ML20093G362

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Addresses Issues Raised by NRC & Inel Personnel During 950925 Conference Call
ML20093G362
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 10/05/1995
From: Mccollum W
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510190033
Download: ML20093G362 (39)
v • d • e


Text

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DukePow Coritpany Wttua R. Mexity, k

. Catanha Nuclear Gercution Department sice President 4300 ConcwdRoad 4 (803)8313;!00 Office

' ' Ywk, SC545 l (803)33/41%Ru DUKEPOWER October 5,' 1995 -

'U.S. Nuclear Regulatory Commission Attention: Document Control Desk i Washington, D.C. 20555

Subject:

Catawba Nuclear Station, Unit 2 I Docket No. 50-414 i Request for Relief 95-04 Submission of AdditionalInformation Gentlemen:

On September 25,1995, a conference call was held among representatives of Duke Power l Company, NRC personnel, and Idaho National Engineering Laboratory (INEL) personnel  !

concerning the subject relief request. Catawba is submitting this letter to address issues that were raised by NRC and INEL personnel during the call. Specifically, each issue, and our associated response, is contained in the following paragraphs:

The original relief request was submitted pursuant to 10 CFR 50.55a(f)(6)(1) 1.

(impracticality of conformance with code requirements). The relief request should more appropriately have been submitted pursuant to 10 CFR 50.55a(s)(3)(i) (proposed alternative that provides an acceptable level of

quality and safety) or 10 CFR 50.55a(a)(3)(ll) (hardship or difficulty without a compensating increase in quality and safety).

lA I . Response: By copy of this letter, Catawba is hereby modifying its original submittal l dated July 25,1995, to submit Request for Relief Number 95-04 pursuant

, to 10 CFR 50.55a(a)(3)(i) and (ii).

2. The NRC and INEL personnel indicated in the conference call that they
' - would li,ke to obtain a better understanding concerning the details of both the hydrostatic test and the system leakage test. Also desired was a

. quantification of the burden to be avoided by not having to perform the  ;

hydrostatic test.:

1 W F. "! 7 /

9510190033 951005 3 I

=== =r*v ai PDR ADOCK 05000414 1

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Page 2 :

October 5,1995 -

Response: - The purpose of the Code-required hydrostatic test (pressure test) is to assure system integrity, The system is pressurized to normal operating pressure and temperature and a visual examination is performed on the pressurized piping. This is accomplished via inspectors walking down the

. system looking for leakage. This test is performed once every ten years in -

order to satisfy ASME Section XI hydrostatic test requirements.

The 10 CFR 50 Appendix J test required by Catawba Technical $

Specifications, which also assures system integrity, is performed every .

refueling outage. Leakage is quantified by means of flow meters or by - t measuring the reduction in NW surge chamber level. The leakage test is ,

performed more frequently than the ASME Section XI pressure test.

Refer to Attachments 1 and'2 for a copy of the governing procedure for the ASME Section XI pressure test and the system leakage test, respectively. 1 (Due to the thickness of the entire system leakage test procedure, only a sample enclosure from this procedure for one valve is provided.) j i

Regarding the quantification of the burden to be avoided by not having to )

perform the ASME Section XI pressure test, this quantification can be i expressed in terms of both person-hour and dose savings. The pressure l test requires approximately 35 separate tests for each unit which take l approximately 60 minutes each. Each separate test requires the presence of one or two inspectors to look for leakage. Hence, approximately 35 to 70 person-hours could be alleviated by not having to conduct the pressure )

test. In addition, this test requires support from both plant Operations and j

Radiation Protection personnel. Radiological dose rates in the areas where the pressure test is conducted range from 2mR/hr to 20mR/hr (general area dose rates). Hence, dose savings range from a minimtim of 70mR to a .l l maximum of 1400mR (based on general area dose rates) if the pressure test did not have to be performed.
3. State the basis for the conclusion that the system leakage test will be an j acceptable alternative to the ASME Section XI pressure test.

- Response: As indicated above, the ASME Section XI pressure test only determines

. whether or not a particular section of NW system piping is leaking. It makes no' attempt to quantify observed leakage. Conversely, the system t i

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Document Control Desk Page 3 October 5,1995 leakage test performed to satisfy 10 CFR 50 Appendix J and technical specification requirements quantifies overall system leakage and ensures that the system can perform its required function. For the NW system to be considered operable, it must pass the system leakage test acceptance criteria. It is Catawba's position that performance of the ASME Section XI pressure test would result in a burden from both a personnel resource and dose perspective with no corresponding increase in the overall level of quality and safety of the NW system.

If you have any questions peaaining to this material, please call L.J. Rudy at (803) 831-3084.

Very truly yours, i

1 W.R. McCollum l

LJR/s Attachments xc (with attachments):

S.D. Ebneter, Regional Administrator Region II R.J. Freudenberger, Senior Resident Inspector R.E. Martin, Senior Project Manager '

ONRR 4

, :t .f-Document Control Desk Page 4 j

. October 5,1995  ;

4 bxc (with attachments): i L.J. Rudy Z.L. Taylor .;

J.C. Bigham l T.E. Hawkins l J.O. Barbour i NCMPA-1

~

NCEMC PMPA SREC

' Document Control File 801.01 Group File 801.01 l f

ELL-EC050 A

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ATTACHMENT 1 PROCEDURE FOR ASME SECTION XI HYDROSTATIC PRESSURE TEST 1

d a

I MP/0/A/7650/088 p Retype # .l_ l

Page 1 of 7

! DUKE POWER COMPANY CATAWBA NUCLEAR STATION CONTROLLING PROCEDURE FOR SYSTEM PRESSURE TESTING OF ASME AND ANSI PIPING SYSTEMS AND AShE SECTION XI SUITABILITY EVALUATION l.0 PURPOSE i

The purpose of this procedure is to provide a means of performing and documenting pressure tests 1 4

where a hydrotest or pneumatic test is act required or where periodic inservice inspection (ISI) is l required by ASME Section XI and Plant Technical Specifications. This procedure is also to provide guidelines and document completion of suitability of replacements and repairs required by ASME l Section XI.

2.0 REFERENCES

2.1 Source Documents i

2.1.1 ASME Code,Section XI,1980 through Winter Addenda of 1981 2.1.2 ANSI B31.1,1973 Edition.

l 2.1.3 CNS-1206.0002-1002, Specification for the Procurement of Power Piping Systems

. Materials and Components. l 2.1.4 Duke Power ASME Section XI Manual.

l

2.1.5 MP/0/A/7650/62, Controlling Procedure For Pressure Testing Of Class A, B, & C Piping Systems. l 2.1.6 CNS Directive 3.3.16, Boric Acid Corrosion On Carbon Steel Piping.

2.1.7 Technical Specification 4.0.2,4.0.3 and 4.0.5 2.2 Applicable QA Procedures 2.2.1 QA Procedure, L-15, ISI Visual Examination, VT-2. l 2.2.2 QA A-2 (QA Inspection Requirements for QA Conditions 2,3, and 4.)

3.0 PERSONNEL REOUIREMENTS 3.1 Refer to Work Request Section III. k\

3.2 ETQS Task No. MMM-5008 YO  !

4.0 SAFETY CONSIDERATIONS '

l 1

4.1 Equipment Clearance and Isolation l

None

C. .

MP/0/A/7650/088

[OR INFORMATION ONh i ,

4.2 Radiation Protection Consideration if applicable, refer to Radiation Work Permit for Radiation Protection requirements.

- 4.3 Special Safety Considerations  !

