Text

Forwards Response to 900327 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
	ML20043E926
Person / Time
Site:	Peach Bottom
Issue date:	06/04/1990
From:	Helwig D; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GL-88-01, GL-88-1, NUDOCS 9006140006
	Download: ML20043E926 (48)
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PHILADELPHI A ELECTRIC COMPANY NUCLEAR. GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD.

WAYNE, PA 19087 5691 (215) 640 4650 DAVID R. HELWlO June 4, 1990 vics.. Slo Nr guctsan aNGINEERING & SERVICES Docket Nos. 50-277 4

50-278 License Nos. DPR-44 DPR-56 i

U.S. Nuclear Regulatory Commission Attna--Document Control-Desk-k

. Washington, DC 20555

SUBJECT:

Peach Bottom Atomic Power Station, Unita 2 and 3

'g' Request for Additional'Information Related to Generic Letter-88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping"

REFERENCE:

(1)

Letter from S. J. Kowalski (PECo) to.

.F. J. Miraglia, Jr. (NRC) dated August 2, 1988 (2)

Letter from S. J. Kowalski (PECo) to U.S. Nuclear Regulatory Commission dated March 31, 1989

.(3)

Letter from G. Y.'Suh (NRC) to G. A. Hunger, Jr. (PECo) dated-March 27, 1990 y

Dear Sir:

L In References (1) and (2),. Philadelphia Electric Company (PECo) subia.itted responses to Generic Letter (GL)- 88-01.

In j

Reference (3), f.he-NRC provided a Safety Evaluation based on the l:

review of our responses.

Included in Reference (3) was'a Request i

t; for Additional Information.

Our response'to this request is t

provided as an_ enclosure to this letter.

Each item is restated followed:by our response.

I If you have any additional questions, please do not 1;

' hesitate to contact us.

t i

Very truly yours, s.

3 Enclosure

/

cc:

T. T. Martin, Administrator, Region I, USNRC

(

J. J. Lyash, USNRd Senior Resident Inspector

(

9006140006 900604 ADOCK0500g7 DR

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. Pacch Bottom Atomic Power Station, Units 2 and 3-Response to Request for Additional Information Related to. Generic Letter 88-01 1.

.The Technical Specifications need to be amended to include a statement.that the inservice inspection program for piping' covered'by the scope of GL 88-01 will be in conformance with the staff positions on schedule, methods and personnel, and sample expansion.

Please provide a revised commitment for this item, with a proposed schedule for submitting an 1

appropriate amendment application, j

PECo Response.

An appropriate Technical Specification Change Request'will be submitted by December 31, 1990.

2.

'Please indicate whether PECo intends to follow the staff positions presented in GL 88-01 on water chemistry, weld o

L overlay reinforcement, stress improvement of cracked l

weldments,-and clamping devices, or propose alternative measures.

In addition, the staff's safety evaluation and.

associated technical evaluation reports presented the staff's understanding of the licensee's position on the remaining-nine subjects discussed in GL 88-01.

Please provide corrections,

.if.any, to the staff's understanding of your positions.

'PEco Response i

L As stated in our August 2, 1988 response, we are currently L

using a Bolling Water Reactor (BWR)' Water Chemistry Control

~

L Program.

This Program was designed using the guidelines of the BWR. Owners' Group, Electric. Power Research Institute 1

o (EPRI), General Electric Company and the Institute of. Nuclear Power Operations (INPO).

Further, modifications are in progress for-both-Units 2 and'3 for the addition of Hydrogen Water Chemistry (HWC).

Full operation'of these HNC systems is planned for the end of 1990.

y For weld overlay reinforcement, stress improvement of cracked weldments and clamping devices, we will follow the staff positions presented'in GL 88-01, if use of these techniques is deemed. appropriate.

The NRC staff's understanding of the remaining nine subjects, as documented in the safety evaluation and associated technical evaluation report, is accurate.

We would like to

-confirm that we accept the staff position on heat sink welding.

Although this process has not been used in the past, we consider this to'be a viable option for potential future applications.

3..

With respect to inspection methods and personnel, the licensee stated that ultrasonic testing of inspectable ASME Class 1 and 2 welds will generally be performed in accordance with ASME Section XI requirements', which implied that there will be j

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Enclosure Page 2 7

exceptions and deviations.

Please clarify.whether there will be exceptions and deviations, and if so, provide a discussion on-whether this is consistent with the NRC position presented in GL 88-01.

