ML20141F235

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Safety Evaluation Supporting Util 830627,840626 & 0814 Requests for Relief from Second 10-yr Inservice Testing Requirements Found Impractical to Perform by Science Applications Intl Corp
ML20141F235
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 02/11/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141F182 List:
References
NUDOCS 8602250461
Download: ML20141F235 (23)
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U f  %'o UNITED STATES NUCLEAR REGULATORY COMMISSICN

, e WASHINGTON. D. C. 20555

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%, *..../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO OPERATION OF ZION NUCLEAR POWER STATION UNIT NOS. 1 AND 2 COMMONWEALTH EDIS0N COMPANY DOCKET NOS: 50-295 AND 50-304 l

INTRODUCTION Technical Specification 4.2 for the Zion Nuclear Power Station Units 1 and 2 states that inservice examination and tests of ASME Code Class 1, 2, and 4 components shall be performed in accordance with Section XI of the.ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CE8 50.55a(g) except where specific written relief has been granted by the Commission.

Certain requirements of later editions and addenda of Section XI are impracti-cal to perform on older plants because of the plants' design, component geometry, and materials of construction. Thus, 10 CFR 50.55a(g)(6)(i) authorizes the Commission to grant relief fron: those requirements upon making the necessary findings.

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By letters dated June 27, 1983, June 26 and August 14, 1984, Commonwealth Edison Company submitted its inservice inspection program, revisions, or additional information related to requests for relief from certain Code require-ments determined to be impractical to perform on the Zion Nuclear Power Stations l Units 1 and 2 during the inspection interval. The program is based on the l requirements of the 1980 Edition through Winter 1981 Addenda of Section XI of j the ASME Code, and remains in effect until December 31, 1993 and September 19, 1994 for Units 1 and 2, respectively, unless the program is modified or changed prior to the interval end dates.

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EVALUATION Requests for relief from the requirements of Section XI which have been determined to be impractical to perform havu been reviewed by the Staf f'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 a'dapts the evaluations and recommenda-tions. A summary of the determinations made by the staff is presented in the following tables:

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1 CONCLUSION "-

For the reasons provided in the attached TER,'the bases and/or alternative examinations or tests proposed by the licensee in the relief request denied in this report have been determined by the staff to be inadequate in providing necessary assurance of the structural integrity of the components involved. Therefore, the licensee must comply with Section XI Code requirements or submit to the staff acceptable bases and alternatives in lieu of those proposed herein. Specifically, in case of the steam r

generator components the licensee implied that performing the test as called for by the Code would put the plant in an unsafe condition. This may be so if the test is performed when the plant is operating. The staff believes, however, that the test can be performed safely during the ,-

time when the reactor vessel examination is being performed and all fuel is out of the vessel.

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 piping and component pressure

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

.ft TABLE 1

' CLASS 1 COMPONENTS LICENSEE ,

PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B3.100 B-D Reactor Nozzle Volumetric Visual Granted Vessel Inside Provided Radius Volumetric Section to Extent Practical is Performed B6.20 & B-G-1 Reactor B6.20: B6.20: Surface and Not Granted l B6.30 Vessel Closure Volumetric Visual (VT-1) l Studs In B6.30: Surface Upon Dis-Place,86.30: and Volu- assembly Closure metric Studs When Removed B3.120 B-D Pressurizer Nozzle Inside Volumetric Visual to Granted Radius Section Extent Practi- Provided cal Volumetric to Extent ,

Practical l is Performed e

B3.110 B-D Pressurizer Nozzle-to- Vol'netric u Volumetric to Granted (Unit 2) Vessel Welds Extent Practi- I cal and Surface B3.140 B-D Steam Nozzle Inside Volumetric Visual Upon Granted Generators Radius Section q Disassembly Provided Volumetric to Extent Practical is Performed

i on TABLE 1 -

' CLASS 1 COMPONENTS (continued)

LICENSEE ,

PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B5.70 B-F Steam Pipe Size > 4 in Volumetric Volumetric Granted Generators Nozzle-to-5afe and Surface to Extent End Butt Welds Practical, Visual (VT-2),

and Surface Pipe Size > 4 in Surface and B9.11 B-J Reactor Examination Granted Coolant Circumferential Volumetric per 1974 Edition System Welds (4 Welds) ASME Code Section XI Through Summer 1975 Addenda and Visual During Pressure Tests I

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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 R.ELIEF REQUEST IlEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B9.11 & B-J Reactor Pipe Size > 4 in Surface and

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Examination Granted B9.17. Coolant B9.11: Volumetric per 1974 Provided System Circumferential Edition ASME Ultrasonic Welds Code Examination 89.12: Section XI 25% Sample Longitudinal Through Summer, Size is Demon-Welds 1975 Addenda, strated to be (Longitudinal Surface, and Impractical Electroslag Visual (VT-2)

Welds and During Pressure Cast-to-Cast Tests Circumferential Welds)

