ML20043G731

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Provides Addl Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Welds Examined During Last Refueling Outage Addressed
ML20043G731
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/08/1990
From: Hunger G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-01, GL-88-1, NUDOCS 9006210064
Download: ML20043G731 (50)
v • d • e


Text

o'-. GL 88-01 PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD.

WAYNE, PA 19087 5691 (tisis40sooo June 8, 1990 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D.C. 20555 L

SUBJECT:

Limerick Generating Station, Units 1 and 2 Response to NRC Letter Dated March 6, 1990, Results of HRC Review of Submittals Responding to NRC Generic Letter 88-01, "NRC Position on i IGSCC in BWR Austenitic Stainless Stecl Piping" i Dear Sir NRC letter dated March 6, 1990 provided the results of the NRC's review of our submittals dated August 2, 1988, April 28, 1989, May 30, 1989, and September 11, 1989, responding to NRC Generic Letter (GL) 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping." This letter stated that our responses to the five specific items-and 13 staff positions presented in GL 88-01 were found acceptable with a few exceptions. These exceptions are restated below along with our response to each.

Five Specific Items

1. " Item 2 requested that you provide the actual list of welds that you were going to examine at the last refueling outage. You stated that the GL-88-01 requirements would be integrated with the regular ISI program and that inspections will be performed at frequencies which will be in conformance with the Staff Positions on Inspection Schedules.

This is not specific enough to assess the scope of your-program. Accordingly, it is requested that you submit your 9006210064 900608 Is '

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U.S.-Nucloat.Resulatory. Commission' June 8, 1990 DocumDnt Control Desk Page 2 IGSCC inspection plans for staff review at least three months prior to the beginning of each refueling outage."

Response-The third refueling' outage for Limerick Generating Station (LGS), Unit 1 is scheduled to begin on September 8,-1990.

Therefore, as requested, the implementation schedule for augmented examinations in accordance with NRC GL 88-01 for LGS, Unit 1, is provided in Attachments A-1/A-2 for review by June 8, 1990.- The first refueling outage for LGS, Unit 2, is scheduled _to begin in March 1991. However, the implementation schedule for augmented examinations in accordance with NRC GL 88-01 fer LGS, Unit 2, is-provided in Attachment B to this letter. These attachments contain a tabular listing of all welds subject to the examination requirements of_the GL, along with an identification of which welds have been selected for examination and the examination schedules for the next two refueling outages.

During a telephone conversation between the NRC Technical Reviewers for GL 88-01 and Philadelphia Electric Company _

(PECo) representatives on April 24, 1990, the NRC concurred that this one-time submittal of examination schedules would be sufficient to satisfy GL 88-01, and that a schedule would not be required to be submitted prior to each refueling outage as requested above.

Please note that the listings of welds provided in the attachments have been adjusted to delete the longitudinal seam welds from our program. Since these welds-are.outside the scope of GL 88-01. ThF eas confirmed with the-NRC Technical Reviewers in the april 24, 1990 telephone conversation. Additionally, welds on reactor vessel attachments and appurtenances less than four inches in nominal diameter have been deleted from.our program, since these welds are also outside the scope of GL 88-01. This was confirmed during a telephone conversation between-an-NRC Technical Reviewer for GL 88-01 and a PECo representative on June 7, 1990. These welds were included in our original and revised responses to GL 88-01 referenced previously. Additionally, Insetvice Inspections (ISI) Program weld numbers have been used instead of construction weld numbers. The schedules provided are for planning purposes and are subject to change. For Intergranular Stress Corrosion Cracking (IGSCC) susceptible welds subject to a sampling process (e.g. Category A welds), selected welds may be examined during a different outage than indicated.

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U.S. Nuclocr ROgulatory Commicsion Juno 8,'1990-Document Control Desk. Page 3;

2. " Item 3 requested that you submit an application to amend the Limerick Technical Specifications (TSs) to include a statement in the section on ISI that the Inservice Inspection Program for piping covered by the scope of GL 88-01 will be in conformance_with the staff position cx) schedule, methods and personnel, and sample expansion. You and some other BWR licensees took exception to this request. The staff reevaluated this issue and concluded that this requirement needed to be in the TSs.- As.part of the TS improvement program, surveillance requirement 3.0.5-will be relocated to the Administrative Controls section of the STS.- You are requested to submit a TS change to include the statement on the ISI program as initially proposed in your letter of August 2, 1988."

