG. MBR OPERATOR OPERATOR PLANNER MAINT.SUPV. ( ) ADDITIONAL OSC SUPPORT PERSONNEL MAINT.SUPV. ( ) POSTION NAME BADGE # Z 0
SHIFT ELECT.
in
'0 SHIFT I&C TECH "I MAINT.SUPPORT ( )
0 MAINT.SUPPORT ( )
CD' MAINT.SUPPORT MAINT.SUPPORT INDICATESJOB CLASSIFICATION (i.e. WELD. MACH. 131-R. REP. ETC.)
ATTP -4MENT 6 P 2 of 2 OSC SIGN IN ROSTER/ACCOUNTABILITY FORM z Hope Creek Salem Unit 1 t
Salem Unit 2 POSITION NAME BADGE # POSITION NAME BADGE #
0 33 Os 0
CRS STA SRO I SRO 2 NCO NCO "0
NCO 0o NCO o0 COMMUNICATOR I COMMUNICATOR 2 OPS ADVISOR COMMENTS ADDITIONAL CONTROL ROOM/OSC PERSONNEL z I13 0
CD OSC Coordinator Signature 0
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7a Page 1 of 3 OSC SETUP - HOPE CREEK 1.0 HOPE CREEK OSC SETUP 1.1 Perform The Following to Setup the OSC:
1.1.1 PROCEED to the OSC storage closet located in the North West corner of the OSC.
- BREAK the glass on the key box located on the wall next to the storage closet and obtain the keys for the closet, if necessary.
1.1.2 OBTAIN equipment and supplies stored in the OSC locker:
- REMOVE cordless phones from chargers.
- DISTRIBUTE OSC cordless phones lAW OSC Setup Diagram found in this Attachment. The setup is for guidance only. Personnel may be relocated around the table as needed or at the discretion of the OSC coordinator.
PERFORM the following in case of cordless phone failure:
A. PLACE the phone strip under the OSC table.
B. IMMEDIATELY SETUP NETS and DID phones lAW OSC Setup Diagram found in this Attachment.
CHECK all phones to ensure proper operation.
1.1.3 PLACE the OSC base radio station in operation as follows:
0 TURN the OSC radio's power on. (The On/Off Switch is on the front of the unit).
0 VERIFY the Control Room radio TAKEOVER yellow indicator is illuminated. If TAKEOVER green indicator is illuminated depress the TAKEOVER push button.
- POSITION the FREQUENCY BUTTON to the UP position for frequency #3.
0 POSITION the HEADSET TOGGLE SWITCH to the DOWN position for headset use or in the UP position for speaker use.
- POSITION VOLUME CONTROL to a comfortable level. (VOLUME CONTROL SWITCH is on the front of the radio).
- PRESS the TRANSMIT BAR on the microphone to transmit a message when the headset OFF.
0 PRESS the hand held transmit button on the headset cord to transmit, if the headset is ON.
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NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7a Page 2 of 3
"* ENSURE OSC hand held radios are selected to the same frequency as the base station radio.
"* TEST the base station radio to a hand held radio.
1.1.4 INCREASE or decrease the OSC page volume control to a comfortable level.
1.1.5 POST a clean copy of the OSC TEAM STATUS BOARD in the OSC.
1.1.6 SETUP the OSC Priority Status Board in the Control Room. This board is found in the storage closet in the CRS office area in the Control Room Complex.
Nuclear Common Page 22 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7a Page 3 of 3 HOPE CREEK GENERATING STATION OSC FLOOR PLAN SRADIO II READYROVMB FING 1BOARDI BS T OSC WORK I I PROTFILES PLANT I
/
PAGESC COORDINATOR 0
SUPPORT CLERK DID NETS ESSX 3123 5226 7977 RP SITE PRO SUPV SUPV.
0 NU)
NETS NETS 5228 5229 I&C MAINT SUPV SUPV LM o NETS DID cc 5227 3155 PLANNER 0
4 0
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F CO)
U, oso Nuclear Common Page 23 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7b Page 1 of 3 OSC SETUP - SALEM 1.0 SALEM OSC SETUP 1.1 Perform The Following to Setup the OSC:
1.1.1 OBTAIN the keys for the OSC cabinets from the Red Key Box on the wall in Work Control. Break the glass if necessary.
