ML20147B359

Forwards Requests for Relief from ASME Section XI Exam Requirements That Would Be Conducted Per Subj Facil Insvc Inspec Prog.Rev Insvc Inspec Prog Reflecting Util Position Will Be Submitted Pending Completion of Prog Dev

ML20147B359
Person / Time
Site:	Browns Ferry
Issue date:	12/11/1978
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	Ippolito T Office of Nuclear Reactor Regulation
References
NUDOCS 7812150248
Download: ML20147B359 (21)

Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374o1 '

830 Power Building DEC 111973 i

Director of Nuclear Reactor Regulation Attention:

Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Ippolito:

In the Matter of the

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Docket No. 50-296 Tennessee Valley Authority

)

Enclosed are requests for relief from ASME Section XI examination requirements submitted as part of the Browns Ferry Nuclear Plant unit'3 inservice inspection program.

These requests reflect our response to NRC questions transmitted by letters from George Lear to N. B. Hughes dated May 31, 1978, and from you to N. B. Hughes dated August 8, 1978, and interpretation of code requirements as discussed in meetings be tween NRC and TVA on August 15 and 16,1978, in Bethesda, Maryland.

A. revised inservice inspection program reflecting these responses'will be submitted pending completion of program develop-ment and approval by Browns Ferry Nuclear Plant management.

Very truly yours,

/

J. E. Gilleland 4

Assistant Manager of Power Enclosure

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An Equal Opportunity Employer

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ENCLOSURE

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l HEQUEST FOR RELIEF ISI-1 Components:

' All Class:

1, 2, and 3 Fune_ tion: '

Various functions.

Test Requirement:

Qualified inspector in accordance with IWA-2130.

Basis for Relief:

Present TVA policy is to provide its own inspection.

services. TVA is a federal. agency and, as other -

J federal agencies, acts as its ovn' inspector and is.

not subject to state or other non-federal inspectors.

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Alternate Inspection: TVA vill provide its own independent review of the Section XI program through its central office staff in Chattanooga.

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e REQUEST POR RELIEF ISI-2 Components:

Reactor Pressure Vessel Class:

1 Function:

Pressure-retaining component.

Test Requirement:

Volumetrie examinstion of reactor pressure vessel pressure-retaining velds, examination categories B-A and B-B.

Basis for Relief:

The Brovns Ferry Nuclear Plant was designed'and' under construction before the issuance of Section XI.

As a result, only those velds above the sacrificial-nhield are accessible for inservice inspection. ' Access has not been provided in the sacrificini shield area for external examinations nor does the BWR design permit internal examinations in this area. Only those velds above the sacrificial shield and portions of we'Is ac may be accessible at nozzle access points vill be examined during the innervice inspection intervals.

Alternate Insnection: None.

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RERtp'ST 70R RELIEF ISI-3 1

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Reactor Pressure Vessel Support Skirt Class:

1 Function _:

Support component.

Test Requirement:

Volumetric examination of support attachment veld to vessel, examination category B-H.

Banis for Relief:

Approximately 6 feet of the attachment veld would require examination to meet code requirements.

However, nonremovable reactor vessel insulation limits inservice examination. Two access ports, approximately 180 degrees apart, provide access for examination of two 2-foot lengths. Four feet of the support skirt-to-reactor vessel veld vill be ultrasonically examined during each inspection interval.

Alternate Insnection: None.

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REQUEST FOR RELIEF ISI 14 Components:

Reactor Recirculation Pumps cla_s s_:

1 Function:

Provides a variable reactor power rate by varying core coolant flow rate.

Test Requirement:

Visual examination of pump internal pressure boundary surfaces, examination category B-L-2.

Basis for Relief:

In absence of required maintenance, disassembly of a recirculation pump solely to perform a visual examination of internal surfaces is impractical. This would represent an unnecessary employee exposure to high radiation and contamination areas and an excessive expense to TVA.

Disassembly of this pump could require transport of the motor outside of containment; consequently, a possibility of damage to the pump, pump motor, or other safety-related equipment exists. Time required for this major task of disassembly, examination, and reassembly vould consume at least three weeks of 21-hours-per-day work. Radiation dose rates of the 4

pump exterior vill average 100-300 mrem / hour, and pu:np internal dose rates vill average 10-20 rem / hour.