4.3.1 Use safety belts and other personal safety equipment necessary to perform job in a i safe manner. I I

4.3.2 Piping and equipment could be a potential slipping hazard due to leakage. )

l 4.3.3 Piping in area could be HOT. ,

l 5.0 UNIT STATUS Prior to beginning work, refer to Work Order,Section II for clearance to begin work.

6.0 PREREOUISITES 6.1 Verify Working Copy and Control Copy of this procedure have been compared and the I Working Copy is current. l HOLD: Personnel sign off Cover Sheet and Data Sheet Enclosure 13.1, Section A. l 6.2 Reverify Working Copy against Control Copy of procedure every 14 days or after procedure has been inactive until work is completed.  !

HOLD: Personnel sign off Data Sheet Enclosure 13.1, Section A. .

)

i 7.0 REPAIR PARTS None l

l 8.0 SPECIAL TOOLS  !

1 8.1 Flashlight  !

8.2 Inspection Mirror 8.3 Gloves 8.4 Hearing Protection 8.5 Face Shield l

8.6 Arm Pietectors l

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i MP/0/A/7650/088 FOR INFORMATION ONLYRetyPe # l-Page 3 of 7

. 9.0 ACCEM'ANCE REOUIREMENTS 9.1 Leakage is e acceptable in piping or welds being inspected.

j 9.2 - Leakage at mechanical joints is to be evaluated by Operations Personnel.

10.0 INTERFERENCE ITEMS None l 11.0 PROCEDURE t

11.1 Crew Changes l

11.1.1 Prior to crew change, sign off last step of procedure completed.

i HOLD: Maint. Rep. sign off Data Sheet Enclosure 13.1, Section C.

I j 11.2 Definitions

. l 11.2.1 Systan IAnkage Test - a test conducted on Class A piping and components at j  ;

i nonunal operating pressure and temperature. (ao hold thne is required after  ;

4 attaining tesaperature and pressure.) l l l 11.2.2 Systeen F=edamal Test - a test conducted to verify operability in systems (or components) a required to operate during normal plant operation while under i system operating pressure. (a ten udmute bold thne is required after attaining

! operating pressusw.)

i . 11.2.3 Systeen Inservice Test - a test conducted to perform visual ===la=*ian while the l system is in service at operating pressure. (no hold thne is required provided the systeun has been in service for at least four hours.)

i a 11.2.4 Systen Hydrostatic Test - a test conducted at a pressure above nominal operating j
pressure.(Refer to MP/0/A/7650/62, System Testing of Class A, B, and C Piping I i Systems.)

> 11.2.5 Systems Pm-made Test - a test similar to a hydrotest normally conducted on air or gas systems at a pressure above nominal operating pressure using air or gas as the

pressurizing medium. (Refer to MP/0/A/7650/62) l 11.2.6 Initial Service Imak Test - a test performed on a Class E, F or H-QA 3 systems at nominal operating pressure. (a tem ad=* bold tiene is required.)

11.3 Applications for Normal Repair, Replaramante, and Maintaanara (Refer to Enclosures 13.2, 13.3 and 13.4) l

N(yrE
CE Representative shall complete step 11.5.1 for any repair or replacement
applications.
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MP/0/A/7650/088 EOR INFORMATION ONLY. '

Page 4 of 7 11.3.1 ASME Class 1 (Duke Class A) 11.3.1.1 A system leakage test shall be conducted following opening and reciosing of a component in the system (i.e., refueling) after pressurization to nominal operating pressure, 11.3.1.2 For disassembly and reassembly of mechanical joints, a system leakage test shall be conducted aAer pressurization to nominal operating pressure.

11.3.2 ASME Class 2 (Duke Class B) 11.3.2.1 For disassembly and reassembly of mechanical joints which does e involve replacement of any pressure retaining components. (no pressure testing is required after . - - - "y.

I1.3.2.2 For disassembly and r**uembly of mechanical joints, which involves replacement of any pressure retaining components, a system functional test shall be conducted to verify operability while under system pressure. (a ten mamde hold thne is required.) ,

11.3.3 ASME Class 3 (Duke Class C) d NOTE: Class C test requires verification.by OPS Rep. to verify system

conditions.

j s 11.3.3.1 For disassembly and reassembly of mechanical Joints which does a J

involve replacement of any pressure retaining components. (no pnesure testing is required after r====Wy.)

j 11.3.3.2 For diamanamhly and reassembly of mechanical joints, which i involves replacement of any pressure retaining components, the j following test shall be performed aAer reassembly:

j a) For systems g required to operate during normal plant

! operation, a system functional test shall be conducted to verify

, operability while under system pressure.(a ten me=de bold

! thne is required.)

l b) For systems required to operate during normal plant operation, a system inservice test shall be conducted. (no hold thee required provided the systeen has been in v - -t for 4 bours.)

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! 11.3.4 ANSI R31.1 (Duke Class E) l

! 11.3.4.1 If it is deemed practical to perform a hydrotest or a pneumatic test,

the forms of MP/0/A/7650/62 shall be used, with references to the ANII marked "N/A".

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i MP/0/A/7650/088 Retype # .2.

  • FOR INFORMATION ONi.Y Page 5 of 7 1

11.3.4.2 If these tests are deemed impractical, an initial service leak test at i normal operating pressure is required after repair by welding. (a 10 minute bold time is r4.:.-M prior to inspection of uninsulated l systems.) For insulated systems, contact the CE Representative.

11.3.5 ANSI B31.1 (Duke Class F) 11.3.5.1 If it is deemed practical to perform a hydrotest or a pneumatic test, the forms of MP/0/A/7650/62 shall be used, with references to the ANII marked "N/A".

11.3.5.2 If these tests are deemed impractical, an initial service leak test at normal operating pressure is required after repair by welding.- (a 10 mines hold thee is requimd prior to inspection of uninsulated ,

sytems.) For insulated systems, contact the CE Representative. l 11.3.6 Fire Protection For repairs on piping > 1" NPS a pressure test in accordance with MP/0/An650/52 is required. For repairs on piping < 1" an initial service leak test is required.(a 10 l ad=* bold time is required prior to inspection of ==in=da*M systens.) For l insulated systems, contact the CE Representative. l

. I1.4 Applications-Inservice inspection (ISI) l

)

This procedure and enclosures shall be used to perform and Mmant all laservice j Inspection required by the ISI program for piping and components.

11.5 Inspection and Evaluation of Components /or Piping

NOTE
Any repair by welding on piping or component > 1" NPS for Class A, B, or C l
piping or Components will require a pressure test in accordance with MP/0/A/7650/62, Controlling Procedure for pressure testing of Class A, B, and C Piping Systems. l l 11.5.1 Complete the ASME Suitability Evaluation (refer to Enclosure 13.2) and document information on Section V of the Work Order.

NOTE #1: If pressure boundary components require replacement or repair, an ASME suitability evaluation by the CE Group is required prior to final approval of the Work Order. This shall be performed prior to turning over a Work Order to another group for testing.

l NOTE #2: ASME suitability evaluation may be required even if a leakage test is 301

performed.

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, NOTE #3: ASME suitability evaluation is required if a hydrotest is performed in lieu of an inservice or functional test.

l HOLD: CE Rep. sign off Data Sheet, Enclosure 13.1, Section B.

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MP/0/A/7650/088 Retype # 1.

FOR INFORMATlON ONLY -

Page 6 of 7 11.5.2 Complete the information steps on description of test on Enclosure 13.1. (Refer to Sections 11.2 and 11.3)

HOLD: Personnel Initiating Test sign off Data Sheet Enclosure 13.1, Section B.