Response

j i

Section 4.0.5 of the LGS TS contains-surveillance requirements for inservice inspection and testing of'ASME i' Code Class 1,2, and 3 components. We.will submit a TS Change: Request (TSCR) by December 31, 1990, requesting that l the^following note be added to TS Section 4'.0.5.  ;

"The Inservice Inspection (ISI) Program for piping-Lidentified in NRC Generic _ Letter 88-01 shall be performed in accordance with the staff. positions on schedule, methods and personnel, and sample expansion included in the Generic Letter. Details for the implementation of these requirements are included as .:  ;

augmented inspection requirements in the ISI program."  !

3. " Item 4 requested BWR licensees to amend the TSs to  !

incorporate the staff position on unidentified leakage - l specifically, that unidentified leakage be limited to an  ;

increase-in leakage of 2 gpm over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, that--

i total unidentified leakage be limited to 5 gpm and that leakage be. monitored every four hours. Your letter of l August 2, 1988 discussed reasons why you concluded the present TS requirements were adequate. Most other BWR licensees also took exception to the leakage detection requirements in GL 88-01. The staff reassessed the leakage requirements and concluded that, with one exception, they were reasonable and necessary. The staff agreed that-monitoring leakage every four hours would create an unnecessary administrative hardship. The staff position was. modified to require that leakage be monitored every eight (8) hours. It is requested that you submit an application to revise the Limerick TSs to incorporate the above limits on unidentified leakage."

0 :. , - 4<

,. LU.S. NuclGGr RGgulctory Commission- Jung 8, 1990 i V

Docum3nt Control Desk. Page 4' i

g, Response TS Section 3/4.4.3.2 for LGS specifies the Limiting Condition for Operation (LCO) and Surveillance Requirements ,

for reactor coolant system operational leakage. By December 31, 1990, we will submit a TSCR requesting that TS Section 3.4.3.2 be revised to specify that unidentified leakage be limited to an increase of 2 gpm over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, and that TS Section 4.4.3.2 be revised, where applicable, to specify leakage monitoring every eight (8) hours instead of every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

13 Staff Positions i

1. "As a result of the fuel failures in the second fuel cycle r of Unit 1, there were many discussions and presentations'by '

your staff on proposed improvements to the water chemistry program. These improvements go well beyond.the "BWR Water  ;

Chemistry Control Program," dated: December 11, 1987,

  • referred to on page 4 of your August 2, 1988 letter. We i

assume that the actions and commitments you made in your letter of April 3, 1989 to avoid future CILC related fuel ,

failures-at Limerick, Units 1 and 2, supersede the- -

discussion of water chemistry in your August 2, 1988 '

letter. Your proposed actions included improved a performance of the condensate-filter /demineralizers, A improved monitoring methods and instrumentation, minimizing  ;

copper in the feedwater, limiting chemical transients and '

total organic carbon and installation of full-flow, deep-bed demineralizers at the next refueling' outages for Units 1 and 2. On the basis of the later submittals, we find your water chemistry program acceptable. In-fact, the actions and evaluations undertaken,by your plant chemistry jl staff following the recent condenser-tube leaks in Unit I l is commendable. Our contractor did not have the benefit of p

the discussions and submittals related to the Unit 1 fuel l

I-failures; hence, the enclosed Technical Evaluation Report (TER) does not fully reflect-the above staff l- determination."

(No response required)

2. "You discussed your plans to notify the NRC of any flaws that do not meet IWB-3500 criteria of Section XI of the Code for continued operation and to obtain NRC approval of

, the disposition for each flaw exceeding the criteria before l resuming operation. You made a very good submittal on the 1:

indication you found during the second refueling outage in the Limerick, Unit 1 recirculation riser nozzle to safe end weld. InyoursubmitpalsonGL88-01,youdidnotaddress g

l

i U.S.'Nucloor R39ulatory Commiccion June 8, 1990' )

Documsnt Control Dask. Page 5-1 1

b your-general position on use of weld overlays and clamping  !

devices or long range plans, if any, for stress improvement of welds in Unit 1." l Response- '

We intend to follow the staff position on weld overlays, clamping ~ devices, and stress improvement if situations dictate the use of these techniques at LGS. We will-approach the NRC on a case-by-case basis if deviations from these staff positions are deemed necessary. This was found acceptable,by the-NRC Technical Reviewers in the April 24, 1990 telephone conversation.

