ML18033B413
| ML18033B413 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/02/1990 |
| From: | Ross T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9007060127 | |
| Download: ML18033B413 (22) | |
Text
1 July 2, 19 Docket No. 50-260 LICENSEE:
Tennessee Valley Authority (TVA)
FACILITY:
Browns Ferry Nuclear Plant, Unit 2
SUBJECT:
SUMMARY
OF MEETING MITK TVA REGARDING: (1)
ENVIRONMENTAL QUALIFICATION OF ELECTRICAL BOARDS FOR MOTOR OPERATED VALVES AND (2)
AN ALLEGATION On May 30, 1990, the NRC staff met with TVA in Rockville, Maryland to discuss two distinct topics - (1) operability and environmental qualification (EQ) requirements for the RMOV Boards (2D/2E) that power several safety-related motor operated valves (MOV) and (2) a particular allegation about cables.
A list of attendees is provided as Enclosure 1.
TVA's handouts during the meeting for topic (1) are provided as Enclosure 2.
No handouts were prepared for topic (2).
At this meeting TVA presented a rationale for not including RMOV electrical boards 2D/2E in their EQ program.
In essence, TVA stated that these boards would be exposed to a harsh environment only during a Reactor plater Cleanup (RWCU) System line break, and that the affected flow control valves (FCV),
with little or no additional modifications, could still accomplish their intended safety functions during a
RMCU line break should these boards fail.
As such, RMOV boards 2D/2E would not be required for a postulated RMCU line
- break, and since their environment remains mild or essentially mild for other postulated line breaks, TVA concluded these boards should not be upgraded for EQ.
The staff plans to examine these boards in greater detail during the EQ team inspection conducted onsite from June 25 through 29, 1990.
The staff has been reviewing allegation OSP 90-A-0018, "Cable Contracts for Class lE Systems."
Following the discussions on the aforementioned EQ issue, the staff probed TVA for additional information to support its review.
TVA noted that the corrective actions prescribed by the Condition Adverse to Quality Report (CAQR) related to this allegation were almost completed to the satisfaction of all concerned, including the alleger.
The staff plans to examine TVA's corrective actions and discuss them with the alleger while onsite during the EQ team inspection.
1 'ed by Frederick J.
Kebdon for
Enclosures:
- l. Attendees 2.
TVA handouts Thierry M. Ross, Project Manager Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures see next page 9007060127 900702 SEE PREVIOUS CONCURRENCE PDFi ADOCK os0002so P
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Docket No. 50-260 LICENSSE:
Tennessee Valley Authority (TVA)
FACILITY:
Browns Ferry Nuclear Plant, Unit 2
SUBJECT:
SUMMARY
OF MEETING WITH TVA REGARDING: (I) ENVIRONMENTAL QUALIFICATION OF ELECTRICAL BOARDS FOR MOTOR OPERATED VALVES AND (2)
AN ALLEGATION On Hay 30, 1990, the NRC staff met with TVA in Rockville, Maryland to discuss two distinct topics - (1) operability and environmental qualification (EQ) requirements for the RHOV Boards (2D/2E) that power several safety-related motor operated valves (MOV) and (2) a particular allegation about cables.
A list of attendees is provided as Enclosure 1 ~
TVA's handouts during the meeting for topic (I) are provided as Enclosure 2.
No handouts were prepared for topic (2).
At this meeting TVA presented a rationale for not including RHOV electrical boards 2D/2E in their EQ program.
In essence, TVA stated that these boards would be exposed to a harsh environment only during a Reactor Water Cleanup (RWCU) System line break, and that the affected flow control valves (FCV),
with little or no additional modifications, could still accomplish their intended safety functions during a
RWCU line break should these boards fail.
As such, RHOV boards 2D/2E would not be required for a postulated RWCU line
- break, and since their environment remains mild or essentially mild for other postulated line breaks, TVA concluded these boards should not be upgraded for EQ.
The staff plans to examine these boards in greater detail during the EQ team inspection conducted onsite from June 25 through 29, 1990.
Th'e staff has been reviewing allegation OSP 90-A-0018, "Cable Contracts for Class 1E Systems."
Following'the discussions on the aforementioned EQ issue, the staff probed TVA for additional information to support its review.
TVA noted that the corrective actions prescribed by the Condition Adverse to Quality Report (CAQR) related to this allegation was almost completed to the satisfaction of all concerned, including the alleger.
The staff plans to examine TVA's corrective actions and discuss them with the alleger while onsite during the EQ team inspection.
