ML18033B562
| ML18033B562 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/27/1990 |
| From: | Mozafari B Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| NUDOCS 9011300317 | |
| Download: ML18033B562 (25) | |
Text
Docket No 50-260 MEMORANDUM FOR:
T. Hurley F. Miraglia W. Russell J. Partlow F. Gillespie S. Varga G. Lainas B. Boger L. Reyes, RII November 26, 1990 D. Crutchfield J. Zwolinski M. Virgilio W. Travers E. Butcher C. Rossi J.
Richardson A. Thadani Operations Center Pdc ~02-fo G. Holahan B. Grimes F.
Congel J.
Roe W. Lanning A. Chaffee W. Bateman, EDO L. Plisco T.
Cox THRU:
FROM:
SUBJECT DATE lI1 TItlE:
LOCATION:
PURPOSE:
Frederick J.
Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Brenda Hozafari, Project Engineer Project Directorate,II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation DAILY HIGHLIGHT - FORTHCOMING MEETING WITH TENNESSEE VALLEY AUTHORITY -
BROWNS FERRY NUCLEAR PLANT, UNIT 2
- Tuesday, November 27, 1990 9:00 a.m. - 1:00 p.m.
One White Flint North 11555 Rockville Pike Rockvi lie, Maryland 20852 Room 15-H-10 TVA will present information in support of requested amendment concerning Reactor, Protection System setpoint.
PARTICIPANTS*:
NRC B. Hozafari H. Garg 90ii3003i7 90ii27 PDR ADOCN, 05000260 PNU I cc:
See next page UTILITY T. Crib, et al Original signed by Brenda Mozafari, Project Engineer Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"
43 Federal
~Re 1ster 28068, 6/28/78.
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NOTICE NOV. 27
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Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 7A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. Edward G. Wallace
- Manager, Nuclear Licensing, and Regulatory Affairs Tennessee Valley Authority 5N 157B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. John B. Waters, Director Tennessee Valley Authority ET 12A 9A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. W. F. Willis Chief Operating Officer ET 12B 16B 400 West Summit Hill Drive Knoxville, Tennessee 37902 General Counsel Tennessee Valley Authority 400 West Summit Hill Drive ET 11B 33H Knoxville, Tennessee 37902 Mr. Dwight Nunn Vice President, Nuclear Projects Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Dr. Mar k 0. Medford Vice President, Nuclear Assurance, Licensing and Fuels Tennessee Valley Authority 6N 38A Lookout Place Chattanooga, Tennessee 37402-2801 Mr. Oliver D. Kingsley, Jr.
Senior. Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Mr. 0. J. Zeringue, Site Director Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabam-35602 Mr. P. Carier, Site Licensing Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35602 Mr. L. W. Myers, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35602
- Chairman, Limestone County Commission P. 0.
Box 188
- Athens, Alabama 35611 Claude Earl Fox, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Comnission 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Route 12, Box 637
- Athens, Alabama 35611 Tennessee Valley Authority Rockville Office 11921 Rockville Pike Suite 402 Rockvi lie, Maryland 20852
V F
DISTRIBUTION FOR MEETING NOTICE DATED:
November 27, 1990 Facility:
Browns Ferry Nuclear Plant, Unit 2 c
Docket--F-i le RRC PDR~
Local PDR SQN Rdg. File T. Murley/F. Miraglia J. Partlow S. Varga G. Lainas F.
Hebdon B. hayes B. Wilson, Region II E. Jordan B. Grimes P. Kellogg C. Patterson T. Ross D. Moran B. Mozafari W. Lanning OGC ACRS(10)
GPA/PA GPA/CA(2)
E. Tana V. Wilson L. Thomas J. Scarborough G. Marcus L. Norrholm J. Gray R. Borchardt K. Clark, Region II N. Green, PMAS E. Tana, PHAS R II RI I
I I/
tiOY 2 3 gg NOTICE OF SIGNIFICANT MEETING Name of Licensee:
Tennessee Valley Authority (TVA)
Name of Facility:
Browns Ferry Unit 2 Docket Numbers:
50-260 Date and Time of Meetings:
November 27, 1990 at 1:00 p.m.
