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Forwards Revised Relief Requests from ASME Section XI Insp Requirements for Class 1 Pump & Valve Internals,Per NRC 870226 Telcon.Relief Request 2 Re B-M-1 Volumetric Exams of Class 1 Body Welds Withdrawn
	ML20214T816
Person / Time
Site:	Beaver Valley
Issue date:	06/01/1987
From:	Sieber J; DUQUESNE LIGHT CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8706100440
	Download: ML20214T816 (6)
	v • d • e

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"3hplC Telephone (412) 393-6000 Nuclear Group P O. Bom 4 Shippingport. PA 15077M4 June 1, 1987 j

U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Revised Class 1 Pump and Valve Internals Relief Requests Gentlemen:

In a letter dated June 17, 1986, we requested relief from certain i

ASME Section XI inspection requirements for Class 1 pump and valve internals.

On February 26, 1987 members of my staff conducted a

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telephone conference with Messrs. T. Sullivan, G. Johnson and S. Lee of the NRC staff concerning the relief requests.

Attached are revised relief requests addressing the concerns of the NRC staff.

l The revisions are noted by side bars in the margin.

Please note that we are withdrawing relief request 2

regarding B-M-1 volumetric examinations of Class 1

valve body welds since no body welds have i

been identified in Class 1 valves at Beaver Valley Unit 1.

If there

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are any questions concerning this matter, please contact my office.

j This is a

revision to a

request for relief for which an application fee has been provided pursuant to 10 CFR 170, therefore, l'

we have determined that no additional fee is required.

j Very truly yours,

'.5b~ber Vice President, Nuclear i

Attachment d%

0706100440 070601

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PDH ADOCK 05000334 4

p PDR

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Revised Class 1 Pump and Valve Internals Relief Requests Page 2 cc: Mr.

S. M. Pindale, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A washington, DC 20555

- Mail Stop 316 Addressee only 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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f CLASS 1 PUMP AND VALVE INTERNALS RELIEF REQUESTS 1

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Components Affected l

Reactor Coolant Pumps (RC-P-1A, 1B, IC)

Section XI Requirements (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 i

coolant pump (RCP) vill be examined volumetrically and visually, respectively, by the end of the inspection period.

Basis for Relief The required examinations ot the RCP casing veld and casing internal pressure boundary requires the complete disassembly of the RCP.

l Complete disassembly of an RCP vould result in large expenditures of l

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.

The volumetric examination of the casing veld is extremely technically difficult. The inherent course grain structure of ASTM A351-65 Grade CF8 material precludes meaningful ultrasonic examination with present technology. The combination of surface radiation levels and material thickness (5"-6" minimum) preclude conventional radiographic techniques, leaving only high-curie Cobalt 60 or HINAC as possible alternatives.

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 flov and by RCS leakage.

Considering the technical difficulty, radiation exposure, cost, and I

possible damage resulting form pump disassembly, along with past industry results of RCP casing examinations and the continuously monitored pump parameters that vould detect pump degradation, it is concluded that the required examination vill not provide a compensating increase in the level of safety to justify such examinations.

Alternate Examination As an alternative to the B-L-1 examination, the exterior of the pump casing vill be visually examined during pressure tests as required by IVB-5000 and a surface examination vill be performed on the veld of one Reactor Coolant Pump.

The B-L-2 examination vill be performed only when the pump is disassembled for maintenance.

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4 2.

Components Affected Class 1 Valve Bodies (See page 4 for the specific valves)

Section XI Requirement (74S75) t Table 2500, B-H-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 This request for relief has been withdrawn as no Class 1 valves have body velds (per EH 90229).

3.

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 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. The required examination would result in unnecessary exposure and cost and is therefore not justified. '

Alternate Examination The B-H-2 visual cxamination, vill be deferred until valve disassembly is required for maintenance purposes.

4.

ML20214T816

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