11.5.3 Verify valve line up for section described in step 11.5.2 is pressurized. (performed from performance or operations procedures.)  ;

HOLD: Ops Rep sign off Data Sheet Enclosure 13.1, Section B.

!!.5.4 Verify normal operating conditions for piping joints to be inspected as specified in i step 11.5.2.

HOLD: Ops Rep. sign off Data Sheet Enclosure 13.1, Section B.

11.5.5 Inspect the components and/or piping for evidence of leakage.

NOTE #1: Steps 11.5.3 and 11.5.4 shall be signed off prior to step 11.5.5.

NOTE #2: QA condition 1 pressurized piping shall be performed by VT-2 certified QA Rep.

NOTE #3: QA condition 2, 3, and 4 piping can be performed by NPD or CMD personnel, i HOLD: QA Rep./or Maint Rep. sign off Data Sheet Enclosure 13.1, Section B.

i1.5.6 If evidence of leakage is found the following actions are required:

NOTE: Leakage of welded cannacelaas are -- --C':

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e Imks at mechanical joints are to be evaluated by operations personnel.

{

l e Evaluation shall be dew.

HOLD: Ops Rep. sign off Data Sheet, Enclosure 13.1, Section B.

j 11.5.7 System was under normal operating conditions while ernminations for leakage was being performed.

HOLD: Ops Rep, sign off Data Sheet, Enclosure 13.1, Section B.

I1.5.8 Inspect all areas of leakage identified in step 11.5.6 per Station Directive 3.3.16 (Boric Acid Corrosion of Carbon Steel Components)

HOLD: Maint. Rep. sign off Data Sheet Enclosure 13.1, Section B.

! 11.5.9 Review procedure Data Sheets to verify all sign offs have been properly filled in i and information properly documented.

HOLD: Supervisor /or Designee sign off Data Sheet Enclosure 13.1, Section B.

" '0'A'

~ RlNFORMATION ONLN,Y, f o#h 11.5.10 ANII (if applicable) and QA Reviews completed.

HOLD. ANII and/or QA Rep, sign off Data Sheet Enclosure 13.1, Section B.

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12.0 RESTORATION l

None 13.0 ENCLOSURES .

13.1 Data Sheets i 13.2 Guidelines for Suitability Evaluation 13.3 Definitions of Repair and Replace 13.4 Chart of Pressure Test Requirements 1

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Enclosure 13.1 MP/0/A/7650/088

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  • She t

, , ' 'os, FOR INFORMATION ONQ'o, "' W ISI ID Controlling Procedure For System Pressure Testing of ASME and ANSI '

A. PREREOUISITES 6.1 The Working Copy has been compared with the Control Copy of this procedure and the procedure is correct and current.

Verifier Date Time 6.2 The Working Copy has been compared with the Control Copy of procedure every 14 days until work is complete or after procedure has been inactive.

Verifier Date / Time i

1 A

B. PROCEDURE CHECKS / DATA i1.5.1 ASME suitability evaluation has been performed and information documented in Section V of the Work Order.

CE Rep. Date 1

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Enclosure 13.1 MP/0/A/7650/088 Data Sheet Retype # 7_ l Page 2 of 5 0#

FOR INFORMATION ONLY *SIID I

11.5.2 Description of test (Refer to Sections 11.2 and 11.3)

1. Type of pressure test and holding time requirements:

System Iaakage Test (Class A) no hold time is required after attaining nominal operating pressure and temperature.

Systeen Functional Test (Class B & C ) a ten minute hold time is required after attaining system operating pressum.

Systeen I_.1s Test (Class C ) no hold time is required provided -

the system has been in service for at least four hours.

Initial Service IAnk Test (Class E,F & H-QA 3) a ten minute hold time is required.

Class C test requires notification of OPS Representative to verify system operability. (Refer to Section 11.3.3)

Is the section to be tested required to be in operation (i.e. in service) while the plant is in normal operation?

NOTE: This is not an operaility determination. ' Itis is to determine the proper test to be performed per IAW ASME Section XI.

Required Not Required SRO or OPS Eng. Staff

2. Code or Standard
3. Piping Class
4. Buried / Embedded / Insulated
5. QA Required Yes No
6. ANII notified. (QA Condition 1 only)

NOTE: If ANII can not be reached, contact QA Technical Support.

7. Sketch or describe section to be tested using applicable methods (weld numbers, valve numbers, flange numbers, flow \or isometric drawings) i NOTE: All drawings shall be attached to the data sheet.

9

Enclosure 13.1 MP/0/A/7650/088

  • " Retype # 1 ag. Ior*5 FOR INFORMATION ONLY,o, ISI ID
8. Remarks or Instructions concerning test:

2 Personnel Initiating Test Date j l ,

11.5.3 Valve line up is pressurized Ops Rep. Date/ Time l 11.5.4 System has been under operating conditions for the period of time requirements identified on Data Sheet, Step 11.5.2.

System Pressure psig Pressure Inst. No. or Control Room computer point I.D. No.

Ops. Rep. Date 7

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Enclosure 13.1 MP/0/An650/088 Data Sheet Retype # _7_

Page 4 of 5 FOR INFORMATlON ONLY Wo

  • ISIID l 11.5.5 Inspection of Components /and or piping
l. Section(s) of piping or components described in step 11.5.2 have been
examined for leakage.

. Yes No List variation

2. Optical Aids (type)
3. Test Results:

Acceptable Rejectable (any thru wall or weld leakage is rejected.)

Leakage at mechanical joints or valve

.' List any leakage noted l

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! (QA condition I test} QA Rep. VT-2 level Date l

{QA condition 2,3 o r 4 test) NPD or CMD Rep. Date 11.5.6 Operations evaluation of leakage noted in step 11.5.5 acceptable rejectable 4 If applicable, Boric Acid leakage reported per Station Directive 3.3.16, Boric Acid Corrosion of Carbon Steel Components.

Remarks Ops Rep. Date 11.5.7 Verification that system was under normal operating condition through out examinations.

Ops Rep. Date

Enclosure 13.1 MP/0/A/7650/088 Retype # _2.

Na*g'e oE5 FOR INFORMATION ONLY,g, ISI ID 11.5.8 Boric Acid leakage reported per Station Directive 3.3.16, (Boric Acid Corrosion of Carbon Steel Components.)

- WO No. (if applicable)

Maint. Rep. Date 11.5.9 Procedure completion review has been performed prior to final QA and ANII review.

Supervisor /or Designee Date 11.5.10 ANII Review (QA condition 1) Date 1

Final QA Review Date l C. Crew Changes Step 11,1.1 Maint. Reo. Procedure Step Completed Date / Time Remarks:

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Enclosure 13.3 MP/0/A/7650/088

, Guidelines for Suitability Evaluation FOR INFORMATION ONLY Retype # .2.

Page 1 of 2 A. The replacement or repair of the following DgJg1 require an ASME Section XI suitability evaluation by CE.

l. Piping, tubing, and piping components which are 1 inch and less in nominal pipe size.
2. Any non-pressure retaining parts.
3. s: 1/2" thickness packing, gaskets, 0-rings, bearings bushing, springs, and spacer rings
4. Leak repair injection sealants, structural pump and valve internals unless otherwise specified, stems, valve seats, rubber valve diaphrams, trim shafts, mechanical pump seals, wear plates, impellers, spray nozzles, orifice plates, instruments, electrical conducting and insulating materials.

B. The replacement or repair of the following do require an ASME Section XI suitability evaluation by CE.

1. Piping, tubing, and pipe components which are greater than 1" nominal pipe size.
2. Any pressure retaining parts including: studs, nuts, bolts, valve bodies, valve

{ bonnets,

  • valve discs, pump casings, pump covers, pump housing, gland plates, mechanical cartridge seals, vessel shells, manway covers, vessel heads, nozzles.

