ML20041C365
| ML20041C365 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/22/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Fiedler P JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-05-05, TASK-5-5, TASK-RR LSO5-82-02-100, LSO5-82-2-100, NUDOCS 8203010223 | |
| Download: ML20041C365 (9) | |
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a February 22, 1982
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i FE Docket No. 50-219
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Mr. P. B. Fiedler 4
to Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION - OYSTER CREEK NUCLEAR POWER PLANT Enclosed is a copy of our final evaluation of SEP Topic V-5 for the Oyster Creek Nuclear Power Plant, This assessment was based on a comparison of the facility, as described in Docket No. 50-219, with the criteria currently used by the regulatory staff for licensing new facilities. This final evaluation factors in the information contained in the March 16, 1981 letter from the NRC to JCPLCo., the November 4,1981 letter from GPU to the NRC, and information contained in SEP Topic V-10. A and available 10 CFR 50, Appendix I submittals for Oyster Creek.
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 conditions at your facility. This assessment may be revised in the future if your facility design is changed or if NRC criteria relatin; i
to this subject are modified before the integrated assessment is completed.
Sincerely, NSE gga-9 M Dennis M, Crutchfield, Chief Operating Reactors Branch No. 5 9 /
Division of Licensing
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Docket No. 50-219 LS05-82 Mr. P. B. Fiedler Oyster Creek fluclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION - OYSTER CREEK NUCLEAR P0tfER PLANT
-C D A Enclosed is a copy of our 4 raft-revised evaluation of SEP Topic V-5, for the Oyster Creek fluclear Power Plant. This assessment was based on a comparison of the facility, as described in Docket No. 50-219, with the criteria currently used by the regulatory staff for licensing new facilities. This draft revised evaluation facters in the infons-tion contained in the March 16, 1981 letter from "'e fiRC to JCPLCo.,
the flovember 4,1981 letter from GPU to the NRC, and information con-tained in SEP Topic V-10.A and available 10 CFR 50 Appendix I submittals for Oyster Creek. -Please-infom us-within 30 days-whether-or-not-the-
-as-built-facility-4iffers-from-the. licensing-basis-assurrwi in our assess..cnt. Alserplease supply anymissing pertinent-information-in-
-Tables-1Mid-3 of the enclosure.
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 conditions at your facility.
This assessment may be revised in the future if your facility design is changed or if flRC criteria relating to this subject are modif;ed before the integrated assessment is completed.
Sincerely, Dennis !!. Crutchfield, Chief Operating Reactors Branch flo. 5 Division of Licensing Enc.losure:
As stated cc w/ enclosure:
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February 22, 1982 4
Docket No. 50-219 LS05-82 100 Mr. P. B. Fiedler Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBdECT: SEP TOPIC V-5, REACTOR COOLANT PRESSURE B0UNDARY LEAKAGE DETECTION - OYSTER CREEK NUCLEAR POWER PLANT Enclosed is a copy of our final evaluation of SEP Topic V-5 for the Oyster Creek Nuclear Power Plant, This assessment was based on a comparison of the facility, as described in Docket No. 50-219, with the criteria currently used by the regulatory staff for licensing new facilities.
This final evaluation factors in the information contained in the March 15, 1981 letter from the NRC to JCPLCo., the November 4, 1981 letter from GPU to the NRC, and information contained in SEP Topic V-10. A and available 10 CFR 50, Appendix I submittals for Oyster Creek.
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 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.
Sincerely,
- 4! 4 k.
DennisM.Crutchfield,shief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 1
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Mr. P. B. Fiedler cc G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U. S. NRC 1800 M Street, N. W.
Post Office Box 445 Washington, D. C.
20036 Forked River, New Jersey 08731 J. B. Lieberman, Esquire
-Commissioner Berlack, Israels & Lieberman New Jersey Dep'artment of Energy 26 Broadway 101 Commerce Street New York, New York 10004 Newark, New Jersey 07102 Natural Resources Defense Council Ronald C. Haynes, Regional Administrator 917 15th Street, N. W.
Nuclear Regulatory Commission, Region 1 Washington, D. C.
20006 Office of Inspection and Enforcement 631 Park Avenue J. Knubel King of Prussia, Pennsylvania' 19406 BWR Licensing Manager GGPU Nuclear 100 Interplace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety.
36 West State Street - CN 112 Trenton, New Jersey 08625 Ms. Phyllis Hacfner 101 Washington Street Toms River, New Jersey 08753 Mayor Lacey Township 818 Lacey Road Forked River, New Jersey 08731 U. S. Environmental Protection Agency Region II Office ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Licensing Supervisor Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 aw a--a
SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 0YSTER CREEK 1
TOPIC:
V-5, Reactor Coolant Pressure Soundary (RCPB) Leakage Detection 4
I.
INTRODUCTION 1
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 i
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 Guide 1.45,
" Reactor Coolant Pressure Boundary Leakage Detection Systems."
i IV.
EVALUATION i
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 March 16,-1981 letter from the NRC to JCPL, the t{ovember 4,1981 letter from GPU to the NRC, information contained in SEP Topic V-10.A i
and available 10 CFR 50, Appendix I review information for Oyster Creek 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-l tainment 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 l
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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 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 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 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 1.
Detailed 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 determined:
(1) The types of systems employed for the detection of leakage from the reactor coolant pressure boundary to the containment meet the recommendations of Regulatory Guide 1.45.
However, although the airborne particulate and airborne gaseous radioactivity monitoring systems are in place at Oyster Creek, these systems have never been placed into operation because of condensation problems.
Also, the sensitivity, seismic qualification, control room indication and testability specificatiens for the three recommended detection systems either do not meet the recommendations of the Guide or are not known.
(2)
The Oyster Creek Technical Specifications do not impose requirements concerning the operability of the leakage detection systems to monitor leakage to the primary containment, as recommended by Regulatory Guide 1.45.
(3)
Provisions are made to monitor reactor coolant in.-leakage as listed in Table 2 of Enclosure 1.
However, from the review of the referenced information it is not clear that this table includes all systems which interface with the reactor coolant pressure boundary.
(4)
Information concerning the use of reactor coolant inventory balances for detection of RCPB leakage, as indicated in Table 3, is incom-plete, therefore, its contribution to the overall detection system effectiveness cannot be determined.
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V.
CONCLUSIONS Our review indicated that the systems employed at Oyster Creek to measure reactor coolant pressure boundary leakage do not meet the
. recommendations given in Regulatory Guide 1.45.
Specifically, our review concludes that:
(1) Although all the types of leakage detection systems recommended by Regulatory Guide 1.45 for measurement of leakage from the reactor coolant pressure boundary to the containment are present, the airborne particulate and airborne gaseous radioactivity moni-
. toring systems have never been made operational.
Also, it cannot be determined if the design specifications of these systems meet the recommendations of the Guide.
(2) The Oyster Creek Technical Specifications should be revised to incorporate operability requirements for all of the leakage detec-tion systems.
The Standard Technical Specifications for General Electric Boiling Water Reactors, NUREG-0123, should be used as a basis for this revision.
(3)
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.
(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 modifications will be considered during the integrated safety assessment.
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REACTOR COOLANT PRESSURE B0UNDARY LEAKAGE DETECTION SYSTEMS Plant: Oyster Creek 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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