1.1.2 OBTAIN equipment and supplies stored in the OSC locker and cabinets.
1.1.3 SETUP the OSC phones lAW figure found in this Attachment 7b.
Phone connections are located on the underside of the table. The setup is for guidance only. Personnel may be relocated around the table as needed or determined by the OSC coordinator.
1.1.4 CHECK all phones to ensure proper operation.
NOTE The OSO base radio station is permanently set up in the 0SC.
1.1.5 PLACE OSC base radio station in operation as follows:
A. TURN the unit power on. (The On/Off Switch is on the front of the unit.)
B. VERIFY the Control Room radio TAKEOVER yellow indicator is illuminated in the affected unit's Control Room.
(IF TAKEOVER green indicator is illuminated, THEN depress the TAKEOVER push button).
C. POSITION the FREQUENCY BUTTON to the UP position for frequency #1 (Unit #1) or DOWN for frequency #2 (Unit #2).
D. POSITION the HEADSET TOGGLE SWITCH to the DOWN position for headset use or in the UP position for speaker use.
E. POSITION VOLUME CONTROL to a comfortable level.
(VOLUME CONTROL SWITCH is on the front of the radio.)
F. DEPRESS the TRANSMIT BAR on the microphone to transmit a message when the headset OFF.
G. DEPRESS the hand held transmit button on the headset cord to transmit, if the headset is ON.
Nuclear Common Page 24 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7b Page 2 of 3 H. ENSURE OSC hand held radios are selected to the same frequency as the base station radio.
I. TEST the base station radio to a hand held radio outside of the Control Room/OSC Complex.
1.1.6 DIRECT the OSC Page turned up to a comfortable level.
1.1.7 SETUP the OSC TEAM STATUS BOARD.
1.1.8 PROVIDE the Control Room with one of the OSC PRIORITY STATUS BOARDS.
1.1.9 SETUP the other OSC PRIORITY STATUS BOARD in the OSC near the OSCC.
Nuclear Common Page 25 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 7b Page 3 of 3 SALEM GENERATING STATION OSC FLOOR PLAN TEAM BRIEFING AREA Nuclear Common Page 26 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 8 Page 1 of I TEAM LEADER BRIEFING SHEET TEAM LEADER TIME DISPATCHED TEAM MEMBERS TASK PURPOSE/EXPECTED RESULTS TEAM NUMBER SAFETY EQUIPMENT NEEDED/ENVIRONMENTAL CONCERNS BY RADIO, PLANT PAGE OR DID PHONE #___ CONTACT______
EVERY ____MIN.
SPECIAL INSTRUCTIONS/EQUIPMENT BACK OUT DOSE REM EXPECTED RADIOLOGICAL CONDITIONS INDICATE DOSE RECEIVED NEXT TO NAME ABOVE AND INFORM RP SUPERVISOR DEBRIEF INFORMATION INDICATE WHAT WAS OBSERVED IN THE FIELD/TEAM RESULTS. DEBRIEF THE ASSIGNING SUPERVISOR ON FINDINGS/RESULTS Nuclear Common Page 27 of 28 Rev. 05
NC.EP-EP.ZZ-0202(Q)
ATTACHMENT 9 Page 1 of 1 ASSEMBLY/ACCOUNTABILITY INSTRUCTIONS FOR HIGH NOISE AREAS - OSC (SALEM ONLY)
NOTE This ATTACHMENT shall be implemented upon request by Security Force Supervision to support implementation of ASSEMBLY or ACCOUNTABILITY for high noise areas.
1.0 HIGH NOISE AREA INSTRUCTIONS FOR ACCOUNTABILITYIASSEMBLY 1.1 THE OSC COORDINATOR SHALL:
NOTE Acceptable methods that should be used to check on high noise areas are:
"* Physical Observation.
"* Verification of Key Control.
"* Card Reader Record of Entry (requested from Security).
