ML18046A486
| ML18046A486 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point, Palisades File:Consumers Energy icon.png |
| Issue date: | 03/10/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-05-05, TASK-5-5, TASK-RR LSO5-81-03-012, LSO5-81-3-12, NUDOCS 8103110735 | |
| Download: ML18046A486 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 10, 1981 Docket Nos. 50-155/255 LS05-81-03-012 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201
Dear Mr. Hoffman:
RE:
SEP TOPIC v~s, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION BIG ROCK POINT AND PALISADES Enclosed is a copy of our evaluaton of SEP Topic V-5 for the Big Rock Point and Palisades. This assessment compares your facility, as described in Docket. No. 50-155/255s with the criteria currently used by the regulatory staff for licensing new facilities. Please inform us within 30 days if your as-built facility differs from the licensing basis assumed in our assessment or this topic will be assumed complete.
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.
In future correspondence regarding this topic, please refer to the topic number in your cover letter.
Enclosure:
SEP Topic V-5 on Big Rock Point and Palisades cc w/enclosure:
See next page 8103110 735.
Sincerely,
/J
. M.
~Crutchfield, Operating Reactors Bra 5
Division of Licensing*
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Mr. David P. Hoffman cc M. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Co~any 212 West Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Joseph Gallo, Esquire Isham, Lincoln & Beale 1120 Connecticut Avenue Room 325 Washington, D. c. 20036 Peter w. Steketee, Esquire 505 Peoples Building Grand Rapids, Michigan 49503 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan 49720 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Summerset Drive Midland, Michigan 48640 Resident Inspector Big Rock Point Plant c/o U.S. NRC RR #3, Box 600 Charlevoix, Michigan 49720 PALISADES BIG ROCK POINT DOCKET NO, 50-155 DOCKET NO. 50-255 Charles Bechhoefer, ~sq*., Chai nnan Atomic Safety and Licensing Board Panel
- u. S. Nuclear Regulatory CoRITlission *.,.
Washington, D. C.
20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston 1005 Calle Largo Santa Fe, New Mexico 87501 Alan S. Rosenthal, Esq. Chainnan Atomic Safety and Licensing Appeal Board:.
- U~ S. Nuclear Regulatory CoRITlission Washington, D. C.
20555 Mr. John O'Neill, lI
. Route 2,~ox 44 Maple City. Michigan 49664 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board
- u. S. Nuclear Regulatory Conmission Washington, D. C.
20555 Dr. Oscar H. Paris Atomic Safety and Licensing Board U. S. Nuclear Regulatory Conmission Washington, D. C. 20555 Mr. Frederick J. Shon Atomic Safety and Licensing Board
- u. S. Nuclear Regulatory Conmission Washington, D. c. 20555 Big Rock Point Nuclear Power ~lant ATTN:
Mr. C. J. Hartman Plant Superintendent Charlevoix, Michigan 49720 Mr. Jim E. Mills Route 2, Box 108C Charlevoix, Michigan 49720
Mr. David P. Hoffman cc Chairman County Board of Supervisors Charlevoix County Charlevoix, Michigan' 49720 Office of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C.
20460
- u. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Resident Inspector c/o U. S. NRC P. O. Box 87 South Haven, Michigan 49090 Palisades Plant ATTN:
Mr. J. G. lewis Plant Manager Covert, Michigan 49043 Township Supervisor Covert T<Mnship Route 1, Box 10 Van Buren County, Michigan.49043 Christa-Maria Route 2, Box 108C Charlevoix, Michigan 49720 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103
-*-* *. -- ~.,.. *"-""""".:.:*-.--*.... -_-.... -.,,.:... _.....__.... -.. *----- - e BIG ROCK POINT
- DOCKET NO, so~1ss Ms. JoAnn Bier PALISADES DOCKET NO. 50-255 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. s. Nuclear Regulatory Conmission Washington, D. c. 20555 Dr. John H. Buck Atomic Safety and licensing Appeal Board U. S. Nuclear Regulatory Conmission Washington, D. C. 20555
I.
lntroductton BIG ROCK POINT SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY (RCPB) LEAKAGE DETECTION The safety* objective of Topi.c V-5 i.s to determine the rel tab.fl ity and sensitivHy of the leak detectfon systems which. monftor 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 Aopendix 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 source of leakage in the reacto.r coolant pressure boundary.