Location of Yeeting:
101 Marietta. Street, N.M..
31st Floor Conference, Ro'om
~
- Atlanta, GA 30323 Purpose of Meeting:
Management Meeting to discuss plans for the training and testing of Browns Ferry operators prior to startup of Unit 2.
NRC Attendees:
B. A. I/ilson, Chief, TVA Projects P. Kellogg, Section Chief, TVAP, Browns Ferry T. A. Peebles, Chief, Operators
- Branch, DRS C. Casto, Section Chief, Operator Licensino Section 2
D.
C. Payne, Senior License Examiner, DRS Licensee Attendees:
Yi. Harrell, Operations Superintendent T. Dexter, Director of Training R. Jones, Operations Supervisor M. DeRouche, Operations Training J. Carlson, Operations Coordinator NOTE:
Attendance by NRC personnel other than those listed above should be made known by 4:00 p.m.,
November 26, 1990, via telephone to C.
Payne (404) 331-4666.
Enclosure:
Yieeting Agenda Approi ed By:
(ORIGINAL SIGNED BY P.
3. KELLOGG)
Paul
. Kellogg, Chief Projects Section 2
TVA Projects
.A
Notice of Significant Meeting 2
November 21, 1990 cc w/encl:
B. A.
Wi 1 son, TYA, RI I P. Kellogg, TVA, RII T. A. Peebles, DRS, RII C. Casto, DRS, RII D.
C. Payne, DRS, RII bcc:
J.
H. Sniezek, EDO H. L. Thompson, EDO T.
E. Murley, NRR R.
W. Borchardt, EDO S.
D. Ebneter, RII J.
L. Milhoan, RII B. A. Wilson, TVAP/RII L. A. Reyes, RII J.
P. Stohr, RII A. F. Gibson, RII P. J. Kellogg, TVAP/RII T. A. Peebles, RII C. A. Casto, RII D. C. Payne, RII R.
H. Bernhard, TVAP/P,II C. A. Patterson, TVAP/RII E.
F. Christnot, TYAP/RII R.
H. Bearden, TVAP/RII K. J.
Ivey, TVAP/RII G.
C. Lainas, NRR F. J.
- Hebdon, NRR K. M. Clark, RII Re eptionist C Document Control Desk RI I.'j)RS II/P j /90 RII:DRS CACasto II/ /90 RII PAP s(~
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 20, 1990 Docket No. 50-260 MEMORANDUM FOR:
FROM:
SUBJECT:
Freder',ck J.
Hebdon, D'.rector Projects Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Scott Newberry, Chief Instrumentation and Control Systems Branch Division of System Technology Office of Nuclear Reactor Regulation SAFETY EVALUATION REPORT SUPPORTING AMENDMENT NO.
287 TO FACILITY OPERATING LICENSE DPR-52 Plant Name:
Docket No.:
Uti 1 ity:
TAC No.:
Directorate:
Project Manager:
Rev'.ew Branch:
Review Status:
Browns Ferry Nuclear Plant, Unit 2 50-260 Tennessee Valley Authority 76902 II-4 T.
Ross SICH Complete By letter dated May 24,
- 1990, TVA submitted an amendment to the technical specifications.
This amendment requests the deletion from the design and the technical specifications pressure switch contacts which provide an open permissive for the RHR discharge valves at reactor pressure less than 100 psig.
Me reviewed the submitted amendment, and concluded that additional information or clarification was required from TVA.
This request for additional information or clarification from TVA was made'y you in your letter, to TVA, dated August 17, 1990.
On September 17, 1990, TVA responded to your letter of August 17, 1990.
As part of that response, calculations were made available for review at the TVA Rockville Office.
Me have concluded that the proposed amendment is acceptable since sufficient permissives are provided via other contacts and circuits.
