ML20198A313

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Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated
ML20198A313
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/15/1998
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20198A279 List:
References
CP-224, NUDOCS 9812160225
Download: ML20198A313 (13)
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CALVERT CLIFFS NUCLEAR POWER PLANT TECHNICAL PROCEDURE CP-224 MONITORING RADIOACTIVITY IN SYSTEMS NORMALLY UNCONTAMINATED REVISION 4 PCR 97 449 SAFETY RELATED V NON-SAFETY RELATED REFERRAL USE - PERIODICALLY REFER TO PROCEDURE DURING USE l,/

Approval Authority ,A4I -

Effective Date / kh

%Q PhR AD 00017 p PDR Enclosure 4

Monitoring Radioactivity in Syst::ms Normally Uncontrminated CP-224

, Revision 4 Page 2 of 13 RECORD OF REVISIONS AND CHANGES Revision PCR

, Number Number Summary Of Revision Or Change 4 97-049 This is a major revision of the procedure. Included below are the major changes inceipci. d. i Mded improved Technical SpecL60s references Specshestens and Surveillancos for primary-to-secondary leaks, along with associated specal acbons were transferred to CP-236.

Revised 3.0.B.1 reference Reference revised where it appeared in procedure.

Removed reference to EPRI TR-104788,"PWR Primary-to-Secondary Leak Guidelines," the reference was transferred with leak rate calculations to CP-236.

Moved Step 6.0.C.2.b.2 to 6.0.C.3.e.

Revised reference in LLD definition to renect ODCM insisad of Tech Spec.

. Spelled out acronym *SPC" as Supervisor-Plant Chemistry.

Several changes to Attachment 1: Mded samphng and analysis for Outfall 002, because routine sampling and analysis of this outfallwas recommended by the NRC. Deleted requwements for diesel oil and yard oil interosplors, since Outfall 002 is downstream of these sample locations Also added action level 1 values for gamma (for Outfall 032). Mded annual sampling for Yard Oil Interceptor sludge and basis captured this requirement to safety evaluabon Reduced frequency of tribum sampling and analysis for sewage treatment plant (STP) offluent, because our operstmg history has demonstrated that the probabitty of tritium at this outfall is low and the new frequency comcides with that of the oilinterceptors increased samping frequency for gamme for turbine building surnps, waste routralambon tanks and precoat sumps to weeldy to reDect current prachce Revised footnote for STP sludge to notify Supervisor-Chemistry Environmental Services (SCES) if sewage sludge is radM;d; contaminated, because SCES is the responsible unit for coonfinating dispceal with Matenals Processing. Mded sampling frequency and specifications for Auxiliary Steam Blowdown Tanks.

Included footnote 12 under Condensate, Precost Sump, Turbine Building Sumps, Wasts Neut. Tank Target, Aux. Blowdown Tanks Columns, and Outfall 002 Action Level 1 Column.. Mded footnotes 14 and 15 to reflect samphng requirements for Tritium Analysis and to clarify sampling frequency for Turbine Building Sump Gamma Analysis.

Formatted Bases according to Technical Procedures Writers Manual. Minor corrections made resulting from Technical Writers Manual review.

Changed ENSURE to VERIFY for clarity.

4 98-073 EC-1: Changed 3.0.B.9. title to reflect use of the same software on different computers.

4 98-094 EC-2: Incorrect master file was used. Captured correct master file.

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. i Monitoring Radioactivity in Syst:ms Normdly Uncontaminated CP.224 1

. Revision 4 t Page 3 of 13 l 1

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TABLE OF CONTENTS 1

1.0 PURPOSE . . .

. . . . . . -.. .. . -. . ..... 5 2.0 APPUCABILITYtSCOPE. .

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3.0 REFERENCES

AND DEFINITIONS . . . . ... .. 5 A. PROCEDUPi DEVELOPMENT ........... .... ... . .......... .. .. .. ... .................................... .. . 5

B. PROCEDURE

PERFORMANCE.... ...... ........................... ...........................................6

'i. DEFINITIONS .. ....... .. ........ .. . .... . . .. .. . ... .. ... . . . . . . . . . . . . . . . . . . . ..

