ML17257A495

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Forwards Revised Draft Evaluation of SEP Topic V-5 Re RCPB Leakage Detection.Leakage Detection Sys Is Acceptable
ML17257A495
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/22/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Maier J
ROCHESTER GAS & ELECTRIC CORP.
References
TASK-05-05, TASK-5-5, TASK-RR LSO5-81-07-073, LSO5-81-7-73, NUDOCS 8107270210
Download: ML17257A495 (28)
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Docket No. 50-244 LS05-81-07-073 C

UN1T E Dpj TAT 5 S NUCLEAR REGULATORY COMiitIMSSION WASHINGTON, D. C. 20555 July 22, 1981

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Mr. John E. Maier Vice President Electric and Steam Produc ion Rochester Gas

& Electric Corp.

89 East Avenue Rochester, New York 14649

Dear Mr. Maier:

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SUBJECT:

SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION R.E.

GINNA NUCLEAR POWER PLANT Enclosed is a copy of our.evised draft evaluation of SEP Topic V-5 for R.E.

Ginna.

This assessment compares your facility, as described in Docket No.

50-244, with the criteria currently used by the regulatory staff for licens-ing new facilities.

This revised draft evaluation factors in the information contained in your March 23, 1981 letter on this subject, and pertinent infor-mation contained in SEP Topic V-10.A and available 10 CFR 50, Appendix I submittals for R.E. Ginna.

Please inform us within 30 days whether or not your as-built facility differs from the licensing basis assumed in our asses-sment.

This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built con-ditions at your facility.

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 Division of Licensing

Enclosure:

SEP Topic V-5 cc w/enclosure:

See next page IE 81072702i0 810722 PDR ADOCK 05000244 PDR I

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R.E.

GINNA SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY RCPB LEAKAGE DETECTION I.

Introduction The safety objective of Topic V-5 is to determine the reliability and sensitivity of the leak detection systems which monitor the reactor coolant pressure boundary to identify primary system leaks at an early stage before fai lures occur.

II.

Review Criteria The acceptance criteria for the detection of leakage from the reactor coolant pressure boundary is stated in the General Design Criteria of Appendix A, 10 CFR Part 50- Criterion 30, "guality of Reactor Coolant Pressure Boundary,"

requires that means shall be provided for detecting and, to the extent practi-cal, identifying the location of the source of leakage in the reactor coolant pressure boundary.

III.

Review Guidel ines The acceptance criteria are described in the Nuclear Regulatory Coomission Standard Review Plan Section 5.2.5,.-"Reactor Coolant Pressure Boundary Leakage Detection."

The areas of the Safety Analysis Report and Technical Specifications are reviewed to establish that information submitted by the licensee is in compli-ance with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems."

IV.

Evaluation Safety Topic V-5 was evaluated in this review for compliance of the information submitted by the licensee with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems."

The information in the Safety Analysis Report, Technical Specifications, the January 30, 1979 letter from RG8E to the NRC regarding SEP Topic V-10.A, the March 23, 1981 letter from RG&E to the NRC regarding SEP Topic V-5, and the available 10 CFR 50, Appendix I-review infor-mation for R.E.

Ginna was reviewed.

Regulatory Guide. 1.45 requires that at least three separate detection systems be installed in a nuclear power plant to detect an unidentified leakage from the reactor. coolant pressure boundary to the primary containment of one gallon per minute within one hour.

Leakage from identified sources must be isolated so that the flow rates may be monitored separately from unidentified leakage.

The detection systems should be capable of performing their functions following certain seismic events and capable of being checked in the control room.

Of the three separate leak detection methods required, two of the methods should be (1) sump level and flow monitor- :

ing and (2) airborne particulate radioactivity monitoring.

The third method may be either monitoring of condensate flow rate from air coolers or monitoring

of airborne gaseous radioactivity.

Other detection

methods, such as humidity, temperature and pressure, should be considered to be alarms of indirect indi-cation of leakage to the containment.

In addition, provisions should be made to monitor systems interfacing with the reactor coolant pressure boundary for signs of intersystem leakage through methods such as radioactivity and water level or flow monitors.

Plant incorportated systems and their corresponding features are tabulated in Enclosure 1.

Detailed guidance for the leakage de-tection system is contained in Regulatory Guide 1.45.