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t UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ENCLOSURE 1
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 287 TO FACILITY OPERATING LICENSE DPR-52 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 2 DOCKET NO 50-26
1.0 INTRODUCTION
The Tennessee Valley Authority, (TVA) by letter (Ref. 1) has submitted a
request to change the Browns Ferry Nuclear Plant (BFN) Technical Specifications (TS) for Unit 2.
The staff reviewed the submittal and requested additional information (Ref.2).
TVA responded by letter (Ref.
- 3) to this NRC request.
A summary of the proposed changes to reactor pressure measurement instruments, used for inter system LOCA protection, are as follows:
The pressure
- switches, that are class~fied as non-Class 1E, are to be replaced with Class 1E pressure switches.
The pressure
- switches, that have two micro switch contacts, are to be replaced with pressure switches with one micro switch contact, and the pressure switches micro switch contact number 1 function is to be eliminated.
The pressure switches range is (50 psig - 1200 psig).
This range is to be changed to (20 psig - 180 psig).
The functional surveillance frequency, that is once every month, is to be changed to once every 3 months.
The calibration surveillance frequency, that is once every 3
months, is to be changed to once every 18 months.
TVA did not propose any change to the pressure switches setpoint settings.
2.0 BACKGROUND
Pressure
- switches, 2-PS-68-93 and 2-PS-68-94, used to measure reactor
- pressure, have two sets of contacts.
The number 2 contact is used as a
bistable input to a control logic (Ref. 4) for protection of the reactor pressure boundary inter connect'.on to the RHR system.
This pressure boundary protection is accomplished by the control logic providing; (1) an automatic isolation signal for closing RHR pumps suet~on outboard/inboard reactor isolation valves (Ref. 5), 2-FCV-74-47 and 2-FCV-74-48 whenever reactor pressure is 100 psig or greater, thus isolating the shutdown cooling system from the reactor vessel, and (2) a permissive to allow opening the valves whenever the reactor pressure is less than 100 psig.
The isolation function protects the shutdown cooling system, that has a maximum allowable pressure of 133 psig, and prevents an inter-system loss-of-coolant-accident (LOCA).
The pressure switch contact number 1 is used as a bistable input to a control logic (Ref. 6) that provides a permissive signal in conjunction with other interlocks, to allow opening of the RHR, pump outboard discharge valves (Ref. 7) 2-FCV-84-53 and 2-FCV-74-67.
The contact closes on decreasing reactor pressure of 1'00 psig or less.
The present switches have an adjustable set point range from 50 to 1200 psig and are classified as non-Class 1E.
The bistable input contacts open and close at a setpoint of 100 plus or minus 15 psig.
As a result of the wide range of the switches excessive drift has caused unacceptable accuracy in the lower pressure ranges.
3.0 EVALUATION TVA proposes to replace the non-Class 1E pressure switches with Class 1E Static-0-Ring (SOR) type, that has a setpoint range of 20 to 180 psig and an accuracy of 1 percent of the upper 1'.mit.
However, the Class 1E pressure switches can only be purchased with one contact.
TVA proposes to eliminate the functional requirement of pressure switch contact number 1 which is used as a permissive open interlock for valves 2-FCV-74-53 and 2-FCV-74-67 described in the above paragraph.
The information concerning pressure switch 2-PS-68-93 and 2-PS-68-94 contact number 1 on TS Table 3.2.B and Table 4.2.B are to be deleted.
In their letter (a)
TVA states:
"The contacts provided a low reactor pressure permissive for isolation valves 2-FCV-74-53 and 2-FCV-74-67, which is not necessary since the permissive signal to these valves is also provided whenever valves 2-FCV-74-47 and 2-FCV-74-48 are in the open [not fully closed] posit~on.
These valves, 2-FCV-74-47 and 2-FCV-74-48, cannot be opened unless reactor pressure is below 100 psig.
The removal of switch contact number 1 in effect provides a permanent low pressure permissive since the contacts are replaced with a jumper."
