ML20210M858

B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0

ML20210M858
Person / Time
Site:	Brunswick
Issue date:	05/14/1999
From:	Mcintyre J, Stanley B CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20210M852	List: BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI ML20210M858
References
ESR-99-00279, ESR-99-00279-R00, NUDOCS 9908100197
Download: ML20210M858 (38)

Text

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l . ENCLOSURE l

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 INSERVICE INSPECTION PROGRAM FOR THE THIRD 10-YEAR INTERVAL - EVALUATION FOR LEAKAGE AT BOLTED CONNECTIONS Engineering Service Reauest 99-00279.

"B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation" i

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9900100197 990805 PDR ADOCK 05000324 P PDR

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Form 1 ENGINEERING SERVICE REQUEST ESR # ' 9900279 Rev # 0 WR/JO # Other Documents (CR, OEF, etc.)

RELIEF REOREST l7 g Multiple Systems l Plant / Unit BNP 2 1005 B21,B11-NUCLEAR BOILER (INC.RX VESSEL & Affected Title Originator / Phone l B214R1 RPV Hydrotest Bolted Connection Corrective Action Eva STANLEY, BOYD J /850-2495 l Plant Customers (Print Name, Sign, Date) Engineering / Plant Programs (Print Name, Sign, Date)  !

ISI Md.Osorer, i <

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Reviews (Print Name, Sgn, e)

I Design Verrfcation ,/ /Y O Othar Reviews Rkuired % Rebrdhttached /

l Engineering Disciplines (Pnnt Name, , Date) l Mechanical [jg u . h ofA h Civil / Seismic {

Materials ytfgm g g dd 8' // V [ M g

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Plant / System e>/4 L;C NMhk _ ** fd / 9 Plant / System hg, / [f fp ff -

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l ESR Quality Class l Response Type ENG EVAL JERRY CPQER l Team PHIL GORE A Safety-Related MIKE GUTHRIE l

MARK GRANTHAM TODD HAMILTON Due Date 05-14-99 JOHN BASS APPROVALS is a 10CFR 50.59 Safety Review required per NAS Before Approval / implementation (plant speck pmcodureR l [

l , NAS Before Closeout @ Yes @ Safety Screen ONLY

, PNSC Before Approval / Implementation

_l NRC Before implementation O uSOD N/A (Engineering Disposition Onh)

O Plant General Manager Responsible Engineer BOYD J GTANLEY b j Responsible Manager (Print Name, Sign, Date) d ,M c yg , 6((I Plant General Manager (Print Name, Sign, Date)  !

Procedure: Form EGR-NGGC-0005-1-9 DCM01a2a 07/0&98 J

Pagn 1 of _

Form 1 ENGINEERING SERVICE REQUEST ESR # . Rev # Title 9900279 O B214R1 RPV Hydrotest Bolted Connection Corrective Action Eva

Response

The attached ESR text provides guidance for the evaluation of leaking ASME Class 1 pressure retaining bolted connections identified during VT-2 Examinations for the B214R1 RPV Leakage Test, OPT-80.1. This ESR implements pressure retaining bolted connection inspections which result from the upgrade of the ASME Section XI 1980 with 1981 Winter edition to the 1989 edition for the third ten year interval. It also implements Relief Request 17, Revision 2, dated 4May99. This guidance includes:

1. The classification of Corrective Action Levels based on observed leakage flow rates,

2. The General Visual Inspection requirements for bolted connections,

3. Details for the inspection methodology.

4. Specific exemption for mechanical packing and seal bolted connections.

Specific bolted connection evaluations for each identified leak are included in Attachment 5.

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l Procedure: Form EGR-NGGC-000#1-9 DCM04 03/28/96

s Paga 1 of _

Form 1 ENGINEERING SERVICE REQUEST ESR #. Rev # Title i 9900279 0 B214R1 RPV Hydrotest Bolted Connection Corrective Action Eva

Response

The attached ESR text provides guidance for the evaluation of leaking ASME Class 1 pressure retaining bolted connections identified during VT-2 Examinations for the B214R1 RPV Hydrostatic Test, OPT-80.1. This ESR implements these inspections as a result of the upgrade from the ASME Section XI 1980 with 1981 Winter edition to the 1989 edition for the third ten year interval, and includes Relief Request 17 dated 4May99. This guidance includes:

1. The classification of Corrective Action Levels b0 sed on observed leakage flow rates,

2. The General Visual Inspection requirements for bolted connections,

3. Details for the inspection methodology.

l 4. Specific exemption for mechanical packing and seal bolted connections.

