ML18143B520

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Requests Relief from Certain ASME Boiler & Pressure Vessel Code,Section XI Requirements,Per 10CFR50.55(a).Bases for Request Discussed
ML18143B520
Person / Time
Site: Surry Dominion icon.png
Issue date: 09/19/1985
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
85-681, TAC-59754, NUDOCS 8509240101
Download: ML18143B520 (11)
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Text

{{#Wiki_filter:e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 19, 1985 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 ASME XI - INSPECTIO!T RELIEF REQUEST 1 Serial No. NO/WRB:cfm Docket Nos. Licensee Nos. 85-681 50-281 DPR-37 Inservice inspection activities for Surry Unit 2 were conducted during the spring refueling outage as required by Section XI of the ASME Boiler and Pressure Vessel Codes. Pursuant to 10 CFR 50.55a paragraph g(5) relief is requested from certain code requirements. The following bases are provided.

1. The regenerative heat exchanger (2-CH-E-3) is classified ASME Class 1 in the first interval inspection plan (ASME XI 74 edition, Summer 75 addenda).

The following items were scheduled per table IWB-2600 to be completed during the refueling outage on the regenerative heat exchanger (Regen Hx) : Table IWB-2600 Table IWB-2500 Item No. Examination Category B3.1 B-B B3.1 B-B B3.2 B-D Parts to be examined (attachment 1) Method Head to shell weld(l 7) Volumetric Shell to tube sheet Volumetric weld(18) Nozzle to vessel

  • substituted welds(5,6,7,8,9 surface 10, 11, 12, 14, and
16)
  • On February 28, 1984, Vepco was granted relief (letter Mr. Varga to Mr. Stewart)to substitute a surface exam for the required volumetric method due to the impractical joint configuration that exists.

r-8509240101 850919 1 PDD ADOCK 05000281 Q n PDR

e VIRGINIA ELEcTRic AND PowER CoMPANY To Mr. Harold R. Denton The seal water return filter (2-CH-FL-3) is classified ASME Class 2 in the first interval inspection plan (ASME XI 74; edition, Summer 75 addenda). The following items were scheduled per table IWC-2600 to be completed during the refueling outage on the seal water return filter: Table IWC-2600 Table IWC-2500 Parts to be examined Method Item No. Examination Category (attachment 2) Cl. l C-A 1 11 head to shell

  • substituted weld(l) surface and visual Cl. l C-A 1

11 shell to flange

  • substituted weld(2) surface and visual Cl.1 C-A 1

11 top head weld(3)

  • substituted surface and visual Cl.3 c-c Welded support (IWS) surface
  • On February 28, 1984, Vepco was granted relief (letter Mr.

Varga to Mr. Stewart) to substitute surface and visual exams for the required volumetric due to the thin structure of the associated materials, reducing the effectiveness of a volumetric exam. Preinspection meetings with the Health Physics Department determined that unreasonable doses would result from completion of these examinations. The close quarters surrounding these components limit shielding and allow effective use of only one individual to remove insulation (Regen Rx only), perform necessary surface preparation, perform the inspection, and reinsulate (Regen Rx only). In addition surface preparation time can be extended significantly as a result of the limited preservice examination requirements associated with the earlier codes. In many cases this has left these type of welds in poor surface condition for examination.

VIRGINIA ELECTRIC AND PowER COMPANY To Mr. Harold R. Denton* The seal water return filter (2-CH-FL-3) is classified ASME Class 2 in the first interval inspection plan (ASME XI 74 edition, Summer 75 addenda). The following items were scheduled per table IWC-2600 to be completed during the refueling outage on the seal water return filter: Table IWC-2600 Table IWC-2500 Parts to be examined Method Item No. Examination Category (attachment 2) Cl. l C-A 1" head to shell

  • substituted weld(l) surface and visual Cl.1 C-A 1

11 shell to flange

  • substituted weld(2) surface and visual Cl.1 C-A 1" top head weld(3) *substituted surface and visual Cl.3 c-c Welded support (IWS) surface
  • On February 28, 1984, Vepco was granted relief (letter Mr.

