ML20042A355

Forwards Draft Revised Evaluation of SEP Topic V-5, RCPB Leakage Detection. Tech Specs Do Not Impose Requirements Re Operability of Leakage Detection Sys to Monitor Leakage to Primary Containment Per Reg Guide 1.45

ML20042A355
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/19/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-05-05, TASK-5-5, TASK-RR LSO5-82-03-087, LSO5-82-3-87, NUDOCS 8203230356
Download: ML20042A355 (9)

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Docket No. 50-155 LS05 03-087 ik6 %

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Nuclear Licensing Administrator Consumers Power Company N[

1945 W. Parnall Road Jackson, Michigan 49201

SUBJECT:

SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION - BIG ROCK POINT NUCLEAR PLANT Enclosed is a copy of our draft revised evaluation of SEP Topic V-5 for Big Rock Point Nuclear Plant. This assessment was based on a comparison of the facility, as described in Docket No. 50-155, with the criteria currently used by the regulatory staff for licensing new facilities.

This draft revised evaluation factors in the information contained in the September 30, 1981 letter from CPCo to the NRC and the March 10, 1981 letter from the NRC to CPCo, both on this subject, and the CPCo to NRC letter of October 9,1979 on SEP Topic V-10.A.

Please inform us within 30 days whether or not the as-built facility differs from the licensing basis assumed in our assessment. Also, please supply the missing infor-mation in Tables 1, 2 and 3 of the evaluation that is pertinent to this facility.

This evaluation will be a basic input to the integrated safety assessment fo: your facility unless you identify changes needed to reflect the as-Y

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built conditions 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.

) l Sincerely, AbOS Dennis M. Crutchfield, Chief

(, S/o Operating Reactors Branch No. 5 7* g 4 Division of Licensing

Enclosure:

As~ stated.

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Docket Ns. 50.155 R3. 2/8/82 Mr. David J. VandeWalle.

cc U. S. Environmental Protection Mr. Paul A. Perry, Secretary Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:

Regional Radiatio'n Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Or. Oscar H. Paris Washington, D. C.

20036

. Atomic Safety and Licensing Board

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U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman' U. S. Nuclear Regulatory Commission

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Atomic Safety & Licensing Appeal Board Washington, D. 'C.

20555 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Big Rock Point Nuclear Power Plant ATTN:. Mr. C. J. Hartman Mr. John O'Neill, II Plant. Superintendent Charlevoix, Michigan 49720 Route 2, Box 44 Maple City, Michigan 49664 Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Soulevard Cou.nty Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County l

Charlevoix, Michigan 49720 Resident Inspector l

Big Rock Point Plant l

Office of the Governor (2) c/o U.S. NRC l

Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semmel Mr. Jim E. Mills Counsel for Christa Maria, e,t al. -

Route 2, Box 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law

.263316th Street, NW Washington, D. C.

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Docket N9, 50.155 Mr. David J. VandeWalle CC Dr. John H. Buck Atomic Safety and Licerising Appeal Board

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'3^t3 Ms. JoAnn Bier

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'Ju'C Charlevoix, Michigan 49720 2.3 n;i: : tivi y Thomas S. Moore

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Washington, D. C.

20555 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III

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Office of Inspection and Enforcement 799~ Roosevelt Road

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SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 BIG ROCK POINT _

V-5, Reactor Coolant Pressure Boundary (RCPB) Leakage Detection.

TOPIC:

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 critsria for the detection of leakage from the reactor coolant pressure boundary is stated in the General Design Criteria,of Criterion 30, " Quality of Reactor Coolant Appendix A,10lCFR Part 50. Pressure Boundary", requires that means sh and, to the extent practical, identifying the location of the sources of leakage in the reactor coolant pressure boundary.

III.

REVIEW GUIDELINES _

The acceptance criteria are described in the Nuclear Regulatory Commis-sion Standard Review Plan Section 5.2.5, " Reactor Coolant Pressure The areas of the Sa.fety Analy. sis Report Boundary Leakage Detection".

