ML20206H428
| ML20206H428 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/17/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Tam P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606260070 | |
| Download: ML20206H428 (7) | |
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'At3 Telephone (412) 393-6000 Nuclear Group P.O. Box 4 shmpinoport. PA 15077-0004 ggng 17, yggg Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn:
Mr. Peter S. Tam, Project Manager Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 -
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Class 1 Pump and Valve Internals Relief Requests Gentlemen:
Attached are requests for relief from certain ASME Section XI inspection requirements for Class 1 pump and valve internals.
The requests provide the code requirements, a basis for requesting relief and proposed alternate examinations.
The code requirements listed in the relief requests have been determined to be impractical for Beaver Valley, Unit 1 in accordance with 10 CFR 50.55a(g)(5)(iii).
Attached is a
check in the amount of $150.00 for payment of the application fee in accordance with 10 CFR 170.
Very trul y urs, J. J. Carey Vice President, Nuclear Attachments cc: Mr. W. M. Troskoski, Resident Inspector U.
S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 gamanM@r
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Banvar Valley Powar Station, Unit No. 1 Dockot No. 50-334, Licsnca No. DPR-66 Class 1 Pump and Valve Internals Relief Requests Page 2 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120
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CLASS 1 PUMP AND VALVE INTERNALS RELIEF REQUESTS I
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Components Affected Reactor Coolant Pumps (RC-P-1A, 1B, IC)
Section XI Requirement (74S75)
Table IVB-2500, B-L-1 (Pump Casing Veld) and B-L-2 (Pump Casing) examinations - The pump casing veld and pump casing of one reactor coolant pump (RCP) vill be examined volumetrically and visually, respectively, by the end of the inspection period.
Basis for Relief The required examinations of the RCP casing veld and casing internal pressure boundary requires the complete disassembly of the RCP. Complete disassembly of a RCP would result in large expenditures of manpower and a substantial increase in radiation exposure. Also, possible damage to the pump could occur since these pumps were not designed for ease of disassembly in the field.
RCP casing examinations performed by other plants have shown no evidence of cracks or surface degradation.
Potential or significant pump degradation would be detected by abnormalities in pump parameters, i.e.,
pump vibration, bearing temperature, seal flow and by RCS leakage.
Therefore, considering the radiation exposure, cost, and possible damage resulting from pump disassembly, along with the past industry results of RCP casing examinations and the continuously maintained pump parameters I
that would detect pump degradation, it is concluded that the required examination vill not provide a compensating increase in the level of quality or safety to justify the difficulties that would be involved in such an examination.
Alternate Examination As an alternative to the B-L-1 and B-L-2 examinations, a visual inspection vill be performed on the external surfaces of the pump casing during the hydrostatic pressure test required by IVB-5000 that is to be performed before the end of the current inspection period.
If pump problems are encountered that require the disassembly of a RCP pump, the pump's interior surface vill be visually inspected and the need for a volumetric examination vill be evaluated at that time.
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Components Affected Class 1 Valve Bodies (See page 4 for the specific valves)
Section XI Requirement (74S75)
Table 2500, B-M-1, requires a volumetric examination of 100% of the pressure retaining velds in at least one valve of each group valves that are of the same constructional design, manufacturing method and manufacturer and that are performing similar functions in the system each inspection interval.
Basis for Relief The majority of the affected valv.e casings are made of ASTM A182 forged stainless steel. The remainder of the affected valve casings are made of ASTM A351 cast stainless steel.
Because of the geometrical configurations and material characteristics in both forged and cast 1
stainless steel valve bodies, it is difficult to obtain meaningful ultrasonic results.
These examinations would require long periods of time in high radiation areas.
Since the affected valves are located in high radiation areas the quality of radiography could be reduced by severe fogging.
Considering the inherent fracture toughness of this material and the service history of valves made of the material, it is concluded that deferring this examination until the valves are disassembled for maintenance purposes vill not have an adverse affect on the integrity of the valves, i
l Alternate Examination f
Defer B-H-1,' volumetric examination, until the valve is disassembled for maintenance purposes. Perform a B-H-2, visual examination at that time and evaluate and, if practical, perform the B-M-1, volumetric examination.
It is concluded, that this examination vill provide assurance of structural reliability.
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Components Affected Class 1 Valve Bodies (See Page 4 for the specific valves)
Section XI Requirement (74S75)
Table 2500, B-H-2, requires a visual examination of the internal pressure boundary surfaces on selected valves exceeding 4 in. nominal pipe size each inspection interval.
Basis for Relief The design of the valves is such that disassembly is required to perform the examination.
Based on past performance of these valves and the
'l service history of stainless steel valves, the requirement to disassemble one valve of each design type for the purpose of visual examination has a small probability of identifying service-induced flaws or degradation.
l The required examination would result in unnecessary exposure and cost and is therefore not justified.
Alternate Examination The B-M-1, visual examination, vill be deferred until valve disassembly is required for maintenance purposes.
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C1ces 1 Valvas Velan, Check SI-10 6"
SI-23 6"
i SI-11 6"
SI-24 6"
SI-12 6"
SI-25 6"
SI-15 6"
SI-48 12" SI-16 6"
SI-49 12" SI-17 6"
SI-50 12" SI-20 6"
SI-51 12" SI-21 6"
SI-52 12" SI-22 6"
SI-53 12" Velan, Gate MOV-SI-865A 12" MOV-SI-865B 12" MOV-SI-865C 12" Vestinghouse, Gate MOV-RC-590 29" MOV-RC-592 29" MOV-RC-594 29" MOV-RC-591 27 1/2" HOV-RC-593 27 1/2" MOV-RC-595 27 1/2" Target Rock, Relief Valve RV-RC-551A 6"
RV-RC-551B 6"
RV-RC-551C 6"
Rockwell, Gate MOV-RC-585 8"
MOV-RC-586 8"
MOV-RC-587 8"
Darling, Gate MOV-RH-720A 10" HOV-RH-720B 10" Copes / Vulcan, Gate MOV-RH-700 14" MOV-RH-701 14" 4
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