Based upon our review of the referenced documents and the summaries presented in Enclosure 1,

we have determined:

1)

The systems employed for the detection of leakage from the reactor coolant pressure boundary to the containment consist of the minimum three required by Regulatory Guide 1.45 plus seven additional systems.

All systems meet the criteria set forth for such as delineated in the guide.

(See Table 1

of Enclosure 1.)

However, the sensitivities of the leak detection systems are not properly reflected in the current Basis for Technical Specifica-tions 3.1.5.3.

Also, all leak detection systems which are present are not discussed in this Basis.

2)

Provisions are made to monitor reactor coolant in-leakage to those systems listed in Table 2 of Enclosure 1.

However, from the review of the refer-enced information it is not clear that this table includes all systems which interface with the reactor coolant pressure boundary.

In addition, information concerning the leak detection methods, similar to that given for the detection systems in Table 1 of Enclosure 1, is incomplete for those in Table 2.

3)

The March 23, 1981 letter from RGSE to the NRC regarding Topic V-5 indi-cates that CVCS. Makeup Flowrate is included as a Plant Incorporated System for leak detection, however, information regarding this method is not given such that Table 3 of Enclosure 1 is incomplete.

4)

The Ginna Technical Specification

3. 1.5.3 does impose requirements concern-ing the operability of the leakage detection systems to monitor leakage to the primary containment, as required by Regulatory Guide 1.45.
However, this does not conform to those given in current Standard Technical Specifi-cation 3/4.4.6.

In addition, corresponding survei'llance requirements in the Standard Technical Specifications are not contained, in the Ginna Tech-nical Specifications.

V.

Conclusi ons 1)

The leakage detection systems incorporated for measurement of leakage from the reactor coolant pressure boundary to the contain-ment are in conformance with Regulatory Guide 1.45 criteria and therefore acceptable.

2)

Standard Technical Specification 3/4.4.6 and the corresponding surveillance requirements concerning the operability of the reactor coolant pressure boundary to the containment leakage detection systems should be added to the R.E.

Ginna Technical Specifications.

Also, the current Basis for Ginna Technical Specification 3.1.5.3 and FSAR should be revised to state that the sensitivities of the reactor coolant pres-sure boundary to containment leakage detection systems a'r e 1

gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

3)

Information concerning the leakage detection systems tor tne aetectlon of inter-system reactor coolant pressure boundary leakage and the CVCS Makeup Flowrate is incomplete.

'Therefore, we cannot determine the extent to which Regulatory Guide 1.45 is met.

The necessity for any modifications in 'this area will be considered during the integrated safety assessment.

REACTO COOLANT PRESSU E BOUNDARY Re ulator Guide 1.45

.Table 1:

Plant:

c LEAKAGE DETECTION SYSTEHS Re uit ements RCPB to Containment System 1)

Sump Level Honftorfng (Inventory) 2)

Sump Pump.Actdatfons'onitorin Time Heters 3)

Airborne Particulate Radioactivit Honitorin 4)

Airborne Gaseous Radioactivit Honitorfn 5)

Condensated Flow Ratt; from Air Coolers

- 6)

Containment Atmosphere Pressure Honftorin 7)

Contaiaaent Atmosphere Humidit Honitorin 8)

Containment Atmosphere Tem erature Honitorin 9)

Accoustfc Emfssfons (Portable UT Detectors 10)

Hoisture Sensitive Tape 11)

Air Conditioner Coolant

~macr Incorporated Yes Yes Yes Yes Yes Yes Yes Yes:

Yes Yes Leak Rate Sensitivity 1

gpm 1

gpm

  • 1 gpm 1

gpm 1

gpm 1

gpm 1

gpm 1

gpm 1

gpm 1

gpm me eq to Achieve Sensitivity 1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

arthquake For Which'Function Is Assured OBE OBE SSE OBE OBE OBE OBE OBE OBE OBE Control Room Indication For Alarms

& Indicators Yes Yes Yes Yes Yes Yes Yes Yes Yes cument-ation Ref-erence **

3/23/81 RG&E ltr. to NRC 1

3/23/81 RG&E ltr. to NRC RE: To ic V-3/3 ltr. to NRC RE: To ic V-3/23/81 RG&E ltr. to NRC 3/23/81 RG&E

r. to.NR 3/23/81 RG&E ltr. to NRC 3/23/81 RG&E ltr. to NRC 3/23/81 RG&E ltr. to NRC 3/23/81 RG&E ltr. to NRC 3/25/81 RG&E ltr. to NRC esta e