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 Sy' stems".

j 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 The information Coolant Pressure Boundary Leakage Detection Systems."

in the Final Hazards Summary Report, Technical Specifications, the Septem-letter from CPCo to the NRC and the March 10,1981 ' letter ber 30,1981 from the NRC to CPCo, both on SEP Topic V-5, and the October 9,1979 letter from CPCo to the NRC regarding SEP Topic V-10.A was reviewed.

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' I Regulatory Guide 1.45 recommends that at least three separate detection systems be installed in a nuclear power plant to detect unidentified leakage from the reactor coolant pressure boundary to the primary con-tainment of one gallon per minute within.one hour. Leakage from identi-fied sources must be isolated so that the flow rates may be monitored separately from unidentified leskage. The detection systems s'hould be capable of performing their functions following certain seismic events and capable o'f being checked in the control room.. Of the three separate leak detection methods recommended, two pf 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 4

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 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 radioactsivity and water level or flow monitors.: Plant incorporated systems and their correspond-ing features are tabula'ted in Enclosure 1.

Detailed guidance for the leakege detection system is contained in Regulatory Guide 1.45.

Based upon our review of the referenced documents and the summari6s pre-sented in Enclosure 1, we have determined:

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1) The systems employed for detection of leakage from the reactor coolant l

pressure boun'iary to the primary containment meet the Regulatory Guide i

1.45 requirement for the types of leakage detection systems to be em-I ployed. However, documentation of the system sensitivities, seismic l

qualification, alarm indication and tastability are not available in l'

the docket file.

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2) The Big Rock Point Technical Specifications do not impose requirements j

concerning the operability of the leakage detection systems to monitor leakage to the primary containment, as recommended by Regulatory Guide 1.45.

Provisions are made to monitor rehetor coolant in-leakage to those 3) systems listed in Table 2 of Enclosure 1.

HoWever, from the review of I

l the referenced information it is'.not clear that this table includes

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l 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, is incomplete for those in Table 2.

4)

Information concerning the use of reactor coolant inventory balances; as indicated in Table 3, for a determination of its usefulness for reactor coolant pressure boundary leak detection is incomplete.

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CONCLUSIONS

1) The review'of Table 1 indicates that the systems incorporated for measurement of leakage from the reactor coolant pressure boundary to the containment do not conform with Regulatory Guide 1.45 criteria regarding sensitivity, seismic qualification, alarm indication and testabili ty.

2) Standard Technical Specification 3/4.4.6 and the corresponding sur-i veillance requirements concerning the operability of the reactor coolant pressure boundary to the containment leakage detection sys-tems (excluding the sump flow monitor) should be added tc the Big 4

Rock Point Technical Specifications.

3)

Information concerning the leakage detection systems for the detection i

of intersystem reactor coolant pressure boundary leakage and the re-actor coolant inventory balance is incomplete. Therefore, we cannot determine the extent to which Regulatory Guide 1.45 is met.

I The necessity for any' modifications will be considered during the inte-grated safety assessment.

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REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS Regulattry Guide 1.45 Requirements

. Table 1 :

Plant: BIG ROCK POINT RCPB to Contiinment Time Req'd Earthquake For Control Room Leak Rate to Achieve Which Function Indication For System Incorporated Sensitivity

' Sensitivity Is Assured Alarms & Indicators

1) Sump Level Mon.itoring (Inventory)

YES

2) Sump Pump-Acteations YES Monitoring _(Time Meters)

3) Airborne Particulate YES Radioactivity Monitoring

4) Airborne Gaseous Radioactivity Monitoring

5) Condensated Flow Rate YES from Air Coolers

6) Containment Atmosphere Pressure Monitoring

7) Containment Atmosphere YES Humidity Monitoring

8) Co'ntainment Atmosphere Temperature Monitoring

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9) Accoustic Emissions

10) Moisture Se'nsitive Tape 11) 12) 4

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REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS Plant: BIG ROCK POINT Table 3:

RCS Inventory Balance

1) Leak Rate Sensitivity:

2) Time Required to Achieve Sensitivity:

3)

Instrumentation Required:

4) Seismic Qualification:

5) Testable During Normal Operation:

6) Documentation

Reference:

7) Description of Inventory Balance Procedure:.

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