ML20082P278

Forwards Request for Relief 91-02 from Hydrostatic Testing Requirements of ASME Code for Portions of Planned Mods to Main Steam Sys

ML20082P278
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/04/1991
From:	Tuckman M DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9109100264
Download: ML20082P278 (8)

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lii: WI fhDUKEPOWER 30ptemLor 4, 1991 U.

S.

Nuclear Regulatery Commission Attention Document Control Desk Washington, D. C.

20555

Subject:

McGuire Nuclear Station Docket No. 50-369 and 50-370 ASME Code Section XI Hydrostatic Testing Requirements Relief Request No. 91-02 Purcuant to 10 CFR 50.55(g)(5)(iii), I am submitting the attached relief request for NRC review and approval.

This request for relief from ASMF Code involves the Codo required hydrostatic testing on portions of planned modifications to the Main Steam system.

Some of the modifications are scheduled to be performed during the upcoming unit I refueling outage.

Tne upcoming unit i refueling outage is currently scheduled to tegin September 20, 1991.

The planned outage length for this refueling outage is 70 days.

Accordingly, the refueling outage is currently scheduled no end December 7, 1991.

I would like to request NRC review and approval of this relief request prior to the re-start of Unit 1,

following the refueling outage.

Should there be any questions regarding this matter, please contact Paul Guill at 704-373-2844.

Very-truly yours, s

C b c,A M.

S. Tuckman, Vice Presider.t Nuclear Operations

/ hydro-1 attachment 9109100264 010904

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Nuclear Regulatory Commission September 8, 1991 Page 2 cci S. D. Ebneter Regional Administrator, Rogion II T. A.-Rood ONRR P. K. VanDooran McGul o Senior Resid

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DUKE POWER COMPANY MCGUI9E NUCLEAR STATION Request for Rollef From ASME Code Section XI Requirement I.

Component for Which Relief 16 Requested A.

Components 1.

Welds on five 6" nozzles on each Main Steam system header (total of 20 nozzle welds per unit).

These nozzles are just upstream of each of the Main Steam ASME Code Safety valves.

Fabricated transition flanges will be wolded to these nozzles under NSM's MG-12302, MG-12303, MG-12304, MG-12305, MG-22302, MG-22303, MG-22304, and MG-22305.

2.

Weld on a 2" drain line just upstream of valve 1SM89.

Valve 1SM89 is damaged and will be replaced under MEVN-2371.

B.

Function Main steam is generated in the four steam generators from feedwater which absorbs heat generated by the Reactor Coolant System.

Main steam is conveyed by four steam headers (one per steam generator) to a steam' equalization and distribution header and th' : to the turbine inlet valves.

The steam generators and all piping and valves to and including the Main Steam Isolation Valves are ASME Section III, Class 2 (Duke Class B).

Self-actuated ASME Code Safety Valves (five por steam header) are located downstream of the steam generator and upstream of the main steam isolation valves.

The piping upstream of these valves is welded to 6" nozzles in the main steam header.

Each main steam header also has a 2" drain line with a containment isolation valve within.he ASME Section III, Class 2 boundary.

These valves (1SM89 on the S/G 1B steam header) provide a means to blow down to the condenser condensate that collects in the steam headers.

1)

NSM's MG-12302,.MG-12303, MG-12304, MG-12305, MG-22302, MG-22303, MG-22304, and MG-22305 will replace the existing butt-welded Crosby valves with welded-in nozzles with flanged Crosby valves with screwed-in nozzles.

The nozzles on the existing valves have eroded to near the point

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where Crosby can no longer ensure proper operation of the valves.

Because the nozzlos are wolded-in, the valves must be cut out and shipped to Crosby for any repairs to the nozzlos.

This modification

[

will allow the station to perform repairs on the t

valves on-site and because the now valves are i

flanged, pressure testing will no longer be required when the valves are removed for future maintonance.

Also, the present piping l

configuration has the valves tilted at a 15 degroo angle.

This tilt has contributed to the nozzlo i

erosion problem that the existing valves are oxperiencing.

The referenced NSM's will reconfigure the piping such that the valves will i

be rotated 15 degrees to the vertical position.

)

2)

MEVN-2371 will replaco valvo ISM 89 with an exact f

replacement valvo.

The existing 2" socket welded

)

Kerotest globe valvo as a damaged yoko that -

cannot be removed.