During Nor-mal Operation Yes Yes Yes '

~

Yes Yes Yes Yes Yes Yes Yes'

.O13 gpm within twenty minutes assuming the presence of corrosion product activity per Technical Specifications 3.1.5.3

~" Discussions reqardinq instrumentation are also contained in th RG&E response to question 7.a contained in "Supplement 1 to Technical Supplement Accompanying Application for a Full-Tenn Operating License". dated December 20,1973.

II.;

lable 2:

REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEHS Re ulator Guide 1.45 Re uirements Plant:

R.E. Ginna I

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2 Inters stem Leaka e

Systems Which Interface w/ RCPB 1)

Secondary System Secondary Section 3)

Component Cooling Water System 4)

Component Cooling Mater System Hethods to Heasure RCPB In-Leakage ondenser Acr jector Rad.

iquid Sample ad. Honitor urge Tank evel ad. Honitor Leak Rate Sensitivity me eq to Achieve Sensitivity arthquake For Which Function Is Assured Control Room Indication For Alarms

& Indicators Yes Yes.

Yes Yes Oocument-ation Ref-erence FSAR Section

11. 2 FSAR Section 11.2 1/30/79 RG&

ltr. to NRC 1/30/79 RG&E ltr. to NRC estab e

Ouring Nor-mal Operation 5)

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.Table 5:

RCG Invent~or Balance Leak Rate Sensitivity Corresponding Time Required to Achieve Sensitivity REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTENS Re ulator Guide 1.45 ReBuirenenta Plant:

R.E. Ginna o25 gpm

  • Normal'Inventory Check Instrumentation Required with Corresponding Location:

Earthquake For Which Instrumentation Hardware Functioning Is Insured:

Testable During Normal Operation:

Documentation

Reference:

Technical Specification 3.l.5.3 I/

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REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1.45 Re uir ements

.Table 1:

RCPB to Conthinment System Sump Level Monitor~ng (Inventory)

Incorporated Yes Leak Rate Sensitivity 1

gpm Plant:

Time Req to Achieve Sensitivity 1 hr.

arthquake For Which;Function Is Assured OBE Control Room'.

Indication For Alarms

&"Indicators Yes Document-ation Ref-erence

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3/23/81 RG&E ltr. to HRC T

i Testab e

During Nor-mal Oper~tion Yes 2) 3)

4) 5)

7) 8)

Sump Pump.Actuations'onitorin Time Meters Airborne Particulate Radioactivit Monitorin Airborne Gaseous Radioactivit Monitorin Condensated Flow Rate from Air Coolers Containment Atmosphere Pressure Monitorin Containment Atmosphere Humidit Monitorin Containment Atmosphere Tem erature Monitorin Yes Yes Yes Yes Yes Yes Yes 1

gpm

  • 1 gpm 1

gpm 1

gpm 1

gpm 1

gpm 1

gpm 1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

OBE SSE OBE OBE OBE OBE OBE Yes Yes Yes Yes Yes Yes Yes 3/23/81. RG&E 1tr. to NRC RE: To ic V-3/23/81 RG&E ltr. to NRC RE: To ic V-3/23/81 RG&E ltr. to NRC RE: To ic V-3/23/81 RG&E

r. to.NR 0 i 3/23/81 RG&E ltr. to NRC RE:

o i V-3/23/81 RG&E ltr. to NRC RE:

To ic V-3/23/81 RG&E ltr. to NRC R

To V-Yes Yes Yes Yes Yes Yes

9) 'ccoustic Emissions (Portable UT Detectors)

Yes 1

gpm 1 hr.

OBE Yes 3/23/81 RG&E ltr. to NRC RE:

i V-Yes lo)

Moisture Sensitive Tape Air Conditioner Coolant, Yes 1

gpm 1 hr.

OBE Yes 3/25/81 RG&E ltr. to NRC Yes'

.013 gpm within twenty minutes assuming the presence of corrosion product activity per Technical Specifications 3.1.5.3 Discussions reqardinq instrumentation are also contained

'.n th RG&E response to question 7.a contained in "Supplement 1 to Technical Supplement. Accompanying Application for a Full-Term'Operating License",

dated December 20,1973.