Stress improvements on weldments have already been applied 1 at LGS, Unit 2. The use of mechanical stress improvement '

on reactor nozzle to safe end weldments at LGS, Unit 1, during the. fourth refueling outage is currently under evaluation. l

3. "It was not clear whether_you plan to inspect the 195 category G' welds in the Reactor Water Cleanup System beyond ,

the outer containment isolation valve."

Response

We-consider the portion of'the Reactor Water Cleanup (RWCU)

System outside containment to ha uninspectable by Ultrasonic. Testing (UT) methods because of the high levels of; worker radiation exposure expected during conduct of such' examinations. All of the subject piping is located in high' radiation areas and most welds would require the-erection of scaffoi u.ng in order to achieve access'for examination. This activity would increase the exposure time for workers'in a high radiation area.

The subject piping is automatically isolated from the.

reactor coolant system and is not required to be examined in accordance with the ASME Section XI ISI Program.

Accordingly, the associated welds' currently exist in their as-welded condition (i.e., no weld crown preparation). As  :

such, effective UT examination of these welds would be difficult. Interpretation of the results of such examinations would be impractical. Preparation of the welds for examination would require removal of permanently installed insulation and grinding of the existing weld surfaces'to a smoothness amenable to UT examination which would further increase worker radiation exposure and  ;

airborne radiation levels.

'l

l U.S. Nucloct Rcgulctorie Commicsion Juna 8, 1990 1 Document-Control Desk Page'6 l u

1 In consideration of the above factors, we consider UT examination of even a representative sample of welds to-be contrary to our goal of keeping radiation exposure "as low as reasonably achievable."

1 There are alternate methods of inspection already in place L at LGS to ensure RWCU system piping integrity. The portion L

of the RWCU system piping outside containment is included L in the ISI Pressure Testing Program. Accordingly, the i o system is pressure tested and visually examined in L accordance with the applicable rules of the ASME Code, Section=XI, each inspection period. This inspection is designated as "VT-2" in Attachments A-1/A-2 and B which- l were discussed previously. We consider the' existing inspections performed on the RWCU system to be sufficient-

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to-preclude the need for individual weld examinations as L recommended in GL 88-01.

If you have any questions, please do not hesitate to contact us.

l Very truly yours,.

-/

G. A. Hunger, Jr.

Manager Licensing Section Nuclear Engineering and Services

-Attachments cc: ,T. T. Martin, Administrator, Region I, USNRC T..J.-Kenny, USNRC Senior Resident Inspector, LGS 1

l

Attachment 'A-1 LIMERICK GENERATING STATION, UNIT 1 &' COPHON Response to NRC Letter Dated March 6. 1990,

-Results of NRC Review of Submittals Responding to NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" 4 pages System. Code (s): RPV - Reactor Pressure Vessel I

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.m , -, 1m PRIOTED: 06/07/90 LIMERICK GENERATING STATION - UNIT 1 & C015 EON ~ ATTACf5EltT M-17 :

AUG-1, NRC GENERIC LETTER 88-01i - PAGE: 1 of 4 '.

INTERGRANULAR STRESS CORNOS10N OtACKING SYSTEM: RPV CLASS: 1' EXAMINATION AREA SIZE AUG-1 AUGMENTED IGSCC EXAMINE DURING OUTAGEI

