ML20141D229

Safety Evaluation Granting Util Request for Relief from Certain Requirements of Section XI of ASME Code Re Inservice Insp for Second 10-yr Interval

ML20141D229
Person / Time
Site:	Quad Cities
Issue date:	03/31/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141D217	List: ML20141D213 ML20141D229 ML20141D243
References
NUDOCS 8604070451
Download: ML20141D229 (12)

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SAFETY EVALUATION RY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUESTS FOR RELIEF FROM INSERVICE INSPECTION RE0VIREMENTS COMMONWEALTH EDISON COMPANY QUAD CITIES UNITS 1 AND 2 00CVE7 4 HUS. 50-254/265 1.0 INTRODETION Technical Specificati nQ 4.6.f for the Quad Cities Nuclear Power Station Units 1 and 2 states tr.at insetvich e tacitaatior) and tests of AS"E Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(o) except where specific written relief has been granted by the Conmission. Certain requirements of later editions and addenda of Sectiun XI are impractical to perform on oloer plants because of the plants' desion, component geometry, and materia's of constructiofi. Thus, 10 CFR 50.55a(g)(6)(i) authorizes the Contnission to orant relief from those requirements uDon making the necersary findinas.

By letters dhted February 17, 1983, January 9,1985, and February 77, 1985, Cnmmonwealth Edison Coinoany submitted its inservice inspection croaram, revisions, or additional information related to requests for' relief from certain Code reouirements defennined to be impractical to parfom oh the

, Ouad cities Nuclear Power Station Units 1 and 2 during the inscettion -fr.terval.

The progran is baserf on the requirements of the 1980 Edition throuch Winter 1980 Addenda of Section XI of the ASME Code, anj remains in effect ur.til February 18, 1993 and March 10, 1993 for Units 1 and 2, respectively, unless the program is modified or changed prior to the interval end dates. ,

2.0 EVALUATION Requests for relief from the requirements of Section XI which have been determined to be impractical to perform have been reviewed by the Staff's contractor, Science Applications International Corporation. The contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the Technical Evaluation Report (TER) attached (ATTACHMENT 1).

The staff has reviewed the TER and adopts the evaluations and recomenda-tions. A summary of the determinations made by the staff is presented in the -

following tables:

8604070451 860331 PDR ADOCK 05000254 0 PDR

1 TABLE 1

- CLASS 1 COMPONENTS 9

LICEN$EE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF RE* QUEST c

ITEM NO. EXAM. CAT. COMPONFhT EXAMINED METHOD EXAMINATION _ STATUS

Bl.4 B-D Standby Nozzle to Volumetric Mcne Crahtad Liquid vessel control welds and inside radius section b) e I

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TABlf 1 CLASS i COMPCMENTS LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM 09 AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT C@PONENT EXAMINED METHOD EXAMINATION STATUS l 81.11 & B-A Reactor Shell Welds Valueetric Volumetric Granted Bl.12 Vessel Bl.11: of Er,uiva-l Circief'erential lent length Bl.12: of tongi--

Longitudinal tedinal Weld in Upper Shell Area E1.21 & B-A Reactor Bottom Volumetric Mone Granted 81.22 Vessel Head (Technically

• Welds No Relief Required) 7

- B3.100 B-D Reactor Nozzle Inside Volumetric None Cranted I' Vessel RadiusSection I (Standby Liquid Control Nozzle) f . . .

B9.11 B-J Control Pipe Size > Surface and (1974 Edition Granted Rod Drive -4 in. Circim- Volumetric of Code Thru Provided

& Residual ferential Summer 1975 Code-Required Heat. Welds (Unit 1 Addenda) 25% Sample Removal Welds03-517 & System Size is Main-System 10HS-58, and Pressure tained, if Unit 2 Welds Tests Practical, for 03-F11,03-518 Examining Other

. and 10HS-F7) Welds in System,

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& Visual During System Pressure Tests

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TABLE 1 CLASS 1 COMPONENTS (continued)

LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NG. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B9.11 B-J Contain- Pipe Size > Surface and (1974 Edition Granted ment 4 in. Circum- Volumetric of Code Thru Provided Penetra- ferential Welds Summer 1975 Code-tions (See Attach- Addenda) Required ment to Table 1 System 25% Sample for List of Pressure Size is Lines Tests & Maintained, Involved) Volumetric if Practical, of First for Exam-Pressure ining Other Boundary Welds in '

Weld Outside System, and

• Containment Visual During i on Each of System Pres-Pipes Involved sure Tests B9.31 B-J Piping Branch Pipe Surface and (1974 Edition Granted Pressure Connection Volumetric of Code Thru Boundary Welds, Pipe Summer 1975 Size > 4 in. Addenda)

(4 Branch- Visual During to-Pipe System Pressure Welds) Tests and Sur-face of Saddle-to-Pipe Fillet Welds l B12.20 B-L-2 Retircu Pump Visual, Visual Upon Granted lation Casing VT-3 Disassembly for Pump Maintenance

TABLE 1 -

CLASS 1 COMPONENTS (continued)

LICENSEE PROPOSED i

IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B12.40 B-M-2 Valve Valve Body Visual, Visual Upon Granted Exceeding 4 in. VT-3 Disassembly i Pipe Size for Main-tenance I e us e

I i

v __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _

TABLE 1 ATTACl#fENT LINE CR0 Return - 0308 - 4" RHR - 1012A and B-16", 1925-20", 1011-4" Rx Water Cleanup - 1202-6" Core Spray - 1403-10", 1404-10" HPCI - 2305-10" Main Steam - 3001 A, B, C, D-20" Feedwater - 3204A and B-18" i

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TABLE 2 CLASS 2 COMPONENTS 1

LICENSEE PROPOSED IWC-2500-1 IWC-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS C2.21 & C-B Residual C2.21: C2.21: Surface of Granted C2.22 Heat Nozzle-to- Surface & Reinforcing Removal Shell Weld Volumetric Saddle Fillet Heat C2.22: C2.22: Welds & Visual Exchanger Nozzle Volumetric During Systea Inside Pressure Radius Tests Section (2 Nozzles in Each of '

2 Heat Ex- '"

changers '

with Rein-forcement Saddles)

C5.31 C-F Piping Pipe Branch Surface Surface of Granted Pressure Connections Saddle Fillet Boundary > 4 in. Branch Welds and Pipe Size, Visual During Circumfor- System Pres-ential Weld sure Tests (25 Welds for Unit 1 and 20 Welds for Unit 2 Covered by

. Reinforcing Saddles) i

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TABLE 5 PRESSURE TESTS IWA-5000 IWB-5000 IWC-5000 & LICENSEE PROPOSED N SYSTEM OR IWD-5000 TEST PRESSURE ALTERNATIVE RELIEF REQUEST N '

COMPONENT REQUIREMENT TEST PRESSURE STATUS s High IWC-5222(a): System Function Granted Provided Pressure Hydrostatic Test Test Alternative Test Coolant Pressure shall be is at Highest Injection at least 1.10 Times Attainable Pres-Turbine System Pressure P sures Consistent for Systems with sv with Technical Design Temperature Specifications of 200*F or Less, ,

and at least 1.25 Times System Pres- o sure P for Systems '

withD55ignTempera-ture Above 200 F

e e TABLE 6 ULTRASONIC EXAMINATION TECHNIQUE LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST STATUS Calibration Documentation Continued Use of Granted Block Specified in Existing Calibra-Article 4 of tion Block, Which Section V of Lacks Code-Required Code for Documentation, After Ferritic Vessels Demonstration of Greater Than Acoustic Properties 2 in. Thick to be Similar to Those in Reactor Vessel ,

X

12

3.0 CONCLUSION

Based on the review summarized, the staff concludes that relief granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the pipina and component tressure -

boundary and suoport structural integrity, that granting relief where the Code requirements are impractical is authorized by law and will not endanger life or oroperty, or the common defense and security, and is otherwise in the public interest considerina the burden that could result if they were imposed on the facility.

Principal Contributor: George Johnson.

Dated: March 31, 1986.

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