Text

Plant Operating Manual CH-632, Rev. 2, Post Accident Sampling and Analysis of Reactor Coolant, Decay Heat, and Reactor Building Sump.
	ML042530253
Person / Time
Site:	Crystal River
Issue date:	09/02/2004
From:	; Florida Power Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CH-632, Rev 2
	Download: ML042530253 (78)
	v • d • e

ToCK PASSPORT DOCUMENT To NRC NRC Facility CR3 Department : TRANSMITTAL Address CR3-01242 / MAIL CODE: N/A DC DESK SAFEGUARDS TO S. GANGI NA2S Page: 1 From Address CR3DOCSVCS Attention: DOCUMENT SERVICES - SA2A FLORIDA POWER CORPORATION CRYSTAL RIVER COMPLEX 15760 WEST POWERLINE STREET EI NMIUHI allld elIlllulil ID City CRYSTAL RIVER State:FL Postal Code: 34428-6708 Country UNITED STATES Email Contact Date/Time : 09/02/04 09:26 Transmittal Group Id:0000018845 Trans No. : 000165444

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aJ Progress Energy PROGRESS ENERGY CRYSTAL RIVER UNIT 3 PLANT OPERATING MANUAL CH-632 Post Accident Sampling and Analysis of Reactor Coolant, Decay Heat, and Reactor Building Sump K>

I CH-632 I Rev.2 1 Page 1 of 77

TABLE OF CONTENTS 1.0 PURPOSE............................................................................................................4

2.0 REFERENCES

............................. 4 2.1 Developmental References ............................. 4 2.2 Equipment Database References ............................. 5 3.0 PERSONNEL INDOCTRINATION ......................... .. 6 3.1 Description .................................................. 6 3.2 Definitions ................................................... 7 3.3 Responsibilities ......... 7...........................

3.4 Limits and Precautions ................................................... 7 3.5 Prerequisites ................................................... 9 4.0 INSTRUCTIONS .......... 12 4.1 Reactor Coolant Gamma Isotopic or Boron Analysis ............................... 12 4.2 Reactor Coolant Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler .......................................... 20 4.3 Decay Heat System Gamma Isotopic or Boron Analysis ......................... 29 4.4 RB Sump Gamma Isotopic and Boron Analysis ....................................... 34 4.5 Decay Heat Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler .......................................... 42 4.6 RB Sump Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler .......................................... 49 5.0 CONTINGENCIES ............ 57 5.1 Relief Valve Flow Indicated at CA-50-FS Flow Switch .............................. 57 5.2 PASS Temperatures Greater Than Expected .......................................... 58 5.3 CAT-8 Hi-Hi Level Alarm .................................................. 59 5.4 Estimating Grab Sample Shipment Curie Content When Gamma Spectroscopy System is Unavailable ......................................... 60 5.5 Manual Collimator Positioning and Manual Gamma Isotopic Analysis .... 60 ICH-632 I Rev. 2 I Page-2-of 77

TABLE OF CONTENTS (Cont'd.)

't> ENCLOSURES

1. Technical Support Center Data Sheet .......................... ........................ 61

2. Guidelines for Monitoring PASS System Parameters ......................................... 63

3. PASS AIMS Pre-Analysis Check Guidelines .................................................. 64

4. Guidelines for Performing Gamma Spectroscopy Analysis ................................ 65

5. Assessment of Core Damage Based on Reactor Coolant Sample ..................... 66

6. Guidelines for Operating EG&G Flow Technology Flow Meters ......................... 68

7. Guidelines for Liquid Grab Sample Installation and Removal ............................. 69

8. Grab Sample Shipment and Notifications .................................................. 70

9. Estimating Grab Sample Curie Content When Gamma Spectroscopy System is Unavailable .................................................. 71

10. Manual Collimator Positioning and Manual Gamma Isotopic Analysis ............... 75 I CH-632 I Rev. 2 1 Page 3 of 77

1.0 PURPOSE This procedure provides instructions for sampling RCS, DH, and RB sump during accident conditions using PASS.

2.0 REFERENCES

2.1 Developmental References 2.1.1 APEX Technologies Post Accident Sample System Modules Manual, FPC Manual

2034 2.1.2 EOP-14, Enclosure 2, PPO Post Event Actions 2.1.3 FD-302-700, Post Accident Sampling System 2.1.4 Nuclear Regulatory Commission RTM-96, Response Technical Manual 2.1.5 NUREG 0737, Post-TMI Requirements 2.1.6 PASS Users Manual Volumes A through C, Crystal River Installation 2.1.7 Radiological Emergency Response Plan 2.1.8 Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. July 2000 2.1.9 Regulatory Guide 1.97, Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident 2.1.10 RSP-600, ALARA Program 2.1.11 EM-104, Operation of the Operational Support Center 2.1.12 CH-234, Post Accident Sampling System Gamma Spectroscopy System 2.1.13 6059-S-002, APEX Technologies PASS Process Flow Diagrams 2.1.14 NUREG 1465, Accident Source Terms for Light-Water Nuclear Power Plants, Feb. 1995 2.1.15 License amendment # 213 I CH-632 I Rev. 2 1 Page4of77 l

2.2 Equipment Database References CAV-1 26 CAV-440 CAV-493 CAV-636 CA-74-FI DWV-337 CAV-441 CAV-500 CAV-702 CA-89-PI CAV-429 CAV-442 CAV-514 CAV-703 CA-94-PI CAV-430 CAV-445 CAV-517 CAV-704 CAX-1 CAV-431 CAV-446 CAV-519 CAV-705 AHF-55 CAV-432 CAV-447 CAV-546 CA-50-FS CASB-5 CAV-433 CAV-448 CAV-549 CA-51-TE CAP-8 CAV-434 CAV-470 CAV-623 CA-54-CE CAP-10 CAV-435 CAV-471 CAV-624 CA-54-XC CAP-14 CAV-436 CAV-484 CAV-625 CA-54-TE-1 CAT-8 CAV-437 CAV-491 CAV-626 CA-54-LT DPDP-5A CAV-439 CAV-492 CAV-627 CA-56-CI DPDP-5B II CH-632 C_- 2 I Rev.

R . 22

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,I.ae7of 77

3.0 PERSONNEL INDOCTRINATION 3.1 Description 3.1.1 PASS is an on-line system designed to sample various liquid and gaseous sample streams during accident conditions.

3.1.2 The liquid PASS system consists of an AIMS detector to perform gamma isotopic analysis of the sample streams.

3.1.3 The PASS system provides the ability to obtain liquid grab samples to be shipped off-site for analysis. [NOCS 100440,100441]

3.1.4 The PASS system has the ability to analyze boron and gamma isotopic from RCS at high pressure. This sample may be obtained from RC letdown, RCP-1A discharge, or RCP-1C suction. [NOCS 100440,100441]

3.1.5 The PASS system has the ability to analyze boron and gamma isotopic on low pressure systems. These systems include DH and RB sump. [NOCS 100440, 100441]

3.1.6 When estimating total activity for liquid grab sample shipment, the following assumptions were made:

Core Nuclide Mix and Half-lives from RADTRAD Code Library

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months since reactor shutdown

Microshield software was used to determine conversion factors for calculating total pCi from dose rate. Sample assumed to be small enough at 7 inches to represent point source. Pig is 17.75 inches tall with diameter of 7 inches.

Weight is 725 pounds. This results in effective density of 7.4 g/cc.

Release fractions from Regulatory Guide 1.183 for gap and early in-vessel melt

Assume no noble gas remain in unpressurized RCS/sump sample 3.1.7 When estimating core damage based on RCS sample (Enclosure 5), the following assumptions were made:

Factor (B)is 1300 based on the following:

Assumed dilution mass = 1.3E9 grams 1300= (1.3E9 grams) x (1E-6 Ci/pCi)

Core Inventory (D) is from RADTRAD library for 2619 MWth core

Expected fraction in gap (F)is from NUREG 1465

Expected in-vessel melt release fraction 100% melt (G) is from NUREG-1465 I CH-632 I Rev. 2 1 Page 6 of 77

3.2 Definitions 3.2.1 AIMS Automated Isotopic Measurement System 3.2.2 EC Emergency Coordinator 3.2.3 PASS Post Accident Sampling System 3.2.4 RE-ENTRY Return of personnel to an area evacuated by an emergency condition 3.2.5 RMT Radiation Monitoring Team 3.2.6 TMI Three Mile Island nuclear power plant 3.2.7 IRP Instrument Relay Panel 3.3 Responsibilities 3.3.1 EC or designee shall authorize re-entry.

3.3.2 OSC Chemistry Coordinator

Ensures EC approval for re-entry has been obtained

Determines which sections of procedure are to be performed during re-entry

Ensures re-entry prerequisites are complete klof 3.3.3 This procedure is performed by a qualified Emergency Sample Team member.

3.4 Limits and Precautions 3.4.1 Any or all of this procedure is done by direction of the EC or designee.

3.4.2 Re-entry must have RMT preplanning, concurrence, and coverage as outlined in EM-104, Operation of the Operational Support Center. Controlled access areas will be defined by the RMT personnel.

3.4.3 Extremely high radiation dose rates may be present during post-accident sampling.

These high dose rates could result in high radiation exposure. Performing this procedure requires ALARA pre-planning.