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EXAMINAJION AREA ID NUMBER DESCRIPTION (NPS) DRAWING REFERENCE SELECTED EXAM METN(2 CATEGORY' 3rd REFUEL - 4th REFtEL' DCA-318-1 FW1 LFCI LOOP D (N178) - SAFE END 12.00 01-11 Yes UT A X t TO PIPE DCA-318-1 N17B LPCI LOOP D (N17B) - N0ZZLE TO 12.00 01-11 Yes UT D X SAFE END DCA-318-2 FW1 LPCI LOOP B (N17A) - SAFE END 12.00 01-04 Yes UT A X TO PIPE DCA-318-2 N17A LPCI LOOP 8 (N17A) - N0ZZLE TO 12.00 01-04 Yes UT D X SAFE END DCA-318-3 FW1 LPCI LOOP A (N17C) - SAFE END 12.00 01-01 Yes UT A X TO PIPE DCA-318-3 N17C LPCI LOOP A (N17C) - N0ZZLE TO 12.00 01-01 Yes UT D X' SAFE END DCA-318-4 FW1 LPCI LOOP C (N17D) - SAFE END 12.00 01-07 Yes UT A X TO PIPE DCA-318-4 N17D LPCI LOOP C (N17D) - N0ZZLE TO 12.00 01-07 Yes UT D X SAFE END DCA-319-1 FW1 CORE SPRAY LOOP B (NSA) - SAFE 10.00 04-04 Yes UT A X END TO PIPE' DCA-319-1 MSA CORE SPRAY LOOP B (NSA) - 10.00 04-04 Yes UT D X N0ZZLE TO SAFE END DCA-320-1 FW1 CORE SPRAY LOOP A (NSB) - SAFE 10.00 04-01 Yes UT A X END TO PIPE DCA-320-1 NSB CORE SPRAY LOOP A (N58) - 10.00 04-01 Yes UT D X N0ZZLE TO SAFE END RPV-11N N8A JET PUDF INST. LOOP 8 - IIOZZLE 6.00 RPV-11M Yes UT D X.

TO SAFE END RPV-11N N8A-SW1 J. P. INSTRUMENTATION LOOP B - 4.00 RPV-11N No  !!T A PENE. SEAL ASSY. WELD RPV-1tN NSB JET PUMP INST. LOOP A - N0ZZLE 6.00 RPV-11N Yes UT D. X TO SAFE END RPV-1tN N88-SW1 J. P. INSTRUIENTATION LOOP A - 4.00 RPV-11N Wo UT A PENE. SEAL ASSY. WELD AUG-1 REPORT - 1 of 2 NRC GENERIC LETTER 88-01, (RPV) INTERGRANUUNt STRESS CORROSION CRACKING

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- PRICTED: 06/07/90 LIMERICK GENERATING STATION - UNIV 1 & COISION ATTACINEWT "A-1? '

AUG-1, NRC GENERIC LETTER 88-01, _PAGE: 2 of 4 .

INTERGRANULAR STRESS CORROSION CRACKING SYSTEM: RPV CLASS: 1 EXAMINATION AREA SIZE . 'AUG-1 AUEBIENTED IGSCC EXAMINE DURING OtFAGE EXAMINATION AREA ID NLDIBER DESCRIPTION M DRAWI K, REFERENCE SELECTED EXAM sETuts QAT(GQRY 3rd REFtKL - 4th REFLEL RPV-11M N9 CRD RETURN (CAPPED) - N0ZZLE TO - 6.03 RPV-11N Yes ~ UT D X CAP RPV-1IN S8A ' J. P. INSTRUMENTATION LOOP 8 - 4.00 RPV-1tN - Yes ' UT 'A X SAFE END TO PENE. SEAL-RPV-11N $8B J. P. INSTRUMENTATION LOOP A - 4.00 - RPV-11N Mo UT A SAFE END TO PENE. SEAL VER-1RD-1A N2F RECIRC. INLET LOOP A - N0ZZLE - 12.00 07-01 Yes UT D X-TO SAFE END VRR-1RD-1A N2G RECIRC. INLET LOOP A - N0ZZLE- 12.00 07-01 Yes UT D X.

TO SAFE END VRR-1RD-1A N2X RECIRC. INLET LOOP A - N0ZZLE 12.00 07-01 Yes UT F X TO SAFE END VRR-1RD-1A N2J RECIRC. INLET LOOP A - N0ZZLE 12.00 07-01 Yes UT D X-TO SAFE END VRR-1RD-1A N2K RECIRC. INLET LOOP A - N0ZZLE 12.00 07-01 Yes UT D X TO SAFE END VRR-1RD-1A WA15 RECIRC. IntET N2F, LOOP A - 12.00 07-01 Yes UT A X

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NRC GENERIC LETTER 88-01, -

(RPV) INTERGRANULAR STRESS CORROSION CRACKING Pw .