The staff's evaluation of the opening logic (Ref. 6) for valves 2-FCV-74-53 and 2-FCV-74-67 indicates that all of the following signals are required to be satisfied to open the valves:
Valve 2-FCV-74-47 is not fully closed.
Valve 2-FCV-74-48 is not fully closed.
The reactor pressure must be 100 ps'.g or less.
A containment isolation signal (CIS) must not be present.
The logic for opening valves 2-FCV-74-53 and 67 is; (1) the unit is ',n the shut down mode with the RHR suction valves open [not fully closed],
(2) the reactor pressure is 100 psig or less, and (3) there is
n no CIS signal present and therefore, the valves may be open manually.
In, the revised circuit, the reactor low pressure perm'.ssive has been elim'.nated.
The staff's review of the schematic diagrams (Ref. 4) indicates that pressure switch 2-PS-68-93 contact number 2'loses on reactor pressure above shutdown pressure
[greater than 100 psig] causes relay 10A-K97A to be energized and that relay causes relay 10A-K98A to be energized.
Relay 10A-K98A, "a" contact is connected to the shutdown cooling suet'.on valve (Ref. 5), 2-FCV-74-48, motor started closing circuit and the, "b"
contact is connected to the opening circu'.t. Therefore, the valve 2-FCV-74-48 can not be opened unless the reactor pressure is 100 psig or less and the valve will be automatically closed if the reactor pressure is greater than 100 psig.
Pressure switch 2-PS-68-94 contact number 2
functions similar to valve 2-FCV;74-47.
Based on the above review, the staff concludes that pressure switch 2-PS-68-93 and 2-PS-68-94 contact number 1 requirements may be eliminated and references to this function may be removed from the TS without a decrease of safety function.
Pressure switches 2-PS-68-93 and 94 are not identified in TS Table 3.2.A, "Primary Containment and Reactor Building Isolation Instrumentation."
They are listed under function, "Instrument Channel-Reactor High Pressure" Amendment No. 158, dated December 15, 1988.
TYA, in the~r letter (Ref. 3), indicated that the pressure switch numbers have been added to Table 3.2.A in TS change 282.
The staff verified that this correction has been made.
TYA proposes to ',dentify pressure switches 2-PS-68-93 and 94 in TS Table 4.2.A in this TS change.
TVA proposes to change the functional test interval from once each month to once every 3 months, and the calibration test interval from once every 3 months to once every 18 months.
TVA justified the increase in the functional test surveillance interval and the calibration test interval because the new Class 1E Static-0-Ring (SOR) pressure switches have improved reliability and accuracy.
TVA stated in their letter (Ref. 3) that, "Although the pressure switches are not required to operate during a
10 CFR 50.49 event the purchased pressure switches have been subjected, by the vendor, to mechanical aging by cycling the units 33,000 times at the upper adjustable 1'.mit and exposing the unit to the LOCA environment to determine the effect on the switch performance.
The vendor has successfully demonstrated the swi.tch capability to withstand the test conditions.
The anticipated duty cycle would be the quarterly functional testing cycle and number of plant shutdowns."
TVA cons~dered a duty cycle of 10 per year as being a conservative number.
The staff concurs that the SOR pressure switches purchased have increased reliability and accuracy.
TVA has reduced the range of the instrument from (50 - 1200) psig to (20 - 180) psig.
The vendor's repeatabi lity accuracy is 1 percent of 180 psig or 1.8 psig from setpoint.
This gives a better accuracy and better stability near the
~
100 psig setpoint.
The setpo'.nt value in the TS '.s 100 psig plus or minus 15 psig and has not been changed.
Furthermore, the setpoint is 80 ps'g from either the upper or lower range of the instrument which also is a more accurate setting.
TVA has performed a Setpoint and Scaling Calculation (Ref. 8) to determine the accuracy of the instrument loops.
This accuracy was compared to the required accuracies to assure that there was sufficient margin between the setpoints and the operating limits and the safety limits.