Discs shall be considered pressure retaining only on valves included in the Section XI IWV program.(as listed in the performance testing i . program.)

i C. CE shall generate a PIR if a pressure boundary component (of Section B above) failed. To determine a faliure Refer to Section D. step 2 for guidance.

D. A suitability evaluation should address the following and be documented in Section V of the i Work Order.

) 1. Identify the component (s) being evaluated.

2. Explain why the replacement or repair was required as follows:

(steps a thru f)

a. Preventative Maintenance
b. Typical degradation of a component (see note 2)
c. Failure of a component due to service conditions (see note 2) 1 l

Enclosure 13.2 MP/0/A/7650/088 Guidelines for Suitability Evaluation Retype # ,,1 Page 2 of 2 fQR lNf0RMATION ONLY

d. Failure of a component that occurred during maintenance, not operation,
e. Failure of a component due to an undesigned, non service condition. (i.e.

failure of tubing due to the weight of a human)

f. Other
3. If (c) is chosen, is an identical replacement or repair suitable and why 7 Address the cause of failure.
4. If (c) is chosen and and identical replacement is not suitable, generate a SPR to correct the component's specification. The current work order should contain a copy of the SPR and document the project's work order number if possible.

I NOTE #1: An evaluation of nach replacemeat or repair must be completed grigt to supervisor signoff in W/0 Section IX. More than one

evaluation may be made if more then one component is replaced or repaired.

I NOTE #2: Degradation and failure should be determined with the following l guidance. These are not definitions.

4 Failure is considered abnormal, significant, or important to nuclear safety. This J

includes
l
1. Broken fasteners l

, 2. Crack in a pressure boundary material 1

3. Erosion, corrosion, or cavitation damage that could approach minimum wall  ;

prior to next scheduled inspection.

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Degradation includes: I
1. Typical damage to valve seating surfaces
2. Typical corrosion build up f 3. Galling of threads during disassembly

, 4. Imkage damage from bolted, pressure seal or screwed joints i

4 NOTE #3: Repair and replacement are defined in Section E of the Duke Power Company ASME Section XI Manual. Repair by welding suitability evaluations are addressed in Section E. ,

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Enclosure 13.3 MP/0/A/7650/088 Definitions Retype # .]_ ,

Page 1 of 1 'I FOR INFORMATION ONLY. l i

Repair i Repair, as referenced in ASME Section XI IWX-4000 paragraphs (except IWP), is the process of removing or correcting an unacceptable condition (defect) as defined by O!WX-3000 paragraphs, or a condition l unacceptable for service by:

1 a. Removing metal from or adding weld metal to,Section XI pressure-retaining l

components and their supports, or i
b. Tightening, realigning, adjusting, or reworking Section XI supports, j F=mations from Selan XI P= airs -
Minimum metal removal for improving sealing surfaces or fit shall not be l 1

l considered a Section XI repair. Examples are lapping, polishing and skim cuts that do not violate minimum wall thicknans. However, if more than .010 inches of rnetal must be removed, the responsible engineer must be l

l contacted. ,

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Replacenynt, as defined in Section XI, IWX-7000 paragraphs, is the addition or substitution of pressure-i retaining spare and renewal components, parts or subassemblies on Section XI components, and the addition

< or substitution of Section XI component supports, support parts, orpubmaammhlies. Replacamsat includes j modification, and system changes to pressure-retaining components , such as rerouting of piping.

4 i Pressure-Retaining Components - Items that serve as a pressure boundary such as vessel shells, heads anp nondes, pipes tubes and fittings, valve bodies j and bonnets, valve discs , pump casings and covers, and bolting which joins )

pressure-retaining items. 1 1

Specifically excluded are itsun not associated with the pressure retaining

^

function of a component such as: shafts, items, trim, bearings, bushings,

wear plates, machanical seals, packaging, gaskets, seals, and valve seats. l 1

1 Discs shall be considered pressure-retaining only on valves included in the Section XI IXV Program as listed in performance testing program.

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Enclosure 13.4 " " ^ * " 88

- Dea shem FOR INFORMATlON ONLY Recype ,1 Page 1 Of 1 TEST.REOU(REMENTS

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QA CLASS PIPE SIZE BREAKING AND REMAKING REPLACING A CUTTING OUT AND PRESSURE BOUNDARY PRESSURE BOUNDARY AND REMAKING JOINT USING THE SAME COMPONENT WELD MATERIAL LB881 MAN OIt PUNCTIONAL PUNCIlONAL FUNCTIONAL 80"*'T 3 '* -

P 1 A OILEATER THAN MP/0/An650488 MP/0/An650/088 MP/0/An650/062 1 IN.

LESS THAN OR PUNCTIONAL FUNCTIONAL FUNCTIONAL 1 B BQUAL M 1 IN.

GREATER THAN FUNCTIONAL MP@An650/088 MP/0/A/7650/062 1 IN.

LB881 MAN OR PUNCTIONAL FUNCTIONAL FUNCTIONAL 1 C BQUAL M 1 IN.

aREATBit THAN PUNCI10NAL MPMAn650/088 MP/0/An650/062

. 1 IN.

LJISS THAN OR FUNCTIONAL FUNCTIONAL PUNCIlONAL 3 E BQUAL M 1 IN.

l

! OILEATIBt THAN FUNCTIONAL FUNCTIONAL MP/0/An650/088

4 1 IN.

t LESS THAN OR FUNCTIONAL FUNCTIONAL FUNCTIONAL 4 F EQUAL M 1 IN.

OREATER THAN PUNCIlONAL PUNCT10NAL MP/0/An650/088 I IN.

N LB88 THAN OR FUNCTIONAL FUNCTIONAL FUNCTIONAL

, O EQUAL 701 IN.

3 N O j E GREA115t THAN FUNCTIONAL FUNCTIONAL FUNCTIONAL a 1 IN.

4 N LESS THAN OR PUNCTIONAL FUNCTIONAL FUNCTIONAL O BQUAL 101 IN.

N H

E GREATER 1 MAN FUNCTIONAL PUNC110NAL PUNCT10NAL l I M.

1 LESS THAN OR MP/0/An650/088 MP/0/An650/088 MP/0/An650/088 3 H EQUALTO 1 IN.

1, l OREATER THAN MP/0/An650/088 MP/0/An650/052 MP/0/An650/052

i m.

CATAWBA NUCLEAR STATION FOR INFORMATION O MAINTENANCE PROCEDURE PROBLEM REPORTING FORM Directions: The Requester of a change will complete the information below and identify any problems or discrepancies found in the procedure. The requester will also assign an appropriate priority level.

Then route this form to the appropriate Procedure Writer. The Writer will then route this form to either a Job Sponsor or Engineer for approval, as required.

NOTE. . Attach additional sheets or red marked copy of procedure as necessary.

Procedure No.

Procedure Name Section/ Step No.