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PRICTED: 06/07/90 'LIfERIDC GENERATING STATION - UNIT 1 & ODOION . CTTACIEENT W1? .- _

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SYSTEN: RPV CLASS: 1 l

i EXAMIIIATION AREA - SIZE . . AUG-1 ' AUGNENTED IGSCC ' EIUNIINE DURING OUTAGE -

EXAMINATION AREA 10 NLBSER DESCRIPTION LE DRAWING REFEREIICE SELECTED EXAM IETN@ CATEGERY 3rd REFEL - 4th REFW L VRR-1RD-15 N2D RECIRC. INLET LOOP S - IIOZZLE 12.00 07-02 Yes UT . D- ~X TO SAFE END VRR-1RD-18 N2E 'RECIRC. INLET LOOP B - N0ZZLE 12.00 07-02 Yes' UT- 'D X-TO SAFE END VRR-1RD-1B WB15 RECIRC. INLET N2A, LOOP B - 12.00 07-02 No - UT A SAFE END TO PIFE VRR-1RD-1B WB16 RECIRC. INLET N28, LOOP 8 - 12.00 07-02. No UT .. A SAFE END TO PIPE

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VRR-1RD-1B WB17 RECIRC. INLET N2C, LOOP 3 - 12.00. 07 No - UT 'A SAFE END TO PIPE VRR-1RD-18 WB18 RECIRC. INLET N2D, LOOP 8 - 12.00 07-02 No UT A SAFE END TO PIPE VRR-1RD-18 WB19 RECIRC. INLET N2E, LOOP S - 12.00- 07-02 No UT . A SAFE END TO PIPE VRR-1RS-1A N1A RECIRC. OUTLET LOOP A - N0ZZLE 28.00 07-01 Yes UT D X TO SAFE END VRR-1RS-1A WA1 RICIRC. OUTLET N1A LOOP A - 28.00 07-01 Yes UT A X SAFE END TO PIPE VRR-1RS-1B N1B RECIRC. OUTLET LOOP 8 - N0ZZLE 28.00 07-02 Yes. UT D X TO SAFE Ele VRR-1RS-18 WB1 RECIRC. OUTLET N18 LOOP 5 - 28.00 07-02 Yes UT A XI SAFE END TO PIPE t

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AUG-1 REPORT - 1 of 2 NRC GENERIC LETTER 88-01, (RPV) INTERGRANULAR STRESS CORPOSION CRACKIIIG

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.AttachmenE A LIMERICK GENERATING STATION, UNIT-1 & COMMON Response'to NRC Letter Dated March 6, 1990,

.Results of:NRC Review of Submittals Responding to NRC Generic letter 88-01, "NRC Position on IGSrc in BWR Austenitic Stain h s Steel Piping" 18 pages System Code (s): 'CS'- Core Spray RCIC - Reactor Core Isolation Cooling

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AUG-1, NRC GENERIC LETTER 88-01,

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. ATTAOWENT "A-2*

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

PAGE: 4 of 18 .-

1 INT [Ry8 m AR STRE$S QRROS!QN RA KINS SYSTEM: RNR - CLASS: 1 _

EXAft! NATION AREA . EXAMINATION AREA SIZE AUG-1 AUGNENTED. IGSCC ~ EXARINE SURING OtnAGE . .c ID. NUN 8FR DESCRIPfl0N M' ~ DRAWING REFERElfCE SELECTED EXAft UETNMP CATEGORY ~ 3rd REF1EL - 4th REFIEL RHA 078 12" PIPE To VALVE 12.00 01 01- No UT A OCA-104-4-2 HV-1F0504 FW52

