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Provides Addl Info in Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Completion of Evaluation of Thermal Effects on Auxiliary Spray Piping Expected by 891231 After Which Results Will Be Provided
	ML20244E639
Person / Time
Site:	Point Beach
Issue date:	06/16/1989
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	CON-NRC-89-074, CON-NRC-89-74 IEB-88-008, IEB-88-8, VPNPD-89-340, NUDOCS 8906210028
	Download: ML20244E639 (34)
	v • d • e

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Wisconsin l

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POWER COMPANY l

231 W Michigan. PO. Box 2046. Milwoukee, W153201 M14) 221-2345 j

VPNPD-8 9-34 0 NRC-6 9-07 4 June 16, 1989 1

l U.

S. NUCLEAR REGULATORY COMMISSION Document Cont: 31 Desk Mail Stop Pl.37 Washington, D.C.

20555 Gentlemen:

DOCKET NO. 50-266 ADDITIONAL RESPONSE TO BULLETIN 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR, COOLANT SYSTEMS POINT BEACH NUCLEAR PLANT UNIT l-Reference 1)

WE letter VPNPD-88-480/NRC-88-089 to NRC dated September 27,'1988

2).

WE letter VPNPD-88-616/NRC-88-128.to NRC dated December 21,.1988 Reference 1 identified piping which had the potential to be subjected to stresses from temperature stratification or temperature oscillations which could be induced by leaking isolation or check valves.

We evaluated the piping in accordance with the criteria presented in NRC Bulletin 88-08, " Thermal Stresses in Piping Connected to Reactor Coolant Systems." 1The lines identified were the two-inch diameter auxiliary charging piping and'the two-inch diameter auxiliary spray piping of both Unit 1 and Unit 2.

Reference 2 provided results of the Unit 2 inspections and described

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the temperature monitoring equipment installed,' data collection system, and preliminary information regarding temperature distributions in these lines.

I This letter provides results of inspections and actions taken on these two piping systems during the Unit.1 outage recently completed.

Further, it provides a description of our current plans I

and schedules regarding evaluations of the data being collected.

During the initial stages of the outage, the auxiliary spray and-auxiliary charging piping configurations were also walked and visually inspected.

No visual damage or distress in the piping systems were identified.

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' June 16, 1989 Page 2

) presents the results of the non-destructive examinations performed on the Unit 1 lines.

Areas of the piping identified in the figures of the attachment were' examined.using dye l

penetrant and ultrasonic techniques.

Two shallow welding-related flaws were identified in the auxiliary charging piping, one of which was removed with no remaining indications.

The.other flaw was considered acceptable without removal since it met the acceptance criteria established by the inspection code.

No evidence of crack l

propagation from either flaw since original construction was identified.

No indications were identified in the auxiliary spray piping.

Since the Unit 2 auxiliary charging line is not experiencing stratified conditions as reported by Reference 2, instrumenting the Unit 1 auxiliary charging line was not considered necessary.

However, since the NDE results described above identified two indications in this system and in order to verify that stratification is not occurring, WE elected to place,three thermocouple at one location on the piping system.

The location and configuration of the thermocouple is shown on Figure A-39 of.

Data collected from these thermocouple to date J

indicates a temperature difference from top to bottom of the piping of approximately 30 F.

We attribute this to turbulence effects due to the proximity of the thermocouple to the hot leg connection and not to upstream valve leakage.

Since the temperature difference is low, non-cyclic in nature, and resulting from RCS iniluence alone, j

we conclude as we did for Unit 2, that the auxiliary charging line is not experiencing thermal effects like those described in Bulletin 88-08.

One thermocouple was added to the auxiliary spray line as shown on Figure A-40.

This thermocouple was added only to detect whether leakage was occurring through the isolation valve since we had observed apparent stratification on the Unit 2 auxiliary spray I

piping system.

The data collected seems to indicate that-valve leakage may be occurring and the potential for stratified conditions may exist.

Based on the Unit 1 and Unit 2 data collected to date, we believe evaluation of thermal effects on the auxiliary spray piping for Units 1 and 2 is required to comply with requirements of IE Bulletin 88-08.