Problem Description Suggested Resolution Problem Description Suggested Resolution Requester signature Date (Mail to Procedure Writing Group - Mail Code: CNO3PS)

Priority High Medium Low (Circle one) 3 Engineering / Job Sponsor Approval Date (Major Change Only)

Resolution incorporated by:_ Date f

1

i 9 . 4 s

ATTACHMENT 2 PROCEDURE FOR 10 CFR 50 APPENDIX J SYSTEM LEAKAGE TEST

P P

PT/2/A/4200/01T

^

ER COMPANY CATA LEAR STATION CONTAINMENT PENETRATIO 4NJECTION WATER SYSTEM PERFORMAN 1.0 PURPOSE 1.1 To comply with Catawba Technical Specifications for:

  • Total Containment Isolation Valve seat leakage for the NW System 1.2 To comply with Catawba IWV Testing Program requirements for:
  • Full stroke of NW check valves 1.3 To verify post maintenance operability for:
  • Total Containment isolation Valve seat leakage for the NW System
  • Containment Isolation Valve opf.rability
  • NW valve operability

2.0 REFERENCES

2.1 Source Documents

  • CN-2569-1.0, NW Flow Diagram
  • CN-2223-19, NW System Description
  • CN-2561-1.0, Residua 4 Heat Removal Flow Diagram
  • CN-2554-1.0, Chemical and Volume Control System Flow Diagram
  • CN-2565-2.0, Liquid Radwaste System Flow Diagram
  • CN 2565-2.1, Liquid Radwaste System Flow Diagram
  • CN-2565-2,4, Liquid Radwaste System Flow Diagram
  • CN-2565-2.6, Liquid Radwaste System Flow Diagram
  • CN-2573-1.3, Component Cooling System Flow Diagram
  • CN-2599-2,2, Interior Fire Protection System Flow Diagram
  • CN-2562-1.0, Safety injection System Flow Diagram
  • CN-2562-1.2, Safety injection System Flow Diagram
  • CN-2562-1.3, Safety injection System Flow Diagram
  • Catawba Nuclear Station (CNS) Technical Specifications:
  • 4.6.6.2 NW System Operability
  • ASME Performance Test Codes: Code on Definitions and Values, Copyright 1971 by ASME
o. .

y-PT/2/Al42MIT

[OR INFOPMTlON ONty Page 2 of 7

  • CNS Operability Evaluation, RE: PIR-0-C88-0294, File No. CN-2223.19-00, October 6,1988 E.W. Fritz e Uncertainity. Calibration and Probability by C.F. Dietrich, Copyright 1973.

2.2 References Needed to Perform Procedure

  • OP/2/Al6200/19 Containment Valve Injection Water System Operating Procedure 3.0 TIME REOUIRED As specified in enclosures.

4.0 PREREOUISITE TESTS None. .

5.0 TEST EOUIPMENT As specified in enclosures.

6.0 LIMITS AND PRECAUTIONS As specified in enclosures.

7.0 REOUIRED UNIT STATUS As specified in enclosures.

8.0 PREREOUISITE SYSTEM CONDITIONS As specified in enclosures.

9.0 TEST METHOD The penetration (s) for the Containment Isolation Valve (s), CIV(s), under test is (are) aligned to allow seat leakage upstream and downstream of the CIV(s) under test. The CIV(s) is(are) stroked individually to verify flow to the CIV(s) and through associated NW check valves. This flow verification satisfies the full stroke verification requirement of ASME Section XI, Subsection IWV for the following NW check valves:

A - Train 2NW-37 2NW-135 2NW 159 2NW-138 2NW-178 2NW-47 2NW-40 2NW 171 2NW-21 2NW-184 2NW-132 2NW-136 2NW-172 2NW-139 2NW 183 2NW-50 2NW-164 2NW-l% 2NW-24 2NW-189 2NW-133 2NW-163 2NW-197 2NW-140 2NW-188 2NW-53 2NW-169 2NW-201 2NW 27 2NW-194 2NW 134 2NW-168 2NW-202 2NW-141 2NW-193 2NW-43 2NW-160 2NW-17 2NW 179

FT/2/A/4'200/01T Page 3 of 7 B - Tra.in FOR INFORMATION ONLY -

2NW-107 2NW 206 2NW 124 2NW-127 2NW-131 2NW-230 2NW 111 2NW-209 2NW-80 2NW-98 2NW-213 2NW-236 2NW-120 2NW 210 2NW-123 2NW 128 2NW-214 2NW-235 2NW 114 2NW-70 2NW-83 2NW-95 2NW-218 2NW-241 2NW-109 2NW-126 2NW 122 2NW 129 2NW-219 2NW-240

'ANW-147 2NW-74 2NW-86 2NW-92 2NW-233 2NW-246 2NW 148 2NW 125 2NW-121 2NW-130 2NW-224 2NW-245 2NW 205 2NW-77 2NW-101 2NW-89 2NW<

  • a After reclosure of the CIV(s), NW seat leakage for the CIV(s) is measured and recorded. Valve seat leakages are totaled to determine overall leakage for each NW train. Once all testing is complete, affected penetrations and NW i

supply isolation valves are returned to normal alignment by Operations.

Leakage is measured using either process flowmeters (in cc/ min) or by measuring the drop in NW surge tank level over a period of time (10 minutes) and calculating the volume of water per unit time (gallons per minute - GPM).

10.0 DATA REOUIRED

<

  • Flow Rate e Surge Tank Pressure
e Surge Tank Level Change 11.0 ACCEPTANCE CRITERIA 11.1 Total containment isolation valve seat leakage for NW Train 2A is less than or equal to 0.7434 gpm with the tank pressure 2,46.5 psig.

11.2 Total containment isolation valve seat leakage for NW Train 2B is less than or equal to 0.9916 gpm with tank pressure _> 46.5 psig.

1 12.0 PROCEDURE NOTES: 1. Only those enclosures for tests being performed need be included with the working copy of this procedure.

2. NW valve positions may be verified to be in the Required Test Position by transferring signatures from the most recent NW System Train alignment.
3. NW solenoid valve positions may be N/A'd in the individual enclosures if NW solenoid valves are failed open. Isolation for the other CIV's not t , der test will be n ade by closing the associated manual isolation valve (s) and documenting on the associatel enclosure for hand-operated NW valves.

13.0 ENCLOSURES 13.1 NW Penetration Alignments 13.2 NW Leakage Test for CIV 2KC-320A 13.2.1 NW Leakage Test for CIV 2KC-320A A - Train Hand Operated NW Valves 13.3 NW Leakage Test for CIV 2KC 333A 13.3.1 NW Leakage Test for CIV 2KC-333A A - Train Hand Operated NW Valves

~'. .

"' 'A'" *' ' T FOR INFORMATION ogy '*****

13.4 NW Leakage Test for CIV 2KC-425A 13.4.1 NW Leakage Test for CIV 2KC-425A A - Train Hand Operated NW Valves 13.5 NW 1eakage Test for CIV 2NI-121 A 13.5.1 NW Leakage Test for CIV 2NI 121 A A - Train Hand Operated NW Valves 13.6 NW Leakage Test for CIV 2NI-162A 13.6.1 NW Leakage Test for CIV 2NI 162A A - Train Hand Operated NW Valves 13.7 NW Leakage Test for CIV 2NI-173A 13.7.1 NW Leakage Test for CIV 2NI-173A A - Train Hand Operated NW Valves 13.8 NW 1eakage Test for CIV 2NS-29A 13.8.1 NW Leakage Test for CIV 2NS-29A A - Train Hand Operated NW Valves 13.9 NW leakage Test for CIV 2NS-32A 13.9.1 NW Leakage Test for CIV 2NS-32A A - Train Hand Operated NW Valves 13.10 NW Leakage Test for CIV 2NS-43A 13.10.1 NW Leakage Test for CIV 2NS-43A A - Train Hand Operated NW Valves 13.11 NW Leakage Test for CIV 2NV 10A 13.11.1 NW 1eakage Test for CIV 2NV-10A A - Train Hand Operated NW Valves 13.12 NW Leakage Test for CIV 2NV-11A 13.12.1 NW Leakage Test for CIV 2NV-II A A - Train Hand Operated NW Valves 13.13 NW Ixakage Test for CIV 2NV-13A 13.13.1 NW 1eakage Test for CIV 2NV-13A A - Train Hand Operated NW Valves 13.14 NW Leakage Test for CIV 2NV-89A 13.14.1 NW Leakage Test for CIV 2NV-89A A - Train Hand Operated NW Valves 13.15 NW Leakage Test for CIV 2RN-429A 13.15.1 NW leakage Test for CIV 2RN-429A A - Train Hand Operated NW Valves 13.16 NW Lea'kage Test for CIV 2RN-484A 13.16.1 NW leakage Test for CIV 2RN-484A A - Train Hand Operated NW Valves 13.17 NW leakage Test for CIV 2WL-805A 13.17.1 NW leakage Test for CIV 2WL-805A A - Train Hand Operated NW Valves

