ML20215F402

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Rev 0 to 1PCP08-AP-0001, Post-Accident Core Damage Assessment Sampling & Analysis
ML20215F402
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 09/18/1986
From: Kinsey W
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20215F286 List:
References
RTR-NUREG-0737, RTR-NUREG-737 1PCP08-AP-0001, 1PCP8-AP-1, NUDOCS 8610160193
Download: ML20215F402 (11)


Text

b HOUSTON LIGHTING AND POWER COMPANY SQUTH TEXAS PROJECT ELECTRIC GENERATING STATII PLANT PROCEDURES MANUAL.

R INFORMATION ONLY STATION PROCEDURE NON-SAFETY RELATED (Q)

Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. 0 Page 1 of 11 APPROVED:

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DATE APPROVED DATE EFFECTIVE TABLE OF CONTENTS Pg 1.0. Discussion 2

1.1 Purpose and Scope

2 1.2 Definitions 2

1.3 Principle 2

1.4 Limitations 3

2.0 Prerequisites 3

3.0 Precautions 3

4.0 Procedure 3

4.1 Responsibilities 3

4.2 Initiation of PASS 4

4.3 Post Accident Sampling 5

4.3.1 Liquid Sampling and Analysis 5

4.3.2 Gas Sampling and Analysis 6

4.4 PASS Shutdown 7

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5.0 Calculations 8

6.0 Standardization 8

7.0 Documentation 8

8.0 References 8

9.0 Support Documents 9

9.1 Core Damage Assessment Data Package Cover Sheet 10 9.2 Back-up Analyses Data Sheet 11 86'0160193 861009 PDR ADOCK 05000498 E

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Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 2 of 11 1.0 Discussion

1.1 Purpose and Scope

1.1.1 Purpose

The purpose of this procedure is to establish the steps necessary to complete the sampling and analysis of the Reactor Coolant System and of containment atmosphere under accident conditions in a safe, effective manner.

1.1.2 Scope

1.1.2.1 This procedure will define the responsibilities of chemical analysis personnel who will be involved in post accident sampling and analysis activities.

1.1.2.2 This procedure will also outline the steps necessary to complete the following:

a.

Initiation of the Post Accident Sampling System (PASS) b.

Post Accident Sampling and Analysis c.

Shutdown of the PASS 1.2 Definitions 1.2.1 Post Accident Sampling System (PASS): A system composed of various components that provides the capability to obtain Reactor Coolant System and containment atmosphere samples, and perform required analyses during post accident conditions within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time a decision is made to sample.

1.3 Principle 1.3.1 In the'bvent that OEPP01-ZA-0002 (Emergency Direction) activates any portion of the Emergency Plan relating to the integrity of the Reactor Coolant System (RCS), fuel cladding failure, or a potential LOCA, it will be necessary to monitor both plant chemical and radiochemical conditions. Parameters of the Reactor Coolant System (RCS), Residual Heat Removal (RHR) System, and Reactor Containment Building (RCB) sump that will be monitored include pH, specific conductivity, dissolved oxygen, gross gamma activity, boron, chloride, and dissolved hydrogen. Also, the RCB atmosphere will be monitored for gross gamma activity, hydrogen, and oxygen.

From these analytical results, it will be possible to assist in assessment of the accidents" severity, the condition of the core, and verification of the shutdown margin.

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1 Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 3 of 11 1.3.2 This procedure establishes a chronological set of events that 4

will occur in the event of an accident up to a design-base type. These will include the set-up of associated instrumentation, inline and offline monitoring of the various parameters, liquid and gaseous sampling, performing required lab analyses, and shutdown of the PASS when completed. This procedure will also describe the responsibilities of the Chemical Analysis Supervisor, the Lead Chemical Technician, and the Chemical Technician.

1.4 Limitations None 2.0 Prerequisites 2.1 Ensure that a radiation survey has been performed and a Radiation Work Permit (RWP) has been issued in accordance with OPGP03-ZR-0002 (Radiation Work Permit.) An Emergency Radiation Work Permit'may have to be issued immediately af ter the entry.

1 2.2 Entry to and exit from the Pass facility will be coordinated through and directed by the Emergency Director.

3.0 Precautions 3.1 Due to the possibility of high contamination levels, personnel I

entering the PASS facility will dress out in accordance with the RWP, or as directed by Health and Safety Services.

i 3.2 In addition to accepted practices for laboratory safety, additional safety requirements listed in Section 3.7 of OPCP01-ZA-0017 (Post Accident Sampling and Analysis Program) will be followed.

l 4.0 Procedure 4.1 Responsibilities i'

4.1.1 The Chemical Analysis Supervisor is responsible for l

supervising all post accident sampling and analysis activities.