Varga to Mr. Stewart) to substitute surface and visual exams for the required volumetric due to the thin structure of the associated materials, reducing the effectiveness of a volumetric exam. Preinspection meetings with the Health Physics Department determined that unreasonable doses *would result from completion of these examinations. The close quarters surrounding these components limit shielding and allow effective use of only one individual to remove insulation* (regen. only), perform necessary surface preparation, perform the inspection,* and reinsulate (regen. only). In addition surface preparation time can be extended significantly as a result of the limited preservice examination requirements associated with the earlier codes. In many cases this has left these type of welds in poor surface condition for examination.

e VIRGINIA ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton The following estimated doses are provided for each component examination (assuming average weld preparation time): Regenerative Heat Exchanger 7000 mr/hr Contact 3000 mr/hr 12 inches 400-1400 mr/hr general area TASK Insulation Removal Weld Preparations Inspection Reinsulation TOTAL Seal Water Return Filter MAN HOURS 3 3 2 3 11 2000 mr/hr Contact 15 man-rem (estimate) (general area unknown) TASK Weld Prepar~tions Inspection TOTAL MAN HOURS 1 2 3 6 man-rem (estimate) As an alternative, it is requested that the normal hydrostatic pressure tests be accepted in lieu of the previously described examinations. These hydrostatic pressure tests were successfully completed in conjunction with their VT-2 examination as follows: Component Date test Completed Regen Hx (charging side) June 4, 1985 Regen Hx (letdown side) June 30, 1983 Seal Water Return Filters May 2, 1985 Test Pressure 3427 psig 2340 psig 192 psig Acceptance of this relief request would greatly reduce exposure of personnel and would be commensurate with our ALARA practice. L-*

l e VmoINIA ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton

2. The residual heat removal return isolation valve (MOV-RH-2720B) is classified ASME Class 1 (attachment 3).

A Table IWB-2600, (ASME XI 74 edition, Summer 75 addenda) item B6.7, category B-M-2, valve internal visual inspection was required this refueling outage. A substituted thickness measurement examination from the exterior wall was attempted. This atlernative was approved by relief request on January 24, 1984 (letter Mr. Varga to Mr. Stewart), relief request SR-1. As noted by the attached inspection form (attachement 4), accurate thickness readings could not be achieved. By previous agreement (phone conversation Mr. Neighbors et al, NRC and Mr. Hegner et al, Vepco, March 21, 1985) relief from the thickness measurement requirement would be addressed on an individual basis. Therefore, it is requested that acceptance of the system hydrostatic pressure test be allowed as the alternative examination requirement. These tests (Class 1 to Class 2 boundary valve) were completed with the associated VT-2 examinations on July 1, 1983 and April 22, 1985 at test pressures of 600 psig and 750 psig, respectively. It is our opinion that acceptance of this relief request provides the most practical resolution to the examination difficulties presented.

3. The current code edition, ASME Section XI 1980 edition, Winter 1980
addenda, states in paragraph IWA-7210(a) that replacement components shall meet the original construction code requirements or, alternatively, the requirement of IWA-7210(c).

IWA-7210(c) states that replacements may meet the requirements of later editions of the construction code (in this case USAS B-31.1 - 1967), providing any additional requirements are met and that the later edition has been approved by the NRC. No later editions of USAS B31.l were approved by the NRC for nuclear work in 10 CFR 50.55a limiting Surry, under the rules of ASME Section XI, to the original code in power piping/component type replacement. It is requested that the use of ASME Section III be permitted in the same context that paragraph IWA-7210(c) above is intended for later editions of the original construction code for these types of replacements. Use of ASME Section III as approved by the NRC, allows the use of more "state of the art" requirements and provides more flexibility in our repair/replacement program.

e e VrnoINIA ELECTRIC AND PoWER CoMPANY To Mr. Harold R. Denton Specific use of this relief was already applied during the outage in the replacement of 2-SI-338, a 2 inch ASME Class 2 manual valve (attachment 5), used in setting flow for the high head safety injection system. Procurement of a valve meeting the original construction code and nuclear code cases could not be made, however the original manufacturer stocked a valve, which met ASME Section III NC requirements, except for stamping and met the requirements of ASME Section XI, IWA 7210 (c) as discussed. It is our opinion that this request is administrative only, but acceptance is necessary to fully comply with the code requirements. We also feel that adequate bases for the relief requested herein have been presented above, and that Surry will continue to meet, with the alternative proposals, the integrity assurance intended by the code. Very truly yours, W. L. Stewart Attachments cc: Cw/attachment) Mr. T. L. Chan NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station

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. ATTACHMENT 1, v,8.,.3200 ~ Rev. 0 1

  • REGENERATIVE HEAT E*XCHANGER 01, 01184 Ref: 1-4507

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3 3* INLET 2-CH-Fl-3 3* OUTL 3* OUTLET ATTACHMENT 2

e. YJR*?-J3?0 Rev. 0 RFT\\JR~.J FIi TFR 01/01/84 MATERIAL:

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