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Specific bolted connection evaluations for each identified leak are included in Attachment 5.

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i Procedure: Form EGR-NGGC-00051-9 DCM04 03/28/96 l

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ESR 99-00279 Revision 0 Page4of ESR Table of Contents l l

Form I coversheet Page1 Rev 0 I request 2 0 response 3 0 List of effective pages 4 0 Purpose 5 0 Problem Identification 5 0 ESR Design specification 5 0 ESR Scope Description 5 0 Design inputs 5 0 References 7 0 Evaluation 7 0 : ASME TABLE IWB 2500-1, Examination B-G-1 (6 pages)

ASME TABLE lWB 2500-1, Examination B-G-2 ASME TABLE IWB 2500-1 Examination B-P : Leakage results from ESR's 96-00208 and 97-00486 (3pages) : Memo: Jerry Crider from Ray Acomb, ANil dated SMay99,Section XI- 5250 ( l Page) : General VisualInspection Data Sheet for ASME Class 1 Bolted Connections (1 Page) : OPT-80.1 RPV Leakage Test Bolted Connection Leakage Evaluation Data Sheet (13 Pages) l

ESR 99-00279 Revision 0 Page5 of Purpose The purpose of this engineering evaluation is to review the bolted connection history of the last two BNP Unit 2 refueling outage OPT-80.1 RPV Leakage Test results, and to establish corrective action level guidelines for corrective measures for similar leaks if found during the B2i4RI leakage in accordance with the ASME Section XI Code 1989 Edition, and BNP Relief Request 17, evision 2.

Problem Identification Implementation of.he ASME Section XI ,1989 edition, by Carolina Power and Light Company at the Brunswick rwckar Plant (BNP) in June 1998 resulted in new requirements for evaluating pressure retaining bolted connections observed leaking during the VT-2 examination of OPT-80.1," Reactor Pressure Vessel ASME Section XI Pressure Test". BNP ASME Code Relief Request 17 revision 2 has been approved modifying the new requirements for the B214RI refueling outage only. This ESR provides guidance for the evaluation of these bolted connections. He last two Unit 2 refueling outage OPT-80.1 test results will be reviewed for generic material issues, and for historical component leakage candidates.

ESR Design specification ESRScope Descr& tion his ESR applies to ASME Section XI Code Class I pressure retaining bolted connections included in the test boundary for the OPT-80.1 RPV Leakage Test.

Design inputs Relief Reauest RR-17 Revision 2: Leakane at Bolted Connections Carolina Power and Light Company at the Brunswick Nuclear Plant (BNP) implemented ASME Section XI,1989 edition, in May 1998. Upon completion of a VT-2 examination documenting pressure retaining bolted connection leakage in accordance with approved site procedure OPT-80.l," Reactor Pressure Vessel ASME Section XI Pressure Test" removal of bolting and a supplemental VT-3 examination is required for all leaks per IWA-5250(a). Subsequently, Relief Request RR-17 revision 2:" Leakage at Bolted Connections" was approved by the Nuclear Regulatory Coms. ssion as follows:

When leakage is detected at bolted connections, as an alternative to the requirements of IWA-5250(a)(2), the requirement of either 1 or 2 below shall be met:

1) De leakage shall be stopped and the bolting and component material shall be evaluated to determine joint integrity and the susceptibility of the bolting to corrosion and failure. The evaluation will, at a minimum, consider the following factors: -

a. He number and service age of the bolts

b. Bolt and component materials

c. Corrosivity of the process fluid that is leaking

d. Leakage location and system function

c. Leakage history at the connection or other system components

f. Visual evidence of corrosion at the connection (i.e while the connection is assembled).

2) If the leakage is not stopped, the joint shall be evaluated in accordance with IWB-3142.4 to determine joint integrity and the susceptibility of the botting to corrosion and faFure. The evaluation will, at a minimum, consider the following factors:

a. He number and service age of the bolts

b. Bolt and component materials 1

ESR 99-00279 Revision 0 Page6of

- c. Corrosivivity of the process fluid that is leaking "d. Leakage location and system function

e. Leakage history at the connection or other system components

f. Visual evidence of corrosion at the connection (i.e while the connection is assembled).

When' the evaluation of the abo've factors is concluded, and if the evaluation determines that the leaking conditions has not degraded the fasteners, then no further action is required. However, reasonable attempts shall be made to stop the leakage as appropriate. In accordance with IWB-3144(b), the evaluation analyses

will be submitted to the regulatory authority having jurisdiction at the plant site.