The evaluation will utilize data collected from Unit 2.

i Because the temperature data from Unit 1 appears less severe than for Unit 2, we expect that the Unit 2 evaluation results will be bounding for the Unit 1 auxiliary spray piping.

We expect this evaluation to be completed by December 31, 1989.

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t U.S. NRC June 16, 1989 Page 3 We will provide you the results of the evaluation upon completion'to document our final response to the Bulletin.

If you have any questions, please contact us.

Very truly yours,

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C.

W.

Fy f

Vice President Nuclear Power Copies to NRC Regional Administrator, Region III NRC Resident Inspector f

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NRC BULLETIN 88-08 THERMAL STRESS IN PIPING CONNECTED TO RCS-

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I NDE RESULTS OF IDENTIFIED AREAS FOR THERMAL FATIGUE DAMAGE Th'e Unit 1 piping areas within.the scope of NRC Bulletin 88-08 l

were selected for examination based-on a modeled heatE-loss and j

temperature gradients.

Additionally,-data gathered from Unit 2-l was considered.

The selected areas are shown on attached. Figures A-32, A-39, and A-40.

1 These areas were subjected to examination by the visible dye penetrant method to identify flaws at the surface.and by.the

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ultrasonic method to identify flaws internaltto.the pipe wall.

The techniques which were used were similar to those used by Ebasco Services, Inc., to identify IGSCC at'BWR facilities.

The extent of examination' included welds, heat affected zones, and base metal.

With the exception of two-(2) auxiliary charging welds, no flaws were identified.

The two (2) welds'with identified flaws.were evaluated and found to be shallow welding-related flaws.- There was no evidence to indicate that the flaws had propagated'since.

original construction.

Copies of the examination data are attached.

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ATTACHMENT' NRC BULLETIN 88-08 NDE INSPECTIONS Figure Line Identification Area Examined Method Results A-32 RC-3-A5-1001 Weld 2 PT No Recorded (3" Auxiliary Spray)

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reducer A-39 CVC-2-ACH-1001 Weld 22 PT 0.2" linear (2" Auxiliary Charging) acceptable to i

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Weld 23 PT No Recorded Indications Weld 24 PT 0.3": linear at weld start /stop removed with no indications remtining-2" pipe between UT No Recorded Welds 22 and 23 Indications 2" pipe between UT No Recorded Welds 24 and 25 Indications A-40 CVC-2-AS-1001 Weld 27 & 1" PT No Recorded (2" Auxiliary Spray) of adjacent Indications base material 30" length of UT No Recorded pipe below Indications Weld 27 and above Weld 26 I

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20 -^

i hI N

i l

l NOTE: Il response chove is *NO" refer to Calibration Check

+h l

l

}

secticos ol proceclure, i

i i

iA

/

i i

i EXA NER 0

1 2

3 4

5 6 F 8 9 +

d7 m SWEEP _

l4 t.

Tc.t A LEVEL d'

NO TE: when performing e,a,nination s indicare reference reflector location e anplitude above.

r., A g gyE g $A DAC is required.

4 are e.

s.

w N6' A mEviEwto av DATE ADDitlCN AL REu Amns

See Reverse Sode'

f 1 mP A bs$ar-Y S'? Pb

_JIT-6 RECORDAOLE e

WE O ' C PONENT IN DIC A TION COMMENT 3 OR REFERENCE TO INDIC ATION D ATA $HEET (10$)*

YES NO CVC-1.AS-/ooI A

6% AmineJ 3O" Si 9me 8e becu bov,V.dA. A nd

__N we ta

a 6, nk'nai,~ wa Pe#O,a > ~

\\

iResannse to N RC buLLe4)N 88 08 l

N\\\\x N

N N

N N s N\\

N N\\

N N

N

~

N N

N\\\\

N N

I x

Comments may include geomerrue reflectors, oreas of inaccessibility, surface condition, etc.., Also include the location of *kene conditions.

- _ _ - - _ _. - _ _.

ML20244E639

Text

==

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