L

'PECo Response b

We do not plan any deviations or exceptions to the staff-positions on examination methods and personnel qualifications.

Examinations performed on weldsents. subject to the Generic i

Letter 88-01 will comply with the requirements of the Edition and Addenda ~of the ASME Code Section XI applicable to PBAPS 2 and 3, in accordance with 10 CFR 50.55a, paragraph (g).

Personnel performing these examinations will be qualified for such examinations by means of a formal, approved qualification program.

i j

4.

Please provide the reasons that reactor water cleanup system welds located outside containment are considered to be uninspectable.

PECo Response L

We consider the portion of Reactor Water Cleanup (RWCU) system outside containment to be uninspectable because of-the undue risk to' workers performing the inspection.

This risk is.

considered to be undue because of the alternate methods which are already in place which ensure RWCU piping integrity.

This portion of RWCU is included in the Inservice Inspection (ISI)

Pressure Testing Program.

Accordingly, the system is pressure tested and visually examined for leakage during each inspection. period.

This inspection is designated as "VT-2" on the attached tables.which are discussed in further detail in-our responseLto Item 5 of the Request for Additional Information..

In addition, in accordance with Technical Specification 6.14 " Integrity of Systems Outside Containment,"

~ Surveillance Tests (STs) 12.15.7 "RWCU Contaminated Piping Inspection" and 12.15.9 " Outboard MSIV Room Contaminated Piping Inspection" are performed every six months.

The purpose of these STs is to inspect the integrity of the RWCU system externally for leakage.

These STs are performed by a combination of air sampling and visual inspections of equipment rooms and related areas.

Air sampling determines if significant concentrations of specific isotopes are present.

This would be indicative of reactor coolant leakage.

Air sampling-is used only when the reactor is at a temperature and pressure which could cause steam leaks.

We consider the existing inspections performed on the RWCU system to be sufficient to preclude the need for individual weld examinations as recommended in the GL.

Further, this portion of RWCU is 4-inch piping which is isolable from the reactor coolant pressure boundary, and therefore not within the scope of ASME Section XI for individual weld examinations.

The risk to workers is primarily a result of the RWCU piping being located in high radiation areas.

The radiation concern 1

~.

i 1.

Enclosure Page 3 is heightened by.several factors.

First, most of the subject piping is at an. elevation,which would require the erection of scaffolding to perform an inspection.

This activity increases the exposure time for workers in a high radiation area.

Second,.because the subject piping was originally-designated as non-ASME,-and therefore inspections were not. anticipated,.

permanent insulation was installed on the piping.

This insulation would have to be removed for an inspection, further increasing radiation exposure time.

Some of this permanently installed insulation on Unit 2 contains asbestos.

This introduces a hazardous materials concern.

Third, the welds on L

this portion of piping currently exist in theirLas-welded condition (i.e., no weld crown preparation).

This again is a result of the piping originally being designated as exempt from ASME weld inspection requirements.

Effective ultrasonic testing-(UT) examination of these welds would require grinding the existing weld surface to a smoothness amenable to UT

. examination.

This activity increases both the worker exposure time and the airborne radiation levels.

~The collective effect of these factors makes inspecting even a representative sample of the welds to be contrary ~to our goal l

of keeping radiation exposure "as low as reasonable achievable."

i S.

Please provide actual inspection plans in tabular form using a format such as that illustrated in Table 3 of the Request for i

Additional Information transmitted in a June 16, 1989 letter.

PECo Response As requested, please find as Attachment A and B to this L

enclosure the implementation schedules for PBAPS Units 2 and p'

3, respectively.

These attachments contain a tabular listing of all welds subject to the examination requirements of the Generic Letter, along with an identification of which welds have been selected for examination.

Examination schedules for the next two refueling outages are also provided.

Please note that these listings of welds have been adjusted to delete the longitudinal seam-welds from the program since they-are outside the scope of the GL.

Deletion of the longitudinal welds from the listings was discussed with the NRC during a

. telephone conversation on April 16, 1990.

Additionally, continued review of construction records have resulted in category changes for some welds.

Also note that the schedules provided are for planning purposes and are subject to adjustment.

For Intergranular Stress Corrosion Cracking (IGSCC) susceptible welds subject to a sampling process (e.g.,

L Category A welds), selected welds may be examined during a different outage than indicated.

