ML20081F958

Requests Mod of 830826 Insp Order to Permit Delay of Unit 2 Shutdown Until Completion of Weld Overlays on Unit 1, Expected to Be Completed 831109

ML20081F958
Person / Time
Site:	Brunswick
Issue date:	10/27/1983
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
References
LAP-83-504, NUDOCS 8311040045
Download: ML20081F958 (8)

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SERIAL: LAP-83-504

~ Carolina Power & Light Company 0CT 2 71983.

Director. of Nuclear Reactor Regulation At tention:

W. D.. B.' Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United ~ States Nuclear Regulatory Commission Washington, DC-20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62

-INSPECTIONS OF BWR STAINLESS STEEL PIPING

Dear.Mr. Vassallo:

On August 26,1983,' the' Division of Licensing, Operating Reactor

.. Branch 2, issued an Order to Carolina Power & Light Company (CP&L) for the Brunswick Steam Electric Plant, Unit No. 2 (Brunswick-2). ~ This Order required o

Brunswick-2 to be shutdown by November 1,.1983 to conduct an examination program f or piping w' elds susceptible to intergrannular stress corrosion cracking (IGSCC).

Brunswick-1 'is presently shutdown having just cogleted examinations of six recirculation system piping welds in accordance with our committment of

~ August-19,-1983 as amended by out letter dated September 27, 1983.

During the

. examinations of:the Brunswick-1 piping system, indications were discovered on two welds. 1his information was reported by telephone to Region II on' October 21, 1983 and confirmed by telecopy on. October -24,1983 (see Licensee Event b

Re port ' No. 1-83-49).

The weld overlays ' required to repair these indications could extend the ' Brunswick-1 outage past the required November - 1,1983 shutdown date for Brunswick-2.

In order to minf aize the period of time that both Brunswick Units'will be out of service, CP&L requests modification of the August 26, 1983 order f or Brunswick--2.

Carolina Power & Light Company requests that the Bruns' wick-2' Order be modified to permit-delaying the Brunswick-2 shutdown until coupletion of weld overlays-on Brunswick-1 expected to be cogleted November 9, 1983. 1his will-preclude any unnecessary overlap as a result of

. the extension of the Brunswick-1 outage resulting f rom the weld repairs.

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' B311040045 831027 PDR ADOCK 05000324 PM G

411 Fayetteville Street

• P. O. Box 1551

• Raleigh, N. C. 27602

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' D. B J Vassallo,

' Based on the information receivsd during the October. 21, 1983 meeting concerning IGSCC inspections, CP&L understands that new criteria-

-were proposed as. appropriate for weld selection in lieu of current IE Bulletin 83-02 guidance.

The f ollowing sample' selection criteria apply to nonconforming materials 4 inches in diameter or larger out to the second 2

containment' isolation valve.with operating temperatures-greater than 200*F:

1.

Examine ? 20 percent of the unmitigated welds not previously inspected' for each pipe size,;but in no case less than f our welds f or.each pipe size.

p 2.

-Re-examine 20 percent of 'the number of welds previously examined and found acceptable for each-pipe size.

3.

Re-examine all welds with IGSCC indications which we ;e not

> repaired.

(Note BSEP lhit 2 has none in this categ.ry).

4 Re-examine previous weld overlays.

(Note BSEP Unit 2 has no weld overlays).

5.

If a rejectable indication is f ound, expand the sample in accordance with I.E.Bulletin 83-02.

Carolina Power & Light Company requests that the order be amended to inspect a weld sample based on the above criteria in lieu of the current order requirement of E"To the extent practicable, the licensee shall conduct an

. ultrasonic examination of '100 percent, but in no case less than the number specified in Attachment A to the July 21, '1983. 50.54(f) letters, of the welds involving 304 stainless steel piping of greater than or equal to 4" in the following-systems or portions thereof:

a.

Recirculation System b.

ASME Code Class 1 Portion of the Residual Heat Removal System ASME Code Class 1 Portion of the Core Spray System external to the c.

Reactor Vessel-d.

ASME Code Class l' Portion of the Reactor Cleanup System".

We -believe the proposed sample criteria and sample expansion provision provide assurance that unacceptable piping conditions are detected while minimizing unnecessary radiation exposure to qualified piping inspectors.

If the order is' modified, CP&L will commit to inspect the welds

. identified in attachment I during the upcoming November 1983 outage. This includes a sample re-inspection for the twelve welds previously examined on Brunswick-2 in January 1983.

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4 D. B. Vassallo If ' you have any questions concerning this submittal, please contact

g. staff.

Yours very - tru P. W. Ibwe Vice President Brunswick Nuclear Project

.WRM/cfr. (8309WRM)

Enclosure cc:

Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

Mr. M. Grotenhuis (NRC) h l

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ATTACHMENT 1 I.

Basis for Number of Welds to be' Examined

- Total 20% of Total' Pipe Size

<Susceptable Welds-or Minimum of 4 System Re actor -

28" 34 7

. Recirculation

' Re actor 22" 18 4

Recirculation.

Reactor 12" 40 8

Recirculation RWCU-6" 22 5

4 RHR.

24"

'2 2

l' RHR-20" 3

3 II.

Basis -for Number of Welds to be Re-examined Sample of Total Number 20% of Total System-Pipe Size '

Previously Examined or Minimum of 2 Reactor 12" 8

2 Recirculation Reactor 4"

4 2

Recirculation i.

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ATTACHMENT 1 (Continued)

III. Weld Listing to Comply with Sample

UNIT 2 WELD SELECTION REACTOR RECIRCULATION IGSCC Weld SRI Carbon Rank Notes 2B 3 2-28"-A-2 1.08

.055 2

1

-A-8 1.41

.051 1

-A-14 1.51

.059 1

-A-15 1.42-

. 059-1

-B - 8 '

' 1. 3 6 '

.057 1

-B-14 1.48-

.059 1

-B - 15 1.40

.059 1

2B32-22"-AM-6 1.14

.058 1

-AM-5B C-B 1.16

.070 4

2

.14

.056 1

1

-B M-1

-B M-1B C-A 1.16

.060 4

2 2B32-12"-AR-C-1 1.57

.075 1

-AR-A-2.

1.48

.075 1

-AR-D-4 1.35

.075.

1

-AR-E-3 1.53

.075' 1-

-B R-F-2 1.53

.075 1

-B R-G-2

-1.51-

.075 1

-B R-J-4 1.30

.075 1

-B R-K-3 1.38

.075 1

RESIDUAL HEAT REMOVAL Note 2E11-24"-A-12 3

-B-12 3

2E11-20"-A-1 3

-A-1B C 3

-A-2 3

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. REACTOR WATER CLEANUP 2G31-6"-7~

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-8 4'-

-9 4

-10 4

-11 4

Notes "1.

Selected because of f allure at other units although ranked as priority 2 based on SRI-and carbon content.

2.

' Selected because of f ailure at other units although ranked as priority 4-

~due to solution annealing. These are-the header sweepolets nearest the end caps.

These welds constitute all Class 1 susceptable RHR piping welds.

3.

4. ' SRI and' carbon content study not available for BSEP.- Sample constitues ' 5 of-22 Class I welds in RWCU system.

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. REINSPECTION.TO BE PERFORMED r

IGSCC SRI-Carbon' Rank 4..

2832-12"-AR-A-4 1.27 0.075

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' B R-G-4 '

1.42-0.075

-1 4"-A-1 1.22 0.071-1

-B - l '

1.22 0.071

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