B9.31 B-J Piping Branch Pipe Surface and Examination per Granted Pressure Connection Volumetric 1974 Edition Provided Boundary Welds ASME Code Volumetric Pipe Size > 4 in Section XI to Extent Through Summer Practical 1975 Addenda, is Performed Surface, and Visual (VT-2)

During Pressure ,

Tests 86.180 B-G-1 Reactor Bolts and Studs Volumetric Surface and Granted Coolant Visual (VT-1) )

Pump Upon Disassembly

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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 NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B12.50 B-M-2 Valve Valve Body, Visual, VT-3 Code-Examination Granted Exceeding 4 in. Deferred Until P.ipe Size Maintenance 86.210 B-G-1 Valve Bolts and Studs Volumetric Surface and Granted Visual (VT-1) Only When Upon Dis- Valve is assembly Disassembled I

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' CLASS 2 COMPONENTS 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 C1.10,C1.20& C-A Pressure Pressure Volumetric Surface and Granted C1.30 Vessels Retaining Visual (VT-1)

(See Welds l Attach-l ment I to j Table 2) l C1.10,C1.20& C-A Regenera- Pressure Volumetric Surface and Granted C1.30 tive Heat Retaining Visual (VT-1)

Exchangers Welds C2.21&C2.22 C-B Pressure C2.21: Nozzle- C2.21: Surface C2.21:Volu- Granted Vessels to-Shell(or and Volumetric metric to Extent Head) Weld C2.22: Volu- Practical and C2.22: Mozzle metric Surface Inside Radius C2.22: Visual Section (VT-1) Upon l Disassembly and Visual (VT-2)

During Pressure Tests l r

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,g TABLE 2

CLASS 2 COMPONENTS (continued)

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 C5.30 C-F Piping Pipe Branch Surface Visual (VT-2) Granted Pressure Connections > During Pressure Provided Boundary 4 in. Branch Tests Surface

' Pipe Size Examination (With Welded of Saddle-Reinforcing to-Pipe Saddles) Fillet Weld is Conducted at Code-t Required l

Frequency i

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.gr TABLE 2 ATTACHMENT I

, VESSEL SHELL THICKNESS (INCHES)

Seal Water Return Filter 0.165 to 0.185 Seal Water Heat Exchanger 0.165 to 0.185 Reactor Coolant Filter 0 165 to 0.185 Volume Control Tank 0.218 to 0.250 f

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S S T T N S E E N U 3 O Q P E E M R ' ,

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TABLE 4

  • COMPONENTS SUPPORTS NO RELIEF REQUESTS A

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TABLE 5 i PRESSURE inSTS IWA-5000 IWB-5000 .

IWC;5000 & LICENSEE PROPOSED ~

SYSTEM OR IWD-5000 TEST PRESSURE ALTERNATIVE RELIEF REQUEST s COMPONENT REQUIREMENT TEST PRESSURE STATUS -

Class 2 IWB-5222(a): Visual of Hydro- Granted Only Piping Not System Hydrostatic ltatic Test at for Hydrostatic

, Isolable -Test may be at Mrmal Operating Test at Class 1 4 From Class 1 Test Pressure.Specified Prassure Test Pressure

. Piping (See in Table IWB-5222-1 During Class 1

Attachment for Selected Test Test I to Table 5) Temperature IWC-5222(a):

System Hydrostatic i Test shall be at i Least 1.10 Times System Pressure P for Systems wilhDesign Temperature

of 200*F or Less, i

and at least 1.25 Times System Pressure P forSystemPwith ,.

Design Temperature Above 200* F

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's TABLE 5 f PRESSURE TESTS kcontinued)

LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST PRESSURE STATUS Reactor IWB-5.*?2(a) and Pump Seals Granted

, Coolant IWD-Si23(a): Not Tested and 4

Pump Seals System Hydrostatic Component Cooling (See Attach- Test shall be at Lines to be Tested ment 11 to Least 1.10 Times to 187.5 psi Table 5) System Pressure P for Systems wilhDesignTempera-ture of 200*F or Less, and at least 1.25

, Times 5 stem Pressure P fo Systems with

< D8lignTem Above 200*perature F.

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v 1 e TABLE 5 PRESSURE TESTS (continued)

LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST PRESSURE STATUS Class 1 and IWB-5222(a): Hydrostatic Test Granted 2 Piping Not System Hydrostatic During Tank Testable with Test may be at Test for Some Present Test Pressure Specified Pipe Sections

, Configura- in Table IWB-5222-1 and at Normal tions for Selected Test Operating Pressure

, (See Attach- Temperature for Others ment III to IWC-5222(a):

Table 5) System Hyd ostatic Test shall be at least 1.10 Times

. System Pressure P for Systems wl5hDesign Temperature of 200 F or Less, and at least 1.25 Times System Pressure P forSysteelVwith Design Tem Above 200'perature F ,,

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tll TABLE 5 PRESSURE TESTS (co'n'inued) t LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST PRESSURE STATUS __ _