Criterion 32, "Inspection of Reactor Cool ant Pressure Boundary". requires that components 1vhi ch are part of the reactor coolant pressure boundary shall be designed to permit periodic inspection and testing to asses~ their structural and leak tight i n:egrity.
III.
Review Guidelines The acceptance criteria are implemented by the Nuclear Regulatory Commission in Section 5.2.5, "Reactor Coolant Pressure Boundary Leakage Detection",
anc Section 5.2.4, "Reactor Coolant Pressure Boundary Inservice Inspection c:nd Testing", of the Standard Review Plan.
The areas of the Safety Analysis Report and Technical Specifications are reviewed to establish that informa-tion submitted by the licensee is in compliance v:ith Regulatory Guide 1.45.
"Reactor Cool ant Pressure Boundary Leakage Detection Systems", and that the inservice inspection programs are based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, "Rules for the Inservice Inspec-tion of Nuclear Power Components".
Although not a part of this review, the consequences of break and crack location in component failures is analyzed and evaluated in Section 3.6.1,_ "Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment", and Section 3.6.2, "Determination of Break Locations and Dynamic Effects Associated with Postulated Rupture of Piping", of the Standard Revie1*: Plan.
IV.
~valuation Safety Topic V-5 was evaluated in this review for compliance of the infor-r.;ation submitted by the licensee with Regulatory Guide 1.45, Reactor Coolant
?ressure Boundary Leakage Detection Systems.
7he information in the Safety
- nalysis Report and Technical Specifications was substantiated by telephone cci
- iversation with the 1 icensee.
Regulatory Guide 1.45 requires that at
I..
2 -
least three separate detection systems be installed in a nuclear power plant to detect an unidentified leakage from the reactor coolant pressure
- boundary 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 following 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 r:;ay be either monitoring of condensate_ flow rate from air coolers or
~or:itoring of airborne gaseous radioactivity.
Other detection methods, s:.ich as humidity, temperature and pressure, should be considered to be alar~s or indirect indication of leakage to the containment.
The require-r.er.ts of Regulatory Guide 1.45 and Standard Revie\\'/ Plan 5.2.5 and plant incorporated.systems that meet those requirements are tabulated in.
V-..
Conc1 us.ions.
Our review indicates that the Big Rock Point Plant is in compliance with Regulatory Guide 1.45 and SRP 5.2.5.
ENCLOSURE l TABLE l:
REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEM Plant S.R.P. 5.2.5 or Incorporated Reg Guide 1.45 System Svstem Reauirement l ) Sump Level Monitoring (Inventory) x Yes, 1 or 2
- Mandatory
- 2) Sump Pump Actuations x
Yes, 1 or 2 Monitoring (Time Meters)
Mandatory
- 3) Airborne Particulate x
Yes Radioactivity Monitoring Mandatory
- 4) Airborne Gaseous Yes, 4 or 5 Radioactivity Monitoring Mandatory
- 5) Condensated Flow Rate Yes, 4 or 5 from Air Coolers x
Mandatory
- 6) Containment Atmosp~ere
~
Yes Pressure Monitoring Optional
- 7) Containment Atmosphere x
Yes Humidity Monitoring Optional
- 8) Containment Atmosphere Yes Temperature Monitoring Optional
- 9) eves Makeup Fl O\\'Jra te Yes
! Optional
- 0)
Portabl~ Ultrasonic I Yes Detectors Optional 1
l 1 ) Air Conditioner Coolant No Temperature Rise 1 2) 1 3)
I I
i i I
i I
J I I I i I.