....................7 l 4.0 PREREQUlSITES . .... . . . . . . . ...... . 8

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A. RESPONSIBluTIES . ................... . . . . . . .

.................................... . . . . . . . . . . . . . . . .8 5.0 PRECAUTIONS . . . ._ . . ._ . . . . .. _ . . 8 l A. LLDS AND MDAS ... .. ... ....... . ..... . . .... ..... .... . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . ... 8 8.0 P:!!RFORMANCE . .. .. .. . . . .. ..... 8 A. SURVEILLANCES .... ..... ... .. .... .... .. .. . . .. .. . ....................................... .8 B. SPECIFICATIONS.... ... ........ .. .. ....... . ... ... . . . . . . . . . . . . . . . . . . . . . . . . .. ... 8 C. OTHER CORRECTIVE ACTIONS..... . ....... ........................................ . . .. . 8 i

7.0 POST-PERFORMANCE ACTIVITIES . . . . . __ . 10 8.0 BASES . . . . . . ... . . . . 11 I 0.0 RECORDS. ... . ._. . .. .

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Attachment 1, Sampling And Analysis Program For Monitoring Radioactivity in Systems Which

. Are Normally Uncontaminated.... . ....................................,...........................12 i

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i Monitoring Radioactivity in Sy t:ms Normally Uncontaminated CP-224

l. Revision 4 Page 4 of 13 l

l LIST OF EFFECTWE PAGES l

Page No. Change No. Page No Change No. Page No l Change No.

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Monitoring Radiorctivity in Syst;ms Normilly Uncontiminated CP-224

, Revision 4 Page 5 of 13 I 1.0 PURPOSE I.

This procedure defines a sampling and analysis program for monitonng radioactivity in plant systems which are normally (that is, by design) non-contaminated. This procedure also specifies achons taken as a result of detecting radioactivity in such systems.

! 2.0 - APPLICABILITY / SCOPE This procedure is applicable to the Plant Chemistry Unit and Chemistry Environmental Services Unit. i l This procedure is applicable to the systems listed on Attachment 1. I i

This procedure is NOT intended to deGne the specificaten and surveillance program for radioactive affluents discharged to the environment. (The s%Educn and surveillance program for radioactive offluents discharged to the environment is found in CP-212 and CP-213).

3.0 REFERENCES

AND DEFINITIONS A. Procedure Development

1. CP-102, General information Records
2. NRC IE Bulletin 80-10, " Contamination Of Non-radioactive Systems And Resulting Potential For Unmonitored, Uncontrolled Release Of Radioactivity To The

! Environment," May 6,1980 l 3. Radiation Health Handbook, U.S. Department of Health, Education, and Welfare, Public Health Services, January 1970

4. Operation of the Auxiliary Boiler System as a Contaminated System, 50.59 Log Number 904-027 037-R2, MASE 90-8

[B 402]

l- 5. Operation of the Component Coohng Water System as a Contaminated System,50.59 Log Number 82-B-999428-R00 (for. Safety Analysis No. 2, FCR 82-1053, Supplement 1)

[B405]

6. Operation of the Plant Nitrogen System as a Contaminated System,50.59 Log
Number 90-0-074411-R2, MASE 90-7

[B 403]

7. Operation of the Domineralized Water System as a Contaminated System,50.59 Log Number 90-0-037-04d-R1, MASE 90-5

[B-408]

8. Operation of the Condensate Storage Tank as a Contaminated System,50.59 Log Number 90-B-037-120-R1, MASE 90-11 l

[B-406]

l 9. Operation of the Plant Heating System as a Contaminated System,50.59 Log Number t

90-0-029-045-R1, MASE 90-11

[B407]

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l Monitoring Radioactivity in Syst:ms Normilly Uncontiminit;d CP-224

, Revision 4 Page 6 of 13 I

3.0 References and Definitions (Continued) i

. 10. NRC information Notice No. 91-40, " Contamination Of Non-radioactive Systems,"

i June 19,1991

11. Limits For Qualitative Determination And Quantitative Determination, Lloyd A. Cume, Analytical Cnemistry, Volume 40, No. 3, March 1968 i
12. NRC Information Notice No. 89-54, ' Potential Overpressurization of Component ,

Cooling Water System." (See also related POSRC O! 91-188-01) [B-523]  !