-1 a

PRIXTED: 05/31/90

-PEACM BOTTOM ATOMIC POWER STATION - UNIT 2 CTTACMMENT "A" AUG-1,' NRC GENERIC LETTER 88-01, PAGE: 1 of 22:

?NTERGRANULAR STRESS CORROSION CRACKING i

SYSTEM: CORE SPRAY CLASS: 1 EXAMINATION AREA ID NUMBER &

SIZE ISOMETRIC ISI AUG-1 AUGMENTED IGSCC EXAMINE DURING OUTAGE l

DESCRIPTION (NPS)

DRAWING REFERENCE SELECTED SELECTED EXAM METHOD CATEGORY 8th REFUEL - 9th REFUEL 14-A-28 12.00 DCN-14-MI-203-5-8 Yes Yes UT CAT A PIPE TO PIPE

(

14-A-29 12.00 DCN-14-MI-203-5-8 No No UT CAT A PIPE TO P!PE 14-A-30 12.00 DCN-14-MI-203-5-8 No No UT CAT A PIPE TO ELBou 14-A-31 12.00 DCN-14-MI-203-5-B Yes Yes UT CAT A X

ELBOW TO P!PE 14-A-32 12.00 DCN-14-MI-203-5-8 No No UT CAT A PIPE TO ELBOW 14-A-33 12.00 DCN-14-MI-203-5-B Yes No UT CAT A ELBOW TO P!PE 14-A-34 12.00 DCN-14-MI-203-5-8 No No UT CAT A PIPE TO PIPE 14-A-35 12.00 DCN-14-MI-203-5-8 No No UT CAT A PIPE TO ELBOW 14-A-36 12.00 DCN-14-MI-203-5-8 No No UT CAT A ELBCW TO PIPE 14-A-37 12.00 DCN-14-MI-203-5-8 Yes Y es UT CAT A PIPE TO FIPE 14-A-38 12.00 DCN-14-MI-203-5-B No No UT CAT A PIPE TO PIPE 14-A-39 12.00 DCN-14-MI-203-5-8 Yes 2

Yes UT CAT A X

P!PE TO REDUCER 14-A-40 10.00 DCN-14-MI-203-5-8 No No UT CAT A REDUCER TO PIPE 14-A-41 10.00 DCN-14-MI-203-5-8 No

.No UT CAT A PIPE TO ELBOW 14-A-42 10.00 DCN-14-MI-203-5-8 Yes Yes UT CAT A ELBOW TO PIPE 14-A-43 10.00 DCN-14-M1-203-5-8

'Yes Yes UT CAT G

'X~

PIPE TO SAFE-END CUG-1 REPORT NRC GENERIC LETTER 88-01,

!NTERGRANULAR STRESS CORROS10N CRACKING

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' PEACH BOTTOM ATOMIC POWER STATION UNIT 2 C%TACNMENT "A"

' PRf%TED: 05/31/90 AUG-14 NRC GENERIC LETTER 88-01,

. PAGE: 2 of 22 INTERGRANULAR STRESS CORROS10N CRACKlkG SYSTEM: CORE SPRAY CLASS-1 EXAMINATION AREA ID NUMBER &

SIZE ISOMETRIC

.ISI AUG-1 AUGMENTED 1GSCC

' EXAMINE DURING OUTAGE DESCRIPTION

(NPS)

DRAWING REFERErCE. SELECTED SELECTED EXAM METHOD CATEGORY Sth REFUEL - 9th REFUEL 14-B-28 12.00 DCN-14-MI-203 A Yes No UT CAT A PIPE TO PIPE

.i 14-8-29 12.00 DCN-14-MI-203-5-A Yes Yes UT CAT A PIPE TO PIPE 14-B-30 12.00 DCN-14-MI-203-5-A No

-No UT CAT A P!PE TO ELBOW 14 B-31 12.00 DCN-14-MI-203-5-A No No UT CAT A ELBOW TO PIPE 14-B-32 12.00 DCN-14-MI-203-5-A ro No UT CAT A PIPE TO ELBOW 14 8-33 12.00 DCN-14-MI-203-5-A No No UT CAT A ELBOW TO P!PE 14-8-34 12.00 DCN-14-MI-203-5-A Yes Yes UT CAT A X

PIPE TO ELBOW 14 B-35 12.00.