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Table 2:

REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1.45 Re uirements Plant:

R.E. Ginna Inters stem Leaka e

Systems=Which Interface w/ RCPB 1)

Secondary System 2)

Secondary Section Methods to Measure RCPB In-Leakage ondenser Air Ejector Rad.

Liquid Sample ad. Monitor Leak Rate Sensi tivity Time Req to Achieve Sensitivity arthquake For Which. Function Is Assured Control Room Indication For Alarms

&"Indicators Yes Yes.

Document-ation Ref-erence FSAR Section 11.2 FSAR Section 11.2.

Testab e

During Nor-mal Operation 3) 4)

Component Cooling Water System Component Cooling Water System urge Tank evel ad. Monitor Yes Yes 1/30/79 RG&

ltr. to NRC 1/30/79 RG&E ltr. to NRC 5) 7)

B) 9)

10) 11)

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.Table 5:

RCS I

~tB 1

Leak Rate Sensitivity Corresponding Time Required to Achieve Sensitivity

  • Normal'Inventory Check REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEHS Re ulatur Guide 1.45 Requirements Plant:

R.E. Ginna

.25 gpm Instrumentation Required with Corresponding Location:

Earthquake For Which Instrumentation Hardware Functioning Is Assured:

n Testable During Normal Operation:

Documentation

Reference:

Technical Specification 3.1.5.3

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ACCESSIONr NBR;8107270210.

DOC ~ DATE>>z Bf/07/22!,

NOTARIZED'- NO DOCKE>>TI 0 FACIL<:50: 244 Rober t~ Kmmet>> Ginna< Nuclear>> Plantr, Unit", 1t-Rocheste'r>>

G 05000244 AUTH>>e NAME<,

AUTHOR< AFF ILl'AT'IONI CRUTCHFIELD'~D; Operating. Reactors B'ranch 5'ECIP

~ NAMKl RECIPIENT, AFFILIAT'ION-MA.IER'gJ<, E',:

Rochester'as 8 Electric Corp>'.

SU ECT!: For war ds. re'vised<. dr af ti evaluation pf,SEP.'opic-.V 54.,r el RCPB,'leakegel de.tection;Leakage) detection sys. is acceptable,"

OESTRIBUTION COOEi:

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Docket No. 50-244 LS05-81-07-073 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 22, 1981 Mr. John E. Maier Vice President Electric and Steam Produc ion Rochester Gas 8 Electric Corp.

89 East Avenue Rochester, New York 14649

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Dear Mr. Maier:

SUBJECT:

SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTIOI'I R.E.

GINNA NUCLEAR POWER PLANT Enclosed is a copy of our.evised draft evaluation of SEP Topic V-5 for R.E.

Ginna.

This assessment compares your facility, as described in Docket No.

50-244, with the criteria currently used by the regulatory staff for licens-ing new facilities.

This revised draft evaluation factors in the information contained in your March 23, 1981 letter on this subject, and pertinent infor-mation contained in SEP Topic V-10.A and available 10 CFR 50, Appendix I

'submittals for R.E.

Ginna.

Please inform us within 30 days whether or not your as-built facility differs from the licensing basis assumed in our asses-sment.

This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built con-ditions at your facility.

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.

Sincer ely,

Enclosure:

SEP Topic V-5 cc w/enclosure:

See next page pZ Dennis M. Crut field, Chief Operating Reactors Branch No.

5 Division of Licensing

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R.E.

GINNA SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY RCPB LEAKAGE DETECTION I.

Introduction The safety objective of Topic V-5 is to determine the reliability and sensitivity of the leak detection systems which monitor the reactor coolant pressure boundary to identify primary system leaks at an early stage before failures occur.

II.

Review Criteria The acceptance criteria for the detection of leakage from the reactor coolant pressure boundary is stated in the General Design Criteria of Appendix A, 10 CFR Part 50. Criterion 30, "guality of Reactor Coolant Pressure Boundary,"

requires that means shall be provided for detecting and, to the extent practi-cal, identifying the location of, the source of leakage in the reactor coolant pressure boundary.

I II.