1.1.1 IF requested by the Security Force Supervision, THEN form teams to check the areas listed below. (EP97-001)
"* All Trailers within the Protected Area
"* Salem Containment (priority during outages)
"* Outer Penetrations (Salem U1/U2)
"* Inner Penetrations (Salem UI/U2)
"* Check all rooms on Aux Building 84' elevation (Salem U1/U2)
"* Check all rooms on 45' elevation (Salem U1/U2).
"* Salem Service Water Intake Pump Bays
"* Salem Circulating Water Intake Structure
"* Salem Turbine Bldg. (UI/U2)(el. 88' and 100')
1.1.2 IF any personnel are observed still onsite in any of these high noise areas, THEN INSTRUCT them to either leave site or report to their Accountability Station.
Nuclear Common Page 28 of 28 Rev. 05
PSEG Internal Use Only PSE&G NUCLEAR BUSINESS UNIT Page 1 of 1 NC.EP-EP.ZZ-0101(Q) Rev. 02 ACTIONS REQUIRED AT UNAFFECTED STATION USE CATEGORY: II REVISION
SUMMARY
- BIENNIAL REVIEW X YES NO
- 1. Editorial changes including.
- Location of the Emergency Callout envelope
- Added Security Event details to the turnover attachment
- Modified Attachment 6 Security guidelines to move Unusual Event before the alert section as to match the changes in EPEP 102 PSE&G CONTROL COPY#%-L1L,1*9:.
IMPLEMENTATION REQUIREMENTS Implementation Date '- 3 / - &-"
APPROVED: 7 /-(7---
- 1. EP Manager Date APPROVED: A,/
Vice President - Operations Eate
NC.EP-EP.ZZ-0101(Q)
ACTIONS REQUIRED AT UNAFFECTED STATION TABLE OF CONTENTS Section Title Page 1 .0 P UR P O S E .................................................................................................. .. 2 2 .0 P R E R E Q UIS IT E S ........................................................................................ 2 3.0 PRECAUTIONS AND LIMITATIONS ............................................................ 2 4.0 EQ UIPM E NT R EQ UIR ED ............................................................................ 2 5 .0 P R O C E D UR E ............................................................................................ .. 3 5 .1 Initia l Actio ns ........................................ .......................................... . . . 3 5 .2 T u rn o ve r .......................................................................................... .. 4 6 .0 R E C O R D S ................................................................................................... ..5 7 .0 R E F E R E NC E S ............................................................................................ . .5 7 .1 R e fe re nce s ..................................................................................... . 5 7.2 C ross-R eferences .............................................................................. 5 ATTACHMENTS ATTACHMENT 1 OS/EDO EMERGENCY STATUS BRIEFING FORM ......................... 6 ATTACHMENT 2 MINIMUM STAFFING CALLOUT LOG ............................................... 8 ATTACHMENT 3 ACCOUNTABILITY ACTIONS AND RESULTS .................................. 9 ATTACHMENT 4 EMERGENCY ASSEMBLY MESSAGE ........................................... 11 ATTACHMENT 5 UNUSUAL EVENT MESSAGE ...................................................... 12 ATTACHMENT 6 SECURITY EMERGENCY GUIDELINE (SEG) ............................ 13 Nuclear Common Page I of 15 REV. 02
NC.EP-EP.ZZ-0101(Q) 1.0 PURPOSE 1.1 This procedure provides emergency response instructions to the unaffected station's Operations Superintendent (OS) and Emergency Duty Officer (EDO) when an emergency event is declared at the other station (affected station).
2.0 PREREQUISITES 2.1 An emergency event has been declared at either Salem or Hope Creek.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Initials should be used in the place keeping sign-offs, instead of checkmarks.
3.2 Activation of the ERO Callout system is expected during an Unusual Event that is based on a Security Event as called for in Attachment 6, Security Emergency Guideline, (SEG).
4.0 EQUIPMENT REQUIRED 4.1 As provided in the Control Room and Technical Support Center (TSC).
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NC.EP-EP.ZZ-0101(Q)
5.0 PROCEDURE
NOTE Since the Rad Alert alarm is located in the Control Room, the OS directs all emergency status announcements. However, when the EDO or ERM has the Emergency Coordinator duties, he/she is responsible for ensuring the proper announcements are made.