Various IWD-5223(a): Leakage Test Granted Class 3 System Hydrostatic at Normal Piping Test shall be at Operating Least 1.10 Times Pressure (See Attach-ment IV System Pressure P to Table 5) for Systems with sv Design Temperature of 200*F or less, and at least 1.25 Times System Pressure P for Systems with D$lignTemperature Above 200 F 9

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PRESSURE TESTS (cohtinued)

LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST PRESSURE STATUS Steam IWC-5222(a) and Test at Not Granted Generators IWD-5223(a): Maximum and Attached System Hydrostatic Normal Class 2 and . Test shall be at Operating Class 3 Piping Least 1.10 Times Pressure (See Attach- System Pressure ment V to P for Systems Table 5) wiYhDesignTempera-ture of 200'F or Less, and at least 1.25 l Times System Pressure P for Systems with D$lignTem Above 200*peratureF.

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,,3 TABLE 5 ATTACHMENT I t

ATTACHMENT

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2-7 RCLCV-459 to A0V-VC 8149 A, B, C 2 i 4-1 MOV-RH 8703 to RH 8949 A, B 2 5-2 MOV-SI 8802 to SI 9001 A, B 2 4

MOV-SI 8802 to SI 9001 C, D 2 5-3 MOV-SI 9011B to SI 8949 C, D 2 5-4 MOV-SI 9001A to RH 8949 A, B 2 6-1 MOV-SI 8808C to SI 8948 C 2

! MOV-SI 88388 to SI 8948 B 2 i MOV-SI 88080 to SI 8948 D 2 MOV-SI 8808A to SI 8948 A 2 6-2 MOV-SI 8809A to SI 9001 A, B 2 l . 6-3 MOV-SI 88098 to S1 9001 C, D 2 ,

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  • Refers to c+.tachments to licensee's second interval ISI program letter dated June 27, 1983.

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  • PIPE SECTION CLASS 2-2 RCP 'A' Seals 2 2-3 RCP 'B' Seals 2 2-4 RCP 'C' Seals 2 2-5 RCP 'D' Seals 2 13-1 CC 9495A to RCP 'A' 3 13-2 CC 9495B to RCP 'B' 3 13-3 CC 9495C to RCP 'C' 3 13-4 CC 94950 to RCP 'D' 3
  • Refers to attachments to licensee's second interval ISI program letter dated June 27, 1983.

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s TABLE 5 ATTACHMENT II'I ATTACHMENT

  • PIPE SECTION CLASS 1-1 FCV-CS01 to CS 0018 2 1-2 FCV-CS02'to CS 0023 2 1-3 FCV-CS03 to CS 0028- 2 2-8 VC 8152, 8153 to IWO 187 2 3-2 VC-LCV 1120, E to VC 8546 2 3-6 MOV-VC 8110 to VC 84798 2 3-7 VC B413 to VC 8101 2 5-5 MOV-SI 8806 to SI 8926 2 4 5-6 A0V-SI 8883 to SI 8912 2 6-2 MOV-SI 8809A, B to SI 8957.A, B 1,2 6-4 MOV-SI 8812A to SI 8958 2 6-5 MOV-SI 8812A to MOV-SI 8812 B 2 14-55 , SS-0015 to XCV-SS-427 2 14-74-1 55-0015 to XCV-SS-427 2 Refers to attachments to licensee's second interval ISI program letter ,
dated June 27, 1983. , ..,

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TABLE 5 ATTACHMENT IV' ATTAC MENT

  • PIPE SECTION (CLASS 3) 3-5 FCV-VC0111A to VC8429 7-1 MOV-FWOO57 to FWOO69 MOV-FW0056 to FW0069 '

MOV-FWOO55 to FW0068 MOV-FW0054 to FWOO68 7-3 MOV-FW0053 to FWOO67 MOV-FWOOS2 to FWOO67 7-4 MOV-FWOO51 to FWOO66 MOV-FWOO50 to FWOO66 8-1 SW0001 to Pump SWOO3 SW0004 to Pump SWOO2 SWOOO7 to Pump SW001 9-66 Line CC032 Line CC003 Line CC001 Line CC012 9-67 Line CC032-Line CC055 "

  • Line CC056 Line CC057 Line CC012 9-523 Line CC032 .

Line CC055 Line CC056 ' i Line CC057 Line CC012 r

TABLE 5 ATTACHMENT IV (continued)

ATTACHMENT

  • PIPE SECTION (CLASS 3) l 10-1 Boric Acid Transfer Pumps -

12-1 CC-0117 to CC-9441 12-2 CC-0006 to CC-9454

  • Refers ta attachments to licensee's second interval ISI program letter dated June 27, 1983.

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TABLE 5 -

ATTACHMENT V ATTACHMENT

  • PIPE SECTION CLASS ,

11-20 Main Steam 2 11-20 Auxiliary Steam 2, 3 11-45-1 Blowdown (to ist Isolation)' 2 11-22 Feedwater (to ist Isolation) 2

  • Refers to attachments to licensee's second interval ISI program letter dated June 27, 1933.

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