ML17258A523

Forwards Safety Evaluation of SEP Topic V-05,RCPB Leakage Detection.Rcpb Leakage Detection Sys Do Not Presently Conform to Reg Guide 1.45

ML17258A523
Person / Time
Site:	Ginna
Issue date:	02/08/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
References
TASK-05-05, TASK-5-5, TASK-RR LSO5-82-02-049, LSO5-82-2-49, NUDOCS 8202100268
Download: ML17258A523 (16)

Text

4 February 08, 1982 Docket No. 50-244 LS05-82-02-049 M. John E. Maier, Vice President Electric and Steam Production Rochester Gas Im Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

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

GINNA NUCLEAR POllER PLANT This evaluation concludes that the R. E. Ginna reactor coolant pressure boundary leakage detection systems do not presently conform to all of the recommendations of Regulatory Guide 1.45 and presents the modifica-tions needed to establish compliance.

The necessity for implementation of the modifications will be considered during the integrated assessment.

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.

~~0$

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gas Dennis M. Crutchfield, Chief t

Operating Reactors Branch Ro.

6

/6 vlw5 Division of Licensing Sincerely,

Enclosure:

As stated Enclosed is a copy of our final evaluation of SEP Topic V-5 for the R.

E. Ginna Nuclear Power Plant.

This assessment compares this facility, as described in Docket No. 50-244, with the criteria currently used by the regulatory staff for licensing new facilities.

This revised evalua-tion factors in the information contained in your March 23, October 12 and October 20, 1981 letters on this subject, pertinent information from SEP Topic V-10.A and available 10 CFR 50, Appendix I submittals for R.

E. Ginna.

cc w/enclosure:

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Mr. John E. Maier CC

...Harry'H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae

'1333 New Hampshire Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau NNew York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, New York

]4519 Director, Bureau of Nuclear Operations State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 U. S. Environmental Protection Agency Region II Office ATTN:

Regional Radiation Representative 26 Federal Plaza New York, New. York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 James P. O'Reilly, Regional Administrator Nuclear Regulatory Commission, Region II Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Supervisor of the Town of Ontario 107 Ridge Road West

Ontario, New York 14519 Dr'.

Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr; Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 R.

E.

GINNA TOPIC V-5, Reactor Coolant Pressure Boundary Leakage Detection 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.

III, REVIEW GUIDELINES The acceptance criteria are described in the Nuclear Regulatory'Commission Standard Review Plan Section 5.2.5, "Reactor Coolant Pressure Boundary Leak-age Detection."

The areas of the Safety Analysis Report and Technical Specifications are reviewed to establish that information submitted by the licensee is in compliance 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 infor-mation 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-10.A, the March 23, October 12 and October 20, 1981 letters from RG&E to the NRC regar'ding SEP Topic V-5, and the available 10 CFR 50, Appendix I review information for R.

E. Ginna as well as the other information listed in the references was reviewed.

Regulatory Guide 1.45 recommends 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 unidenti'fied leakage.

The detection systems should be capable of performing tfieir 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 monitoring and (2) airborne particulate radioactivity monitoring.

The third method may be either monitoring of condensate flow rate from air coolers or monitor ing of airborne gaseous radioactivity.

Other detection

methods, such as humidity, temperature and pressure, should be considered to be alarms of indirect indication 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 incorporated systems and their corresponding features are tabulated in Enclosure l.

Detailed guidance for the leakage detection system is contained in Regula-tory Guide 1.45.

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

we have determined:

1)

That the types of systems employed for the detection of leakage from the reactor coolant pressure boundary to the containment consist of the minimum.three recommended by Regulatory Guide 1.45.

However, not one of the recommended systems have been sufficiently documented such that it meets all of the acceptance criteria of SRP 5.2.5 (See Table 1 for further details).

2)

Table 1 lists leakage detection systems in addition to the minimum three systems recommended by Regulatory Guide 1,45, If credit is to be taken for these systems in the evaluation of the adequacy of the entire leakage detection

system, then these systems will have to be demonstrated to meet the criteria of the Guide.

3)

Provisions have been incorporated to, monitor reactor coolant in-leakage to systemswhich connect to the reactor coolant pressure boundary.

However, from the review of the referenced information it is not clear that Table 2 includes all of the systems which connect to the reactor coolant pressure boundary.

Also, these systems have not been demonstrated to be able to withstand seismic events up to the OBE 1 evel.