If the evaluation of the factors in 1 or 2 above indicates the need for further evaluation, then a bolt closest to the source ofleakage shall be removed. He bolt will receive a VT-1 examination and be evaluated and dispositioned in accordance with IWB-3317. If the removed bolting shows evidence of rejectable degradation,

. all remaining bolts shall be removed and receive a VT-1 examination in accordance with IWB-3140. If leakage is identified when the bolted connection is in service and the information in the evaluation is supportive, the rernoval of the bolt for the VT-1 examination may be deferred until the next refueling outage.

ASME IWA- 2212(a) Visual E==mination VT-2 De VT-2 visual examination shall be caaA=*d to locate evidence ofleakage from pressure retaining components, or abnormal leakage from components with or without leakage collection systems as requis ed during the conduct of system pressure or functional test.

ASME IWA- 2213 (a) Visual Examination VT-3 General mechanical and structural condition of components and supports such as the ve'.dication of clearances, settings, physical displacements, loose or missing parts, debris, corrosion. wear, erosion, or the loss ofintegrity at bolted or welded connections.

ASME IWA 5250 (a)(2) IfI 4==* occurs at bolted cana~'iaan nerform a VT-3 (a) ne source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:

(2) ifleakage occurs at a bolted connection, the botting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100.

ASME IWB 3141(b) General (b) Acceptance of components for continued service shall be in accordance with IWB-3142 though IWB-3144.

ASME IWB-3142.4 A((+- =* by Analytical Evaluation Components containing relevant conditions shall be acceptable for continued service if an analytical evaluation demonstrates the component's acceptability. De evaluation analysis and evaluation acceptance criteria shall be specified by the owner. Components accepted for continued service based on analytical evaluation shall be subsequently examined in accordance with IWB-2420(b) and ( c ).

ASME IWB 3144(b) Review by Authonties Evaluation analyses of examination results as required by IWB-3142.4 shall be submitted to the regulatory authonty havingjurisdiction at the plant site.

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ESR 99-00279 Revision 0 Page7 of ASME IWB 3517 Standards for Examination Category B-G-1. Pressure Retainine Bolting Greater than 2 in.

' in Diameter. and Examination Category B-G-2. Pressure Retaining Boltine 2 in. and Less in Diameter IWB 3517.1 visual Examination, VT-1 the following relevant conditions shall require correction to meet the requirements ofIWB-3122 prior to service or IWB-3142 prior to continued service:

(a) crack-like flaws that exceed the allowable linear flaw standards ofIWB-3515; (b) more than one deformed or sheared thread in the zone of thread engagement of bolts, studs, or nuts; (c) localized general corrosion that reduces the bolt or stud cross- sectional area by more than 5%;

(d) bending, twisting, or deformation of bolts or studs to the extent that assembly or disassembly is impaired; (e) missing or loose bolts, studs, nuts, or washers; (f) fractured bolts, studs, or nuts; (g) degradation of protective coatings on bolting surfaces; or (h) evidence of coolant leakage near bolting.

ASME TABLE IWB 2500-1. Examination B-G-1 1

See attachment i I ASME TABLE IWB 2500-1, Examination B-G-2 See attachment i ASME TABLE IWB 2500-1, Examination B-P See attachment 1 i

General Visual Inspection Criteria.

A general visual examination SHALL be performed either DIRECTLY or REMOTELY with sufficient ,

illumination (natural or artificial) and resolution (suitable for the local environmental conditions) to detect 1 evidence of corrosion at the "as-found" bolted connection.

References

- ASME Section XI,1989 Edition, no addenda.

Relief Request 17: Leakage at Bolted Connections ESR 96-00208, Evaluation of 0PT-80.1 RPV Leakage test results performed 7 Mar 96 ESR 97-00486, Evaluation of OPT-80.1 RPV Leakage test results performed 90ct97 ,

EER 90 0059, Unit 2 CRD Flange Bolt Evaluation i SEEF 94-0009, Upgrade of CRD Flange Bohing Specific reference information for each pressure retaining bolted connection identified leaking will be described on the datasheet in Attachment 5.

