IR 05000353/1987009

Insp Rept 50-353/87-09 on 870601-05.No Violations Noted. Major Areas Inspected:Welding & Insp of CRD Insert & Withdrawal Lines,Assembly of Recirculation Pump & Review of HPCI Pump & Spent Fuel HX Document Packages

ML20235V503
Person / Time
Site:	Limerick
Issue date:	07/13/1987
From:	Kaplan H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20235V486	List: IR 05000353/1987009 ML20235V482
References
50-353-87-09, 50-353-87-9, NUDOCS 8707230198
Download: ML20235V503 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-09 Docket N l License N CPPR-107 Category A l l

Philadelphia Electric Company

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Licensee:

2301 Market Street Philadelphia, PA 19101 ,

Facility Name: Limerick Nuclear Generating Station, Unit 2 Inspection At: Limerick, PA Inspection Conducted: June 1-5, 1987 Inspectors: N, k /(ct/ derm 7 - 9- P ~/

H. J. Ka$1an, Lsad Reactor Engineer date Materials & Process Section, EB, DRS Approved :c E4M-Chief Materials &

7/3/ff7

' dite r J.Process R. Strosnith@

Secticn, EB, DRS Inspection Summary: A routine unannounced inspection was conducted of activities related to the welding and inspection of the Control Rod Drive (CRD) Insert and Withdrawal lines, assembly of the Recirculation Pump, review of the High Pressure Coolant Injection (HPCI) pump and Spent Fuel Heat Exchanger document packages, '

and a traceability search of stock item Results: No violations were identified.

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8707230198 870715 PDR 0 ADOCK 05000353 PDR

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DETAILS 1.0 Persons Contacted ,

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1.1 Philadelphia Electric Company I D. A. DiPaolo, Quality Assurance Branch Head C. Meck, Quality Assurance Group Leader J. M. Corcoran, Manager Quality Assurance

, U.S. Nuclear Regulatory Commission i

R. A. Gramm, Resident Inspector J. E. Kaucher, Resident Inspector 2.0 Inspection Purpose and Scope The purpose of this inspection was to observe the activities involving welding of the control rod drive (CRD) insert and withdrawal lines, and assembly of the reactor coolant pump; review document packages covering the HPCI pump and spent fuel heat exchangers; and perform a traceability search of stock item .0 Control Rod Drive (CRD) Insert & Withdrawal Line Installation The inspector witnessed the automatic Tungsten Inert Gas (TIG) welding of one of numerous socket joint welds in the CRD Insert and Withdrawal sys-tem. Welding and QA activities were performed by Bechtel. The subject joint weld was performed in accordance with Bechtel Welding Procedure P8-T-Ag-I-0-1 Rev. I as qualified by PQR 636. The inspector reviewed these documents and found them to comply with ASME I Bead placement for each layer was controlled by the welding operator after the weld was al-lowed to cool below 250 F with the aid of an air hose. The pipe material was identified as 3/4" Sch 80, SA-312 type 304 L, heat No. 467059. The inspector verified this by review of the mill test report. The filler material used was .030" dia. ER 308L wire as indicated on the Withdrawal Authorization record dated June 4, 1987. The inspector visually examined the final layer of the subject weld and found it to be free of surface imperfections. The inspector also witnessed liquid penetrant inspection of four previously completed welds located in lines SP-DCP-102, 106, 110 and 114 in accordance with procedure PT(SR)-ASME III/XI Rev. 5. These welds were found to be free of penetrant indication Qualification and certification records for the welding operator and the Q.C. Inspector were reviewed and found to be satisfactory. Welding and inspection data were recorded on Process Sheet WR _ _ _ _ _ _ _ - _ _ _ _ _

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4.0 Reactor Coolant Pump Installation The inspector witnessed the final inspection of the installed internals prior to setting the cover on the Loop B Reactor Coolant Pump. The opera-tion was performed in accordance with Construction Procedure CP-M-1 and documented in Work Package MRP-2BB-201-7. Inspection was performed by a Bechtel QC inspector in the presence of the Authorized Inspector and the manufacturer's (Bryon Jackson) representative. Checks were made for cleanliness and general appearance of the exposed ground surfaces, l including boh noles, after the surfaces had been thoroughly cleaned with '

acetone. Dimensional checks had been performed prior to the inspector's arriva Except for minor surface imperfections and a finely polished groove (approx, 5" long x 1/16" deep x 1" wide) on the side ring of the hydrostatic bearit.; journal no anamolies were noted. The inspector was informed that the groove was introduced in the shop for balancing pur-pose Lowering of the cover on to the pump case was performed without difficult The inspector observed that the bolts to be instd led for connecting the motor drive mount to the pump casing were identified as SA-540-Typ B23 CL 4 from heat Number 66500 .0 HPCI Pump The inspector reviewed the documentation package for HPCI pumps S/N-701-S-0833/35 designated for Units I and II. The pumps were manu-factured by Bryon Jackson in 1972 in accordance with Class 2 requirements of the Standard Code for Pumps and Valves for Nuclear Power (1968) and March 1970 Addenda as specified in GE specification 21A9243. The in-spector questioned two items in the package: (1) Deviation Disposition Request (DDR) - # 6014 and (2) filler metal test report DDR - # 6014 approved a deviation to an approved Atlas Foundry Procedure #