DCN-14-MI-203-5-A No No UT CAT A ELBOW TO P!PE 14-8-36

,12.00

~DCN-14-MI-203-5-A No No UT CAT A P!PE TO PIPE 14-B-37 12.00 DCN-14-MI-203 A No No UT CAT A PIPE TO REDUCER 14-B-38 10.00 DCN-14-MI-203-5-A No No UT CAT A REDUCER TO PIPE 14-B-39 10.00 DCN-14-MI-203-5-A No No UT CAT A j

PIPE TO ELBOW 14-B-40 10.00 DCN-14-MI-203-5-A No No UT CAT A ELBOW TO PIPE l

14-8-41 10.00.

DCN-14-MI-203-5-A Yes Yes UT CAT G X

P!PE TO SAFE-END I

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AUG-1 REPORT NNC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION CRACKING t

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LTTACmENT "A* '

PRlhTED: 05/31/90 1 PEACM 90TTOM ATOMIC' POWER STATION - tMIT 2 PAE:' 3 of 22.,

2AUG-1, NRC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSTON CRACKING..

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SYSTEM: CORE SPRAY CLASS: 1 i

EXAMINAft04 AREA-ISI AUG-1 AUGMENTED IGSCC ENAMINE DURING OUTAGE-ID NUMBER &

SIZE

' ISOMETRIC.

DESCRIPTION (NPS)-

DRAWING REFERENCE SELECTED SELECTED EX4M METNCD CATEGORY 8th REFUEL - 9th REFtEL e

' TOTAL RECORDS PRINTED FOR THE CLASS 1 CORE SPRAY SYSTEM = 30..

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TOTAL CATEGORY A = 28 TOTAL CATEGORY D = 0 TOTAL CATEGORY G = 2 fitG-1 REPORT NRC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION ERACKING n.

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F PRIM ED: 05/31/90 PEAC3 BOTTOM ATOMIC POWE2 STATION - UNIT 2 ATTACNMENT "A*'

INTERGRANULAR STRESS CORROSION CRACEfMG

~ 4 of 22 ~'

AUG-1,'NRC GENERIC LETTER 88-01,

. PAGE:

SYSTEM: MAIN RECIRCULATION CLASS: 1 EXAMINATION AREA ID WUMBER &

SIZE ISOMETRIC ISI AUG-1 AUGMENTED IGSCC-EXAMINE DURING OUTAGE DESCRIPTION (SIPS)

DRAWING REFERENCE SELECTED-SELECTED EXAM MET 800 CATEGORY 8th REFUEL - 9th REFUEL 2-AD-29 28.00 RCS-02-MI-201-1-A No No UT CAT A PUMP TO P!PE

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2-AD-29/C0 4.00 RCS-02-MI-201-1-A No No UT CAT A BRANCH CONNECTION 2-AD-29/CO-1 4.00 RCS-02-MI-201-1-A No No UT CAT A PRANCH CONN TO PIPE 2-AD-29/Co-2 4.00 RCS-02-MI-201-1-A No No UT CAT A PIPE TO FLANGE 2-AD-30 28.00 RCS-02-MI-201-1-A No No UT CAT A PIPE TO VALVE 2-AD-31 28.00 RCS-02-MI-201-1-A No No UT CAT A VALVE TO ELBou 2-AD-32 28.00 RCS-02-MI-201-1-A Yes Yes UT CAT A X

EL80W TO P!PE 2-AD-33 28.00 RCS-02-MI-201-1-A No No UT CAT A P!PE TO TEE 2-AHF-6 12.00 RCS-02-MI-201-1-A No No UT CAT A P!PE BND TO P!PE BND 2-ANF-7 12.00 RCS-02-MI-201-1-A Yes Yes UT CAT A X-PIPE BEND TO SF-END 2-AHG-6 12.00 RCS-02-MI-201-1-A Tes Yes UT CAT A BR CONW TO PIPE BND 2-AHG-7 12.00 RCS-02-MI-201-1-A No No UTJ CAT A P!PE TO SAFE END 2-AHM-6 12.00 RCS-02-MI-201-1-A No No UT WA REDUCER TO PIPE BND 2-AHH-7 12.00 RCS-02-MI-201-1-A No No UT CAT A PIPE BEND TO SF-END 2-ANJ-6 12.00 RCS-02-MI-201-1-A Yes Yes UT CAT A X

BR CONN TO PIPE BEND 2-AHJ-7 ~

12.00 RCS-02-MI-201-1-A No

' No UT.

