ML17157B061
| ML17157B061 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/26/1992 |
| From: | Raleigh J Office of Nuclear Reactor Regulation |
| To: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| GL-89-10, TAC-M77798, TAC-M77799, NUDOCS 9202280078 | |
| Download: ML17157B061 (6) | |
Text
~pR RECT Wp0 A,
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~0 Op**4 Docket Nos.
50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 26, 1992 Hr. Harold W. Keiser Senior Vice President Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Hr. Keiser:
SUBJECT:
GENERIC LETTER 89-10, SUPPLEMENT 3, "CONSIDERATION OF NRC SPONSORED TESTS OF MOV's," SUS(UEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2 (HPA B-116, TAC NOS.
H77798 AND H77799)
Generic Letter 89-10, Supplement 3
(GL Supplement),
was issued to Boiling Water Reactor (BWR) licensees on October 25, 1990.
The GL Supplement refocused licensee GL 89-10 activities by placing a number of con'tainment isolation Motor-Operated Valves (HOVs) on a high priority.
These containment isolation MOVs are located in the steam supply line for the Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI) turbines, the supply line for the Reactor Water Cleanup (RWCU) systems, and isolation condenser lines, as applicable.
The 'staff requested this reprioritization based on receiving the results of NRC-sponsored dynamic HOV tests performed by Idaho National Engineering Laboratory (INEL).
The INEL dynamic testing of typical 6-and 10-inch flex-wedge motor-operated gate valves indicated that several of the historic design assumptions regarding MOV behavior utilized in actuator sizing were not conservative.
This GL Supplement required licensees to provide the NRC staff with:
(a) the criteria applied in determining whether any deficiencies exist in HOVs within the scope of the GL, (b) the identification of any HOVs found to have deficiencies, and (c) a schedule for any necessary corrective action within 120 days from issuance.
On December 12,
- 1990, and March 14,
- 1991, the licensee of the Susquehanna Steam Electric Station, Units 1 and 2, submitted a description of its response to Supplement 3 to GL 89-10 for NRC staff review.
In a submittal dated July 31, 1990, the licensee answered staff questions on its response to the generic letter supplement.
The staff has completed its review of the GL Supplement and request for additional information (RAI) responses from the licensee (Enclosure).
This review has been provided to NRC regional personnel to assist in their inspections of the licensee's GL 89-10 programs which are currently being performed in accordance with Temporary Instruction 2515/109.
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Hr. Harold W. Keiser February 26, 1992 This letter completes licensing actions on Supplement 3 of Generic Letter 89-10 and closes TAC Nos.
H77798 and H77799.
If there are any questions regarding this action, please call me on (301) 504-1447.
Sincerely,
Enclosure:
Review of GL Supplement and responses cc w/enclosure:
See next page DISTRIBUTION:
Docket File NRC 5 Local PDRs PDI-2 Reading SVarga JCalvo CHiller HO'Brien(2)
JRaleigh OGC AGody, Jr.
JNorberg ACRS(10)
- RBlough, RGN-I
- JWhite, RGN-I
/S/
James J. Raleigh, Project Hanager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation OFFICE P
IIAME H
B DATE PDI-2 P
JRALEIG c
92 tP d 92 PDI-
/92 OFFICIAL REC R
COPY F ILENAHE: SUH77798. GEN
Hr. Harold W. Keiser February 26, 1992 This letter completes licensing actions on Supplement 3 of Generic Letter 89-10 and closes TAG Nos.
M77798 and N77799.
If there are any questions regarding this action, please call me on (301) 504-1447.
Sincerely,
Enclosure:
Review of GL Supplement and RAI responses cc w/enclosure:
See next page mes J. Raleigh, Project Nanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ENCLOSURE u
uha na nit an On December 12,
- 1990, and Harch 14, 1991, the licensee of the Susquehanna nuclear power plant submitted a description of its response to Supplement 3 to GL 89-10 for NRC staff review.
In a submittal dated July 31, 1990, the licensee answered staff questions on its response to the generic letter supplement.
The NRC staff conducted an inspection on September 23 to 27, 1991, of the program being developed at Susquehanna in response to GL 89-10.
The inspection report is in preparation.
During the inspection, the NRC staff evaluated the licensee's response to Supplement 3 to GL 89-10 and raised concerns regarding the capability of several of the HOVs within the scope of Supplement 3.
On October 4, 1991, the licensee submitted calculations of available thrust (in the form of valve factors) based on the capability of the motor actuator.
From its review of the licensee's submittal, the NRC staff believes that the evaluation of Unit 1
HPCI HOV 155F002 and Unit 2 HPCI HOV 255F002 should be assigned a high priority because of the low valve factors (as compared to other Supplement 3
HOVs), the use of generic motor curves, omission of the application factors, and other assumptions.
The licensee is taking specific actions in response to the staff concerns.
With those licensee
- actions, the NRC staff considers it appropriate for the licensee to address the HOVs applicable to Supplement 3 as part of its GL 89-10 program and schedule, unless further information dictates accelerated action.
Among the aspects that the licensee should address are (1) the structural limits of each HOV in light of the increased thrust and torque requirements based on industry experience and research
- testing, (2) the reduction in thrust delivered by the actuator that may occur as a result of the "rate of loading" phenomenon, (3) the reduction of motor output that may occur as a result of high ambient temperature, (4) the capability of the valves to satisfy. any leakage limits associated with the licensee's safety analyses when closing under design basis conditions (particularly where the torque switch is set assuming low valve factors, but is bypassed for a significant portion of the valve stroke),
(5).its justification for the assumed stem friction coefficient, (6) its justification for the assumed differential pressure under which the HOVs may be called upon to operate in light of the intent of GL 89-10, (7) the inaccuracy of HOV diagnostic equipment in measuring delivered torque or thrust, (8) the assumed minimum voltage available to the motor as compared to its licensing commitments, and (9) the closing stroke time under design basis conditions in relation to technical specifications or safety analyses (particularly for dc motors).
In addition to its own HOV tests, the licensee will be expected to monitor the HOV tests performed by other organizations for information on the torque and thrust required to operate its valves under design basis conditions.
The licensee will be expected to take action to ensure HOV operability where those tests raise questions regarding the required torque or thrust estimates.
With respect to the review of the NRC-sponsored HOV tests by the Electric Power Research Institute (EPRI), the NRC staff agrees with the evaluation by the Idaho National Engineering Laboratory
( INEL) provided in EGG-SSRE-9926 (November 12, 1991),
"Evaluation of EPRI Draft Report NP-9926
- Review of NRC/INEL Gate Valve Test Program."
During future inspections of the GL 89-10 program, the NRC staff will review the licensee's assumptions and calculations for HOVs within the scope of GL 89-10.
Mr. Harold W. Keiser Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street, P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr, Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603 Mr. Robert G.
Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101