4).

The Ginna Technical Specification

3. l. 5. 3 does impose requirements concerning the operability. of the leakage detection systems to monitor leakag'e to the primary containment, as recommended by Regulatory Guide 1.45.

However, the Technical Specification requirements do not conform to those given in current Standard Technical. Specification 3/4.4. 6.

In addition, corresponding surveillance requirements in the Standard Technical Specifications are not contained in the Ginna Technical Specifications (Table 4. 1-1).

5)

Information concerning the use of reactor coolant inventory balances, as indicated in Table 3, for detection of RCPB leakage is incomplete, therefore, its contribution to overall system effectiveness cannot be determined, V.

CONCLUSIONS Our review indicated that the systems employed at R.

E. Ginna to measure reactor coolant pressure boundary leakage do not meet all of the recommen-dations given in Regulatory Guide 1.45.

Specifically, our review concludes that:

1)

Although all of the recommended types of leakage detection systems for measurement of leakage from the reactor coolant pressure boundary to the containment have been incorporated in the facility, the systems do not meet all of the sensitivity, operability or surveillance criteria.

2)

Information concerning the leakage detection systems for the detection of inter-system reactor coolant pressure boundary leakage is incomplete.

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

3}

Standard Technical Specification 3/4,4.6 and the corresponding sur-veillance 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 pressure boundary to containment leakage detection systems.

4}

Information concerning the use of the primary coolant system inventory balance leak rate sensitivity and time required to achieve sensitivity is incomplete.

Therefore, we cannot determine the contribution of this technique to the overall leak detection sensitivity.

The necessity for any leakage detection system modification's will be considered during the integrated safety assessment.

REFERENCES 1.

Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"

May 1973.

2.

R.

E. Ginna FSAR, Sections 4.2 and 11.2.

3.

R.

E. Ginna "Supplement 1 to Technical Supplement'ccompanying Applica-tion for a Full-Term Operating License, December 20,

1972, response to questions 7c and 10.

4.

Westinghouse Standard Technical Specifications, NUREG-0452, Revision 4.

5.

R.

E. Ginna Technical Specifications.

6.

Letter from John E. Maier, RG&E, to Boyce H, Grier,

USNRC, Region 1, IE Bulletin 80-24, dated 12/31/80.

7.

Letter from John E. Maier, RG&E, to Boyce H. Grier, USNRC, Region 1, LER 81-004, February 25, 1981.

8.

Draft SEP Review of Topic IX-3, Station Service and Cooling Water Systems, by letter from Crutchfield to Maier, June 23, 1981.

9.

Letter from L. D. White, Jr.,

RG&E, to Dennis L. Ziemann,

NRC, SEP Topic V-lO.A, February 2, 1979.

10.

Letter from Dennis M, Crutchfield, NRC, to John E. Maier, RG&E, SEP Topic V-5, March 10, 1981.

ll, Letter from John E, Maier, RG&E, to Dennis M. Crutchfield,

NRC, SEP Topic V-.5, March 23, 1981.

12.

Letter from Dennis M, Crutchfield, NRC, to John E, Maier, RG&E, SEP Topic V-5, July 22,

1981, 13.

Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.

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

.Table l:

RCPB to Containment Systoa 1)

Sump Leve Monitortng (Inventory) 2)

Sump Pump "ctgations Honitorint

'Time Heters 3)

Airborne i I"ticulate Radioactiv':>> Nonitorin 4)

Airborni.

-seous Radioacti-.t Honitorin 5)

CondensI.t.bd Flow Rate from Aii'olers 6)

Container;t.Atmosphere Pressure ~<onitorin 7)

ContainI!kkt Atmosphere KumiditaeKonitorin 8)

Contain'ib'nt Atmosphere

~Ten eraliire Haettarle g) cvcs Incorporated Yes Yes Yes Yes Yes Yes Yes Yes Yes Leak Rate Sensitivity NA 1

gpm (2) 2-10 gpm 1-30 gpm NA 2-10 gpm 0.25 gpm Plant:

me eq to Achieve Sensitivity 1 hr.

1 hr, 1 hr.