CAT A P!PE BEND TO SF-END AUG-1 REPORT NRC GENERIC LETTER 88-01,' -

l#TERGRANULAR STRESS CORROSION CRACRING i _.

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.PRIITED: 05/31/90 PEACH 90TTOM ATOMIC POWER STATION - UNIT'2 (TTAC NT Ma AUG-1., NRC GENERIC LETTER 88-01, PAGE: 5 of 22...

INTERGRANULAR STRESS CORROSION CRACKING SYSTEM: MAIN RECI'RCULATION CLASS: 1 EXAstINATION AREA ID NUMBER &

SIZE ISOMETRIC

.AUG-1 AUGMENTED IGSCC EXAMINE DURING O'JTAGE.

DESCRIPTION (NPS)

DRAWING REFERENCE SELECTED SELECTED EXAM METNOD CATEGORY Sth REFUEL - 9th REFUEf.

2-AHK-6 12.00 RCS-02-MI-201-1-A No No UT CAT A

. PIPE TO P!FE 2-ANK-7 12.00 RCS-02-MI-201-1-A Yes Yes UT ICAT A P!PE BEND TO SF-END 2-AM-6 22.00 RCS-02-M!-201-1-A

.. No No UT CAT A CROSS TO PIPE 2-AM-7 12.00 RCS-02-MI-201-1-A No No UT CAT A REDUCER TO PIPE 2-AM-8 22.00 RCS-02-MI-201-1-A Yes Yes UT -

CAT A X

CROSS TO PIPE 2-AM-9 12.00 RCS-02-MI-201-1-A No No UT CAT A REDUCER TO PIPE 2-AS-19 28.00 RCS-02-M1-201-1-A Yes Yes UT CAT G X

SAFE-END TO ELBOW 2-AS-20 28.00 RCS-02-MI-201-1-A No No UT CAT A ELCOW TO PIPE 2-AS-21 28.00 RCS-02-MI-201-1-A' Yes Yes UT CAT A X

P!PE TO TEE 2-AS-22 28.00 RCS-02-MI-201-1-A No No UT CAT A' TEE TO PIPE 2-AS-23 28.00 RCS-02-MI-201-1-A No No UT CAT A PIPE TO PIPE 2-AS-24 28.00 RCS-02-MI-201-1-A No No UT CAT A PIPE TO ELBOW 2-AS-25 28.00 RCS-02-MI-201-1-A No Yes UT CAT A ELBOW TO VALVE 2-AS-26 28.00 RCS-02-MI-201-1-A No Nc UT CAT A VALVE TO PIPE 2-AS-26/C0 4.00 RCS-02-MI-201-1-A No -

No UT CAT A BRANCH CONNECTION 2-AS-26/CO-1 4.00 RCS-02-MI-201-1-A No No UT CAT A BRANCH CONN TO PIPE sifG-1 REPORT NRC GENERIC LETTER 88-01g INTERGRANULAR STRESS CORROS100 CRACKING

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CTTAC NT

' PRI::TED: 05/31/90 AUG-1, NRC GENERIC LETTER 88-01, PAGE: 7 of 22.:

-INTERGRANULAR STRESS CORROSION CRACKING

'c SYSTEP": MAIN RECIRCULATION -CLASS: 1 EXAMINATION ARIA ID NUMBER &

SIZE ISOMETRIC

'ISI AUG AUGMENTED IGSCC EXAMINE DURING OUTAGE DESCRIPT!ON (NPS)

-DRAWING REFERENCE SELECTED SELECTED EXAM METNOD CATEGORY 8th REFUEL - 9th REFUEL

' 2-BHC-7 '

12.00 RCS-02-M1-201-1-8 No No UT CAT A PIPE BEND TO SF-END

'2-BHD-6 12.00 RCS-02-MI-201-1-8 No No UT CAT A BR CONN TO PIPE BEND 2-BND-7 12.00 RCS-02-MI-201-1-8 No No UT CAT A PIPE BEND 10 SF-END 2-BHE-6 12.00 RCS-02-Mt-201-1-B Yes Yes UT CAT A PIPE BND TO P!PE BND 2-BME-7 12.00 RCS-02-MI-201-1-8 No No UT CAT A PIPE BND TO SF-END 2-BM-6 22.00 RCS-02-MI-201-1-B No No UT CAT A CROSS TO P!PE 2-BM-7 12.00 RCS-02-MI-201-1-B No No UT CAT A REDUCER TO P!PE BND 2-BM-8 22.00 RCS-02-MI-201-1-8 No No UT CAT A CROSS TO PIPE 2-BM-9 12.00