The benefit received from this major effort is minimal considering employee exposure, potential damage to safety-related equipment, and cost in dollars.

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• RbQUESTFORRELIEFISI-h Bacis-for Relief:

-In addition, the multiple units at Browns Ferry Nuclear-(Continued)

~ Plant operate under similar conditions. Therefore, we

_ feel that if a pump from one of the multiple units is disassembled for maintenance during a 10-year interval, the visual examination performed vill be representative of the pump ' condition for each unit. This would avoid unnecessary employee exposure to the high radiation dose rates noted above. We conclude that if one pump is disassembled for maintenance during the.10-year interval, the visual examination performed-satisfies examination category B-L-2 requirements for the three multiple

. units. Disassembly of the pump solely for visual examination is impractical.

Alternate Inspection: The internal surfaces of the recirculation pump casing vill be visually examined whenever the surfaces are made accessible when a pump from any unit is disassembled for maintenance purposes. If during the 10-year interval a pump from any unit is not disassembled, a pump from one unit shall be examined from the exterior. This shall be accomplished by ultrasonic thickness measure-

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REQlIEST FOR REI TEP ISI-5 Components:

Valves Exceeding h-inch Nominal Pipe Size Clans:

1 Punction:

Various functions.

Test Requirement:

Visual examination of valve internal pressure boundary surfaces, exmnination category B-M-2.

Basis for Relief.:

During routine maintenance, visual examinations of valve body internal pressure boundary surfaces are performed and documented under existing plant administrative procedures. Most Class 1 valves, particularly containment isolation valves, are s

disassemble'd" frequently for maintenance. In addition, the multiple units at Browns Ferry operate under similar conditions. If a valve from one of t.he multiple units is disassembled for maintenance within a 10-year interval, vc feel that the visual examination performed would be representative of all three units and would be sufficient to satisfy the examination requirements for all three units for that particular valve classification as defined in examination category B-M-2.

We conclude that if cae valve in each group of valves -

of the same constructional design and manufacturer i

that perform similar fun:tions is disassembled from 1

any unit during the 10-year interval, the visual exsnination performed satisfies examination category l

B-H-2 requirements for the three multiple units.

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REQUEST FOR RELIEF ISI-5 Alternate-Innnection: If a valve from a particular classification has not been disassembled as the end'of the inspection interval approaches, a case-by-case study vill be

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made to determine the practicality of disassembling a valve from one of the multiple units solely for visual examination (determine if draining the vessel vould be required, etc.).

If necessary, a request for relief vill be issued at that time.

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1 REQUEST FOR RELIEF ISI-6 Components:

Control Rod Drive Housing Welds Clans:

1 Function:

Pressure-retaining component.

Test Requirement:

Volumetric examination of peripheral CRD housing velds, 9

examination category B-0.

Basis for Relief:

Should the CRD housing veld fail, the leakage path to the failure meets the make-up exclusion criteria and is therefore excluded from volumetric examination in accordance '.ith IWB-1220(b)(1). The make-up supply system is equivaJ ent to.h-inch nominal pipe size'.

The smalles't leakage path area vould be realized between the guide cap and thermal sleeve as shown on the attached diagrams. The following calculations verify exclusion of volumetric examination in accordance with IVB-1220(b)(1):

For 3-inch nominal pipe size (maximum code exclusion):

D = 3.068 inches 2

A = (TI)(D /h), where A = internal transverse area D = inside diameter A

= 7 39 in.2 3-in.

For the thermal sleeve:

DTS = h.25 inches ATS " lb'19 iD*

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4 REQUEST FOR RELIEF ISI-6

- Bas 5s for Relief:

For the guide cap:

(Continued) 1 DGC = k.125 inches GC = 13 36 in.2 A

Total leakage path area:

Ag = Q-- AGC = 1h.19 in.2 13 36 in.2 = 0.83 in.2 -

A -in. = 7.39 in.2 3

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Alternate Insnection: All peripheral CRD housing velds shall be visually examined during the system hydrostatic pressure tests in accordance with IVB-1220(c).