Evelsenen

• Discuss why mechanical packing and seal leaks do not require a bolted connection evaluation The new ASME Section XI requirements for evaluating bolted connections found leaking during the OPT-80.1 RPV Leakage test VT-2 examinations are for pressure retaining bolted connections and do not apply to non pressure retaining mechanical seals and packing which are designed to wear in service and to leak during the service life of the component. ASME Section XI IWA 5250 Corrective Measures, specifies that the bolting

ESR 99-00279 Revision 0

. Page$ of shall be removed and a VT-3 exammation for indications of corrosion be performed. The ANil confirmed that a packing gland does not constitute a bolted connection subject to the requirements ofIWA 5250,and this is

. documented by memo in Attachment 3. Therefore, mechanical packing and seal leaks are concluded to be outside the bounds of this ESR, and an " EXEMPT' action level classification for corrective measures is specified.

' Discuss each valve / component from the tabulated listing that was observed to leak during the last two refueling outages (B212R1 and B213RI):

1. CRD flange bolting (reference EER 90-059)

2. LPRM/IRM flange bohing ';

3. Recirculating Water Valve 2-B32-F023A/B

4. L Recirculating Water Valve 2-B32-F031 A/B

5. ' Recirculating Water Valve 2-B32-F032A/B

6. Recirculating Water Valve 2-B32-F044A/B

7. Main Steam Inboard Isolation Valve 2-B21-F022A/B/C/D t,. Main Steam Outboard Isolation Valve 2-B21-F028A/B/C/D

• Review fastener materials for susceptibility to corrosion and damage.

- Review of materials:

CRD:

Manufacturer: GE 8 Cap Screws required , SA-193 Grade B7 (AISI 4140 suh originally supplied by GE. EER 91-0324, U2 CRD Flange Bolt Evaluation. All original cap screws were repbced in B210R1 and B21IRI outages per EER action item 2.

SEEF 94-0009 approved use of AISI-4340 bolting material as equivalent on 21Feb94.

There are no nuts installed in this designed use of cap screws. De fasteners thread directly into the reactor Vessel CRD flange housings.

IRM/ LPRM:

Manufacturer: GE 4 Cap Screws required , SA-193 Grade B7 originally supplied by GE. l l

Recist Valves:

Manufacturer: Anchor Darling Valve Company i Bonnet Studs: A193 grade B7 j Bonnet Nuts: A194 grade B8 B32-F023A/B,28 required,1/2FP-05363 B32-F031 A/B,28 required,1/2FP-05363 i B32-F032A/B,8 required, OFP-05365 B32-F043A/B,24 required, OFP-05364 B32-F044A/B,8 required, OFP-05366 MSIV:

Manufacturer: Rockwell International Manufacturmg Co Bonnet Studs: ASTM-540 grade B23 Bonnet Nuts: A194 grade 7

~ B21-F022A/B/C/D,20 studs and nuts required,1/2FP-55013 sheet 3 B21-F028A/B/C/D,20 studs and nuts required,1/2FP-55013 sheet 3

ESR 99-00279 Revision 0 Page$ of Recire piping cleanout bolting:

Manufacturer: Provided with GE supplied piping assembly 1 1/8" stud, AM, Std.

8 required,0FP-05109 sheet 2 For these applications, the original materials include the following steel types:

Stud and cap screw bolting material, A193 grade B7, with A194 grade 8 nuts.

New CRD cap screws, and MSIV bolting material, ASTM A-540 grade B23. MSIV nuts are A194 grade 7.

He Al93, Grade B7 bolting and A194, Grade 7 nut materials are chromium-molybdenum steels with nominal composition of 1.0% chromium,0.2% molybdenum,0.85% manganese, and 0.25% silicon.

ne A194, Grade 8 nut material is an austenitic stainless steel grade with nominal composition of 19%

chromium,9.25% nickel, and 2 % manganese.

He A540, Grade B23 is a chromium-nickel-molybdenum alloy bolting material with nominal composition of l 0.8 % ch~. nnium,1.8 % nickel, and 0.25 % molybdenum.

He austenitic stainless steel material is very resistant to general corrosion, and should not be affected by leakage of reactor coolant water. The other low alloy materials have good resistance to limited exposure to reactor coolant water, but are subject to light general corrosion if exposed to water and oxygen over long periods of time. General corrosion is a dissolution process on the surface of a metal or alloy exposed to a cerrosive environment. Corrosion rates are time dependent and tend to decrease to a low level after prolonged exposure in neutral or slightly alkaline aqueous environments particularly in the absence of aggressive anions such as chloride and sulfate. Samples areas of known or suspected leakage should be visually inspected for general corrosion products within 2 cycles ofidentification of the leakage.

Reactor coolant, during' operation with hydrogen and zinc addition, will be slightly acidic to close to neutral.