Review Guidelines The acceptance criteria are described in the Nuclear Regulatory Coranission Standard Review Plan Section 5.2.5, "Reactor Coolant Pressure Boundary Leakage Detection."

The areas of the Safety Analysis Report and Technical Specifications are reviewed to establish that information submitted by the licensee is in compli-ance with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems. "

IV.

Evaluation Safety Topic V-5 was evaluated in this review for compliance of the information submitted by the licensee with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems."

The information in the Safety Analysis Report, Technical Specifications, the January 30, 1979 letter from RG&E to the NRC regarding SEP Topic V-lO.A, the March 23, 1981 letter from RGSE to the NRC regarding SEP Topic V-5, and the available 10 CFR 50, Appendix I. review infor-mation for R.E.

Ginna was reviewed.

Regulatory Guide. 1.45 requires that at least three separate detection systems be installed in a nuclear power plant to detect an unidentified leakage from the reactor coolant pressure boundary to the primary containment of one gallon per minute within one hour.

Leakage from identified sources must be isolated so that the flow rates may be monitored separately from unidentified leakage.

The detection systems should be capable of performing their functions following certain seismic events and capable of being checked in the control room.

Of the three separate leak detection methods required, two of the methods should be (1) sump level and flow monitor- :

ing and (2) airborne particulate radioactivity monitoring.

The third method may be either monitoring of condensate flow rate from air coolers or monitoring

~

~

of airborne gaseous radioactivity.

Other detection

methods, such as humidity, temperature and pressure, should be considered to be alarms of indirect indi-cation of leakage to the containment.

In addition, provisions should be made to monitor systems interfacing with the reactor coolant pressure boundary for signs of intersystem leakage through methods such as radioactivity and water level or flow monitors.

Plant incorportated systems and their corresponding features are tabulated in Enclosure l.

Detailed guidance for the leakage de-tection system is contained in Regulatory Guide 1.45.

Based upon our review of the referenced documents and the summaries presented in Enclosure 1,

we have determined:

1)

The systems employed for the detection of leakage from the reactor coolant pressure boundary to the containment consist of the minimum three required by Regulatory Guide 1.45 plus seven additional systems.

All systems meet the criteria set forth for such as delineated in the guide.

(See Table 1

of Enclosure 1.)

However, the serpitivities of the leak detection systems are not properly reflected in the: current Basis for Technical Specifica-tions 3. l. 5. 3.

Also, all leak detection systems which are present are not discussed in this Basis.

2)

Provisions are made to monitor reactor coolant in-leakage to those systems listed in Table 2 of Enclosure 1.

However, from the review of the refer-enced information it is not clear Chat this table includes all systems which interface with the reactor coolant pressure boundary.

In addition, information concerning the leak detection methods, similar to that given for the detection systems in Table 1 of Enclosure 1, is incomplete for those in Table 2.

3)

The March 23, 1981 letter from RG&E to the NRC regarding Topic V-5 indi-cates that CVCS Makeup Flowrate is included as a Plant Incorporated System for leak detection, however, information regarding this method is not given such that Table 3 of Enclosure 1 is incomplete.

4)

The Ginna Technical Specification 3.1.5.3 does impose requirements concern-ing the operability of the leakage detection systems to monitor leakage to the primary containment, as required by Regulatory Guide 1.45.

However, this does not conform to those given in current Standard Technical Specifi-cation 3/4.4.6.

In addition, c'orresponding "surve'i'llance requirements in the Standard Technical Specifications are not contained.in the Ginna Tech-nical Specifications.

f

~

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~ V.

Conclusions 1)

The leakage detection systems incorporated for measurement of leakage from the reactor coolant pressure boundary to the contain-ment are in conformance with Regulatory Guide 1.45 criteria and therefore acceptable.

2)

Standard Technical Specification 3/4.4.6 and the corresponding surveillance requirements concerning the operability of the reactor coolant pressure boundary to the containment leakage detection systems should be added to the R.E. Ginna Technical Specifications.

Also, the current Basis for Ginna Technical Specification 3.1.5.3 and FSAR should be revised to state that the sensitivities of the reactor coolant pres-sure boundary to containment leakage detection systems ar'e 1

gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

3)

Information concerning the leakage detect)on systems d'or the aetectlon of inter-system reactor coolant pressure boundary leakage and the CVCS makeup Flowrate is incomplete.