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01 'Yes UT A X DCA-318-2-1 1F0658 FW4 RMS 068 28"X28"X12" TEE TO 12.00 01 No " UT A DCA-104-3-1 12" PIPE FW1 RHB 069R 12" PIPE TO VALVE- 12.00 01-04 No UT A' DCA-104-3-1 1F0608 FW50 RHB 070A 12" 9IPE TO PIPE 12.00 01-04 No UT A DCA-104-3-1 SW3 RHB 070R 12" VALVE 1F0608 TO 12.00 01-04 No UT A DCA-104-3-2 PIPE FW51 RHB 071R 12" PIPE TO VALVE 12.00 01-04 No UT A DCA-104-3-2 ~MV-1F0508 M2 l RNC 001 12" PIPE TO ELBOW 12.00' 01-07 Yes UT A X

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12" ELBOW TO VALVE .12.00 01-07 Yes- UT A 2 DCA-318-4-1 '1F065C.

FW4 C2XI-1 REPORT - 2 of 2 NRC GENERIC LETTER 88-01, (EQUIP & PIPING) INTERGRANULAft STRESS CORROSION CRACKING

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- PRI;TED5 06/07/90 LIERICK GENERATING ST; TION - LEIIT 11 CDOION LTTAONENT "R-2"y AUG-1, NRC GENERIC LETTER 88-01, PAEE: 5 of 18~._

INTERGRAIEILAR STRESS CORROSION CRACKING SYSTEM: RNR CLASS: 1 EXAMINATION AREA EXAMIIIATION AREA SIZE AUG-1 AUGMENTED IGSCC EXAMINE DURING O'JTAGE ID IILpWER DESCRIPTION' @. DRAWIIIG REFERENCE S$LECTED EXAss sETutD CATEEERY 3rd REREL - 4th REFEL RHD 001 12" PIPE TO EL8OW 12.00 01 No UT A DCA-318-1-1 FW3 RMD 001A 12" PIPE TO PIPE 12.00 01-09 No UT A DCA-318-1-3 FW2 RHD 002 12" EL8OW 70 VALVE 12.00 01-09 No UT A DCA-318-1-1 1F065D FW4 TOTAL RECORDS PRINTED FOR THE CLASS 1 RNR SYSTEM = 27 TOTAL CATEGORY A = 27 TOTAL CATEGORY 0 = 0 TOTAL CATEGORY G = 0 i

i CJG-1 REPORT - 2 of 2 NRC EEMERIC LETTER 88-01 (EQUIP & PIPING) INTERGRAIRJLAR STRESS CORROSICII CRACKING

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PRIDED: 06/07/90' LIIERICK GENERATING STATION - UNIT 18 CIWWION ATTAC5Nett "A-2".

AUG"1, NRC GENERIC LETTER 88-01, PAGE: 9 of 18 '

INTERGRANULAR STRESS rmancIGI CRACKING

. SYSTEM: RR' CLASS: 1' EXAMINATION AREA EXAMINATION AREA .- SIZE AUG-1 AUGNENTED ' IGSCC EXAMINE DuttisG OUTAGE

'ID INDWER DESCRIPTI(W M. DRAWING REFERENCE SELECTED EXMt 8ETN(B CATE p Y 3rd WFtEL - 4 tty EFKL RRA 046 12" PIPE TO EL90W 12.00 07-01 Yes' UT A' X RD-1-AT SWB RRA 047 12" EL90W TO PIPE 12.00 07 .Yes UT A X RD-1-A7

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. _ . . _ __. , . . . _ m , _

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PRI2TED
06/07/90 ' LIMERICK GENERATING STATION - UNIT 1 & CUNION J ATTAONEIIT "A-2*, =

!AUG-1, NRC GENFRIC LETTER 88-01, PREE: to of 18 - ~ '