3.4.4 Emergency Sample Team will STOP and go to a low dose area (i.e. primary chemistry laboratory) if dose rates at re-entry work area exceeds limits specified in pre-job briefing.

3.4.5 All sampling actions are performed from the Main Control Board by Operations or from the Count Room unless specifically noted.

l CH-632 l Rev. 2 l Page 7 of 77

3.4.6 CAT-8 HI-HI level has the following interlocks:

CAV-623 closes

CAV-627 closes

CAP-10 stops 3.4.7 Pressure > 175 psig at CA-89-PI may cause relief valves CAV-702 or CAV-491 to open. These relief valves open at approximately 200 psig.

3.4.8 Pressure > 30 psig at CA-94-PI may cause relief valve CAV-705 to open. This relief valve opens at approximately 50 psig.

3.4.9 Relief valves CAV-702, CAV-705, and CAV-491 discharge to the MWST. Lifting these relief valves may cause increased dose rates in the AB.

3.4.10 Sample is flushed through the boronometer at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before obtaining boron results.

3.4.11 Sampling described in Section 4.0 of this procedure CANNOT be performed concurrently due to shared piping in the different sample streams.

3.4.12 Sampling any of the low pressure systems for the first time requires an entry into the PASS room (95' AB) to reposition CAV-701 to PORT 2 which could result in high radiation exposure. CAV-701 is normally positioned to PORT 1. Once positioned to PORT 2, the valve will remain in that position to avoid re-entry into a potentially high dose area.

3.4.13 The RB sump ALTERNATE sample point returns water to the MWST which could result in increased radiation levels in the AB.

3.4.14 Using the RB sump ALTERNATE sample point requires an entry into 95' IB to open CAV-500 which could result in high radiation exposure. A second re-entry is required to close the valve when securing the line-up.

I CH-632 I Rev. 2 l Page 8 of 77

3.5 Prerequisites NOTE Prerequisite steps may be performed in an order.

3.5.1 ASSEMBLE sample team.

Sample Team Leader Sample Team Members 3.5.2 DETERMINE sampling to be perforn __.4 Section Number Descripth

3. . REVIEW procedures.

EM-1 04, Operation of Operational Support Center Emergency Team Member duties per Section 4.0 Team Briefing/Re-entry checklist Sections of this procedure being performed 3.5.4 IF grab sample to be performed via CASB-5, THEN ENSURE the following:

-[3 Grab sampler currently installed OR

[] Grab sampler NOT currently installed New break-away type device available to attach transit cover and transit cover bolts to sampler Replacement sample bomb (Catalog ID 1400513) available to install on grab sampler transit cart lCH-632 I Rev.2 { Page9of77 l

3.5.5 ENSURE electrical breakers are closed.

[I] Operations has performed EOP-14 Enclosure 2, PPO Post Event Actions OR

[I] Operations has NOT performed EOP-14 Enclosure 2, PPO Post Event Actions

1. _ REQUEST Operations CLOSE the following breakers

DPDP-5A Breaker 27 (CAV-433, CAV-434, CAV-429, CAV-430).

DPDP-5B, Breaker 8 (CAV-432, CAV-435, CAV-436)

2. _ Operations REPORTS breakers closed 3.5.6 IF sampling a low pressure system,

DH

RB sump THEN DETERMINE position of CAV-701

[] Low pressure system has NOT been sampled using PASS. CAV-701 is positioned to PORT 1. An entry into the PASS room (95' AB) is required to position CAV-701 to PORT 2. If an entry is needed, CAV-701 is located in the PASS room (95' AB) inside CAX-1. CAX-1 is located on LEFT after entering PASS room. CAV-701 is located MIDDLE LEFT SIDE inside CAX-1 approximately head high.

OR

[] Low pressure system HAS been sampled using PASS. CAV-701 was positioned to PORT 2 at that time and left in that position 3.5.7 IF sampling RB sump using ALTERNATE sample path, THEN DISCUSS the following:

RB sump water will be pumped to MWST. This action could cause increased radiation levels in AB 2 entries into 95' lB will be required to OPEN and subsequently CLOSE CAV-500. Operating CAV-500 could result in increased dose-exposure CAV-500 is located inside IB approximately 15' from IB door (about 3' past OTSG sample valve manifold) on left about 7' above floor CH-632 Rev. 2 Page 10 of 77

3.5.8 PERFORM pre-job brief.

ENSURE RMT member is present for briefing DISCUSS the following access route exit route Communications Radio channel to be used phone number(s) 3.5.9 VERIFY ALL steps of this section are completed before sample team leaves OSC.

Section 3.5 Complete Initial/Date I CH-632 I Rev. 2 .a I Page 11 of 77 1

4.0 INSTRUCTIONS 4.1 Reactor Coolant Gamnma Isotopic or Boron Analysis 4.1.1 VERIFY radio communication.

WHEN sample team exits OSC, THEN VERIFY radio communication with OSC Chemistry Coordinator or designee 4.1.2 ALIGN system for sample.

1. SELECT CAP-1 0 control switch to OFF

2. CLOSE the following valves CAV-439 CAV-636

3. OPEN the following valves CAV-519 CAV-447 CAV-448

4. POSITION the following valves CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK l CH-632 I Rev. 2 1 Page 12 of 77

4.1.3 REQUEST Operations OPEN containment isolation valves.

1. OPEN sample isolation valve

[I] CAV-1 26 (Reactor Coolant Letdown)

OR

[] CAV-429 (RCP-1A Discharge)

OR

[] CAV-430 (RCP-1C Suction)

2. OPEN PASS Containment isolation valve

[ ] CAV-431 (normal AIMS supply)

OR

[] CAV-432 (alternate AIMS supply)

3. OPEN RB sump return isolation valves CAV-436 CAV-434

4. - Operations REPORTS valves OPEN 4.1.4 ALIGN CAT-8.

SELECT CAP-10 control switch to AUTO START CAP-14 CH-632 Rev. 2 Page 13 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valves CAV-702 or CAV-491 to open. Flow from these valves is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Relief valves CAV-702, CAV-705, and CAV-491 discharge to the MWST.

Flow downstream of these valves is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.1.5 ADJUST sample flow.

1. THROTTLE CAV-484 to MAINTAIN 0.35-0.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

2. DEPRESS CA-74-FI RESET button to zero flow totalizer. REFER to Enclosure 6.

3. _ ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch 4.1.6 DETERMINE status of RC letdown flow from Operations.

[] RC letdown flow secured OR

[l RC letdown flow lined up I CH-632 I Rev. 2 1 Page 14 of 77 l

NOTE Steps 4.1.8 and 4.1.9 may be performed while flushing sample.

4.1.7 FLUSH sample lines. Total flush volume is indicated using CA-74-FI totalizer reading. REFER to Enclosure 6.

[] CAV-1 26 open (RC Letdown secured) - FLUSH at least 45 gallons OR

[] CAV-126 open (RC letdown lined up) - FLUSH at least 17.5 gallons OR

[] CAV-429 open (RCP-1A discharge) - FLUSH at least 3 gallons OR

[ ]CAV-430 open (RCP-1 C suction) - FLUSH at least 3 gallons 4.1.8 ENSURE the following temperatures are maintained. REFER to Enclosure 2.

CA-54 TE-1 RCS < 120 QF CA-51 TE WATER <100 9F 4.1.9 IF gamma isotopic analysis is to be performed, THEN ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[ ]Liquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[3] QC requirements met I CH-632 l Rev. 2 I Page 15 of 77

NOTE The gamma isotopic analysis step may be repeated for multiple gamma analyses.

NOTE Enclosure 5 may be used to evaluate % core damage NOTE Gamma isotopic and boron analysis may be performed concurrently.

4.1.10 'IF gamma isotopic analysis is to be performed, THEN PERFORM the following:

1. - VERIFY minimum sample flush volume complete

2. REFER to Enclosure 4 for gamma isotopic analysis SELECT applicable sample point

[] Reactor Coolant Letdown Sample OR

[] RCP-1 A Discharge Sample OR

[] RCP-1 C Suction Sample

3. - ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s)

ICH-632 I Rev. 2 l Page 16of77

NOTE Boronometer readout normally updates once per 15 minutes.

4.1.11 IF boron analysis is to be performed, THEN PERFORM the following:

1. VERIFY sample flushed through boronometer. Flush must meet most restrictive requirement of at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the minimum volume specified in Step 4.1.7.

2. OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm l CH-632 I Rev. 2 - Page 17 of 77 1

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valves CAV-702 or CAV-491 to open. Flow from these valves is routed to the MWST, which could cause radiation levels to increase in the AB.