'RCS-02-MI-201-1-8 Yes Yes UT CAT A RED TO PIPE BENC 2-85-18 28.00 RCS-02-MI-201-1-B No Yes UT CAT G X

SAFE-END TO ELBOW 2-85-19 28.00 RCS-02-MI-201-1-B Yes Yes UT CAT A X

ELBOW TO PIPE 2-85-20 28.00 RCS-02-MI-201-1-B No No UT CAT A PIPE TO P!PE 2-BS-21 28.00 RCS-02-M1-201-1-8 No Yes UT CAT A PIPE TO ELBOW 2-85-22 28.00 RCS-02-Mt-201-1-8 No No UT CAT A ELBOW TO VALVE 2-BS-23 28.00 RCS-02-MI-201-1-8 No No UT CAT A VALVE TO PIPE 4.00 RCS-02-MI-201-1-B No No UT

. CAT A 2-85-23/C0

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BRANCH CONNECTION AUG-1 REPORT NRC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION CRACKING

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4 PRI TED: 05/31/90" PEACH BOTTOM ATOMIC POWER STATION - tm!T 2

f.TTACMMENT M

AUG 1, NRC GENERIC LETTER 88-01, PAGE: 8 of 22 c 3

INTERGRANULAR STRESS CORROS10N CRACKING SYSTEM: MAIN RECIRCULATION CLASS: 1 EXAMINATION AREA.

ISOMETRIC.

151.

AUG-1.

" AUGMENTED IGSCC EXAMINE DURING OUTAGE, ID NUMBER &

SIZE.

DESCRIPTION (NPS)

DRAWING REFERENCE SELECTED SELECTED EXAM METHOD _ : CATEGORY 8th REFUEL - 9th REF'KL -

2-BS-23/Co-1 4.00 RCS-02-MI-201-1-B Yes Yes UT-CAT A BRANCH CONN TO PIPE 2-85-23/C0-2 4.00 RCS-02-MI-201-1-B No No UT CAT A P!PE TO FLANCE~

2-85-24 28.00 RCS-02-MI-201-1-B' No No UT CAT A P!PE TO ELBOW 2-85-25 28.00 RCS-02-MI-201-1-8 No No UT

. CAT A ELBOW TO PUMP TOTAL RECORDS PRINTED FOR THE CLASS 1 MAIN REC!RCULATION SYSTEM = 68 TOTAL CATEGORY A = 66 TOTAL CATEGORY D = 0 TOTAL CATEGORY G = 2 AUG-1 REPORT NRC GENERIC LETTER 88-01,-

INTERGRANULAR STRESS CORROSION CRACKING

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PRt"TED- 05/31/90 PEACH BOTTOM ATOMIC POWEJ ST* TION - UNIT 2 PAGE: 9 of 22...

AUG-1. NRC GENERIC LETTER 88-01, I

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INTERGRANULAR STRESS CORROSION CRACKING SYSTEM: REACTOR PRESSURE VESSEL ~ CLASS: 1 i-l EXAMINATION AREA l

ID NUMBER &

SIZE ISOMETRIC

-ISI AUG-1 AUGMENTED IGSCC EXAMINE DURING OUTAGE DESCRIPTION (NPS)

DRAWING REFERENCE.

SELECTED SELECTED EXAM METM(D CATEGORY 8th REFUEL - 9th REFUEL 1

l 14-A-27 10.00 DCN-14-MI-203-5-8 Yes Yes UT CAT D X

l SAFE-END TO N0Z NSA l

4 14-8-27 10.00 DCN-14-M1-203-5-A Yes Yes-UT CAT D X

l SAFE-END TO N0Z N59' l

l 2-ANF-8 12.00 RCS-02-M1-201-1-A Yes No UT CAT A SAFE-END TO N0Z N2F 2-AMG-8 12.00 RCS- 02-MI -201 A..

Yes.