720-2 which required that the carbon steel castings (ASTM A 216 Gr WCB) be held for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / inch of thickness when heating to the normalizing tempera-ture of 1700 F. Instead the top and bottom casings for Unit I and the top casing for Unit 2 were only held for 1/2 hour /in of thicknes approved the subject DDR apparently on the basis of acceptable mechanical properties (T.S, Y.S, R.A, Elong, and impact) as determined by testing a test coupon conforming to ASTM A 370*. The nspector questioned the validity of the test results, particularly the impact results, since 1/2 hour /in of thickness is considered marginal from the standpoint of pro-viding suf ficent " soaking" time at temperature for the subject casting One (1) hour /in of thickness is considered good standard industry practic In order to determine the validity of the test results the inspector requested that information be provided to show that the test coupon was commensurate with the size of the actual casting. The licensee provided a drawing which showed the maximum thickness of the final machined casting to be 1.876" which is less than the minimum thickness (2.00") specified for a separate test coupon in ASTM A 370, a reference specification in A 216. The usa cf a separate coupon is considered to be

• Specification for Mechanical Testing of Steel Product .

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4 i a conservative assumptio The licensee's resnonse satisfied the inspector's concern in regard to the test coupon and the reported test value j The inspector questioned the test reports of two lots of E7018 filler metal furnished by Atlas Foundry because of the omission of heat treatment information. The two lots of electrodes were presumably used in the repair of the castings. The' licensee responded that since the Pump and Valve Code did not specifically address the issue, the contractual re-quirement for weld metal testing was specified in Paragraph 4.3.2.2 of GE specification 21A9243 which stated that " welding procedures must be quali-fied by impact testing of weld and heat affected zones". Ir. this regard the licensee presented Atlas Foundry's weld procedure specification A 720C and qualification record dated April 1971 that satisfied the requirements of GE specification 21A9243. The qualification record showed acceptable tensile properties and satisfactory impact values at +10 F after subjecting the weld test coupon to a 1700 F normalize and 1250 F post weld heat treatment. The inspector concluded that the castings were weld repaired in accordance with good practice on the basis of the fol-lowin Filler metal test reports showed that the two lots of E7018 electrodes exhibited good weldability, i.e., they were capable of produc-ing reasonably good properties when welded properl The foundry's procedure qualification record results showed that given an electrode of '

good weldability, the weld procedure was capable of producing acceptable properties meeting design requirements after the test coupon was subjected to the foundry's post heat treatment cycle of 1700 F normalize and 1250 F temper. It is noted that the aforementioned sequence consisting of weld repair followed by normalize and temper is in agreement with Atlas Heat Treat Procedure #720-2 (previously mentioned) which required major weld repairs to be performed prior to heat treatmen The above informa-tion satisfied the inspector's question concerning filler metal test report .0 Spent Fuel Heat Exchangers The inspector reviewed the document packages for three spent fuel ex-changers identified as 8031-M14BCF-5-1, F-6-1, and F-4-1. These com-ponents were manufactured by Struthers Wells in accordance with ASME III Class-3. The pressure boundary materials were carbon steel (SA-106 Gr B and SA-516 Gr 70) and stainless steel (SA-182-TYP 304L). The tubes were SA-249 TYP 304 Certified test reports for these materials were reviewed by the inspector and were found to conform to the designated material specifications. The inspector also reviewed Struthers Wells weld pro-cedures used in the fabrication of the subject components. These were found to be in accordance with ASME IX and compatible with the specified material ;

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1 7.0 Traceability of Stock Items The inspecto- lected five safety related items in the warehouse to verify matern traceability. These items were: 3/4" A106 Gr C valves, 2" A194-GR.2H nuLs, 2 1/2" x 2" A403-TYP304L reducers, 3/8" dia x 2 1/4" length A325 bolts and 2/8" dia x 2 1/2" length A 325 bolts. All items were found to be traceable to mill certifications or certificates'of complianc .0 Quality Assurance Quality Assurance participation by Bechtel and GE personnel was evident in the CRD insert and withdrawal line welding and the recirculation pump 4 assembly.- A PECo QA audit was in progress at the time of the inspectio .0 Exit Interview

. An exit interview was held on June E,1987 with members of the licensee's staff as denoted in Paragraph 1, The inspector discussed the scope and findings of this inspection, No violations or unacceptable conditions were identified. At no time during this inspection was written material provided to the licensee by the inspecto l

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