4.1.12 ALIGN for demineralized water flush.

1. NOTIFY Operations to CLOSE containment isolation valves

a. CLOSE sample isolation valve CAV-126 (Reactor Coolant Letdown)

OR

[] CAV-429 (RCP-1A Discharge)

OR

[] CAV-430 (RCP-1 C Suction)

b. CLOSE PASS Containment isolation valve

[] CAV-431 (normal AIMS supply)

OR

[I CAV-432 (alternate AIMS supply)

c. Operations REPORTS valves closed

2. OPEN the following demineralized water supply valves DWV-337 CAV-470

3. - THROTTLE CAV-484 to obtain 0.35-0.50 gpm at CA-74-FI I CH-632 I Rev. 2 1 Page 18 of 77 l

4.1.13 ENSURE adequate system purge.

1. - ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. SELECT Flush Sample Lines

4. SELECT RCS Demin Flush

5. FLUSH at least 10 minutes

6. PRESS ENTER when flush is complete

7. SELECT Quit to exit

8. ENTER LO to log off PASS 4.1.14 SECURE line-up.

1. STOP CAP-14

2. SELECT CAP-10 control switch to OFF

3. CLOSE demineralized water supply valves DWV-337 CAV-470

4. CLOSE the following valves CAV-519 CAV-447 CAV-448 CAV-484 CAV-623 CAV-625 CAV-626

5. NOTIFY Operations to CLOSE the following valves CAV-436 CAV-434 4.1.15 RESTORE normal configuration.

1. OPEN CAV-439

2. OPEN CAV-636

3. SELECT CAP-10 control switch to AUTO Section 4.1 Complete --.-

InitiaVDate l CH-632 I Rev. 2 l Page 19 of 77 l

4.2 Reactor Coolant Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler 4.2.1 WHEN sample team exits OSC.

THEN VERIFY radio communications with OSC Chemistry Coordinator or designee.

NOTE CASB-5 exhaust fan (AHF-55) switch is located to the right of Intermediate Building door (across from RM-A7) 4.2.2 ESTABLISH ventilation for liquid grab sampling.

POSITION AHF-55 switch to ON 4.2.3 ENSURE liquid grab sampler, CASB-5, installed.

[] Liquid grab sampler already installed OR Ii REFER to Enclosure 10 for liquid grab sampler installation instructions 4.2.4 ALIGN system for sample.

1. SELECT CAP-10 control switch to OFF

2. CLOSE the following valves CAV-439 CAV-636

3. OPEN the following valves CAV-519 CAV-447 CAV-448

4. POSITION the following valves CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK l CH-632 I Rev. 2 Page 20 of 77

4.2.5 REQUEST Operations OPEN containment isolation valves.

1. OPEN sample isolation valve

[ ] CAV-1 26 (Reactor Coolant Letdown)

OR

[] CAV-429 (RCP-1A Discharge)

OR

[] CAV-430 (RCP-lC Suction)

2. OPEN PASS Containment isolation valve

[ ] CAV-431 (normal AIMS supply)

OR

[] CAV-432 (alternate AIMS supply)

3. OPEN RB sump return isolation valves CAV-436 CAV-434

4. Operations REPORTS valves OPEN 4.2.6 ALIGN CAT-8.

SELECT CAP-1 0 control switch to AUTO START CAP-14 CH-632 Rev. 2 Page 21 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valves CAV-702 or CAV-491 to open. Flow from these valves is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Relief valves CAV-702, CAV-705, and CAV-491 discharge to the MWST.

Flow downstream of these valves is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.2.7 ADJUST'sample flow.

1. THROTTLE CAV-484 to MAINTAIN 0.35-O.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

2. DEPRESS CA-74-FI RESET button to zero flow totalizer. REFER to Enclosure 6.

3. -ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch K> 4.2.8 DETERMINE status of RC letdown flow from Operations.

[] RC letdown flow secured OR

[J] RC letdown flow lined up 1I CH-632 I Rev.22 XRev. I Page 22 of 77 1I Paqe

NOTE Steps 4.2.10 and 4.2.11 may be performed while flushing sample.

4.2.9 FLUSH sample lines. Total flush volume is indicated using CA-74-FI totalizer reading. REFER to Enclosure 6.

l] CAV-1 26 open (RC Letdown secured) - FLUSH at least 45 gallons OR

[] CAV-126 open (RC letdown lined up) - FLUSH at least 17.5 gallons OR

[I] CAV-429 open (RCP-1 A discharge) - FLUSH at least 3 gallons OR

[I] CAV-430 open (RCP-1 C suction) - FLUSH at least 3 gallons 4.2.10 ENSURE the following temperatures are maintained. REFER to Enclosure 2.

CA-54 TE-1 RCS < 120 2F CA-51 TE WATER < 100 9F 4.2.11 ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[ ]Liquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[] QC requirements met CH-632 Rev. 2 l Pa e 23 of 77

NOTE Gamma isotopic analysis may be performed concurrently with liquid grab sampler flush.

4.2.12 VERIFY system for liquid grab sample

1. ENSURE minimum sample flush complete. Total flush volume is indicated using CA-74-FI totalizer reading

2. OPEN CAV-445

3. OPEN CAV-446

4. _ CLOSE CAV-447

5. - FLUSH at least 15 minutes.

NOTE The gamma isotopic analysis step may be repeated for multiple gamma analyses.

4.2.13 PERFORM gamma isotopic analysis.

1. -'VERIFY minimum sample flush volume complete

2. REFER to Enclosure 4 for gamma isotopic analysis SELECT applicable sample point

[] Reactor Coolant Letdown Sample OR

[] RCP-1 A Discharge Sample OR

[] RCP-1C Suction Sample

3. ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s) l CH-632 I Rev. 2 Pag a e24 of77

NOTE CAV-492 and CAV-493 are on the grab sampler.

4.2.14 ISOLATE grab sample.

1. -CLOSE CAV-492

2. - CLOSE CAV-493 Grab sample Date/Time NOTE Boronometer readout normally updates once per 15 minutes.

4.2.15 IF boron analysis is to be performed, THEN PERFORM the following:

1. VERIFY sample flushed through boronometer. Flush must meet most restrictive requirement of at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the minimum volume specified in Step 4.2.9

2. OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm CH-632 Rev. 2 Page 25 of 77 l

4.2.16 ALIGN for demineralized water flush.

1. NOTIFY Operations to CLOSE containment isolation valves

a. CLOSE sample isolation valve

[ ]CAV-126 (Reactor Coolant Letdown)

OR

[] CAV-429 (RCP-1A Discharge)

OR

[ ]CAV-430 (RCP-1C Suction)

b. CLOSE PASS Containment isolation valve

[)]CAV-431 (normal AIMS supply)

OR

[] CAV-432 (alternate AIMS supply)

c. Operations REPORTS valves closed

2. OPEN the following demineralized water supply valves DWV-337 CAV-470

3. - ADJUST CAV-484 to MAINTAIN 0.35-0.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

4.2.17 ENSURE adequate system purge.

1. ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. SELECT Flush Sample Lines

4. SELECT RCS Demin Flush

5. FLUSH at least 10 minutes

6. PRESS ENTER when flush is complete

7. _ SELECT Quit to exit

8. ENTER LO to log off PASS CH-632 Rev. 2 Page 26 of 77

4.2.18 RESTORE system line-up.

1. OPEN CAV-447

2. CLOSE CAV-445

3. CLOSE CAV-446

4. FLUSH at least 1 minute

5. -STOP CAP-14

6. SELECT CAP-10 control switch to OFF

7. CLOSE demineralized water isolation valves DWV-337 CAV-470

8. CLOSE the following valves CAV-519 CAV-447 CAV-448 CAV-484 CAV-623 CAV-625 CAV-626

9. NOTIFY Operations to CLOSE the following valves CAV-436 CAV-434 4.2.19 RESTORE normal configuration.

1. -OPEN CAV-439

2. OPEN CAV-636

3. SELECT CAP-10 control switch to AUTO I CH-632 I Rev. 2 Page 27 of 77

4.2.20 REMOVE Liquid Grab Sampler, CASB-5.

1. REMOVE liquid grab sampler from sample station, REFER to Enclosure 10

2. TRANSPORT liquid grab sampler to 95' TB Crane Well

3. UNBOLT liquid grab sampler from cart using 3/4" wrench or equivalent as determined by Chemistry Technician

4. INSTALL transit cover over quick connects

5. MEASURE dose rates from liquid grab sampler Contact dose rate (side of pig) mR/hr Dose rate @ 3 feet mR/hr 4.2.21 PREPARE for liquid grab sample shipment.

REFER to Enclosure 11 for off-site shipment and notifications Section 4.2 Complete /

InitiaVDate CH-632 Rev. 2 Page 28 of 77

4.3 Decay Heat System Gamma Isotopic or Boron Analysis 4.3.1 VERIFY radio communication.

WHEN sample team exits OSC, THEN VERIFY radio communication with OSC Chemistry Coordinator or designee 4.3.2 ALIGN system for sample.

1. _ SELECT CAP-1 0 control switch to OFF

2. CLOSE the following valves CAV-439 CAV-636

3. OPEN the following valves CAV-519 CAV-447 CAV-448

4. POSITION the following valves CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK 4.3.3 REQUEST Operations OPEN containment isolation valves:

1. OPEN RB sump return isolation valves CAV-436 CAV-434

2. Operations REPORTS valves OPEN 4.3.4 ALIGN CAT-8.

SELECT CAP-10 control switch to AUTO START CAP-14 4.3.5 ENSURE CAV-701 positioned to PORT 2. This determination was made during the pre-job briefing. If an entry is needed, CAV-701 is located in the PASS room (95' AB) inside CAX-1. CAX-1 is located on LEFT after entering PASS room.