With a loss of hydrogen addition, the pH of the coolant will become more acidic. During shutdown the coolant will be acidic. During acidic conditions, the corrosion rate is slightly higher than in the neutral or alkaline conditions. Since hydrogen interruptions are infrequent, the overall corrosion rate would be expected to be low due to the generally neutral environment.

De presence of lubricants, particularly nickel based lubricants, inhibits general corrosion by preventing the i steel from contacting water and oxygen. As lubricants are removed, such as by sprays of water, this benefit may be reduced In the valve bolting applications, lubricants may significantly delay or retard the degree of corrosive attack due to general corrosion.

Galvanic corrosion occurs when dissimilar metals are in contact with each other and are each simultaneously in contset with an electrolyte (fluid which conducts electrical current due to ion exchange). He chloride and sulfate concentrations in the reactor coolant are low (0.5 ppb and 1-2 ppb respectively) during operation and during shutdown his prevents galvanic conosion from being a problem, since low chloride and sulfate ion concentrations do not promote ion exchange in the electrolyte at the cathode and anode surfaces in a galvanic cell, which is necessary to complete the circuit in such a cell.

ESR 99-00279 Revision 0 PageJ00f

• Establishment of action levels Corrective Action Levels:'

_ ne following corrective action levels are established to supplement the OPT-80.1, RPV Hydrotest VT-2 leakage results for pressure retaining bolted connections.

1.) For leakage greater than 120 drops per minute:

Take corrective action to reduce leakage. This may include retorque of bolting.

Evaluate the bolted connection for structural integrity, or remove the bolt and perform a VT-1 examination as directed in the laspection Guidelines.

2.) For leakage equal to or less than 120 drops per minute, but greater than 30 drops per minute:

Corrective action should be taken to reduce leakage. His may include retorque of bolting.

Acceptable risk for continued operation. Expected to seal during normal plant heat up and be l acceptable for the current operating cycle. I 3.) For leakage less than 30 drops per minute:

Acceptable risk for continued operation. Expected to seal during normal plant heat up and be acceptable for the current operating cycle.

Exempt: All non pressure retaining bolted connections which are designed to leak such as mechanical packing or seals are exempted from these examination requirements and require no further action. Economic issues rather than technical ones are employed by management to evaluate the need to correct these leakage sources. Refer specific recommendations to the Outage l Management Team.

• Establishment ofinspection criteria ne inspection guidelines listed below should be followed in the sequence specified, and documented on an j Attachment 5 "0PT-80.1 RPV Leakage Test Bolted Connection Leakage Evaluation Data Sheet"for each j pressure retaining bolted connection leak. Upon completion the Reviewer shall sign and date the evaluation  !

for final review and appmval of this ESR. De Reviewer shall be a currently qualified System or Component  ;

Engineer familiar with the component being evaluated.

Inspection Guidelines:

1. Verify that a pressure retaining bolted connection is leaking in accordance with the RPV Leakage Test OPT-80.1 data snects.

2. Is it a mechanical seal, packing or otherjoint designed to leak as a function of wear, or other non pressure retaining bolted connection? Dese are exempted from further evaluation, and no further action is required.

3. Refer to the Corrective Action Level guidelines and perform the applicable recommendations for sealing.

~ 4. Request QC to perform a General Visual Inspection of the AS FOUND condition for each bolted connection. Document the inspection on the form in Attachment 4.

5. If the General Visual Inspection results air acceptable, then the pressure retaining bolt is qualified for continued service.

6. If the General Visual Inspection identifies unacceptable indications, one of the following actions must be taken:

a

ESR 99-00279 Revision 0 l

Pagegof Attachment 1: ASME TABLE IWB 2500-1, Examination B-G-1 ASME TABLE IWB 2500-1, Examination B-G-2 ASME TABLE IWB 2500-1, Examination B-P l

Attachment 2: '. %ge results from ESR's 96-00208 and 97-00486 I Attachment 3: Memo to Jerry Crider from Ray Acomb, ANII dated 5May99, Section XI-- i 5250 1 Attachment 4: General Visual Inspection Data Sheet for ASME Class 1 Bolted Connections Attachment 5: OPT-80.1 RPV Leakage Test Bolted Connection Leakage Evaluation Data Sheet i

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5 5 5 5 T Tt sTS ) r

) ) ) )

B 1 1 1 1 O) )23 8 B B B B N (1 ( ( 4 567

( ( ( ( _

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• t" EsR %-*uB Rw O I?.e v. o ATAtenm6M 2. PatG d COMPONENT pg 4of k NATURE OF LEAK LEAKAGE RATE

/ CORRECTIVE ACTION

)*

/ -) - 2-E21-V27 2-B21-744-%-603 Packing leak. 60 dpm Corrected by Maintenance.