5.1 Initial Actions:
5.1.1 IMPLEMENT SEG, Security Emergency Guideline, if Security based emergency, lAW Attachment 6 of this procedure.
NOTE:
For Security based emergency, SEG (Aft. 6) may require modifications of associated actions/announcements.
5.1.2 IMPLEMENT Unusual Event, Assembly, or Accountability, as requested by the affected station Emergency Coordinator:
Unusual Event ASSEMBLY ACCOUNTABILITY Attachment 5 Attachment 4 Attachment 3 5.1.3 IF the emergency is an Alert or higher, THEN the OS/EDO should:
A. DIRECT the OSC Coordinator to activate the OSC lAW EPEP 202.
NOTE Determining available support personnel to assist the affected station is NOT necessary during normal work hours.
B. CONTACT Shift Radiation Protection Technician (Radiation Protection Supervisor during normal work hours) to determine radiological protection personnel available to support the affected station:
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NC.EP-EP.ZZ-0101(Q) 5.1.4 IF the emergency is a Site Area Emergency or General Emergency, THEN the OS/EDO should:
A- ESTABLISH minimum staffing lAW Attachment 2 for the unaffected station on-site emergency response facilities.
B. DIRECT designated communicator to initiate a limited callout to provide minimum staffing of the unaffected station, on-site emergency response facilities lAW Attachment 2.
C. IF directed by the affected station Emergency Coordinator, THEN IMPLEMENT a full callout of emergency response personnel. LOCATE the confidential envelope in the front of the Operations Superintendent's (O.S.) copy of the ECG marked "Emergency Callout. Follow the directions. When complete return to this procedure.
D. DISCUSS unaffected station unit shutdown or load/power level reduction with the Emergency Coordinator AND with Load Dispatcher (Senior System Operator).
F. MONITOR station for habitability based on event conditions, AND CONSIDER evacuating station or response facilities as radiological conditions dictate.
- a. IF circumstances indicate the need to fully activate your station's on-site emergency response facilities, THEN NOTIFY the affected station OS and EDO of actions being taken.
- b. IF your station has indication that conditions at the affected unit may be degrading, THEN NOTIFY the Emergency Coordinator to make the new classification.
G. DIRECT the Shift Rad Pro Tech (SRPT) or Radiological Assessment Coordinator (RAC) to ensure assessment of the Control Room habitability is performed.
5.2 Turnover 5.2. 1 IF relief is required, THEN PROVIDE turnover to the EDO (USE Attachment 1, OS/EDO Emergency Status Briefing Form).
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NC.EP-EP.ZZ-0101(Q) 6.0 RECORDS Forward all completed ECG Attachments / EPEPs / attachments / forms to Manager - CA, EP, & IT.
7.0 REFERENCES
7.1 References 7.1.1 Nuclear Business Unit Emergency Plan 7.1.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 7.1.3 PSE&G Nuclear Business Unit, NC.NA-AP.ZZ-0001(Q), Nuclear Procedure System 7.1.4 PSE&G Nuclear Business Unit, NC.NA-WG.ZZ-0001(Z), Procedure Writer's Guide, 7.2 Cross-References 7.2.1 NC.EP-EP.ZZ-0405(Q), Emergency Termination/Reduction/Recovery 7.2.2 Hope Creek Event Classification Guide (ECG) 7.2.3 Salem Event Classification Guide (ECG) 7.2.4 P-SO.CAV-0001 (Q), Control Room Ventilation Operation 7.2.5 NC.EP-EP.ZZ-0102(Z), EMERGENCY COORDINATOR RESPONSE, Attachment 10. SEG.
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NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 1 Page 1 of 2 OSIEDO EMERGENCY STATUS BRIEFING FORM NOTE Completion of this Attachment is optional. However, the information listed is useful for providing a thorough turnover to the EDO.