CAV-701 is located MIDDLE LEFT inside CAX-1 approximately head high.

4.3.6 OPEN DH system sample isolation valves.

[] Decay Heat Train "A" CAV-441 CAV-440 OR

[] Decay Heat Train "13f CAV-442 CAV-440 CH-632 Rev. 2 Page 29 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.3.7 ADJUST sample flow.

1. THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

2. ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch NOTE Step 4.3.9 may be perfromed while flushing sample.

4.3.8 FLUSH sample lines.

FLUSH at least 5 minutes 4.3.9 IF gamma isotopic analysis is to be performed, THEN ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[] Liquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[] QC requirements met I CH-632 I Rev. 2 1 Page 30 of 771

I NOTE The gamma isotopic analysis step may be repeated for multiple gamma analyses.

NOTE Enclosure 5 may be used to evaluate % core damage NOTE Gamma isotopic and boron analysis may be performed concurrently.

4.3.10 IF gamma isotopic analysis is to be performed, THEN PERFORM the following:

1. VERIFY minimum sample flush time complete

2. REFER to Enclosure 4 for. gamma isotopic analysis SELECT applicable sample point

[] A-Decay Heat Train Sample OR

[] B-Decay Heat Train Sample

3. ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s) l CH-632 I Rev. 2 l Page31 of77

NOTE Boronometer readout normally updates once per 15 minutes.

4.3.11 IF boron analysis is to be performed, THEN PERFORM the following:

1. - ENSURE sample flushed through boronometer at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. - OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

4.3.12 ALIGN for demineralized water flush.

1. CLOSE the following valves

[] Decay Heat Train "A" CAV-441 CAV-440 OR

[] Decay Heat Train "B" CAV-442 CAV-440

2. OPEN the following demineralized water supply valves DWV-337 CAV-471

3. _ START CAP-8

4. _ THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm at CA-74-FI I CH-632 I Rev. 2 l Page 32 of 77 1

4.3.13 ENSURE adequate system purge.

1. _ ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. - SELECT Flush Sample Lines

4. SELECT Sump Demin Flush

5. _ FLUSH at least 10 minutes

6. PRESS ENTER when flush is complete

7. SELECT Quit to exit

8. ENTER LO to log off PASS 4.3.14 SECURE line-up.

1. STOP CAP-8

2. STOP CAP-14

3. SELECT CAP-10 control switch to OFF

4. CLOSE demineralized water isolation valves DWV-337 CAV-471

5. CLOSE the following valves CAV-519 CAV-447 CAV-448 CAV-623 CAV-624 CAV-625 CAV-626

6. NOTIFY Operations to CLOSE the following valves CAV-436 CAV-434 4.3.15 RESTORE normal configuration.

1. OPEN CAV-439

2. OPEN CAV-636

3. SELECT CAP-1 0 control switch to AUTO Section 4.3 Complete /

InitiaVDate l CH-632 Rev. 2 l Page 33 of 77 l

4.4 RB Sump Gamma Isotopic and Boron Analysis 4.4.1 VERIFY radio communication.

WHEN sample team exits OSC, THEN VERIFY radio communication with OSC Chemistry Coordinator or designee 4.4.2 ALIGN system for sample.

1. SELECT CAP-1 0 control switch to OFF

2. POSITION the following valves

[] NORMAL RB Sump sample OPEN CAV-448 CLOSE CAV-439 CLOSE CAV-636 OR

[] ALTERNATE RB Sump sample CLOSE CAV-636

3. OPEN the following valves OPEN CAV-519 OPEN CAV-447

4. POSITION the following valves CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK I CH-632 Rev. 2 - Page 34 of 77

CAUTION When sampling RB Sump ALTERNATE sample point, sample is pumped to the MWST which could result in increased radiation levels in the AB.

NOTE Operating CAV-500 requires an entry to 95' lB 4.4.3 OPEN sample valves.

I] NORMAL RB Sump sample

1. REQUEST Operations OPEN containment isolation valves CAV-434 CAV-436

2. Operations REPORTS valves OPEN OR

[] ALTERNATE RB Sump sample OPEN CAV-500 (located inside 95' IB approximately 3' past OTSG sample valve manifold approximately 7' above floor) 4.4.4 ALIGN CAT-8.

SELECT CAP-10 control switch to AUTO START CAP-14 4.4.5 ENSURE CAV-701 positioned to PORT 2. This determination was made during the pre-job briefing. If an entry is needed, CAV-701 is located in the PASS room (95' AB) inside CAX-1. CAX-1 is located on LEFT after entering PASS room. CAV-701 is located MIDDLE LEFT inside CAX-1 approximately head high.

4.4.6 PRIME CAP-8

1. OPEN demineralized water supply valves DWV-337 CAV-471

2. START CAP-8

3. THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI.

CH-632 Rev. 2 Page 35 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.4.7 REQUEST Operations OPEN containment isolation valves.

1. OPEN sample isolation valves:

[] NORMAL RB Sump sample CAV-433 CAV-435 OR

[] ALTERNATE RB Sump sample CAV-434 CAV-436

2. - Operations REPORTS valves OPEN

3. _ THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI.

4.4.8 WHEN stable flow indicated at CA-74-FI, THEN CLOSE CAP-8 priming water valves.

DWV-337 CAV-471 CH-632 I Rev. 2 1 Page 36 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.4.9 ADJUST sample flow.

1. THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

2. - ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch NOTE Step 4.4.11 may be performed while flushing sample.

4.4.10 FLUSH sample lines.

FLUSH at least 35 minutes 4.4.11 IF gamma isotopic analysis is to be performed, THEN ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[ lLiquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[] QC requirements met I CH-632 I Rev.22 Pa e 37 of 77

NOTE The gamma isotopic analysis step may be repeated for multiple gamma analyses.

NOTE Enclosure 5 may be used to evaluate % core damage.

NOTE Gamma isotopic and boron analysis may be performed concurrently.

4.4.12 IF gamma isotopic analysis is to be performed, THEN PERFORM the following:

1. - VERIFY minimum sample flush time complete

2. REFER to Enclosure 4 for gamma isotopic analysis SELECT Reactor Building Sump Sample

3. - ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s)

I CH-632 I I Rev. 2 l Page 38 of 77 l

NOTE Boronometer readout normally updates once per 15 minutes.

4.4.13 IF boron analysis is to be performed, THEN PERFORM the following:

1. ENSURE sample flushed through boronometer at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

4.4.14 ALIGN for demineralized water flush.

1. OPEN demineralized water supply valves DWV-337 CAV-471

2. REQUEST Operations CLOSE sample isolation valves

[] NORMAL RB Sump sample CAV-433

__ CAV-435 OR -

[] ALTERNATE RB Sump sample CAV-434 CAV-436

3. - Operations REPORTS valves CLOSED

4. - THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm at CA-74-FI I CH-632 II Rev.

Rev.22 X I Page 39 Page 39 of I of 77 1

4.4.15 ENSURE adequate system purge.

1.- ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. SELECT Flush Sample Lines

4. SELECT Sump Demin Flush

5. - FLUSH at least 10 minutes

6. - PRESS ENTER when flush is complete

7. - SELECT Quit to exit

8. - ENTER LO to log off PASS NOTE Operating CAV-500 requires an entry to 95' lB.

4.4.16 SECURE line-up.

1. STOP CAP-8

2. STOP CAP-14

3. SELECT CAP-10 control switch to OFF

4. CLOSE demineralized water isolation valves DWV-337 CAV-471

5. ENSURE CLOSED the following valves CAV-519 CAV-447 CAV-448 CAV-623 CAV-624 CAV-625 CAV-626

6. NOTIFY Operations to ENSURE CLOSED the following valves CAV-436 CAV-434

7. _ IF ALTERNATE RB Sump sample was obtained, THEN CLOSE CAV-500 (located inside 95' IB approximately 3' past OTSG sample valve manifold approximately 7' above floor)

I CH-632 I Rev. 2 l Page 40 40 of of 77 1I I CH-632 I Rev.2 I PaQe 77

4.4.17 RESTORE normal configuration.

1. __ ENSURE OPEN CAV-439

2. -OPEN CAV-636

3. - SELECT CAP-10 control switch to AUTO Section 4.4 Complete /

InitiaVDate l CH-632 I Rev. 2 l Page41 of 771

4.5 Decay Heat Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler 4.5.1 WHEN sample team exits OSC.

THEN VERIFY radio communications with OSC Chemistry Coordinator or designee.

NOTE CASB-5 exhaust fan (AHF-55) switch is located to the right of Intermediate Building door (across from RM-A7) 4.5.2 ESTABLISH ventilation for liquid grab sampling.

- POSITION AHF-55 switch to ON 4.5.3 ENSURE liquid grab sampler, CASB-5, installed.

[I] Liquid grab sampler already installed OR REFER to Enclosure 10 for liquid grab sampler installation instructions 4.5.4 ALIGN system for sample.

1. SELECT CAP-1 0 control switch to OFF

2. CLOSE the following valves CAV-439 CAV-636

3. OPEN the following valves CAV-519 CAV-447 CAV-448

4. POSITION the following valves CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK CH-632 I Rev. 2 Pa e 42 of 77

4.5.5 REQUEST Operations OPEN containment isolation valves.

1. OPEN RB Sump return isolation valves CAV-436 CAV-434

2. - Operations REPORTS valves OPEN 4.5.6 ALIGN CAT-8.

