ML20004D894
| ML20004D894 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/03/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-05-05, TASK-5-5, TASK-RR LSO5-81-06-008, LSO5-81-6-8, NUDOCS 8106100273 | |
| Download: ML20004D894 (8) | |
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r June 3, 1981 Docket No.,50-g45 e
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<@g Mr. W. G. Counsil, Vice President J[jff Os p
Nuclear Engineering and Operations j
u,4%'*g*79g Northeast Nuclear Energy Cocpany 7
v '** 0 P. O. Box 270
\\g Hartford, Connecticut 06101 gg s
Dear Mr. Counsil:
4
SUBJECT:
SEP TOPIC Y-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION MILLSTONE NUCLEAR P0bER STATION Enclosed is a copy of our revised draft evaluation of SEP Topic V-5 for the Millstone Nuclear Pcwer Station. This assessment conpares your facility, as described in Docket No. 50-245, with the criteria currently used by the regulatory staff for licensing new facilities. This revised draft evaluation factors in tne information contained in your April 25, 1981 letter on this subject, and pertinent information contained in SEP Topic V-10.A and available 10 CFR 50, Appendix I submittals for Millstone Unit 1.
Please inform us within 30 days whether or not your as-built facility differs from the licensing basis assumed in our assessaent.
This evaluation will be a basic input to the integrated safety assesscent for your f acility unless you identify changes needed to reflect the as-built conditions at your facility.
This assessment may be revised in the future if your faciity design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is cocpleted.
In future correspondence regarding this topic, please refer to the topic numcer in your cover letter.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
SEP Topic V-5 cc w/ enclosure:
8106100/ M See next page
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June 3,1981 Docket No. 50-245 LS05-81 06-008 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
SUBJECT:
SEP TOPIC V-5, REACTOR COOLANT PRESSURE B0UNDARY LEAKAGE DETECTION MILLSTONE NUCLEAR POWER STATION Enclosed is a copy of our revised draft evaluation of SEP Topic V-5 for the Millstone Nuclear Power Station. This assessment compares your facility, as described in Docket No. 50-245, with t"e criteria currently used by the regulatory staff for licensing new facilities.
it's revised draft evaluation factors in the information contained in your April 25, 1981 letter on this subject, and pertinent information contained in SEP Topic V-10.A and available 10 CFR 50, Appendix I submittals for Millstone Unit 1.
Please inform us within 30 days whether or not your as-built facility differs from the licensing basis assumed in.our assessment.
This evaluatton 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 factity design is changed or if NRC criteria relating to this subject are modified before the integrated assessment i? co@leted.
In future correspondence regarding this topic, please refer to the topic number in your cover letter.
Sincerely,
)
y 4ief M. Crutchfield, Denn Operating Reactors Panch No. 5 Division of Licensing
Enclosure:
SEP Topic V-5 cc w/ enclosure:
See next page L
Mr. W. G. Counsil 1
cc William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Couns'elors at Law Research and Policy One Constitution Plaza Development Hartford, Cor.necticut 06103 Department of Planning and Energy Policy Natural Resources Defense Council 20 Grand Street 91715th Street, N. W.
Hartford, Connecticut 06106 Washington, D. C.
20005 Director, Criteria and Standards Division Northeast Nuclear Energy Company Office of Radiation Programs ATTN: Superintendent (ANR 460)
Millstone Plant U. S. Environmental Protection P. O. Box 128 Agency Waterford, Connecticut 06385 Washington, D. C.
20460 Mr. James R. Hirr.elwright U. S. Environmental Protection Northeast Utilities Service Company Agency P. O. Box 270 Region 1 Office Hartford, Connecticut 06101 ATTN: EIS COORDINATOR JFK Federal Building Resident Inspector Boston, Massachusetts 02203 c/o U. S. NRC P. O. Box Drawer KK Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385 John F. Opeka Systens Superintendent Northeast Utilities Service Conpany P. O. Box 270 Hartford, Connecticut 06101 b
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p MILLSTONE 1 SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDAdf (KLFb) LLAKAUL ULitCTION i
I.
Introduction The safety objective of Topic V-5 is to determine the reliability and sensitivity of.the leak detection systeas 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, " Quality 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 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 April 25, 1981 letter from NU to the NRC regarding SEP Topic V-5 for Millstorie Unit 1, the April 30, 1981 letter from NU to the NRC regarding SEP Topic V-5 for Haddam Neck, the March 5,1979 letter from NU to the NRC regarding SEP Topic V-10.A. and the available 10 CFR 50, Appendix I review information for Millstone Unit I 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 o
9 following ce*tain seismic events and capable of being checked in the control room. Of the three separata 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 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 ficw monitors. Plant incorporated systems and their corresponding features are tabulated in.
Detailed guidance for the leakage detection system is con-
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tained in Regulatory Guide 1.45.
Based upon our review of the referenced documents and the summaries presented in Enclosure 1, we have determined:
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- 1) The systers employed for the detection of leakage from the reactor coolant pressure boundary to the primary containment meet the Regu-latory Guide 1.45 requirement for the types of leakage detection systems to be employed. However, the systems required to be present do not have the required sensitivity for the detection of leaks of I gpm within I hour. Furthermore, information on many of the features of the leakage detection systers is incomplete.
(See Table 1 of Enclosure i
1.)
(
- 2) The Millstone Unit 1 Technical Specifications do not impose require-ments concerning the operability of the leakage detection systens to monitor leakage to the primary containment, as required by Regulatory Guide 1.45.
- 3) Provisions are made to monitor reactor coolant in-leakage to those t
systems listed in Table 2 of Enclosure 1.
However, from the review of the referenced information it is not clear that this table includes l
all systems which interface with the reactor coolant pressure boundary.
l In addition, information concerning the leak detection methods, similar i
to that given for the detection systems in Table 1 of Enclosure 1, is inconplete for those in Table 2.
- 4) Information concerning the use of reactor coolant inventory balances, as indicated in Table 3 of Enclosure 1, for a determination of its usefulness for reactor coolant pressure boundary leak detection is not available.
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' V.
Conclusions
- 1) The review of Table 1 of Enclosure 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.
In addition, due to the lack of information in the table, we cannot determine the complete extent of the deviations from the additional Guide criteria. The necessity for modifications will be considered during the integrated safety assessment.
- 2) A section should be added to the Millstone Unit 1 Technical Specifica-l tions concerning operability of the reactor coolant pressure boundary to the containment leakage detection systems. Standard Technical Specification 3/4.4.6 and the corresponding surveillance requirements should be used as guidance for the development of this section for the leakage detection systems relied upon as a result of the integrated safety assessment.
3)
Information concerning the leakage detection systens fer the detection of intersystem reactor coolant pressure boundary leakage and the reactor coolant inventory balance 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.
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t REACTOR COOLANT PRESSURE B0tR4DARY LEAKAGE DETfCTION SYSTEMS Regulatory Guide 1.45 Requirements Table 3:
Plant: M11 htnn, Unit 1 RCS Inventory Balance Leak Rate Sensitivity Corresponding Tice Required to Achieve Sensitivity (Normal Inventory Check Instrumentation Required with Corresponding Location:
Earthquake For Which Instrisnentation Hardware Functioning 15 Assured:
Testable Daring Normal Operation:
1 Documentation Reitrence:
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