13. Operation of the Service Water System as a Contaminated System,50.59 Log Number 90-B-012-043-R1, MASE 90-4

[B-404]

14. QAU Recommendation 88-37-R05

[B085]

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15. NRC Insp. Rpt 80-22 / 80-18

[B-209] l

16. QAU Recommendation 89-06-R01 (B294]
17. NRC inspection Report 89-03

[B-344]

18. SOER 93-1, " Diagnosis and Mitigation of Reactor Coolant System Leakage including Steam Generator Tube Ruptures *
19. Operation of the Yard Oil interceptor as a Contaminated System,50.59 Log Number SE00244

[B-574]

20. Memorandum from Greg Barley to Jeff York, dated July 23,1998; ' Radiological effluent permits for secondary releases."

B. Precedure Performance 1, 10 CFR 20, Appendix B,1987 revision

2. CP-102, General information Records
3. CP-212, Specifications And Surveillances Radioactive Uquid Waste Releases
4. CP-213, Specifications And Surveillance Radioactive Gaseous Waste
5. CP-502, Sampling Of Gases For Activity
6. CP-504, Radioactive Liquid Waste Sampling and Compositing
7. CP-108, Chemistry Technical Evaluations 1

, 8. CP-972, Determination Of Tritium Using the TRI CARB 2300TR Liquid Scintillation Counter.

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Monitoring Radioactivity in Systems Normilly Uncontaminat:d CP-224

' R3 vision 4 Page 7 of 13 3.0 References and Defm' itions (Continued)

9. CP-977, Operation of Gamma Spectroscopy Counting System l EC-1
10. RM-1 101, Regulatory Reporting C. Definnens
1. Target:

l The value or range of values for a chemical or radkx:hemical parameter which is a goal or predetermined waming limit. A TARGET is not a w*=*ian.

2. Action Level 1:

A value or range of values for a chemical or radiochemical parameter which (1) is l inconsistent with the goals of the Chemistry Section, (2) indcates an adverse trend l has c:wW, and (3) indcates long-term impads should be anicipated or expected. l i

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3. Action Level 2:

i A value or range of values for a chemical or radiochemical parameter whidi (1) exceeds a Technical Specificahon, govemment regulation, or regulatory commitment, or (2) indicates an adverse trend has developed, or (3) indcates short-term adverse

impacts should be anticipated or expected.
4. Action Level 3:

l A value or range of values for a chemical or radiochemical parameter for which contmuod operation of the unit or plant system may not be advisable due to immediate impacts on safety or system integrity.

5. Lower Limit Of Detection (LLD):

l The LLD is defined as the smallest concentration of radioadive matenalin a sample that wlE yield a net count, above system background, that will be detected with 95%

probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signa!. (See ODCM 3.11.1.1, Table 4.11-1, footnote (a) for mathematicaldefinition of LLD).

6. Minimum Detectable Activity (MDA):

' MDA is defined as the amount of schvity which must be present to be assured that there is only a predefined probability (for example,0.26%) of the observed activity being the resut of statistical fluctuations in the background. Mathematically, the MDA l is typically defined as a predetermined multiple (for example,3 times) of the standard i deviation of the back0round count.

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M:nitoring Ridinctivity in Syst;ms Norm lly Uncontamirtted CP-224 Ravision 4 Page 8 of 13 4.0 PREREQUISITES A. Responsibilities

1. The Supervisor-Plant Chemistry (SPC)is responsible for verifying all surveillances, except Yard Oil Interceptor sludge, are completed PER this procedure.
2. The Supervisor-Chemistry Environmental Services is responsible for venfying that the Yard Oil Interceptor sludge surveillance is completed PER this procedure.
3. Technicians are responsible for completing the actions prescribed by this procedure.