SELECT CAP-10 control switch to AUTO START CAP-14 4.5.7 ENSURE CAV-701 positioned to PORT 2. This determination was made during the pre-job briefing. If an entry is needed, CAV-701 is located in the PASS room (95' AB) inside CAX-1. CAX-1 is located on LEFT after entering PASS room.

CAV-701 is located, MIDDLE LEFT inside CAX-1 approximately head high.

4.5.8 OPEN DH system sample isolation valves.

[] Decay Heat Train "A" CAV-441 CAV-440 OR

[3 Decay Heat Train "B" CAV-442 CAV-440 l CH-632 I Rev. 2 1 Page 43 of 77

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.5.9 ADJUST sample flow.

1. THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI. DO NOT exceed 175 psig at CA-89-PI

2. ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch NOTE Step 4.5.11 may be performed while sample flushing.

4.5.10 FLUSH sample lines.

FLUSH for at least 5 minutes.

4.5.11 ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[] Liquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[] QC requirements met NOTE Gamma isotopic and boron analysis may be performed concurrently with liquid grab sampler flush.

CH-632 Rev. 2 Page 44 of 77 1

4.5.12 ALIGN system for liquid grab sample

1. - ENSURE minimum sample flush time complete

2. - OPEN CAV-445

3. _ OPEN CAV-446

4. CLOSE CAV-447

5. FLUSH at least 15 minutes.

NOTE The gamma isotopic analysis step may be repeated for multiple gamma analyses.

4.5.13 PERFORM gamma isotopic analysis.

1. - VERIFY minimum sample flush time complete

2. REFER to Enclosure 4 for gamma isotopic analysis SELECT applicable sample point

[] A-Decay Heat Train Sample OR

[] B-Decay Heat Train Sample

3. ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s)

NOTE CAV-492 and CAV-493 are on the grab sampler.

4.5.14 ISOLATE grab sample.

1. - CLOSE CAV-492

2. -CLOSE CAV-493 Grab sample Date/Time l CH-632 I Rev. 2 I Page45 of 77

NOTE Boronometer readout normally updates once per 15 minutes.

4.5.15 IF boron analysis is to be performed, THEN PERFORM the following:

1. ENSURE sample flushed through boronometer at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

4.5.16 ALIGN for demineralized water flush.

1. CLOSE sample isolation valves.

[ I Decay Heat Train UA" CAV-441 CAV-440 OR

[] Decay Heat Train UB" CAV-442 CAV-440

2. OPEN the following demineralized water supply valves DWV-337 CAV-471

3. _ START CAP-8

4. _ THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI CH-632 I Rev. 2 Pa e 46 of 77

4.5.17 ENSURE adequate system purge.

1. ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. SELECT Flush Sample Lines

4. SELECT Sump Demin Flush

5. FLUSH at least 10 minutes

6. PRESS ENTER when flush is complete

7. SELECT Quit to exit

8. ENTER LO to log off PASS 4.5.18 SECURE line-up.

1. OPEN CAV-447

2. CLOSE CAV-445

3. CLOSE CAV-446

4. FLUSH at least 1 minute

5. STOP CAP-8

6. STOP CAP-14

7. SELECT CAP-10 control switch to OFF

8. CLOSE demineralized water isolation valves DWV-337 CAV-471

9. CLOSE the following valves CAV-519 CAV-447 CAV-448 CAV-623 CAV-624 CAV-625 CAV-626

10. NOTIFY Operations to CLOSE the following valves CAV-436 CAV-434 4.5.19 RESTORE normal configuration.

1. ENSURE OPEN CAV-439

2. OPEN CAV-636

3. SELECT CAP-10 control switch to AUTO I CH-632 I Rev. 2 I Page Paae 47 47 of of 77 77 I CH-632 Rev. 2

4.5.20 REMOVE Liquid Grab Sampler, CASB-5.

1.- REMOVE liquid grab sampler from sample station, REFER to Enclosure 10

2. - TRANSPORT liquid grab sampler to 95' TB Crane Well

3. - UNBOLT liquid grab sampler from cart using 3/4/4" wrench or equivalent as determined by Chemistry Technician

4. - INSTALL transit cover over quick connects

5. - MEASURE dose rates from liquid grab sampler Contact dose rate (side of pig) mR/hr Dose rate ©3 feet mR/hr 4.5.21 PREPARE for liquid grab sample shipment.

REFER to Enclosure 11 for off-site shipment and notifications Section 4.5 Complete /

Initial/Date I CH-632 I Rev. 2 1 Page 48 of 771

4.6 RB Sump Gamma Isotopic, Boron, or Grab Sample Via CASB-5 Liquid Grab Sampler 4.6.1 WHEN sample team exits OSC.

THEN VERIFY radio communications with OSC Chemistry Coordinator or designee.

NOTE CASB-5 exhaust fan (AHF-55) switch is located to the right of Intermediate Building door (across from RM-A7) 4.6.2 ESTABLISH ventilation for liquid grab sampling.

POSITION AHF-55 switch to ON 4.6.3 ENSURE liquid grab sampler, CASB-5, installed.

[] Liquid grab sampler already installed OR

[] REFER to Enclosure 10 for liquid grab sampler installation instructions 4.6.4 ALIGN system for sample.

1. SELECT CAP-1 0 control switch to OFF

2. POSITION the following valves

[] NORMAL RB Sump sample OPEN CAV-448 CLOSE CAV-439 CLOSE CAV-636 OR

[] ALTERNATE RB Sump sample CLOSE CAV-636

3. OPEN the following valves:

OPEN CAV-519 OPEN CAV-447

4. POSITION the following valves:

CAV-623 to SAMPLE CAV-625 to SAMPLE CAV-626 to DRAIN TANK CH-632 Rev. 2 l Page 49 of 777

CAUTION When sampling RB Sump ALTERNATE sample point, sample is pumped to the MWST which could result in increased radiation levels in the AB.

NOTE Operating CAV-500 requires an entry to 95' lB 4.6.5 OPEN sample valves.

[] NORMAL RB Sump sample

1. REQUEST Operations OPEN containment isolation valves CAV-434 CAV-436

2. Operations REPORTS valves OPEN OR

[] ALTERNATE RB Sump sample OPEN CAV-500 (located inside 95' lB approximately 3' past OTSG sample valve manifold approximately 7' above floor) 4.6.6 ALIGN CAT-8.

SELECT CAP-10 control switch to AUTO START CAP-14 4.6.7 ENSURE CAV-701 positioned to PORT 2. This determination was made during the pre-job briefing. If an entry is needed, CAV-701 is located in the PASS room (95' AB) inside CAX-1. CAX-1 is located on LEFT after entering PASS room.

CAV-701 is located MIDDLE LEFT inside CAX-1 approximately head high.

4.6.8 PRIME CAP-8

1. OPEN demineralized water supply valves:.

DWV-337 CAV-471

2. _ START CAP-8

3. THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI.

. I CH-632 I Rev.2 Rev. 2 Pane Page 50 77 1I of 77 50of

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.6.9 REQUEST Operations OPEN containment isolation valves.

1. OPEN sample isolation valves:

[ ] NORMAL RB Sump sample CAV-433 CAV-435 OR

[] ALTERNATE RB Sump sample CAV-434 CAV-436

2. - Operations REPORTS valves OPEN

3. - THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-FI.

4.6.10 WHEN stable flow indicated at CA-74-FI, THEN CLOSE CAP-8 priming water valves.

DWV-337 CAV-471 CH-632 Rev. 2 P 51 of 777 Page

CAUTION Exceeding 175 psig on CA-89-PI may cause relief valve CAV-491 to open.

Flow from this valve is routed to the MWST, which could cause radiation levels to increase in the AB.

NOTE Flow downstream of CAV-491 is indicated at CA-50-FS located on countroom mimic panel. The GREEN light indicates NO FLOW. The RED light indicates FLOW.

4.6.11 ADJUST sample flow.

1. _ THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm at CA-74-FI. DO NOT exceed 175 psig at CA-89-PI.

2. - ENSURE NO FLOW indicated (GREEN light lit) at CA-50-FS flow switch.

NOTE Step 4.6.13 may be performed while flushing sample.

4.6.12 FLUSH sample lines.

- FLUSH at least 35 minutes 4.6.13 ENSURE PASS AIMS detector CA-54-CE ready for use.

REFER to Enclosure 3 for guidance

[] Liquid nitrogen dewar > 50 pounds

[] Detector voltage adjusted

[] QC requirements met CH-632 Rev. 2 Page 52 of 77

NOTE Gamma isotopic and boron analysis may be performed concurrently with liquid grab sampler flush.

4.6.14 ALIGN system for liquid grab sample 1.- ENSURE minimum sample flush time complete

2. - OPEN CAV-445

3. OPEN CAV-446

4. - CLOSE CAV-447

5. FLUSH at least 15 minutes.

NOTE.

The gamma isotopic analysis step may be repeated for multiple gamma analyses.