[OR MONATION ONLY PT/2/A/4200/0lT Page 5 of 7 13.18 NW Leakage Test for CIV 2WL-825A 13.18.1 NW 12akage Test for CIV 2WL-825A A + Train Hand Operated NW Valves 13.19 NW leakage Test for CIV 2WL-867A 13.19.1 NW leakage Test for CIV 2WL-867A A - Train Hand Operated NW Valves 13.20 NW Leakage Test for CIV 2WL-A24

13.20.1 NW Leakage Test for CIV 2WL-A24 A - Train Hand Operated NW Valves 13.21 NW leakage Test for CIV 2KC-305B 13.21.1 NW 12akage Test for CIV 2KC-305B B - Train Hand Operated NW Valves i

13.22 NW leakage Test for CIV 2KC-315B 13.22.1 NW Leakage Test for CIV 2KC-315B B - Train Hand Operated NW Valves

.13.23 NW leakage Test for CIV 2KC-332B 13.23.1 NW 12akage Test for CIV 2KC-332B B - Train lland Operated NW Valves 13.24 NW Leakage Test for CIV 2KC-338B l I

13.24.1 NW 12akage Test for CIV 2KC-338B B - Train Hand Operated NW Valves i

13.25 NW Leakage Test for CIV 2KC-424B l 13.25.1 NW Leakage Test for CIV 2KC-424B B - Train Hand Operated NW Valves 13.26 NW Leakage Test for CIV 2NC-56B 13.26.1 NW Leakage Test for CIV 2NC-56B B - Train Hand Operated NW Valves 13.27 NW Leakage Test for CIV 2NI 152B 13.27.1 NW Leakage Test for CIV 2NI-152B B - Train Hand Operated NW Valves 13.28 NW leakage Test for CIV 2NI-178B I l

13.28.1 NW 12akage Test for CIV 2NI-178B B - Train Hand Operated NW Valves 1 13.29 NW leakage Test for CIV 2NI 183B 13.29.1 NW Leakage Test for CIV 2NI-183B B Train Hand Operated NW Valves 13.30 NW Leakage Test for CIV 2NS 12B 13.30.1 NW Leakage Test for CIV 2NS-12B B - Train Hand Operated NW Valves 13.31 NW Leakage Test for CIV 2NS-15B 13.31.1 NW Leakage Test for CIV 2NS-153 B - Train Hand Operated NW Valves

1

^'

.[OR INFORMATION ONLY N'e'6 or 7 8

13.32 NW Leakage Test for CIV 2NS-38B l 13.32.1 NW Leakage Test for CIV 2NS-38B B Train Hand Operated NW Valves 13.33 NW Leakage Test for CIV 2NV-91B 13.33.1 NW Leakage Test for CIV 2NV-91B B - Train Hand Operated NW Valves 'I 13.34 NW Leakage Test for CIV 2RF-389B 13.34.1 NW 1eakage Test for CIV 2RF-389B B - Train Hand Operated NW Valves 13.35 NW Leakage Test for CIV 2RF-447B 13.35.1 NW Leakage Test for CIV 2RF-447B B - Train Hand Operated NW Valves 1 13.36 NW 12akage Test for CIV 2RN-404B 13.36.1 NW Leakage Test for CIV 2RN-404B B - Train Hand Operated NW Valves 13.37 ENCLOSURE DELETED 13.37.1 ENCLOSURE DELETED 13.38 NW Leakage Test for CIV 2RN-437B i 13.38.1 NW 1eakage Test for CIV 2RN-437B B - Train Hand Operated NW Valves 13.39 NW Leakage Test for CIV 2RN-487B 13.39.1 NW leakage Test for CIV 2RN-487B B Train Hand Operated NW Valves 13.40 NW Leakage Test for CIV 2WL-807B 13.40.1 NW Ieakage Test for CIV 2WL-807B B - Train Hand Operated NW Valves 13.41 NW leakage Test for CIV 2WL-827B 13.41.1 NW Leakage Test for CIV 2WL-827B B - Train Hand Operated NW Valves 13.42 NW IEakage Test for CIV 2WL-869B ,

13.42.1 NW Leakage Test for CIV 2WL-869B B - Train Hand Operated NW Valves 13.43 NW leakage Test for CIV 2WL-A21 13.43.1 NW leakage Test for CIV 2WL-A21 B - Train Hand Operated NW Valves 13.44 NW Leakage Test for CIVs (Group Testing) A - Train 13.44.1 NW Leakage Test for CIVs (Group Testing) A Train Hand Operated NW Valves 13.45 NW 1eakage Test for CIVs (Group Testing) B - Train 13,45.1 NW leakage Test for CIVs (Group Testing) B Train Hand Operated NW Valves 13.46 A-Train Acceptance Criterion 11.1 Verification

PT/2/A/4200/01T FOR INpORMATION ONLY j 13.47 B Train Acceptance Criterion 11,2 Verification-13.48 Flowmeter 2NWFE5070 Calibration 13.49 Flowmeter 2NWFE5060 Calibration ,

l 13.50' level Gauge Diagram for A Train 13.51 level Gauge Diagram for B - Train 13.52 Penetration Alignment Valves Not Returned to "As Found" Position e

' ' PT/2/A/4200/0lT  !

Page 1 of 7 )

. *g' .

1 NW LEAKAGE TEST FOR CIV 2NV-10A 3.11.0 TIME REOUIRED 3.11.1 Penetration Alignment and Restoration Two Nuclear Equipment Operators - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1

3.11.2 NW System Alignment Two Nuclear Equipment Operators - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.11.3 Test One Test Coordinator - I hour  !

5.11.0 TEST EOUIPMENT 5.11.1 Pressure Test Gauge Range 0-200 psig, Accuracy better than or equal to i 0.25% full scale.

5.11.2 Level Sight Gauge 3/8" Tygon Tubing Manometer, approximately 37" long.

5.11.3 Stopwatch 6.11.0 LIMITS AND PRECAUTIONS

)

6.11.1 Any work performed in a Radiation Area must be performed under an appropriate Radiation Work Permit.

1 6.11.2 Do not allow the NW surge chamber of either train to be filled with raw lake water I from the Nuclear Service Water System. This will occur if tank level drops beneath the Lo-Lo level setpoint of 21.25" (measured from bottom of tank) ARQ a "T" signal is present.

6.11.3 If unable to complete a step, return system to "As Found" condition. N/A, initial, and date steps N_QI required for system restoration or corrective action.