No UT CAT A SAFE-END TO N0Z N2G 2-AHH-8 12.00 RCS-02-MI-201-1-A Yes No UT CAT A SAFE-END TO N0Z N2H 2-ANJ-8 12.00 RCS-02-MI-201-1-A Yes Yes UT CAT A x

SAFE-END TO N0Z N2J 2-ANK-8 12.00 RCS-02-MI-201-1-A Yes No UT CAT A SAFE-END TO 1:02 N2K 2-AS-1 28.00 RCS-02-MI-201-1-A Yes Yes UT CAT D M

SAFE-END TO N0Z N1A 2-8HA-8 12.00 RCS-02-MI-201-1-8 Yes No UT CAT A SAFE-END TO N0Z N2A 2-8H8-8 12.00 RCS-02-MI-201-1-B Yes

-Yes UT CAT A SAFE-END TO N0Z N2B 2-BHC-8 12.00 RCS-02-MI-201-1-8 Yes No UT CAT A SAFE-END TO N0Z N2C 2-8HD-8 12.00 RCS-02 MI-201-1-8 Yes Yes UT CAT A SAFE-END TO NO2 N2D 2-8HE-8 12.00 RCS-02-MI-201-1-B-Yes No UT CAT A SAFE-END TO N0Z N2E 2-85-1 28.00 RCS-02-Mt-201-1-B Yes Yes UT CAT G X

SAFE-END TO N0Z N18 3-1-19R 4.00 ISI-2-RPV-05 Yes Yes UT CAT G x

N0ZZLE N9 TO CAP 4-N10-1 6.00 151-2-RPV-05 Yes Yes UT CAT C x

M10 N0Z TO SF-END NRC GENERIC LETTER 88-01, AUG-1 REPORT INTERGRANULAR STRESS CORROSION CRACKING'

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PRIXTED: 05/31/90

'PEACM SOTTOM ATOMIC POWER STATION Y UNIT 2 ~

- CTTACINEE#T "A" 1 AUG-1, NRC GENERIC LETTER 88-01,

-PAGE: 10 of 22; INTERGRAmVLAR STRESS CORROSION CRACKING-SYSTEM: REACTOR PRESSURE VESSEL CLASS: 1 EXAMINATION AREA ID NUMBER &

SIZE ISOMETRIC ISI AUG-1 AUGMENTED IGSCC EXAMtWE DURING OUTAGE' DESCRIPTION (NPS)

DRAWING REFERENCE SELECTED SELECTED EXAM METN3D CATEGORY -~ 8th REFUEL - 9th REFUEL 4-N11A-1 2.00-ISI-2-RPV-05 Yes

Yes UT CAT G X

N11A NO2 TO COUP 4-N118-1

~2.00 ISI-2-RPV-05 Yes Yes UT CAT G X

N118 NO2 TO COUP 4-N12A-1 2.00 ISt-2-RPV-05 Ves Yes UT CAT G-X N12A NO2 TO COUP 4-N128-1 2.00 ISI-2-RPV-05 Yes Yes UT CAT G X

N128 WO2 TO COUP 4-N16A-1 2.00 Ist-2-RPV-05 Yes Yes UT CAT G X.-

Nt6A NO2 TO COUP 4-N168-1 2.00 ISI-2-RPV-05 Yes Yes UT CAT'G X

N168 NO2 TO COUP JP-A 4.00 ISt RPV- 05 Yes Yes UT CAT G X

M8A NO2 TO SF-END JP-A-7 4.00 ISI-2-RPV-05 No No UT CAT A SAFE-END TO PEN SEAL JP-8-6 4.00 ISI-2-RPV-05 Yes Yes

- UT CAT G-X NSB NO2 TO SF-END JP-8-7 4.00 ISI-2-RPV-05 No No UT CAT A SAFE-END TO PEN SEAL TOTAL RECORDS PRINTED FOR THE CLASS 1 REACTOR PRESSURE VESSEL SYSTEM = 26 i

TOTAL CATEGORY A = 12 TOTAL CATEGORY D = 3 TOTAL CATEGORY G = 11 AUG-1 REPORT MRC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION CRACKING I

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e JPRI:TED: 05/31/90 PEACN BOTTOM ATOMIC POWER STATION - UNIT 2 LTTACNMENT "A" PAGE: 14 of 22 61 AUG-1, NRC CENERIC LETTER 88-01, INTERGRANULAR STRESS CORROS10N CRACX1NG SYSTEM-REACTOR MATER CLEAN-UP CLASS: N/A EMAMINATION AREA' ID NUMBER &

SIZE ISOMETRIC ISI AUG-1 AUGNENTED IGSCC EMANINE DURING OUTAGE DESCRIPTION (NPS)

DRAWING REFERENCE SELECTED SELECTED EXAM METHOD CATEGORY 8th REFUEL - 9th REFUEL 12-08-28 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G.