4.6.15 PERFORM gamma isotopic analysis.

1. VERIFY minimum sample flush time complete

2. REFER to Enclosure 4 for gamma isotopic analysis SELECT Reactor Building Sump Sample

3. ATTACH gamma scan(s) to this procedure Gamma Scan ID number(s)

NOTE CAV-492 and CAV-493 are located on the grab sampler 4.6.16 ISOLATE grab sample.

1. -CLOSE CAV-492

2. -CLOSE CAV-493 Grab sample Date/Time CH-632 Rev. 2 Page 53 of 77

NOTE Boronometer readout normally updates once per 15 minutes.

4.6.17 IF boron analysis is to be performed, THEN PERFORM the following:

1. ENSURE sample flushed through boronometer at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. OBSERVE boron concentration at CA-56-CI Boron Concentration(s) ppm ppm ppm 4.6.18 ALIGN for demineralized water flush.

1. OPEN demineralized water supply valves DWV-337 CAV-471

2. REQUEST Operations CLOSE sample isolation valves

[] NORMAL RB Sump sample CAV-433 CAV-435 OR

[] ALTERNATE RB Sump sample CAV-434 CAV-436

3. - Operations REPORTS valves CLOSED

4. - THROTTLE CAV-624 to MAINTAIN 0.35-0.50 gpm on CA-74-Fi I CH-632 I Rev. 2 Page 54 of 77

4.6.19 ENSURE adequate system purge.

1. ENSURE logged onto PASS computer

2. ENSURE PASS Menu selected

3. - SELECT Flush Sample Lines

4. _ SELECT Sump Demin Flush

5. - FLUSH at least 10 minutes

6. - PRESS ENTER when flush is complete

7. SELECT Quit to exit

8. - ENTER LO to log off PASS NOTE CAV-500 is located in the Intermediate Building 4.6.20 RESTORE system line-up.

1. OPEN CAV-447

2. CLOSE CAV-445

3. CLOSE CAV-446

4. FLUSH at least 1 minute

5. STOP CAP-8

6. STOP CAP-14

7. SELECT CAP-10 control switch to OFF

8. CLOSE demineralized water supply valves DWV-337 CAV-471

9. ENSURE CLOSED the following valves CAV-519 CAV-447 CAV-448 CAV-623 CAV-624 CAV-625 CAV-626

10. NOTIFY Operations to ENSURE CLOSED the following valves:

CAV-436 CAV-434

11. IF ALTERNATE RB Sump sample was obtained, THEN CLOSE CAV-500 I CH-632 I Rev. 2 l Page 55 of 77

4.6.21 RESTORE normal configuration.

1. ENSURE OPEN CAV-439

2. OPEN CAV-636

3. SELECT CAP-10 control switch to AUTO 4.6.22 REMOVE Liquid Grab Sampler, CASB-5.

1. - REMOVE liquid grab sampler from sample station, REFER to Enclosure 10

2. - TRANSPORT liquid grab sampler to 95' TB Crane Well

3. - UNBOLT liquid grab sampler from cart using 3/4" wrench or equivalent as determined by Chemistry Technician

4. - INSTALL transit cover over quick connects

5. - MEASURE dose rates from liquid grab sampler Contact dose rate (side of pig) mR/hr Dose rate @ 3 feet mR/hr 4.6.23 PREPARE for liquid grab sample shipment.

REFER to Enclosure 11 for off-site shipment and notifications Section 4.6 Complete /

Initial/Date l CH-632 I Rev. 2 l Page 56 of 77

5.0 CONTINGENCIES 5.1 Relief Valve Flow Indicated at CA-50-FS Flow Switch k5.1.

5.1 .1 NOTIFY OSC Chemistry Coordinator, or designee 5.1.2 ENSURE CAV-484 adjusted to maintain the following parameters

CA-89-PI < 175 psig

CA-74-FI 0.35-0.50 gpm 5.1.3 IF relief valve(s) are lifting AND CANNOT be re-seated, THEN PERFORM the following:

OSC Chemistry Coordinator, or designee, approves continued system operation CONTINUE with applicable section of this procedure OR

[1 PERFORM demineralized water flush and secure PASS per applicable section of this procedure.

il Section 5.1 complete Initial/Date l CH-632 I Rev. 2 l Page57 of 77

5.2 PASS Temperatures Greater Than Expected 5.2.1 NOTIFY OSC Chemistry Coordinator or designee 5.2.2 REDUCE sample flow by throttling CAV-484. ENSURE CAV-484 adjusted to maintain the following parameters.

CA-89-PI < 175 psig

CA-74-FI 0.35-0.50 gpm 5.2.3 ENSURE relief valves NOT lifting. Flow downstream of relief valves is indicated by CA-50-FS RED light lit.

5.2.4 IF temperatures are greater than expected AND CANNOT be adjusted to desired temperatures, THEN PERFORM the following:

[] OSC Chemistry Coordinator, or designee, approves continued system operation.

CONTINUE with applicable section of this procedure OR

[] PERFORM demineralized water flush and secure PASS per applicable section of this procedure.

I/

Section 5.2 complete Initial/Date CH-632 Rev. 2 Page 58 of 77

5.3 CAT-8 Hi-Hi Level Alarm 5.3.1 ENSURE the following interlock functions occurred:

[] CAV-623 indicates CLOSED (green light lit)

[] CAV-627 indicates CLOSED (green light lit)

[] CAP-10 STOPPED (green light lit) 5.3.2 ENSURE the following control switches positioned as followed:

[] CAV-623 selected to CLOSE

[] CAV-627 selected to CLOSE

[] CAP-10 selected to OFF 5.3.3 PUMP CAT-8.

1. DEPRESS and HOLD CAT-8 level RESET button

2. START CAP-1 0 (control switch to ON position)

3. CONTINUE depressing CAT-8 level RESET button until CAT-8 HI-HI and Hi LEVEL alarms are clear 5.3.4 RESTORE system.

POSITION CAV-623 to SAMPLE (if valve was positioned to SAMPLE for section of procedure being performed)

- POSITION CAV-627-to SAMPLE (if valve was positioned to SAMPLE for section of procedure being performed)

SELECT CAP-10 control switch to AUTO 5.3.5 CONTINUE procedure at applicable step.

SmI_

Section 5.3 complete Initial/Date CH-632 Rev. 2 Pae 59 of 77 l

5.4 Estimating Grab Sample Shipment Curie Content When Gamma Spectroscopy System is Unavailable 5.4.1 ESTIMATE curie content of grab sample.

REFER to Enclosure 12 l

Section 5.4 complete Initial/Date 5.5 Manual Collimator Positioning and Manual Gamma Isotopic Analysis 5.5.1 PURGE sample line.

ENSURE sample line flush complete per applicable gamma spectroscopy section of this procedure 5.5.2 PERFORM gamma isotopic analysis.

1. - POSITION collimator and near line valves manually per Enclosure 13.

2. - PERFORM gamma isotopic analysis manually per Enclosure 13.

3. - RECORD gamma ID number in applicable gamma isotopic analysis section and CONTINUE procedure at that point.

Section 5.5 complete InitiaVDate l CH-632 I Rev.22 Page 60 of 77 l

ENCLOSURE 1 (Page 1 of 2)

TECHNICAL SUPPORT CENTER DATA SHEET Sample Point

[] RC Letdown LI DH

[] RB Sump Chemical Analyses Boron ppm Initials/Date/Time Boron ppm Initials/Date/Time Boron ppm Initials/Date/Time Boron ppm Initials/Date/Time OSC Chemistry Coordinator I CH-632 Il Rev. 2 - Page 61 of 77 1

ENCLOSURE 1 (Page 2 of 2)

TECHNICAL SUPPORT CENTER DATA SHEET Sample Point

[] RC Letdown

[I DH

[] RB Sump Gamma Isotopic Analysis Mai(or Contributing Isotopes Isotope Activity PCirnI PCVmI PCilml pCi! ml PCVmI pCi/mi pCi/mi PCi/mi pCi/MI pCi/mI pCi/mi pCi/mI PCi/mi Total Activity pCimi Initials/Date/Time ESTIMATE core damage per Enclosure 5.

OSC Chemistry Coordinator II Rev.2 Page 62 of 77 I I1CH-632 - Rev. 2 l Page 62 of 77

ENCLOSURE 2 (Page 1 of 1)

Guidelines for Monitoring PASS System Parameters

1. LOG ON to PASS

[] LOG ON from CRCHEM ENTER PASS. There is no password OR

[] Log on from CHIP

a. LOG ON to CHIP using personal username and password

b. SELECT PASS (CRCHEM) from Main Menu

c. ENTER username PASS. There is no password.

2. SELECT PASS menu

3. SELECT DISPLAY ND68DC INPUT VALUES NOTE The displayed parameters are not continuously updated. Pressing ENTER updates the displayed parameters with current values.

4. MONITOR the required parameters.

5. WHEN monitoring is complete, THEN ENTER Q to quit.

6. [ 3 ENTER Y to obtain a hard copy of the parameters and return to PASS Main Menu OR

[] ENTER N to return to PASS Main Menu I CH-632 I Rev. 2 l Page 63 of 77

ENCLOSURE 3 (Page 1 of 1)

PASS AIMS Pre-Analysis Check Guidelines

1. VERIFY dewar weight > 50 as indicated at liquid nitrogen monitor CA-54-LT.

CAUTION AIMS detector CA-54-CE HV supply potentiometer should be adjusted to 0 volts before resetting liquid nitrogen monitor CA-54-LT low level voltage trip or detector damage may occur.