1 EAL that is the basis for the emergency classification:
Unusual Site Area General Event Alert Emergency Emergency
- a. EAL(s)#
- b. Time declared
- c. PAR based on 10 Wind dir.
points? ___ Yes _ NO (from)
- d. Accountability? Yes NO Time Results:
- 2. Status of important safety systems:
- 3. Status of fuel cladding, reactor coolant system, and containment integrity:
- 4. Unusual radiological conditions currently existing:
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NC.EP-EP.ZZ-0101(Q)
ATTACHMENT I Page 2 of 2
- 6. Identification of "out-of-service" equipment that needs repair: (not on priority list)
- 7. Offsite emergency actions underway (Did a release occur? Have field-monitoring teams been dispatched? State's PADs, Etc.)
- 8. Prognosis for the situation to improve or worsen:
- 9. Adequacy of current Control Room staffing (Is an additional person needed to assist with communications?)
- 10. Emergency Operating Procedures (EOPs) being implemented.
- 11. Security Event details, were SEG Attachment 6 actions completed?
- 12. Other Nuclear Common Page 7 of 15 REV. 02
NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 2 Page 1of 1 MINIMUM STAFFING CALLOUT LOG
- 1. WHEN directed by the OS, THEN COMPLETE Part A, Event Description.
- 2. CONTACT the persons in Part B - Minimum Staffing Callout, as determined by the OS AND READ Part A - Event Description.
- 3. INFORM each individual contacted to call out their organization as appropriate to provide minimum staffing of the unaffected station Control Point, TSC, or OSC, as applicable.
- 4. PROVIDE this completed Attachment to the OS.
PART A - EVENT DESCRIPTION This is Communicator in the (HOPE CREEK - SALEM) Control Room:
Circle one - cross out the other Circle one - cross out the other declared (a UE, an Alert, a SAE, a GE) at (Affected Station) (Time)
Due to:
PART B - MINIMUM STAFFING CALLOUT REFERENCE FOR INDIVIDUAL TITLE TELEPHONE NUMBER CONTACTED TIME
- 6. Technical Support Team EPIP 204S ATT. 3 OR Leader (TSTL) EPIP 204H ATT 3 DATEý Nuclear Common Page 8 of 15 REV. 02
NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 3 Page 1 of 2 ACCOUNTABILITY ACTIONS AND RESULTS Initials/Time
+0 Min SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION, ATTENTION ALL ACCOUNTABILITY STATIONS.
IMPLEMENT ACCOUNTABILITY.
Announcer
+20 Min after above announcement was made.
ANNOUNCE TWICE "ATTENTION, ATTENTION. ALL ACCOUNTABILITY STATIONS.
COMPLETE ACCOUNTABILITY.
Announcer (Instructions for the OS to perform accountability continue on next page.)
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NC.EP-EP.ZZ-01 01 (Q)
ATTACHMENT 3 Page 2 of 2 Initials
+30 min after implement accountability announcement was made.
- 1. OBTAIN from Security a list of unaccounted personnel. IF Security has not supplied results of the accountability within 30 minutes of the first accountability announcement, THEN contact the TSC Security Liaison at the affected unit and request accountability results.
EDO/OS Hope Creek Salem NETS X5214 NETS X5117
- 2. DESIGNATE an individual to attempt to locate unaccounted personnel as follows:
A. Page individuals over the plant page.
B. Obtain feedback from unaccounted person's co-workers/supervisors on last known location/job assignment.
C. Call individual's home to verify work schedule.
D. Request Security's assistance in locating unaccounted personnel.
EDO/OS
- 3. UPDATE Security as missing personnel are located.
EDO/OS
- 4. INITIATE search and rescue operations in accordance with EPEP 202, OSC Activation and Operations, if appropriate.
EDO/OS
- 5. As the situation dictates and/or as radiological conditions permit:
IF all onsite Emergency Response Facilities are completely staffed, THEN release/evacuate extra personnel who reported to the OSC, TSC, CP or Maintenance Shop for accountability.
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NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 4 Page 1 of 1 EMERGENCY ASSEMBLY MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.
(HOPE CREEK - SALEM) IS IN Circle one - cross out the others (AN ALERT - A Site Area Emergency - A General Emergency)
ALL PSE&G PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.
Announcer RADIO REPEAT EMERGENCY ANNOUCEMENT MESSAGE Announcer Nuclear Common Page 11 of 15 REV. 02
NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 5 Page 1of 1 UNUSUAL EVENT MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.