Introduction PALISADES SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY (RCPB) LEAKAGE DETECTION The safety objecti:ve of Topic V-5 i.s to determine the rel tab.fl ity 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
.. :.pJendix A, 10 CFR Part 50.
Criterion 30, "Quality of Reactor Coolant
- Jressure Boundary", requires that means shall be p!"'ovided for detecting
- nd, to the extent practical, identifying the location of the source of
- e::.kage in the reactor coolant pressure boundary.
Criterion 32, "Inspection of Reactor Coolant Pressure Boundary", requires that components which are Jart of the reactor coolant pressure boundary shall be designed to permit oeriodic inspection and testing to assess their structural and leak tight integrity.
~
III.
Review Guidelines The acceptance criteria are implemented by the Nuclear Regulatory Commission in Section 5.2.5, "Reactor Coolant Pressure Bound::.ry Leakage Detection",
ari'.:l Section 5. 2. 4, "Reactor Cool ant Pressure Bouncai-y Inservice Inspection and Testing", of the Standard Reviev1 Plan.
The areas of the Safety Analysis
~eoort and Technical Specifications are reviewed :o establish that informa-
~iJn submitted by the licensee is in compliance \\\\1ith Regulatory Guide 1.45.
"Reactor Cool ant Pressure Boundary Leakage Detection Systems 11
, and that the i~service inspection programs are based on the rec~irements of Section XI of the ASME Boiler and Pressure Vessel Code, "Rules for the Inservice Inspec-tion of Nuclear Pm'ier Components".
Although not a part of this review, the consequences of break and crack location in component failures is analyzed and evaluated in Section 3.6.1, "Plant Design for Protection Against Postulated DiJing Fa.ilures in Fluid Systems Outside Containment", and Section 3.6.2,
'Tetermination of Break Locations and Dynamic Effects /l.ssociated with Pcstulated Rupture of Piping", of the Standard Reviev: Plan.
~valuation Safety Topic V-5 was evaluated in this review for co~pliance of the infor-
- =.tion submitted by the licensee with Regulatory S
- .iide 1.45, "Reactor Coolant
?:-essure Boundary Leakage Detection Systems".
The information in the Safe~y
~nalysis Report and Technical Specifications was s~bstantiated by telephone
- .:wersation with the l~censee.
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 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 detectio.n systems should be capable of performing their functions following 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 monitoring of airborne gaseous radioactivity.
Other detection methods, such as humidity, temperature and pressure, should be considered to be alarms or indirect indication of leakage to the containment.
The require-ments of Regulatory Guide 1.45 and Standard Revie\\-.J Plan 5.2.5 and plant incorporated systems that meet those requirements are tabulated in En c 1 o s u re 1.
V.
Conclusions.
Our review indicates that the Palisades Plant is in compliance with Regulatory Guide 1.45 and SRP 5.2.5.
ENCLOSURE 1 TABLE 1 :
REACTOR COOLANT -PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEM Plant S.R.P. 5.2.5 or Incorporated Reg Guide 1.45 Svstem System Reauirement
- 1) Sump Level Monitoring (Inventory) x Yes*, l or 2 Mandatory
- 2) Sump Pump Actuations x
Yes, l or 2 Monitoring (Time Meters)
Mandatory
- 3) Airborne Particulate x
Yes Radioactivity Monitoring Mandatory
- 4) Airborne Gaseous Yes, 4 or 5 Radioactivity Monitoring Mandatory
- 5) Condensated Flow Rate x
Yes, 4 or 5 from Air Coolers Mandatory
- 6) Containment Atmospnere Yes Pressur~ Monitoring
~
Optional
- 7) Containment Atmosphere x
Yes Humidity Monitoring Optional
- 8) Containment Atmosphere Yes Temperature Monitoring Optional
- 9) eves Makeup Fl owrate Yes
! Optional 1 0) Portable Ultrasonic I Yes Detectors Optional 1 ) Air Conditioner Coolant No Temperature Rise 1
1 2) 1 3)
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