Therefore, we cannot determine the extent to which Regulatory Guide 1.45 is met.

The necessity for any modifications in this area will be considered duri ng the integrated safety assessment.

.Table 1:

REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1.45 Re uirements

'lant:

RCPB to Conthinment System Sump Level Monitoring (Inventory)

Incorporated Yes Leak Rate Sensitivity 1

gpm Tsme Req to Achieve Sensitivity 1 hr.

arthquake For Which.Function Is Assured OBE Control Room'.

Indication For Alarms

&"Indicators Yes Document-ation Ref-erence

  • ~

3/23/81 RG&E ltr. to NRC T

i Testab e

During Nor-mal Oper~tion Yes j

2) 3)

4) 5)

Sump Pump.Actuations Monitorin Time Meters Airborne Particulate Radioactivit Monitorin Airborne Gaseous Radioactivit Monitorin Condensated Flow Rate from Air Coolers Containment Atmosphere Pressure Monitorin Yes Yes Yes Yes Yes 1

gpm

  • 1 gpm 1

gpm 1

gpm 1

gpm 1 hr.

1 hr.

1 hr.

1 hr.

1 hr.

OBE SSE OBE OBE OBE Yes Yes Yes Yes Yes 3/23/81 RG&E ltr. to NRC RE: To ic V-3/23/81 RG&E ltr. to NRC RE: To ic V-3/23/81 RG&E ltr. to NRC RE:

To ic V-3/23/81 RG&E

r. to.NR To 1

3/23/81 RG&E ltr. -to NRC RE:

To i V-Yes Yes Yes Yes Yes 8)

Containment Atmosphere Humidit Monitorin Containment Atmosphere Tem erature Monitorin Yes Yes 1

gpm 1 hr.

1 gpm 1 hr.

OBE OBE Yes Yes 3/23/81 RG&E ltr. to NRC RE:

To ic V-3/23/81 RG&E ltr. to NRC R

To V-Yes Yes 9)

Accoustic Emissions (Portable UT Detectors Yes 1

gpm 1 hr.

OBE Yes 3/23/81 RG&E ltr. to NRC RE:

i V-Yes lo)

Moisture Sensitive Tape Air Conditioner Coolant

~T Yes 1

gpm 1 hr.

OBE Yes 3/25/81 RG&E ltr. to NRC Yes'

    • ..013 gpm within twenty minutes assuming the presence of corrosion product activity per Technical Specifications 3.1.5.3 Discussions regarding instrumentation are also contained

'.n th RG&E response to question 7.a contained in "Supplement 1 to Tecnnical Supplement. Accompanying Application for a Full-Term Operating License",

dated December 20,1973.

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REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1.45 Re uirements

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Table 2:

Inters stem Leaka e

Systems'hich Interface w/ RCPB 1)

Secondary'ystem Methods to Measure RCPB In-Leakage ondenser Air Ejector Rad.

Leak Rate Sensi tivity Time Req to Achieve

'Sensitivity Plant:

R.E. Ginna arthquake For Which. Function Is Assured Control Room Indication For Alarms

&"Indicators Yes Document-ation Ref-erence FSAR Section 11.2 Testab e

During Nor-mal Operation I~

I

~

I

~..2)

Secondary Section iqui d Sampl e Rad. Monitor Yes.

FSAR Section 11.2.

I ~

I

~

I 3)

Component Cooling Water System urge Tank evel Yes 1/30/79 RG&

ltr. to NRC 4)

Component Cooling Water System I'

ad. Monitor Yes 1/30/79 RG&E ltr. to NRC 5) e)

7)

I i

I i

I I

~

i I

i y i

i I

B) 9)

I.

I.

j 1O)

I',

~i

.I 11)

I

t 1

~,

r

.Table 5:

RCS t t~B1 REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1.45 Regufrements Plant:

R.E.

Ginna Leak Rate Sensitivity Corresponding Time Required to Achieve Sensitivity

.25 gpm

  • Normal'Inventory Check Instrumentation Required with Corresponding Location:

Earthquake For Which Instrumentation Hardware Functioning Is Assured:

Testable During Normal Operation:

Documentation

Reference:

Technical Specification 3.1.5.3

AI

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