6.11.4 If the performance of this procedure is suspended for any reason for a period exceeJing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, any modification in place such as open sliding links, lifted leads,

)

or temporary jumpers, must be returned to normal or the proper station modification  ;

procedure implemented per Site Directive 4.4.5.

l 7.11.0 REOUIRED UNIT STATUS l

/ 7.11.1 Unit 2 is in Mode 5 or 6, or fuel is unloaded from the core. '

8.11.0 REREOUISITE SYSTEM CONDITIONS

/ 8.11.1 Verify that the YM System is available, to the extent that it can supply makeup to  !

NW Surge Chamber 2A.

'/ 8.11.2 Ensure that the Nitrogen System is available to pressurize NW Surge Chamber 2A.

_ _ ____ _ __ l

. t

' PT/2/A/4200/0lT I Page 2 of 7 VOR INFORMATION ONLY ENCLOSURE 13.!!

NW LEAKAGE TEST FOR CIV 2NV-10A

/ 8.11.3 I Ensure that instrument 2NWFE5070 has been calibrated per Enclosure 13.48.

/ 8.11.4 Ensure that a pressure test gauge and tygon tubing manometer (used for level i

q indication) is installed on NW Surge Chamber 2A as shown on Enclosure 13.50.

/ 8.11.5 Verify that Penetration M347 has been vented and/or drained, per Enclosure 13.1,  ;

Page 13 of 27.

/ 8.11.6 Verify that the NW System Train A valve alignment has been completed per Enclosure 13.11.1.

NDlg Those A Train Hand Operated NW valves not required to be either OPEN .QB CLOSED may have their " Required Test Position" blanks and signoffs N/A'd, initialed, and dated at the discretion of the Test Coordinator. Current valve positions may, however, be placed in the " Required Test Position

  • blanks to track valve positions in preparation for next valve test.

11.11.0 ACCEPTANCE CRITERIA As specified in Procedure Body.

12.11.0 PROCEDURE Initial /Date

/ 12.11.1 Obtain Shift Supervisor's permission to perform test.

/ 12.11.2 Log test into Unit 2 Test legbook.

/ 12.11.3 Notify Unit 2 Nuclear Control Room Operator of test.

/ 12.11.4 Verify unit status and prerequisites in Sections 7.11.0 and 8.11.0 are met.

12.11.5 Perform the following:

/ 12.11.3 1 Have Control Room Operator close, or verify closed, the following valves:

(V)

a. 2NW 35A CONT VLV INJ HDR 2A CONT ISOL
b. 2NW-13A SEAL WATER TO 2KC-425A
c. 2NW-175A SEAL WATER TO 2NI-173A
d. 2NW-180A SEAL WATER TO 2NS-43A e.

2NW-185A SEAL WATER,TO 2NI-162A

f. 2NW 190A SEAL WATER TO 2NI-121 A 1
g. 2NW-195A SEAL WATER TO 2NS-32A
h. 2NW-200A SEAL WATER TO 2NS-29A

'

  • PT/2/A/4200/0lT Page 3 of 7 FOR INfQB4MIIGN ONLY NW LEAKAGE TEST FOR CIV 2NV-10A
i. 2NW-46A SEAL WATER TO 2WL-867A,2RN-484A AND 2RN-429A i j.

2NW 20A NW SURG CHMBR 2A OUTLET VLV 12.11.5.2 Have Control Room Operator open the following NW valve:

/

a.

2NW 35A CONT VLV INJ HDR 2A CONT ISOL 12.11.5.3 To obtain permissive signal to open 2NV 10A, perform the following;

/

a.

/_ (IV) Place a jumper between C 24 and C-53 in 2EATCl2 (AB,577', FF 59) to bypass interlocks for NC flow to Regenerative Heat Exchanger isolation, low pressurizer level, and charging pump running (CNEE-0257-03.03) to allow 2NV 10A to be opened.

12.11.6 Determination of 2NV-10A leakage by NW Process Flowmeter 1

12.11.6.1 l If NW Surge Chamber 2A Pressure is 154.0 psig N/A, initial, and date the following substeps. If EQI, perform the following steps.

/___

a.

Have Control Room Operator open 2NW-2, NW SURGE l CHMBR 2A N2, to pressurize NW Surge Chamber 2A. I

/ b.

After NW Surge Chamber 2A pressure has reached 154.0 psig (as indicated by installed test gauge or 2NWP5040 in Control Room), have Control Room Operator close 2NW-2, NW SURGE CHMBR 2A N2.

/ 12.11.6.2 Record NW Surge Chamber 2A pressure as indicated by test gauge 2NW5000H.

Pressure = psig.

/__

12.11.6.3 Have Control Room Operator open 2NW 20A, NW SURG CHMBR 2A OUTLET VLV.

l

/_ 12.11.6.4 Have 10A.

Control Room Operator open Containment Isolation Valve 2NV-

,_.f 12.11.6.5 Verify that NW flow is present to 2NV-10A by observing response in the NW Surge Chamber 2A level as indicated by tygon tubing manometer or Control Room gauge (2NWP5000).

/_

12.11.6.6 Have 10A.

Control Room Operator close Containment Isolattos Valve 2NV-

/_

12.11.6.7 Open 2NW-154, NW SURGE CHMBR 2A OUTLET FLOW ELEMENT ISOL.

/_ 12.11.6.8 Open 2NW 155, NW SURGE CHMBR 2A OUTLET FLOW

.. . ^

F7g7'4f7[4' FOR INFORMATION ONLY ENCLOSURE 13.11 NW LEAKAGE TEST FOR CIV 2NV 10A ELEMENT ISOL.

/ 12.11.6.9 Have Control Operator close 2NW-20A, NW SURG CHMBR 2A OUTLET VLV.

12.11.6.10 If leakage can be measured by 2NWFE5070, perform the following steps. If EQI, N/A, initial, and date the following steps:

/ a. Record the leakage flowrate (ml/ min) that is measured by 2NWFE5070.

2NV 10A Seat leakage = ml/ min.

/ b. Record final NW Surge Chamber 2A pressure as indicated by test gauge at 2NW5000H.

Pressure = psig.

/ c. Verify the NW Surge Chamber 2A final pressure in 12.11.6.10.b is 150.5 psig.  ;

l

/ d. Determine actual flowrate of the NW process flowmeter per the calibration curve for 2NWFE5070 on Enclosure 13.48, 1 Flowmeter 2NWFE5070 Calibration, and record '

ml/ min.

/ e. Convert ml/ min to gpm as follows:

I nallon Q(gpm) = ml/ min x 3785.422 mi 1 aallon Q(gpm) = ml/ min x 3785.422 ml =

gPm.

EQIE: Step 12.11.6.10 f may be performed out of sequence.

/ f. Ensure that the calculation in Step 12.1.6.10.e has been verified.

Initial /Date Calculation Verified By: /-

/ 12.11.6.11 Close 2NW-155, NW SURGE CHMBR 2A OUTLET FLOW ELEMENT ISOL.

/ 12.11.6.12 Close 2NW 154, NW SURGE CHMBR 2A OUTLET FLOW ELEMENT ISOL.

NOTE: Section 12.11.7 may be signed off as N/R (Not Required) if leakage was determined in Step

. PT/2/A/4200/0lT Page 5 of 7 t

FOR INFQRLMiDGEOg2N NW LEAKAGE TEST FOR CIV -10A .

12.11.6.10.

12.11.7 Determination of 2NV-10A Leakage by Surge Chamber level Change 12.11.7.1 If NW Surge Chamber 2A Pressure is 154.0 psig, N/A, initial, and date the following substeps, if NLQI, perform the following steps.

l

/ a. Have Control Room Operator open 2NW-2, NW SURGE CHMBR 2A N2, to pressurize NW Surge Chamber 2A.