5.0 PRECAUTIONS A. LLDs and MDAs 1.

The minimum sampie volumes and count times specified elsewhere in the chemistry sampling and analysis program (for example, in CP 977) will ensure LLDs for gamma isotopic analysis are appropriate for this procedure.

6.0 PERFORMANCE A. Surveillances

1. SAMPLE the systems AND ANALYZE the samples at the frequencies specified on Attachment 1.

B. Specifications

[B-085]

1. COMPARE the surveillance results to the TARGET, ACTION LEVEL 1. ACTION LEVEL 2, AND ACTION LEVEL 3 values listed on Attachment 1, AND
2. PERFORM the special corrective actions required by Attachment 1, AND
3. PERFORM the other corrective actions listed below.

C. Other Corrective Actions

[B-085}

1.

VERIFY all information is documented in accordance with CP-102 and other applicable chemistry procedores.

2. IF a TARGET is exceeded, THEN; a) PERFORM corrective actions required by Attachment 1.

b) NOTIFY the SPC of the following:

(1) Activity has been detected in a normally (that is, by design) non-contaminated system. [B402), [B403], [B-404), [B405), [B406),

[B407),[B408)

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4 1 M:nitoring Radioactivity in Syst::ms Norm:lly Uncontaminated CP-224 R& vision 4 t

Page 9 of 13 6.0  !

Perforrmnce (Continued)

(2) to ensure Rad. Con. Ops. is (or has been) notified that activity has been detected in a normally (that is, by design) non-contaminated system. [B-294],[B-402),[B403),[B404],[B406],[B-406],

IB407],IB40s]

c) RECORD -in the appropriate document "significant details" associated with all notifications required by this procedure. Exarnples of"significant details" may include - but are not limited to - the following, as appropriate.

(1) date and time of notificaton, (2) person or Section notified, or (3) changes in surveillance frequencies.

d) IMPLEMENT other corrective actions (for example, increase surveillance frequencies) as directed by the SPC.

3. IF an ACTION LEVEL 1 is exceeded, THEN; a) i PERFC RM corrective actions PER Sechon 6, step 6.c.3, listed above. '

b) On initial entry into ACTION LEVEL 1, VERIFY Shift Manager is (or has been) notified that activity has been detected in a normally (that is, by design) non-contaminated system. [B402], [B403], [B 404], [B406], [B406],

[B-407],[B-408]

c) On initial entry into ACTION LEVEL 1, VERIFY System Engineer is (or has been) notified that activity has been detected in a normally (that is, by design) l non-contaminated system.

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1 d) On initial entry into ACTION LEVEL 1, RECORD -in the appropnate  !

document - the component, the date and time the sample was collected and  !

that ACTION LEVEL 1 was initiated, e) All subsequent releases from this system to the environment are subject to the specifications and surveillances for liquid and gaseous radweste as outlined in CP-212 and CP-213. [B402],[B-403],[B 404],[B 406],[B406),[B407],  !

[B408]

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f Monitoring Radioactivity in Systems N:rm lly Uncont;minated CP-224 Revision 4 Page 10 of 13 6.0 Performance (Continued)

4. IF an ACTION LEVEL 2 is exceeded, THEN:

a) PERFORM corrective actions PER Section 6, steps 6.C.3 - 6.C.4 listed above.

b) NOTIFY the SPC to:

(1) REVIEW CP-108, Chemistry Technical Evaluation. for applicability, AND (2) REVIEW RM-1-101, Reoulatory Reporti_ng. I 1

c) VERIFY the GSC and the Shift Manager are promptly notifieci that activity has I been detected in a normally (that is, by design) non-contaminated system. I

[B-402], [B 403], [B-404), [B-405], [B-406), [B-40Tj, [B408] i d) On initial entry into ACTION LEVEL 2, RECORD -in the appropriate 3 document - the component, the date and time the sample was collected and l that ACTION LEVEL 2 was initiated.