NA 1 hr.

art quake For Which'Function Is Assured SSE Control Room Indication For Alarms 5 Indicators Yes Yes Yes Yes Yes No Yes Document-esta e

ation Ref-During N!r ~

erence mal Operant on Yes Yes Yes Yes Yes Yes Yes Yes NA

=. Not available; (1) See References 2, 3, 5, and 7; (2) 0.013 gpm within twenty minutes assuming the presence of corrosion products per Technical Specification 3.1.5.3.

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Hethods to Heasure RCPB In-Leakage on ensate r

Ejector Radia-Leak Rate Sensitivity me Req to Achievq Sensitivity arthquake For Mhich Function Is Assured Control Room Indication For Alarms A.Indicators REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEHS Re ulator Guide 1.45 Re uirements Document-ation Ref-erence est>

e Durf >g Nor-mal 3peration s

2) Seconc'ary System B'lowdown Honitor 0.0025 gpm>>

l hr.

Yes Reference 2

Yes I.':

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~,f Surge ank Level adiation ionitor R

4) Component Cooling Mater System

3) Comporent Coolino Mater System T

0.16 gpm Yes Yes Reference 8

References Yes Yes 2 a r

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• Total Leakage of 0.5 gallons necessary for indication,

'I i-..Table 3:

-',:; RCS inventor lalance au 'rel REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTENS Re ulatar Ruing 1.45 Requirements

'lant:

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REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEMS Re ulator Guide 1 P45 Re uirements

.Table 1:

Plant:

R.

E G'CPB to Conthinment System 1)

Sump Leve Monitoring {Inventory)

Incorporated Yes Leak Rate Sensitivity NA Time Req d to Achieve Sensitivity arthquake For Which'Function Is Assured Control Room" "..

Indication For Alarms

&"Indicators.

'i Yes Document-ation ',Ref-erence Testab e

During Nor.

. mal Operant on Yes Sump Pump-'ctuations Monitorin-. 'Time Meters Yes NA Yes Yes 3)

Airborne..:-'"ticulate Radioactiv-'-.

Monitorin 4)

Airborni.

- seous Radioaci:i =-.-:;

. Monitorin 5)

Condens<.-"-.

". Flow Rate from Air..coolers h

-6)

ContainIe

.=.~.Atmosphere Pres sum -Aonitorin a ~

7)

ContainIli~t Atmosphere

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Humidit'-Monitorin 8)

Contain

nt Atmosphere

~T:

N g) cvcs Yes Yes Yes Yes Yes Yes Yes 1

gpm (2}

2-10 gpm 1-30 gpm HA 2-10 gpm NA 0.25 gpm 1 hr.

h 1 hr, 1 hr, 1 hr.

NA NA

. SSE NA Yes Yes Yes Yes No Yes (1)

I' Yes Yes Yes Yes Yes NA = Not available;

{1}'See References 2, 3, 5, and 7; (2) 0.013 gpm within twenty minutes assuming the presence of corrosion products per Technical Specification 3.1.5.3.

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'..Table 2:

', 'l-:",'~I Systems.

Ms ich Interface w/ RCPB Plant:

Methods to Measure RCPB In-Leakage Condensate ir Ejector Radia-Leak Rate Sensi tivity T me Req to Achieve Sensi tivity arthquake For Which Function Is Assured Control Room Indication For Alarms 8" Indicators REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTEHS Re ulator Guide 1.45 Re uirements Document-ation Ref-

'rence'st>

e Duri >g Nor-mal Operation 55 5

'5 ~f.') Second'.cry System Blowdown Monitor 0.0025 gpm" 1 hr.

Yes Reference 2

Yes

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.3) Comporent Cooling Water System Surge Tank Level adiation onitor R

4) Component Cooling Water System M

0.16 gpm NA Yes Yes Reference 8

References Yes Yes.

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I 55

• Total Leakage of 0.5 gallons necessary for indication,

4 4

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"..-'-::.'.Table 3:

~CS Znve s

ntor t.3alance REACTO COOLANT PRESSU E BOUNDARY LEAKAGE DETECTION SYSTENS Re ulatur Guide 1.45 Requirements Plant:

';"..-".. Leak Rate Sens;'tivity

~ ~4 rresponding

..oe Required

'.o

~'. Achieve S<<nsitiyity

,- 'Normal 'Invento y Check

-1.

. 'nstrumentatio Required with Corresponding Location:

Earthquake Fo-4Jhich Instrumentation Hardware Functioning Is Assured:

3'estable Duri". " Normal Operation:

Dncumentation

" ference:

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