X PIPE TO VALVE

.I 12-08-29 4.00 DE-12-MI-203-5 too Yes VT-2 CAT G X

VALVE TO ELBOW 12-08-30 4.00 DE-12-MI-203-5 No Yes vi-2 CAT C X

ELBOW TO PIPE 12-08-31 4.00 DE-12-MI-203-5 s

No Yes vi-2 CAT G X

' P!PE TO MX 12-08-32 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

TEE TO PIPE 12-08-33 4.00 DE-12-M!-203-5 No Yes vi-2 CAT G X

PIPE TO ELBOW 12-08-34 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

ELBOW TO PIPE 12-10-1 4.00 DE-12-MI-203-5 No Yes vi-2 CAT C

.X P!PE TO ELBOW 12-10-2 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

ELBOW TO PIPE 12-10-3 4.00 DE-12-MI-203-5 No Yes VT-2 CAT G X

PIPE TO ELBOW 12-10-4 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

ELBOW TO PIPE 12-10-5 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G

'X PIPE TO ELBOW 12-10-6 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

ELBOW TO VALVE 12-10-7 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

VALVE TO PIPE 12-10-8 4.00 DE-12-MI-203-5 No Yes vi-2 CAT G X

PIPE TO VALVE 12-10-9 4.00 DE-12-MI-203-5 No

.Yes VT-2 CAT G X.

VALVE TO P!PE AUG-1 REPORT NRC GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION CRACXING-

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CAT A PIPE TO ELBOW 12-0-334 6.00 DCA-12-MI-201-1 No No UT CAT A PIPE TO PIPE 12-0-33R 6.00 DCA-12-MI-201-1 Yes Yes UT CAT A X

ELBOW TO PIPE 12-0-34R 6.00 DCA-12-MI-201-1 No No UT CAT A P!PE TO PENT N-14 12-0-35

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DRAWING REFERENCE SELEC7ED SELECTED ERAM METN(B CATEGORY 8th REFUEL - 9th #EFtKt 14-A-46 10.00 DCN-14-MI-303-4-8 Yes No UT CAT A SATE-END TO NOZ NSA

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NOZZLE M9 TO CAP 4-N10-1 6.00 ISt-3-RPv-05 Yes Yes UT CAT G X

N10 N0Z TO SF-END AUG-1 REPORT NRC GENERIC LETTER 88-01 INTERGRANULAR STRESS CORROSION CRACKING

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SIZE ISOMETRIC ISI AUG-1 AUGMENTED IGSCC EMAMlWE DURING OUTAGE DESCRIPTION (UPS)

DRAWING REFERENCE SELECTED SELECTED EMAM Mein 0D CATEGORY 8th REFUEL - 9th REFUEL 12-8-5 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G X

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12-8-6 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G X

ELBOW TO PIPE 12-8-7 4.00 DE-12-MI-303-5 wo Yes VT-2 CAT G M

PIPE TO EL9OW 12-8-8 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G M

ELBOW TO PIPE 12-8-9 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G M

PIPE TO ELBOW 12-8-10 4.00 DE-12-MI-303-5 wo Yes vi-2 CAT G X

ELBOW TO PIPE 12-8-11 4.00 DE-12-MI-303-5 No Yes VT-2 CAT G X

PIPE TO ELBOW 12-8-12 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G X

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PIPE TO EL90W 12-8-14 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G N

EL9OW TO PIPE 12-8-15 4.00 DC 12-MI-303-5 wo Yes vi-2 CAT G N

PIPE TO FLANGE 12-8-16 4.00 DE-12-MI-303-5 no Yes vT-2 CAT G x

FLANGE TO PIPE 12-8-17 4.00 DE-12-MI-303-5 no Yes vT-2 CAT G X

PIPE TO TLANGE 12-8-18 4.00 DE-12-MI-303-5 no Yes vi-2 CAT G X

FLANGE TO PIPE 12-8-19 4.00 DE-12 MI-303-5 no Yes vi-2 CAT G M

PIPE TO TEE 12-8-20 4.00 DE-12-MI-303-5 no Yes WT-2 CAT G X

TEE TO PIPE AUG-1 REPORT NRC GENERIC LETTER 88-01, INTERGRAuULAR STRESS CORROSION CRACKl#G

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ML20043E926

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