4.1.2 The Lead Chemical Technician (LCT) is responsible for l

initiating operation of the PASS upon direction from the j

Emergency Director. The LCT is responsible for supervising all shift post accident sampling and analysis activities, and for reviewing and reporting all analytical results to the Emergency Director.

Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 4 of 11 4.1.3 The Chemical Technician is responsible for taking all required post accident samples and performing all associated analyses, then reporting results to the Lead Chemical Technician.

4.2 Initiation of PASS NOTE The following steps should be performed in the order in which they are written. However, some steps may be omitted as directed by the Lead Chemical Technician based on the fact that portions of the system may already be in operation or that certain backup analyses may not be required.

4.2.1 Upon rotification from the Emergency Director that any portion of the Emergency Plan has been activated relating to the integrity of the RCS, fuel cladding failure, or a potential LOCA, perform the following steps.

4.2.1.1 Verify that the PASS has been placed in operation in accordance with IPCP08-AP-0002 (Operation and Maintenance of the Post Accident Sampling System).

4.2.1.2 Verify that the PASS in-line analyzers have been standardized in accordance with IPCP08-AP-0002 (Operation and Maintenance of the Post Accident Sampling System).

4.2.1.3 Verify that the Gamma Spectroscopy System has been standardized in accordance with OPCP09-ZO-0001 (Operation of the Gamma Spectroscopy System).

4.2.1.4 Verify that standardizations for the following backup PASS analyses have been completed in accordance with the indicated procedures, if backup analyses will be required.

a.

Boron-1PCP08-AP-0006 (Backup Determination of Boron-Post Accident).

b.

Chlorides-1PCP08-AP-0007 (Backup Determination of Chlorides-Post Accident).

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Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 5 of 11 c.

Hydrogen-1PCP08-AP-0008 (Backup Determination of Hydrogen-Post Accident).

4.3 Post Accident Sampling 4.3.1 Liquid Sampling and Analysis

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4.3.1.1 Perform the sections of IPCP08-AP-0003 (Sampling and Analysis of RCS, RHR, and RCB Sump-Post Accident) as required to complete any of the following.

a.

PASS checkout (4.1 through 4.6) b.

LGSP Flushing (4.7 through 4.12) c.

In-line gross activity analysis (4.8.7)

NOTE Samples will be collected in a shielded syringe.

d.

Collect diluted and/or undiluted RCS, RHR, or RCB Sump Samples (4.14) e.

In-line pH analysis (4.15.1) f.

In-line conductivity analysis (4.15.1) g.

In-line dissolved oxygen analysis (4.15.1) h.

In-line boron analysis (4.15.2) 1.

In-line chloride analysis (4.15.3) j.

In-line dissolved hydrogen analysis (4.16) 4.3.1.2 Report results of in-line analyses to the Lead Chemical Technician as they become available.

NOTE Data Sheets may be completed later in a lower dose area.

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Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. 0 Page 6 of 11 4.3.1.3 Complete the appropriate sections of the RCS, RHR, and RCB Sump Data Sheet (IPCP08-AP-0003-02) corresponding to the analysis performed.

4.3.1.4 Transport diluted samples to the Radiochemistry Laboratory in accordance with OPRP03-ZM-0014 (Movement of Material Out of Radiologically Controlled Area), if required.

4.3.1.5 Perform the backup analyses on a diluted liquid sample if required.

a.

Boron-1PCP08-AP-0006 (Backup Determination of Boron-Post Accident).

b.

Chlorides-1PCP08-AP-0007 (Backup Determination of Chlorides-Post Accident).

c.

Hydrogen-1PCP08-AP-0008 (Backup Determination of Hydrogen-Post Accident).

4.3.1.6 Report backup analyses results to the Lead Chemical Technician as they become available.

NOTE Data Sheets should be completed later in a lower dose area.

4.3.1.7 Complete the appropriate sections of the Back-up Analyses Data Sheet (-02).

4.3.2 Gas Sampling and Analysis 4.3.2.1 Perform the sections of IPCP08-AP-0004 (Sampling and Analysis of RCB Atmosphere-Post Accident) as required to complete any of the following.

a.

PASS checkout (4.1 through 4.8) b.

LGSP Flushing (4.9 through 4.11) c.

In-line gross activity analysis (4.12)

NOTE Samples will be collected in a shielded syringe.

Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 7 of 11 d.

Collect diluted and/or undiluted RCB atmosphere samples. (4.13 and 4.14) e.

In-line hydrogen analysis (4.15) 4.3.2.2 Report results to the Lead Chemical Technician as they become available.

NOTE Data Sheets may be completed later in a lower dose area.