5. IF an ACTION LEVEL 3 is exceeded, THEN:

I a) PERFORM corrective actions PER Sechon 6, steps 6.C.3 - 6.C.5 listed above. ,

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b) NOTIFY the Shift Manager that continued operation of the system may not be

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advisable due to activity that has been detected in a normally (that is, by j design) non-contaminated system. [B-402), [B-403), [B-404), [B-40s],

[B406], [B-407],[B408]

c) RECORD, in the appropriate document, (on initial entry into ACTION LEVEL

3) the component, the date and time the sample was collected and that ACTION LEVEL 3 was initiated.

7.0 POST-PERFORMANCE ACTIVITIES None l

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t Monitoring Radioactivity in Systsms Normilly Uncontamintted CP-224

' R; vision 4 Page 11 of 13 8.0 BASES PROCEDURE SECTION BASES REFERENCE 3.A, 6.B, 6.C [B-085] See Section 3.0,

  • References" 3.A, Attachment 1 See Section 3.0,
  • References"

[B-209]

3.A, 6.C [B-294] See Section 3.0," References" 3.A Attachment 1 [B-344] See Section 3.0, " References" 3.A,6.C [B402] See Sechon 3.0, "fleferences" 3.A,6.C [B403] See Section 3.0,

  • References" 3.A,6.C [B-404] See Sechon 3.0, " References" 3.A, 6.C [B405] See Secten 3.0, " References" 3.A,6.C [B-406] See Sechon 3.0," References" 3.A,6.C [B-407] See Sechon 3.0," References" 3.A,6.C [B408] See Section 3.0," References" 3.A, Attachment 1 [B-523] See Sechon 3.0," References" 3.A. Attachment 1 [B-574] See Seebon 3.0, " References" 9.0 RECORDS Records generated by this procedure shaE be captured and controlled. Prior to transferring records to Records Management for retention, legibility and completeness of the record shall be verifed by the transmitting organization.

Records generated by this procedure are L.sfehme Records and shall be retained for the life of the plant.

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Monitoring Radioactivity in Systems Normally Uncontaminated CP-224 Revision 4 t Page 12 of 13 Attachment 1, ing and Analysis Program For Monitoring Radioactivity in Systems h Afe Normally Uncontaminated (Page 1 of 2)

Sample Analysis Fs m -..;y Target Aedon Level 1 Action Level 2 Action Level 3 i Outfall 992 gemme M < MDA > MDA (12)

H4 0 < MDA 21E-SpCi/cc (12)

Aug. Boiler Steam gamme W(1) {B-209) < MDA (2) 2 0.5 MPC 21 MPC (3),(4) 296 MPC Drum H-3 M(1) < MDA (2) 2 0.5 MPC 21 MPC (3),(4) 2 96 MPC Aun.Boller Blowdown gemme W(1) [B-209] <MDA (2) g MDA (12) 31 MPC (3), (4) 3310 MPC Tanks H-3 M(1) <MDA (2) > 1E-5 pCFce (12) >1 MPC (3), (4) 1310 MPC  ;

CCW gamma W[B-299)(5) < MDA(10) 2 MDA (2), (6),(10) 21 MPC (3), (7), (4), (10) 2 3000 MPC (7)(10)

H-3 M < MDA 2 MDA (2),(6) 21 MPC (3), (7), (4) 2 3000 MPC (7)

Cond. Demm. Weste gamma, H-3 Prior to dscharge < MDA ,

Resen Pit Condensate gamme, During dhcharge < MDA (12)

H4 Subsequent to < MDA 11E-5pCVcc (12)

Discherge (14)

CST gemme, H-3 M < MDA (2) 2 0.05 MPC 2 0.1 MPC (3). (4) 21 MPC Domen, Water Sys, gamma W[B-299l < MDA(2,3,4) 2 0.1 MPC 2 0.2 MPC 2 0.3 MPC EC-2 (e.g., Chem. Lab.) H-3 M < MDA(2,3,4) 2 0.1 MPC 2 0.2 MPC 2 0.3 MPC j MPF Chercoat and gamme W < MDA l Particulate Filters Plant Air gemme M [B-299l < MDA Plant Hesting Sys gemme, H-3 M < MDA(2,6) 2 0.005 MPC 2 0.01 MPC (3), (4) 2 0.3 MPC Plant lettrogen gemme W < MDA (2) 2 05 MPC 21 MPC (3), (4) 213,500 MPC Precost Sump gamma W < MDA (12)

