ML20041F892
| ML20041F892 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/11/1982 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-05-05, TASK-5-5, TASK-RR LSO5-82-03-070, LSO5-82-3-70, NUDOCS 8203170517 | |
| Download: ML20041F892 (7) | |
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March 11,1982 Docket No. 50-29 LS05-82-03-070 to o
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R E C 5.Y M O Mr. James A. Kay Senior Engineer - Licensing 2-MAR 171982a-9
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Yankee Atomic Electric Company n caosum cmr L 1671 Worcester Road CNTN
~f Framingham, Massachusetts 01701 y
Dear Mr. Kay:
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SUBJECT:
SEP TOPIC V-5, REACTOR COOLANT PRESSURE B0UNDARY LEAKAGE DETECTION - YANKEE NUCLEAR POWER STATION Enclosed is a copy of our draft evaluation of SEP Topic V-5 for the Yankee Nuclear Power Station. This assessment was based on a com-parison of the facility, as described in Docket No. 50-29, with the criteria currently used by the regulatory staff for licensing new facilities. This evaluation factors in the information contained in the Yankee Technical Specifications and information in SEP Topic V-10. A.
Please inform us within 30 days if your as-built facility differs from the licensing basis assumed in our assessment. Al so,
pleasa supply the missingiinformation in Tables 1, 2 and 3 in the evaluation that is pertinent to this facility.
This evaluation will be a basic input to the integrated safety as-f60Y sessment for your facility unless you identify changes needed to f
e reflect the as-built conditions at your facility. This assessment
- p may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the m u6(ib integrated assessment is ccmpleted.
4001 Sincerely,
(,. Slo /67 i
a Ralph Caruso, Project Manager 8203170517 820311 Operating Reactors Branch No. 5 PDR ADOCK 05000029 Division.of Licensing P
Enclosure:
As stated cc w/ enclosure:
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NRC FORM 318 (10-80) NRCM oua OFFICIAL RECORD COPY usceo. mi-me
ANKEE Docket No. 50-29 Mr. James A. Kay CC Mr. James E. Tribble,. Pres' dent Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chai rma n Board of Selectmen Town of Rowe Rowe, Massachusetts 0136' Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108
~ U. S. Environmental Protection Agency Region I Office ATTN: EIS C0ORDINATOR JFK Federal Building Boston, Massachusetts 02203 Residert Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 1
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.i SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 YANKEE 7
TOPIC:
V-5, Reactor Coolant ' Pressure Boundary-(RCPB) Leakag'e ' 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.
REV!EW 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, " Quality of Reactor Coolant Pressure Boundary," requires that means shall be provided for detecting 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 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 compliance with Regulatory Gu'ide 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 Final Hazards Summary Report, the Final Safety Analysis Report, the Technical Specifications and SEP Topic V-10. A was reviewed.
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-fled 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
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-2' leak detection methods recommended, two of the methods should be (1) sump level and flow monitoring and (2) airborne particulate
_ _ radioactivity monitoring. The third method may be either moni-toring 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 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 in.tersystem leakage through methods such as radioactivity and water level or flow monitors.
Plant incorporated systems and their corresponding features are tabulated in Enclosure 1.
Detail.ed guidance for the leakage detection 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 deteru ned:
- 1) The systems employed for the detection of leakage from the reactor coolant pressure boundary to the containment do not meet the recommendations of Regulatory Guide 1.45.
Specifically, all of the recommended types of detection systems are not employed and for those systems employed, the system sensitivity,. seismic qualification and testing specifications do not meet the recommen-dations of the Guide.
- 2) Provisions are made to monitor reactor coo 3 ant in-leakage to those systems listed in Table 2.
However, from the review of the refer-enced information it is not clear that this table includes all sys-tems which interface with the reactor coolant pressure boundary.
3)
Information concerning the use of reactor coolant inventory balances, for RCP5 leakage detection as indicated in Table 5, is incomplete, therefore, its contribution to overall detection system effectiveness cannot be determined.
V.
CONCLUSIONS Our review indicated that the systems employed at Yankee to measure reactor ccciant pressure bouncary leakage co not meet'tne recc :mendations given in Regulatory Guide 1.45.
Specifically, our review concludes that:
- 1) The types of leakage detection systems incorporated for measurement of leakage from the reactor coolant pressure boundary to the contain-ment do not meet the minimum recomendations of Regulatory Guide 1.45, 2)
Information concerning the leakege 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)
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.
I The necessity for. any leakage detection system modification will be considered during the integrated safety assessment.
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REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS Regulatery Guide 1.45 Requirements Plant: YANKEE NUCLEAR POWER STATION Table 1:
Time Req'd Earthquake for Control Room' Docu Leak Rate to Achieve Which function Indication For atto RCPil to Containment E-Incorporated Sensitivity
' Sensitivity Is Assured Alarms & Indicators ererW
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System s
- 1) Sump Level Monitoring (Inventory)
YES u2Sgpm 12 hrs YES FSAR
- 3
- 2) Sump Pump Actuations NO Monitoring (Time Meters) f^
- 3) Airborne Particulate YES lgpm 12 hrs YES ad Radioactivity Monitoring 18 NO
- 4) Airborne Gaseous Radioactivity Honitoring Condensated Flow Rate N0 5)^ from Air Coolers YES 73,g;
- 6) Containment Atmosphere Pressure Monitoring I
- 7) Containment Atinosphere YES FSAI liumidity Monitoring FilSl YES
- 8) Co'ntainment Atmosphere gq; Temperature Monitoring A !>
- 9) Accoustic Emissions N0 t
- 10) Moisture Sensitive Tape
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) Vapor Containce Sound System-YES YES.
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REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS Plant: YANKEE NUCLEAR P0tlER STATION Table 3:
RCS Inventory Balance
- 1) Leak Rate Sensitivity:
- 2) Time Required to Achieve 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Sensitivity:
3)
Instrumentation Required:
- 4) Seismic Qualification:
- 5) Testable During Normal 4
Operation:
- 6) Documentation
Reference:
Yankee Technical Specification 3/4.4.5
- 7) Description of Inventory Balance Procedure:
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