2. ENSURE PASS HV supply voltage adjusted per PASS and RANGE AIMS Equipment Logbook.

CAUTION Increasing detector voltage > 100 volts/second may cause detector damage.

3. IF PASS detector voltage is secured, THEN ADJUST detector voltage as follows:

a. ENSURE CA-54-CE HV supply voltage potentiometer adjusted full counterclockwise

b. DEPRESS liquid nitrogen monitor CA-54-LT HV RESET button.

c. DEPRESS CA-54-CE HV supply voltage. RESET button.

d. ENSURE CA-54-CE HV supply power switch selected to ON position

e. ADJUST CA-54-CE HV supply voltage per PASS and RANGE AIMS Equipment Logbook.

f. LOCK CA-54-CE voltage potentiometer at correct voltage reading

4. ENSURE calibration check completed.

Calibration Check completed within past 7 days OR PERFORM calibration check per CH-234, Post Accident Sampling System Gamma Spectroscopy System.

I CH-632 I Rev. 2 l Page 64 of 77

ENCLOSURE 4 (Page 1 of 1)

Guidelines for Performing Gamma Spectroscopy Analysis

1. LOG ON to PASS

[ ] LOG ON PASS from CRCHEM ENTER username PASS. There is no password.

OR

[ ] LOG ON PASS from CHIP

a. LOG ON'to CHIP using personal username and password

b. SELECT PASS (CRCHEM) from Main Menu

c. ENTER username PASS. There is no password.

2. SELECT PASS menu

3. SELECT Liquid Sampling

4. SELECT sample point based on section of procedure being performed

5. IF system parameters are displayed (MUX display),

THEN ENTER Q to quit AND ENTER N at prompt for aborting sample NOTE The default sample parameters are normally used. Sample time and volume are automatically updated by software. Specific parameters may be edited as needed on a case by case basis..

6. UPDATE sample parameters

7. SELECT ACCEPT I CH-632 I Rev. 2 l Page 65 of 77

( C C ENCLOSURE 5 (Page 1 of 2)

ASSESSMENT OF CORE DAMAGE BASED ON REACTOR COOLANT SAMPLE Assumptions and Limitations

1. Use of RCS sample results to estimate the extent of core damage is subject to significant uncertainties. Many orders of magnitude error are possible due to factors such as:

fraction of an isotope assumed to be released from the fuel matrix

homogeneity of the activity in the RCS

whether or not sample is representative

effects of removal mechanisms

2. Given the possible magnitude of the above errors, no corrections are made for the following minor factors:

Radioactive decay (longer half-life nuclides chosen to minimize error)

Dilution volume (assumes CFT's have discharged and BWST injection to low alarm setpoint)

RCS temperature and density corrections

Reactor power history (assumes end of cycle activities for long lived nuclides and assumes shorter lived nuclides at equilibrium)

Release from the RCS. Nuclides chosen should remain in RCS (noble gases not included)

3. Appropriate corrections may be applied if desired. For example, if no water has been added from the CFT's or BWST, then results could be reduced by a factor of 5.5 (510,000 lb RCS mass vs. 2,800,000 lb mass RCS, BWST and CFT's)

Estimating Core Damage

1. COMPLETE Table 1.

2. REPORT results to Radiation Controls Coordinator and Accident Assessment Team CH-632 Rev. 2 l Page 66 of 77

( c (7 ENCLOSURE 5 (Page 2 of 2)

ASSESSMENT OF CORE DAMAGE BASED ON REACTOR COOLANT SAMPLE DATE/TIME OF RCS SAMPLE: DATE/TIME OF RX SHUTDOWN:_

Table 1 F l ea c t o orIrc t o ai E pe t d .'E C.u pe t d O tj X X W W X ffi f i i -MelV90 Samplt .( - - Axtc) % yer ea lt ,., nRes - n~len r -. e ease Fractlon'1tr. K'

) ( C~ I m~ RC ~ ~ ( C) :; <~ t t ~ SF r at i o O x E- - F , i 1 0 o~ l O x( E +( G)~

1-131 1300 6.7E7 0.05 0.4 Cs-134 1300 8.9E6 0.05 0.3 Cs-1 37 1300 5.OE6 0.05 _ 0.3 Te-132 1300 9.7E7 0 NA 0.05 Ru-103 1300 9.4E7 0 NA 0.0025 Ba-140 1300 1.3E8 0 NA 0.02 Ce-144 1300 7.1 E7 0 NA 0.0005 Np-239 1300 1.3E9 0 NA 0.0005 Note 1: Enter 100% if greater than 100%

OSC Chemistry Coordinator Initial/Date I CH-632 I C 2R

_6 Rev. v2 Page a~ e67 6 off 77 7 1

ENCLOSURE 6 (Page 1 of 1)

Guidelines for Operating EG&G Flow Technology Flow Meters Zeroing flow totalizer DEPRESS RESET button Displaying Totalizer Reading DEPRESS TOTAL (number 1) button. Total volume (gallons) is displayed Displaying Flow Rate Readinq DEPRESS RATE (number 3) button. Flow rate (gpm) is displayed Displaying both Totalizer and Flow Rate Readings DEPRESS DISPLAY (number 0) button to display both total volume (gallons) and flow rate (gpm)

CH-632 Rev. 2 l Page 68 of 77

ENCLOSURE 7.

(Page 1 of 1)

Guidelines for Liquid Grab Sampler Installation and Removal Installation NOTE Grab sampler preparation is normally done in a low dose area.

1. PREPARE grab sampler

a. ENSURE grab sampler bolted to grab sampler cart

b. ENSURE transit cover removed from grab sampler

c. STORE transit cover by attaching to lifting ring on grab sampler with break-away type device.

d. OPEN CAV-492

e. OPEN CAV-493

2. INSTALL grab sampler

a. ENSURE ramp installed

b. GUIDE grab sampler into sample station until sampler is within several inches of connection point

c. CONTINUE to GENTLY guide grab sampler until fully inserted into sample station

d. ENGAGE Cart to Station Lock

e. GENTLY PULL Engagement Handle to connect quick connects

f. DISENGAGE Cart to Station Lock

g. ENSURE grab sampler moves when Engagement Handle is moved back and forth.

h. ENGAGE Cart to Station Lock Removal

1. ENSURE ramp installedO

2. SQUEEZE Engagement handle lever and PUSH to engagement handle toward wall

3. DISENGAGE Cart to Station Lock

4. REMOVE grab sampler from sample station I CH-632 I Rev. 2 Page69 of 77

ENCLOSURE 8 (Page 1 of 1)

Grab Sample Shipment and Notifications NOTE Notifications may be made in any order.

1. NOTIFY Superintendent, Nuclear Operations Materials Controls

A grab sample has been collected

INITIATE acquisition process for shielded sample cask

2. NOTIFY RNP E&C Superintendent that a grab sample has been collected

3. The following information is needed:

Utility and plant name

Name and phone number of E&C Specialist to whom follow-up communication should be addressed

Number and type of samples being shipped

Measured radiation levels at surface and three feet from shipping container

Estimated shipping time

Mode of transportation

Carrier

Estimated time of arrival at RNP in Hartsville, SC

4. USE the following shipping address:

Progress Energy Carolinas Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29990 Attn: E&C Superintendent Phone (Caronet) 450-1837 -

I CH-632 l Rev. 2 Page 70 of 77

ENCLOSURE 9 (Page 1 of 4)

Estimating Grab Sample Curie Content When Gamma Spectroscopy System is Unavailable

1. DETERMINE which of the following best represents the sample. Emergency Response support personnel may be used to make this determination Pressurized Liquid Sample

[ ] Fuel Gap Release - use column A OR

[ Fuel Melt Release - use column B Depressurized Liquid Sample

[ Fuel Gap Release- use column C OR

[ Fuel Melt Release- use column D

2. RECORD Contact Dose Rate (side of pig) from the grab sample, CASB-5.

Contact Dose Rate (side of pig) mR/hr

3. DETERMINE pCi per mR/hr Pressurized Liquid Sample

[ ] Fuel Gap Release = 2.OOE+4 pCi per mR/hr OR

[ Fuel Melt Release = 2.50E+4 pCi per mR/hr Depressurized Liquid Sample

[] Fuel Gap Release = 1.50E+4 pCi per mR/hr OR

[ Fuel Melt Release = 1.50E+4 pCi per mR/hr

4. CALCULATE total activity.

Total Activity = Contact Dose Rate (side of pig) x ,uCi per mR/hr Total Activity pCi

5. CALCULATE individual nuclide activity. RECORD results in Table 1.

Individual Nuclide Activity = Total Activity x nuclide fraction of total activity l CH-632 I Rev. 2 l Page71 of77

(

ENCLOSURE 9 (Page 2 of 4)

.,., ;, -_- TA B LE A -

V,;',` ,

- .;--eIt-O'. . , ... I- . ".'I ,I -- ,1'-",',-_.",;", P. .i -

r, ." " 'i. ,-

.;" , , " ;., t

. .l. 1,' !, , :'t F,'-...