(HOPE CREEK - SALEM) IS IN AN UNUSUAL EVENT.
Circle one - cross out the other Announcer RADIO REPEAT UNUSUAL EVENT ANNOUCEMENT MESSAGE Announcer Nuclear Common Page 12 of 15 REV. 02
NC.EP-EP.ZZ-0101(Q)
ATTACHMENT 6 Page 1 of 3 SECURITY EMERGENCY GUIDELINE (SEG)
ENTRY CONDITIONS:
Security based common site Unusual Event or security based Alert or higher is declared at the affected station. (Continue these actions until the security threat is averted or other specific direction is provided in response to the event).
I1. PROMPT ACTIONS
- 1. IF entry into this guideline was based on a Security Event classified at an UNUSUAL EVENT level, THEN:
Call-out the Emergency Response Organization (ERO) by locating the confidential envelope marked "Emergency Callout" in the Operations Superintendent's (OS) copy of the ECG. Follow the directions.
- 2. IF entry into this guideline was based on a Security Event classified at an ALERT or higher level at the affected station, ( EAL 9.1.2 or 9.1.3 or 9.1.4 ) AND, the Security Event/Threat is ongoing, OR, IF Operation's Superintendent (OS) judgment is that a credible threat to plant structures/equipment is imminent by a security event in progress, THEN:
" SCRAM/TRIP the reactor. If time allows, ensure scramming/tripping the reactor is coordinated with the other unit to prevent tripping all three units concurrently. (HC.OP-AB.ZZ-0000 & S1(2)-EOP-TRIP-001)
" COMMENCE plant cool down to cold shutdown. (HC.OP.IO.ZZ-0004 &
S1(2).OP-IO.ZZ-0006)
" START Emergency Diesel Generators. Do not load. (HC.OP-SO.KJ 0001 & S1(2).OP-SO.DG-001, 002, 003)
" (SALEM ONLY) PLACE the Control Room Ventilation in the Fire Outside Control Room Mode lAW SI (2).OP-SO.CAV-0001.
" (HOPE CREEK ONLY) PLACE the Control Room Ventilation in the Recirculation Mode lAW HC.OP-SO.GK-0001.
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ATTACHMENT 6 - SEG Page 2 of 3
- 3. IFIWHEN, Assembly or Accountability and Evacuation is directed by the affected stations's emergency coordinator (EC),
MODIFY plant page announcements as directed by the EC as needed to maximize the safety of the plant and plant personnel.
"o Assembly announcement is directed in Attachment 4.
"o Accountability/Evacuations announcement is directed in Attachment 3.
III. SUBSEQUENT ACTIONS 1 IF in an outage condition, THEN:
TERMINATE fuel movement. Place any currently loaded fuel bundles in a safe location (preferably either the original location or destination location).
- TERMINATE Containment Purge
- ESTABLISH Containment Integrity
- 3. TERMINATE planned releases that are in-progress.
- 4. (SALEM ONLY) START Unit 3 if needed to provide additional backup power capability.
- 5. (HOPE CREEK ONLY) WHEN the OSC is staffed, DIRECT the OSCC to have the TSC staff align the TSC ventilation system in Recirculation Mode.
- 6. (SALEM ONLY) WHEN the OSC is staffed, DIRECT the OSCC to have the Salem TSC staff align the TSC ventilation in the "Operations During Toxic or Chemical
-Release" lineup, (SC.OP-SO.TSC-0051).
- 7. ENSURE the availability of injection systems by performing the following:
" Terminate surveillance activities and restore systems to a normal standby alignment.
" Ensure the Condensate Storage Tank is filled to the upper end of the normal operating band.
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ATTACHMENT 6- SEG Page 3 of 3
"* Ensure the Demineralized Water Storage Tanks are filled to the upper end of the normal operating band.
"* Ensure RAP tanks (RWST, AFWST, & PWST) at Salem 1 & 2 are filled to the upper end of the normal operating band.
"* Ensure the potable and firewater storage tanks are at normal capacity.
"* Verify firewater header pressure is normal.
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