.INTERGRANULAR STRESS N ION CRACKlWG SYSTEM: RR CLASS: 1 EXAMINATION AREA-- EXAMINATION AREA SI2E ~ AUG-1 AUGNENTED - IGSCC ' EMff8INE DURING OUTAGE ID NLsqBER DESCRIPTION '(NPS) DRAWING REFERENCE SELECTED EXAll MTN@ AT(GCRY 3rd REFEL - 4th REFLEL RRB 012 '28* EL80W TO PtMP '28.00 07-02 No " UT A RS-1-83 1BP201 FwB5 RRB 013 '28" PUMP 1BP201 TO 28.00 07-02 No UT A RD-1-B1 PIPE FWWB6 RRB 016 '28" PIPE TO VALVE 28.00 07-02 No ' UT A RD-1-B1 HV-1F0318 FWWB7 RRB 017 28" VALVE HV-1F031B 28.00 07-02 No UT A RD-1-82 TO ELBOW FWWB8 RRB 018 28" ELBOW TO PIPE -28.00 07-02 No UT A RD-1-B2 SWA RRB 021 28" PIPE TO 28.00 07-02 No UT A RD-1-82 28"x28"x12" TEE SWC RRB 022 28"x28"X12" TEE 70 28.00 07-02 No UT A RD-1-82 28"x22" CROSS FWWB9 RRB 023 28"x12" CROSS TO 22" 22.00 02 No UT A l

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LINERICK GENERATING STATION - UNIT 1 & C05540N ' LTTAONIENT "A-2"

' PRICTED- 06/07/90 AUG-1, NRC GENERIC LETTER 88-01, PAGE: 17 of 18 =

INTERGRANUUtR STRESS CURROSTON CRACKING.

SYSTEMS RWCU CLASS: 3' EXANINATION AREA SIZE - AUG-1 AutNIENTED 'IGSCC EXANINE DURING CUTAGE -

EXAMINATION AREA ID NIAINER DESCRIPTION (NPS) DRAWING REFERENCE SELECTED EXAN SETN00 . CATEGORY . 3rd REFtEL - 4th REFLEL .

Yes VT-2 G X DCC-101-1 PIPING 0.00 DCC-101-1 Yes - VT-2 G X DCC-101-2 PIPING 0.00 DCC-101-2 Yes VT G X DCC-107-2 PIPING 0.00 DCC-102-2 VT-2 G X DCC 103-1 -PIPING 0.00 DCC-103-1. Yes Yes VT G X DCC-104-1 PIPIM 0.00 DCC-104-1 Yes- VT-2 G X ECC-105-1 PIPING 0.00 ECC-105-1 VT G X RW 138 6" VALVE HV-1F040 TO 6.00 05 Yes DCC-103-1-1 PIPE FW1 Yes VT-2 G X RW 139 6" PIPE TO ELBOW 6.00 08-05 DCC-103-1-4A SW1 Yes VT-2 G X RW 140 6" ELBOW TO PIPE 6.00- 08-05 DCC-103-1-4A SW2 TOTAL RECORDS PRINTED FOR THE CU.SS 3 RWCU SYSTEN = 9 TOTAL CATEGORY A = 0 TOTAL CATEGORY D = 0 TOTAL CATEGORY G = 9

' htC GENERIC LETTER 88-01, t"JG-1 REPORT - 2 of 2 INTERGRANULAR STRESS CORROSION CRACKING -

(EQUIP & PIPING)

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PRINTED: 06/07/90 LIE RICK GENERATieG $TA7805 - UNIT 2 . ATYaremmert go AUG-1, NRC EEEERIC LETTER W-01, Pam: 5 of 19 *.

leTEgesamma as STRESS CIMA051W CRACK 15G SYSTEM: RMR CLASS: 1 EMAMinRTION AREA C7AttuRTION AREA SIZE ISOETRIC AUG-1 AUOMENTER IGSCC OUWPluE BURieG OUTAGE ID uupWER DESCRIPTION M DRAutuG utis--- SELECTED y*gt ETHWP CATEGERY 1st REMEL - 2nd W.FEL DCA-416 12" PIPE TO PIPE 12.00 NI-DCA-418-4 Yes UT A FW2 DCA-418 12" EL90W TC PIPE 12.00 XI-DCA-418-4 Yes UT A TW3 DCA-418 12" vmLVE 5 -2F065C 12.00 XI-DCA-418-4 no UT A FW4 TO EL50W DCA-418 SAFE END TO N0ZZLE 12.00 XI-DCA-418-4 Yes UT 8 a M17D (AZ.315 OEG.)

TOTAL RECORDS PRlWTED FOR TME CLASS 1 RM SYSTEM = 34 TOTAL CATEGORY A = 30 TOTAL CATEGORY 8 = 4 l

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