,j C.

ASME III Code Class Equivalent Class 2.

f D.

Materials and Wolds l

l Reference' attached drawings.

j II.

ASME Code Section XI Requirement That Has Boon Determined to f

be Impractical ASME Code Section XI, 1980 Edition through Wintor 1980

. Addenda, Article IWA-4400, IWC-5000.

-III. Basis for Requesting Re11of f

1)-

Performing a presture test on the nozzle wolds upstream i

of the Main Steam ASME Codo Safety Valves is impractical for'the following'reasonst i

a)

The pressure test would require pressurizing each associated steam generator.

This would require approximately 200 workhours por steam generator, some personnel radiation exposure, and procuroment of a large capacity hydro pump.

l b)-

The pressure test could potentially damage the

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steam generator and its internal components.

i c)

The pressure test could significantly affect other i

planned outage maintenance activities and possibly j

extend the overall outago length.

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i d)

Alternate pressure testing methods using frooze s

plugs or hydro plugs is not feasible due to the close proximity of the nozzles to the main steam headers and the conical shape of the nozzles.

i Performing a pressure test on the socket wold on the 2) upstream side of valve 1SM89 is impracsical for the

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following reasons:

a)

The pressure test would require pressurizing the IB steam generator.

Thi'J uould require a significant amount of workforce, some personnel t

radiation exposure, and special hydro equipment.

b)

The pressure test could potentially damage the steam generator and its internal components, j

The pressure test could significantly affect other c) planned outage maintenance activities and possibly l

extend the overall outage length, d)

Alternate pressure testing methoda using freeze plugs or hydro plugs is not feasible due to the i

close proximity of the valve to the main steam header and the physical barrier that the valve

)

internals present.

l IV.

Alternate Testing t

The butt welds on the 6" nozzles upstream of the ASME 1)

Code Safety Valves shall be subjected to MT's or PT's on the root pass and MT's or PT's and'RT's or UT's on the finished weld.

In addition an in-service leak test shall be performed at normal system operating temperature and pressure.

The socket welt on the upstream side of valve ISM 89 2) shall be subjected to PT's on both the root pass and on the finished weld.

In addition an in-service leak test shall be performed at normal system operating temperature and pressure.

Why Alternate Testing Will Provide an Acceptable Level of l

V.

Quality and Safety, and Not Endanger the Public Health and Safety The ASME Code requires an RT or UT on the finished weld 1)

)

surface for the Class 2 (Duke Class B) butt welds on the 6" nozzles.

Duke will impose additional MT's or PT's on both the root pass and on the finished weld l

that will ensure that any defects in the weld are detected.

Also, the in-service leak test will verify that the welds do not leak at normal system operating temperature and pressure.

It is Duke's position that k

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t the alternate testing is comparable to hydrostatic testing for finding defects in the welds and that the levol of quality and safety of the welds will be in no l

way reduced.

2)

The ASME Code rt< quires an MT or a PT on the fin;shed wold-surface for the Class 2 (Duke Class B) socket wold on the upstroan sido of valvo ISM 89.

Duke will impose an additional M? or PT on the root pass that will onsure that any defects in the weld are detected.

i Also, the in-service leak test will verifV that the wold does not leak at normal system operating temperature and pressure.

It is Duke's position that the alternate tetting is comparable to hydrostatic testing for finding defects in wolds and that the level i

of quality and safety of the welds will be in no way reduced.

/

McGuiro Nucioar Station has succoesfully utilized alternato l

NDE in lieu of pressure testing on numerous occasions and has not experienced any wold related piping failures.

VI.

Implementation schedule i

The following are scheduled implomontation datos for the subject modifications:

[

Unit 1 A.

MG-12302 1EOC8 Refueling Outage 1/93 i

B.

MG-12303 1EOC7 Refueling Outage 9/91 C.

MG-12304 1EOC7 Refueling Outage 9/91

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D.

MG-12305 1EOC8 Refueling Outage 1/93 E.

MEVN-2371 1EOC7 Refueling Outage 9/91 i

Unit 2 F.

MG-22302 2EOC8 Refueling Outage 4/93 G.

MG-22303 2EOC7 Refueling Outage 1/92 H.

MG-22304 2EOC7 Refueling Outage 1/92 I.

MG-22305 2EOC8 Refueling Outage 4/93 r

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