The staff review of the calculation indicated that TVA addressed errors associated with the following:
repeatabi lity drift temperature over-pressurization radiation reading test equipment seismic water leg The vendor',s errors are extrapolated to 18 months plus 25K, which is 22 1/2 months.
This is the max'.mum calibration interval.
The staff concludes that the TS 'ncrease in surveillance frequency for the functional test and calibration, does not decrease the safety function of the instruments.
5.0 CONCLUSION
The staff concludes that the present pressure sw',tches contact number 1
requirement may be eliminated and all references may be removed from the TS.
The pressure switches are proper ly identif'ed in the TS.
The increase in the pressure switches surveillance; (1) functional test frequency from once every month to once every thr ee months and (2) calibration test frequency from once every three months to once every eighteen months is acceptable.
t
,A ENCLOSURE 2
REFERENCE 1.
Letter dated tray 24, 1990, tl.J.Ray to NRC, TVA-BFN-TS-287 2.
Letter dated September 17,
- 1990, E.G Wallace to NRC, TVA-BFN-TS-111 3.
Letter dated August 17, 1990, T.Ross to TVA O.D.K'ngsley 4.
Logic for 2-PS-68-93, contact number 2, Schematic drawing 2-730E937, sheet 4, revision 5
Logic for 2-PS-68-94, contact number 2, Schematic drawing 2-730E937, sheet 7, revision 5
5.
Valve 2-FCV-74-47, Schematic drawing 2-730E937, sheet 23, revision 1, Schematic drawing 2-45E714-2 revision 3
Valve 2-FCV-74-48, Schematic drawing 2-730E937, sheet 19, revision 0, Schematic drawing 2-45E779-7, revision 4
6.
Logic for 2-PS'-68-93, contact number 1, Schematic drawing 2-730E937, sheet 5, revision 4
Logic for 2-PS-68-94, contact number 1, Schematic drawing 2-730E937, sheet 8, revision 4
7.
Valve 2-FCV-74-53, Schematic drawing 2-730E937, sheet 3, revision 3, sheet 15, revision 1
Valve 2-FCV-74-67, Schematic drawing 2-730E937, sheet 3, revision 3,
sheet 17, revision 2
8.
Setpoint and Scaling Calculation ED-f2068-890288/
EBB-TI-28, revision l.
Principal Contributor: Frederick P. Paulitz, NRR/DST/SICB
r
ENCLOSURE 3
SYSTEM lATIC ASSESSMENT OF LICENSEE PERFORMANCE BROWNS FERRY NUCLEAR PLANT UNIT 2
SUMMARY
OF REVIEW The l.censee submitted a licensee amendment change to the technical specification for instruments that measure reactor pressure and provided inputs to logic control that is designed to protect the reactor system pressure boundary.
NARRATIVE DISCUSSION OF LICENSEE PERFORMANCE FUNCTIONAL AREA Although the staff had to spend a considerable amount of time and effort requesting additional information and clarification by letter and telephone, it should not reflect on TVA's effort.
Once the staffs request for additional information was given to the right TVA personnel, the information was received in a timely manner..
Author:
F. Paulitz Date:
10/31/90
~l
F. J.
Hebdon Enclosure 1 is our evaluation of the licensee's submittal, Enclosure 2 is the reference material, and Enclosure 3 is the Systematic Assessment of Licensee Performance (SALP) input for this evaluation.
Original signed by Scott Newberry, Chief Instrumentation and Control Systems Branch Division of System Technology Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/enclosures:
A. Thadani R. Jones T. Ross DISTRIBUTION SICB R/F (2)
FPaulitz A. Marinos SNewberry SEE PREVIOUS CONCURRENCE OFC
- SICB
- SICB NAME :*FPaulitz: lm:*AMarinos DATE:10/ /90: 10/
/90
- SICB:
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90 ICIAL RECORD COPY Document Name:
FRED HEBDON 05
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