/ b. After NW Surge Chamber 2A pressure has reached 2 54.0 I psig (as indicated by installed test gauge or 2NWP5040 in l

Control Room), have Control Room Operator close 2NW-2,

{'

NW SURGE CHMBR 2A N2

/ -

12.11.7.2 Record NW Surge Chamber 2A pressure as indicated by test gauge at 2NW5000H.

Pressure = psig.

/ 12.11.7.3 Mark tygon tubing manometer, indicating the present NW Surge Chamber 2A water level.

/ 12.11.7.4 Simultaneously have Control Room Operator open 2NW-20A, NW l

SURG CHMBR 2A OUTLET VLV, and start stopwatch. l l

/ 12.11.7.5 After sufficient time has elapsed (10 minutes) or tank lo-level alarm (OAC point D3476) is activated (at 36.5" measured from bottom of tank), have Control Room Operator close 2NW-20A, NW SURG CHMBR 2A OUTLET VLV, and simultaneously stop stopwatch.

/ 12.11.7.6 Record elapsed time _:_ minutes: seconds.

/ 12.11.7.7 Convert minutes: seconds to minutes as follows:

Total Minutes = Whole Minutes (from Step 12.11.7.6)

+ Seconds (from Steo 12.I1.7.6)  !

60 I 1

Total Minutes = + = Minutes, i 60

/ 12.11.7.8 Record final NW Surge Chamber 2A pressure as indicated by test gauge at 2NW5000H.

I Pressure = psig.

/ 12.11.7.9 Verify the NW Surge Chamber 2A final pressure as recorded in 12.11.7.8 is 150.5 psig, j l

l

I

  • PT/2/A/4200/0lT  ?

___ Page 6 of 7

, FORJ@l%%EQN ON;.f-NW LEAKAGE TEST FOR CIV 2NV-10A

/ 12.11.7.10 Record the change in NW Surge Chamber 2A water IcVel using the mark placed on the tygon tubing manometer by Step 12.11.7.3 as a zero reference.

Level change = inches.

/ 12.11.7.11 - Calculate the volume ofleakage as follows:

l

)

V (gals.) = 1,8443 X AH (inches)

V (gals.) = 1,8443 X = gals. t="

where V = gallons I AH = Level Decrease

/ 12.11.7.12 Calculate leakage flow rate as follows:

gals. + Total Minutes =

(Step (Step  !

12.I1.7. I1) 12.I1.7.7) 8Prn NOTE- Step 12.11.7.13 may be performed out of sequence. .

/ 12.11.7.13 Ensure that the calculations in Steps 12.11.7.7,12.13.7.11, and 12.11.7.12 have been verified.

Initial /Dalq Calculations Verified By: /

MQTE- Acceptance Criteria 11.1 is dependent on Total A-Train NW-supplied CIV seat leakage, l Verification process of Acceptance Criteria 11.1 is performed completely on Enclosure 13.46.

/ 12.11.8 Record 2NV-10A seat leakage (Normal Test or Retest) as determined by Section ,

12.I1.6 or 12.I1.7 (Steps 12.I1.6.10.e or 12.I1.7.12) on Enclosure 13.46, Table I. 1

/ 12.11.9 Remove jumper between C-24 and C-53 in 2EATCl2

/ (IV)

(AB, 577*, FF-59).

j 12.11.10 Have Control Room Operator close the following NW valve:

l

/ 12.11.10.1 2NW-35A CONT VLV INJ HDR 2A CONT ISOL

/ 12.11.11 Inform Operations that Penetration M347 may be returned to "As Found" condition as required by Enclosure 13.1, Page 13 of 27.

/ 12.11.12 If A Train NW testing is to continue, N/A, initial, and date this step. If EQI, infonn Operations that all A-Train NW valves are to be realigned for standby readiness per OP/2/A/6200/19.

1 I

i'. . .- PT/2/A/4200/0lT FOR liifoRMATION ONLy "" ' "

3 ENCLOSURE 13.11

NW LEAKAGE TEST FOR CIV 2NV 10A

/ 12.11.13 If all A-Train NW testing is complete, perform Enclosure 13.46 calculations and acceptance criteria verification. If N_QI, N/A, initial, and date this step.

/ 12.11.14 Log test out of Unit 2 Test Logbook.
/ 12.11.15 If all NW testing is complete, remove pressure gauge and I

! / 1.V. tygon tubing manometer from NW Surge Chamber J

l 1

3 l

i '

\

E I

a a

J 1

1 5

l J

1 4

i 4

1 l

'o ** o PT/2/A/4200/0lT

' FQR INFORMATION ONLY'

ENCLOSURE 13.11.1 NW LEAKAGE TEST FOR CIV 2NV-10A A TRAIN HAND OPERATED NW VALVES Valve Valve Name (Location) Reauired Test Position

(AB,592', GG-HH/61-62, RM 427) 2NW-22 NW SUPPLY ISOL TO 2WL A24 CLOSED /

(AB,576', JJ-62, RM 308A) 2NW-25 NW SUPPLY ISOL TO 2KC-333A CLOSED /

(AB, 576', JJ-62. RM 308A) 2NW-28 NW SUPPLY ISOL TO 2KC-320A CLOSED /

(AB,576', JJ-62, RM 308A) 2NW-41 NW SUPPLY ISOL TO 2WL-825A CLOSED /

(CV, 557', 56'-248 *)

2NW-44 NW SUPPLY ISOL TO 2WL-805A CLOSED /

(CV, 566', 53'-245')

(CV, 560', 49'-164 *)

(CV, 560', 51'-175')

(CV, 563', 56'-195')

2NW 157 NW SUPPLY ISOL TO 2NV-10A OPEN /

(CV, 579', 49'-l 17 *)

2NW 161 NW SUPPLY ISOL TO 2NV ll A CLOSED /

(CV, 579', 51' l19')

2NW-166 NW SUPPLY ISOL TO 2NV 13A CLOSED /

(CV,580', 45' l16')

CAUTION I Do not apply excessive torque when closing NW valves.

NOTES: 1.

"As Found" and 'As Left" valve positions are not required. Operations performs OP/2/A/6200/19 to return NW System to standby readiness upon completion of testing.

2.

" Required Test Position" is not necessary for valves marked with "". Current valve positions may, however, be placed in the " Required Test Position" blanks to track valve position in preparation for next valve test. These blanks may also be N/A'd at the discretion of the Test Coordinator.

$q ,, o PT/2/A/4200/0lT Page 2 of 2

~

ENCL Sd i NW LEAKAGE TEST FOR CIV -

CI![.}'

A-TRAIN HAND OPERATED NW VALVES yjalyg Valve Name (Location) Reauin " Test Position 2NW 173 NW SUPPLY ISOL TO 2NV-89A CLOSED i_

(CV, 561', 54'-167 *)

(AB,565', llH-62, RM 308A)

(AB, 579', JJ-62, RM 427)

  • 2NW 186 NW SUPPLY ISOL TO 2NI 162A /

(AB,564', HH-63, RM 308A)

(AB,567', FF-GG/62, RM 308A)

(AB,585', GG-62, RM 427)  !

(AB, 577', HH-62, RM 427) l l

l CAUTION l

Do not apply excessive torque when closing NW valves.

NOTES' l. "As Found and "As Left" valve positions are not required. Operations performs OP/2/A/6200/19 to return NW System to standby readiness upon completion of testing.

2. " Required Test Position" is not necessary for valves marked with **". Current valve positions may, however, be placed in the " Required Test Position" blanks to track valve position in preparation for next valve test. These blanks may also be N/A'd at the discretion of the Test Coordinator.
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