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.v 1 l ~ HEQUEST FOR RELIEP ISI-7 l-N Inaccessible Residual Hedt Removal, Main Steam, and Components: Feedvater Circumferential Pipe Welds Class: 1 Function: Pressure-retaining component. Test Requirement: Volumetric examination of pressure-retaining velds in piping, examination category B-J. Basis for Relief: One RHR veld is located inside a containment penetration and is inaccessible for any type of examination. Four main steam velds and two feedvater velds are located under rigid pipe restraints and are inaccessible for volumetric eEamination. These velds are identified in the inservice inspection program. Alternate Inspection: A "best effort" visual examination vill be performed during system leakage and hydrostatic pressure tests. l t-t v.v e. - -r, ,,,e, ,,-n e-~ ,-s - -. ~ - - .m~ -- ~

REQUEST FOR RELIEF ISI-8 i Components: Pressure-Retaining Welds in Piping Class: 1 and 2 Function _: Pressure-retaining component Test Reouirement: Volumetric examination of longitudinal, circumferential, and pipe branch connection velds, examination categories B-J and C-F. Basis for Relief: .In some cases it vill be impractical to inspect all velds'from both sides, i.e., nonremovable hanger interference or valve and pump casings ajoining the velds. These velds will be noted on the ultrasonic examination data sheets. Alt'ernate Inspection: In addition to the visual examination performed during system leakage and hydrostatic pressure tests, a "best effort" ultrasonic examination vill be performed. Where there is interference or problems from one direction only, consideration vill be given to performing an angle beam examination for 2T + (greater than two vall thicknesses from one edge of weld) from the accessible side of the veld in order to examine the entire veld cross-section. M I ..w ..m.,.. m s, ,-m, w-,m ---,.w.w .,.c .._,-r. =e-

REOUEST F0H RELIEF ISI-9 j Components: Intecrally-Welded External Support Attachments for > Piping and Valves Class: 1 Function: Support components. Test Requirement: Volumetric examination of the support attachment velds, examination category B-K-1. Basis for Relief: During the first Browns Ferry baseline inspection, the ultrasonic examinations of the integrally-velded Class 1 supports were meaningless because of the lack of penetration indications that existed for the full length of the support velds. The supports were fabricated to ANSI B31.1.0 and General Electric Company specification 21A2100. The GE specification required a full penetration veld and surface examination requirements, which would not verify penetration. The TVA Division of Engineering Design has taken actual veld dimensions of randomly-chosen piping supports and compared the load capabilities of these velds as installed to the loads based on design the supports would see during operation. This analysis indicated that all supports studied have high factors of safety in their load-carrying capability; therefore, ve feel the integrally-velded supports on the primary coolant piping are acceptable i as installed. Future ultrasonic examinations of these I supports would be meaningless. m .,n .-,4

A ~2-REQUEST FOR RET,IEF ISI-9 Alj ernate Incticetion: Class 1 integrally-velded supports vill be liquid penetrant examined in' place of ultrasonie examinations.. i The liquid penetrar; examinations performed during each inspection interval vill cover 25 percent of the-integrally-velded supports. O r S t. ,w.- .r~ , + - - - .-...c- ....x .--rw v --.....>~m e e v.,, w., -~

. 41 - t ,p REQU,EST FOR RELIEF ISI-10 + ' I Components: Ultrasonic Calibration Standards Class: 1 and 2-Function: ' Ultrasonic calibration for examination of welded 2 - components. ~ Test Requi_re:aent: Ultrasonic calibration blocks fabricated to 1974 Editio'n', Summer 1975 Addenda, of Section'XI', IWA-2232. Basis for_ Relief _: Ultrasonic calibration blocks cyployed for the Browns Ferry baseline examination were fabricated to the '1971 Edit.on of Section XI. These blocks will continue to be used for. future excminations to assure the repeatability of data, i Alternate Inspection: Future examinations which require fabrication of new calibration blocks vill be performed using calibration blocks which will meet the 1974 Edition, Summer 1975 Addenda, of Section XI. - t I 9 ,e r r +--c -,,,n -~, ,c, wr

A REQUEST FOR RELIEF ISI-11 System:. Main steam- ~ Class: 2 Test Requirement: Surface examination of support members for piping examination category C-E-1. Basis _for Relief: ' The' main steam system includes four special restradnts, each of which is partly embedded in a wall. Each embedded restraint includes 12 guide lugs which are welded to the process pipe. These welds are inacer.asible for examination. Each restraint also includes 12 stop plates welded to the process pipe which are acces",1ble for examination, and they will be sur face examin' d during the inspection intervals (see attached drawings). Alternate Inspection: None. 8 y a. i m

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