1, 1 -, 11 I ,, " , .. .

- I. . t " ?.- " it "- " 'I, :-

1. ; v. ".t ,I,-' I .,- .1,I I

' i'i.,

- .-- . ; -, '.,,b

,, i,.": ! Ili .,;It,!.. '. ; ",

.1! IjI

-,, J,,1;,. Y .,. i.. , `;

I., I. i .. " ,A I ,; - :` `:,: : _;4 .., "".1. ". . 1.1i ; . I.... ... A ...... -. ,z.. . V-itt ; cid r-, < :~ldiidal ~ N clde ;;-: lndivid I ;- -cidi .!-ldividuai. !@ HNdclide ;,...

7:'di tvf iif pluci Ntci Kr85 1.22E-03v -fia: V6i .ivi:

I.4E0 -,:Av T6taW'6v- civt,-,; ,Act 'it': ,;i,}

Kr85 1 Il5-0 2.49E-025Ns ,.P>XSa>8. ,o, t@,l't ',t\*

Kr87~ ~~~~~~~~~

1.3l.0 ' 2.02E-0 -- JD>-s.5 ~;-U ,tg Rb86091E0 4.16-58.E-0-0 1.02E-04 Sr89 1.22E-03tw ;1ti^ .31E-03 ttfzF?'n6++--lr o&s-sFlAi :13E0 Sr90m 1 .88E-04 f' <-y - ; , +,-^J-;^:-

2l.49 s S70E-04 -i Sr92 1.3>.---*^; ;.,<.>: ;;- .4E-043 ;t>et:,.:

2.27E-03 ¢ ,j--t Kg f88-*

Zt 2.OO tr E-06 ;t .; 3.01 E ;;t 't ~ .6-02 Y9Rb86J";;o 9.19E~tiJ -05t M*;., 416E-05 _ 5 -E'-04 r. , 19B .66E-05 Yr93 -. ;-> s.-:r n~ .9 -5i -0;F¢i, Zr95 ,. .. ;.".. ;31 , ~ ^7,.2- <.F -F-:20E-04

-- ]8.1E-05 Zr97 i- 7 t,.,,t ,niir/*¢!ri;; $<$ ;!61E-053 Mo99 . ,ztl.n, v. a .:- 9i .04E 03 - ,03.,

Tc9 m i !'Uttjlvg'i'-.." t-06 <t' 6,*~t' 2 z.90E-046,,>;r.

Ru1038>;-4! r{ E~ e; >; 8.39E-045; ; < jr s;S wr 20E-0 Ru0Y92 ~ j<. t8iwss ,.U ' ,'! i' 1 .49E-05 -t{ ;.i -j- 3.87E-04 Ru10 i --. ti;wq-192E-04 4.6;v.>- :1 <# *,j l- .715E-04 ZRhl5 i:;,@ ;; jF+;lt0;4;- 32E :;; 4-.; ; ' .i Sb7itr;<'-.1tt:I , 2.40E-0 g-9.7E-045fg-2-s; r ;"- '

Sbl 29 -> F <,,;- ,i*, v +-, l ,vi ; - >,1.0E3E ;;251 Tel27 4:¢=. >{ -;- 1.:-;>1;e~; 5.5E0 A-Te2m;7S ¢---S ; .32E-04 .,;;;.- ; ^--.. ,:. 325-04 I CH-632 I: Rev. 2 I Page 72 of 77 l

c ENCLOSURE 9 (Page 3 of 4)

.ou . . ,s. n q~~~~ ~~~~ c.IifdX n AeCTtjXfil.;g Te2F,-rA, . ctio o-~,',!29E0 Uc-1,......<,.-'Fa;,--.--... -i .1E0 s

Te13m . c<t ^'-I

2fib~rf-i`A 1.5E0 v; I... _tvty, ; lr-;- tiv ' Aci'if_3 E0 11329 2.9E921

.6-23E-050 3.0-02 1133 2.5E-0 1 9.54E-01 2.2E-0 37E-03 Te113 6.3E0 14.0E-04 1 0E0.2-03 1135 1 .36E-01 8.22E-02 . 2.24E-01 2.02E-01 Xe133 3 .26E0115E-01 4.82E-01 3s;.,-,,,L7,

<^¢ )',*rt-!,>^r' ; '9E-0-;

Cs134 2.13E-02 9.64E-03 3.51 E-02 2.37E-02 Cs136 6.37E-03 2.88E-03 1 .05E-02 7.08E-03 Cs137 1.1 9E-02 5.39E-03 1 .96E-02 1.32E-02 Ba139 ~;v,;3';W

. T,-g -seS_4 1.67E-04 IrE ,;04;' 4.1>

Ba140 8 >S t-'itX<J '.f~ j7Y,,i90E0 -,*-S .,...;--2.23E-02 La1 40 fl .0-

2.10OE-05 ^! ' 5.1 6E-05 t,,t>t42,<.,Wt>

La142 -5.62EQ:.!,- s,4arto-06,*, 22E-6W Ce143 -. ,. .?i'( ,*,

4.24E 04

, j ;rir ,:-, .r:17E-04 Ce144 -- . -f.., -,,

,,,;,S'i'tii -. >>j*t';'31E0

+i-'/ ...... '& ,

ICH-632 -- - Rev. 2 _ Page 73 of 77 1

( (

ENCLOSURE 9 (Page 4 of 4)

,L A- , 66 Ur) ______________________

, . lColumn 'A; - ! 1,'Colu'n.B.< ' . Columnm C Nuclide' Individual A

, N -N' clide,. i " 'Nuclide -lninvidual 'lndividualV, -Nucide - i Individual Frac'tiono >-Nuclide Fractiaction ,N'uclide-

,cino' o Jir Tota ctivit ctivty pCij 'T t1,ActivitV -Activit JiiTotal ,ct it Activit (i Tota Actiit, Actii P r143 f' 7.89E-05 ' ' 1.94E-04 Nd147 ; 3.51 E-05 '4 .>Fi 8.62E-05 Np239 - ... .. 2.18E-03 _;.. 5.35E-03 Pu238 v. .. 1.3 6 E0 7 ; S t - :o..'., . . . . . . . . . 31346-07 Pu239 - -';' 3.07E-08 ______-__ 7.54E-08 Pu240 !r , * '.;- 3.87E-08 _ A i , .51 E-08 __'____'

Pu241 '.- . 6.52E-06 _ - . 1.60E-05 Am 241 . "'1.72E-09 __ _ _ _ _ _ _ _.;7' ~ m 4.23E-09 _ _ _ _ _ _ _ _

Cm242 :, #--" 6.59E07 . - , 162E 0 ______.-___.;

Cm244 , , 3.86E-08 . . . -. ' 9.48E-08 9_

I CH-632 I Rev. 2 1 Page74of77l

ENCLOSURE 10 (Page 1 of 2)

Manual Collimator Positioning and Manual Gamma Isotopic Analysis NOTE Starting with FAR CLOSED and progressively trying more efficient geometries is recommended but not required.

1. POSITION collimator and near line valves per Table 2 until one of the following criteria is met:

adequate count rate observed at CA-54-CE rate meter

NEAR OPEN position lined up with adequate count rate

OSC Chemistry Coordinator or designee determines geometry to be used

2. Manually PERFORM gamma spectroscopy analysis.

I CH-632 I Rev. 2 T Page 75 of 77

ENCLOSURE 10 (Page 2 of 2)

NOTE The collimator position lights represent binary code. The 1, 2, and 3 lights may be disregarded when manually positioning the collimator. These lights represent a total of 7 binary units which is <10% of total collimator movement.

Table 2 Far Closed 258 1,2,9 CLOSED CLOSED OFpaern 101 3,6,7 CLOSED CLOSED RCS Near Closed 210 3,5,7,8 OPEN OPEN Near Open 51 3,5,6 OPEN OPEN Far CLOSED CLOSED Coe 706 1,7,8,10 Far , , , , 10 CLOSED CLOSED Open 868 113,67,9,1CLSD LOE SUMP Na Closed 670 1,2,3,4,5,8,10 OPEN OPEN Nea 3,4,5,6,9,10 OPEN OPEN

___I Open 82 ICH-632 I Rev. 2 l Page 76 of 77 1

RevisionHhitory

1. Deleted RCS Hydrogen, pH and chloride sampling and analysis references due to their removal from Tech Specs. Reference LAR 279 and License Amendment 213.

2. Removed MWST sampling and analysis references due to their removal from Tech Specs.

Reference LAR 279 and License Amendment 213.

3. Added reference to NOCS 100440 for maintaining contingency plans for obtaining and analyzing samples from the RCS, Containment sump and containment atmosphere to Section 3.

4. Added reference to NOCS 100441 for Classifying fuel damage events at the Alert Level for

>300 uCVgm 1-131 Equivalent and for the capability for assessment of radioactive iodines released to the off-site environs to Section 3.

5. Updated Equipment Data Base Reference Section 2.2.

6. Changed title of procedure to reflect those sample points and analysis that are still applicable.

I CH-632 I Rev. 2 l Page 77 of 77

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