  • H-3 M (14) < MDA > IE-5 pCVcc (12)

Serv 6ce Water gamma W[B-299) < MDA(10) 2 MDA (2),(6),(10) 2 0.01 MPC(3),(4),(10) 2 0.1 MPC,(7),(10)

H-3 M < MDA 2 MDA (2),(6) 2 0.01 MPC (3),(4) 2 0.1 MPC,(7)

$TP Effluent gemma M < MDA(8) > MDA (12)

H-3 0 < MDA STP Studge gemma Prior to escherge < MDA(15)

TurtHne Bldg Sumps gamme W[B-344] (15) < MDA (12) 2 MDA (11) l (9) H-3 M (14) < MDA 21E-5pCl/cc (12)

Weste Neut. Tank gamma, W < MDA (12)  !

H-3 M (14) < MDA 21E-SpCl/cc (12)  !

Yard Oliinterceptor gamma A < MDA 2 0.04 MPC (13) [B-574]

Sludge

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4 CP-224 Revision 4 i

Page 13 of 13 Attachment 1, Footnotes (Page 2 of 2)

(1) ' Apphcable only when auxiliary boiler is steaming or when auxiliary boiler is in hot standby, (2) IF this limit is exceeded, THEN CALCULATE the MPCs IMhe affected system as follows. Use the formula i910 CFR 20, Appendix B (1987 revision), Note t and-for each nuclide identified - use the kallet of the two MPC values (Soluble or insoluble) listad in 10 CFR 20, Appendix B (1987 revison), Table 11, Column 2.

(3) IF this limit is awe, surveillance frequency for shift (per appbcable safety evaluaton listed in Secte. gamma actuty should be increased to once per n3.0).

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i (4) IF this limit is exceeded. THEN NOTIFY the SPC that contmuod uperation of this system may I involve an unrevowed safety question, and therefore, a 10 CFR 50.59 safety evaluation shall be warranted in order to continue safe operabon of the affected system (pursuant to NRC IE Bulletin 80-10 and the applicable safety evaluations listed in Section 3.0).

(5) IF the CCW Radssten Monitor (1-RE-3819 or 2-RE-3819) is inoperable. THEN INCREASE the surveillance frequency to once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the affected unit.

[B823]

(6) IF this limit is exceeded, THEN %OTIFY the SPC that a leak delechon in the affected system (per applicable safety evaluations listed in Secten 3d wn should be initiated for (7) IF this limit is awemadad, THEN SAMPLE the salt water system and analyze for gamma emitters and tritium as directed by the SPC.

(8) IF this limit is exceeded, THEN DETERMINE if is related to medicaltrealment of nt personnel. IF radioacthnty is not the result of treatments THEN CONTACT the (because all releases to the environment are subject to the specificahons and surveillances for liquid and 6 gaseous radweste outlined in CP-212 and CP-213). ,

i (9) Not applicable to Turbine Building Oily Sumps.

Excluding Ar-41. i (10) '

(11) Place Turbine Building Sump Pumps in MANUAL until authorized by SPC to return to AUTO.

l (12) IF required, PREPARE release permit PER CP-601 or CP-614.

(13) CALCULATE MPC fracton using 10 CFR 20 Table 11 Column 2 (1987) MPC values. IF > 0.04 MPC.

THEN NOTIFY the Supervisor - Chemistry Environmental Services that a revision to the Safety i

Evaluation SE00224 may be necessary.

[B-874]

(14) Tritium speedication is met by analyzing the monthly composite setup PER CP-504.

. (15) Turbine Building Sump samples for gamma activity is weekly in Mode 1. When in Modes 2 6 on affected unit, sample frequency is three times per week.

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