Enclosures:
- 1. Attendees 2.
TVA handouts cc w/enclosures see next page Thierry HE Ross, Project Manager Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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/Docket F i-1 e NRC PDR Local PDR F. h1iraglia J. Partlow S.
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Hebdon S. Black Y. Krebs T.
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Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 7A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Director Tennessee Valley Authority ET 12A 11A 400 West Summit Hill Drive Knoxville, Tennessee 37902 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 Engineering Tennessee Valley Authority 6N 38A Lookout Place 1101 Mar ket Street Chattanooga, Tennessee 37402-2801 Dr. Mark 0. Medford Vice President and Nuclear Technical Director Tennessee Valley Authority 6N 38A Lookout Place Chattanooga, Tennessee 37402-2801 Mr. Edward G. Wallace
- Manager, Nuclear Licensing ard Regulatory Affairs Tennessee Valley Authority 5N 1578 Lookout Place Chattanooga, T'ennessee 37402-2801 Mr. 0. J. Zeringue, Site Director Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 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 Commission 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. Danny Carpenter 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 1 le, Maryland 20852 Mr. Oliver D. Kingsley, Jr.
Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Enclosure I Attendees For NRC/TVA Meetin Of 5/30/90 Name Fred Hebdon Thierry Ross George Hubbard Harold Walker James Watt Ike Zeringue Pedro Salas Tom Ippo1 ito J.C. Delockery Henry Jones Jim Hutson Titie Project Director Project Manager Section Chief Technical Reviewer Technical Reviewer Site Director Compliance Supervisor Contractor Engineer Engineer Project Engineer Or anization NRC/NRR/PD II-4 NRC/NRR/PD II-4 NRC/NRR/SPLB NRC/NRR/SPLB NRC/NRR/SPLB TVA/BFN TVA/BFN TVA TVA/BFN TVA/BFN TVA/BFN
ENCLOSURE 2
OPERABILlTY REQUIREMENT> FOR RNOV BOARDS 2D AND 2H FOLLOWING AN RWCU LINE BREAK
RMOV BOARDS 2D/2E POWER THE FOLLOWING MOTOR OPERATED VALVES:
FCV-68-79 (-03)
FCV-74-07 (-30)
FCV-74-53 (-67)
FCV-74-59 (-73)
RECIRC PUMP DISCHARGE VALVE RHR PUMP MINI-FLOW VALVE RHR LPCI INJECTION VALVE RHR TEST RETURN/TORUS COOLING VALVE
N%'P!KBSSN POOL SPRhY A"
. TQRNKR
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PCV-68-79
(-03) HAIK; PUMP DISCHARGE VALVE 0
Safety function is to close for LPCI operation.
LPCI operation is not required following an BRCU break.
0 No modifications or compensatory measures are required for the recirc pump discharge valve.
PCV-74-07
(-30)
RHR PUMP MINI-FKCNVALVE Safety function is to open for pump protection.
Valve will be deenergized in the open position prior to plant startup.
During a normal reactor shutdown, operator-can reenergize and close the valve prior to initiation of RHR shutdown cooling.
0 No modifications will be required for the mini-flow valve.
e
FCV-74-53
(-67)
RHR LPCI INJECTION VMVE Safety functions are:
(l) to remain closed to maintain high pressure/lour pressure barrier between the reactor coolant system and
- RHR, (2) to open for LPCI operation, and (3) to isolate the LPCI flow path for torus cooling operation.
Ninor modifications to the valve control circuit at the BMOV board (replacement of wiring, terminal blockh, and two hand-switches) will ensure a spurious signal does not bypass the high pressure interlock and open this valve as a result of an IXCU line break.
LPCI operation is not required following an BNCU break.
PCV-74-59
(-73)
BHR TEST PZZURN TORUS COOLING VMVE 0
Safety functions are:
. (l) to close for LPCI operation (short-term)
(2) to open for torus cooling operation following an accident (long-term).
LPCI operation is not required following an BNCU break.
0 No modifications or compensatory actions are required for the RHP, test return/torus cooling valve.-.
CONCLUSION RNCV'BOARDS 2D/2E NOZ REQUIRED P3R POSTULATED RNCU LINE BREAKS
4 k
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C RNOV BOARDS 2D/2E EQ EVALUATION FOR OZHER POSTULATED LINE BR1W,KS PEAK TEMPERATURES 2D ESSENTIALLY NILD MS LINE FN LINE HPCI 120 133 116 (100 117 (100 MILD ENVIRONMENT RCIC (100'
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