4.3.2.3 Complete the appropriate sections of the RCB Atmossphere Data Sheet (IPCP08-AP-0004-02) corresponding to the analyses performed.

4.3.3 Transport the diluted liquid and gas samples to the counting room in accordance with OPRP03-ZM-0014 (Movement of Material Out of Radiologically Controlled Area), if required.

4.3.4 Perform a gamma isotopic analysis on each sample in accordance with IPCP08-AP-0005 (Determination of Radionuclides / Post Accident).

4.3.5 Report the gamma isotopic results to the Lead Chemical Technician as they become available.

4.3.6 Complete Core Damage Assessment Data Package Cover Sheet

(-01), assemble data package, and give to Lead Chemical Technician.

4.4 PASS Shutdown 4.4.1 Upon coupletion of all PASS sampling and analysis, perform the following sections of OPCP08-AP-0002 (Operation and Maintenance of the Post Accident Sampling System).

4.4.1.1 SCR Flushing (4.2) 4.4.1.2 Liquid Dilution Loop Flushing (4.3) 4.4.1.3 Liquid Sampling and Analysis System Flushing (4.4)

Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. 0 Page 8 of 11 5.0 Calculations None 6.0 Standardization 6.1 All standardizations on PASS analyzers will be done in accordance with IPCP08-AP-0002 (Operation and Maintenance of the Post Accident Sampling System).

7.0 Documentation 7.1 Forms are dispositioned in accordance with OPCP01-ZA-0011 (Chemical Laboratory Logsheets and Reports).

7.2 All results will be recorded on appropriate data sheets and assembled into one data package.

8.0 References 8.1 OPCP01-ZA-0017 (Post Accident Sampling and Analysis Program),

Rev. O.

8.2 1PCP08-AP-0002 (Operation and Maintenance of the Post Accident Sampling System), Rev. O.

8.3 1PCP08-AP-0003 (Sampling and Analysis of the RCS, RRR, and RCB Sump-Post Accident), Rev. O.

8.4 1PCP08-AP-0004 (Sampling and Analysis of the RCB Abnosphere-Post Accident), Rev. O.

8.5 1PCP08-AP-0005 (Determination of Radionuclides-Post Accident),

Rev. O.

8.6 1PCP08-AP-0006 (Backup Determination of Boron-Post Accident),

Rev. O.

8.7 1PCP08-AP-0007 (Backup Determination of Chlorides-Post Accident),

Rev. O.

8.8 IPCP08-AP-0008 (Backup Determination of Hydrogen-Post Accident),

Rev. O.

8.9 OPGP03-ZR-0002 (Radiation Work Permit), Rev. O.

8.10 OPGP03-ZR-0025 (Use of Protective Clothing and Respiratory Equipment), Rev. O.

8.11 OPCP09-ZO-0001 (Operation of the Gamma Spectroscopy System), Rev. O.

Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 9 of 11 8.12 OPCP09-ZR-0004 (Determination of Radionuclides by Gamma Spectroscopy Method), Rev. O.

8.13 OPRP03-ZM-0014 (Movement of Material Out of Radiologically Controlled Area), Rev. O.

9.0 Support Documents 9.1 Core Damage Assessment Data Package Cover Sheet (-01) 9.2 Core Damage Assessment Data Sheet Back-up Analyses (-02) 1

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Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 10 of 11 CORE DAMAGE ASSESSMENT DATA PACKAGE COVER SHEET (lPCP08-AP-0001-01)

(Page 1 of 1) 1.

Have the following data sheets been completed and included?

a.

RCS, RHR, and RCB Sump Data Sheet (IPCP08-AP-0003-02)

Yes No Not Required b.

RCB Atmosphere Data Sheet (IPCP08-AP-0004-02)

Yes No Not Required c.

Back-up Analyses Data Sheet (IPCP08-AP-0001-02)

Yes No Not Required 2.

If any of the above were answered "No", why?

Completed by:

Chemical Technician Date/ Time Reviewed by:

Lead Chemical Technician Date/ Time This form, when completed, shall be retained for the life of the plant.

T Post Accident Core Damage Assessment IPCP08-AP-0001 Sampling and Analysis Rev. O Page 11 of 11 CORE DAMAGE ASSESSMENT DATA SHEET BACK-UP ANALYSES (IPCP08-AP-0001-02)

(Page 1 of 1)

Sample Date:

Technician:

Sample Point RCS RHR RCB Sump Sample Time

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Boron, ppa Chloride, ppa Hydrogen,%

Remarks:

Performed by:

Chemical Technician Date/ Time Reviewed by:

Lead Chemical Technician Date/ Time This form, when completed, shall be retained for the life of the plant.

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