Through wall.

WR/JO 96-ACPBI

• l 2-B21 F005 Packing leak. 80 dpm Corrected by Maintenance.

2-B21-F01IA P M % leak. 80 dpm WR/JO 96-ACOH1

• 2-EIl F009 Packing leak. 50 dpm i CorixW by M" ^- =

2-B21 F019 PM% leak. 25 dpm CcrixW by Maintenance 2-B21-F028B PMN leak. 50 dpm Corrected by t'" ^

2-B21-F028C Pa% leek. 10 dpm Corra u by u a- _

2-B21 F028D Pd% leak. 20 dpm 1

1 Cor; W by "- = l 2-B32-F044B Sc.4/ - -leak. 5 dpm Hestup.

2-E41-F002 Pa% leak. 20 dpm Corrected by m:-tenance 2-B32-F043A Pecking leak. 5dpm Heatup.

i 2-B32 a 3:B l ggi.k.,,,,, g,g;p,,,,,,,,  !

gyg,,,,c,,,(g,,,,p, 2-B32-F025A Pecking leak. 30 dpm Cc .-W by "'

2-B32-F023B Body?c ^ leak. Steady stream. Heatup.

2-B32-F032A Pecking leak. 3 dpm Heatup.

2-El1-F015B Packing leak. 2 dpm Ae :;^ ade.

2-B21-V55

?A leak. I dpm Hestup 1 l 2-B11 CRD(18-31) Flange leek. 5 dpm Hontup.

2-B11-CRD(22-23) Flange leek. 3 dpm Hostup.

2-Bil-CRD(42-19) Flangeleak. 60 dpm gptggghentu will oPernung ,

2-Bl1-CRD(34-39) Flan 6e leak. 60 dpm will operang ,g -

2-BIl CRD(50-3!) Thige leak. 40 dpm gSiakthat will operstagN -

2-BIl-CRD(02-35) Flange leek. 60 dpm

_ Sink 1 bat will operunas =; ,

2-B11 CRD(1015) Flangeleek. 60 dpm Biskg will

. - =v -

2-Bi14RD(22 03) Flange leak.

60 dpm will o peronas- g ,-

2-BIl CRD(14-47) Flange leek. 8dpm

~ Hestup.

%

• RECOMMENDED PRIOR TO STARTUP

ae>

ESR EVALUATION A"E A tM A6*JT 2. Revision 0 seM3 -con 9 L.EAKAGE RESULTS OUTSIDE DRYWELL %V O pass 20

/ -

hMiMY/E!9.5 bbNh

@Nk bkh0FiLEAK" < iEkbGE CORRECTIVE ACTION

$@$'! F , NR fE-:

2-E21-F005B Packing 40 dpm Adjust packing (97-AGSK1)'

2-E11-F017A Packing 47 dpm Adjust packing (97-AGRM1)*  ;

2-E41-V176 Packing idpm Heatup I 2-E11-F008 Packing 1dpm Adjusted packing (97-AGRP1) 2-E11-V103 Packing idpm Heatup 2-021-V169 Packing 2 dpm Toolpouch work (ADM-NGGC-104)*

2-821-F042 Packing <1 dpm Heatop 2-E21-F005A Packing 10 dpm Adjust packing (97-AGSJ1)*

2-E21-F004A Packing 60 dpm Adjust packing (97-AGS11)*

2-821-V49 Packing 1dpm Heatup 2-821-V50 Packing idpm Heatup 2-821-V51 Packing idpm Heatup l 2-B21-V45 Packing 1 dpm Heatup 2-821-F028A Packing 10 dpm Heatup j 2-021-F0288 Packing 3 dpm Heatup 2-821-F028B Body / Bor. net 3 dpm Heatup 2-B21-F0200 Body / Bonnet 3 dpm Heatup 2-821-F028D Packing 10 dpm Heatup 2-C12- Packing Total of 38 leaks Heatup, repair via Toolpouch V101N102(xx-yy) noted, all s2 dpm work on-line if necessary 2-C12-F101(10-31) Plug 20 dpm Repair (97-AGRX1)*

2-C12-F101(10-19) Plug 60 dpm Repair (97-AGRY1)*

2-C12-F101(18-19) Plug 20 dpm Repair (97-AGRZ1)*

2-C12-F101(10-39) Plug 20 dpm Repair (97-AGSA1)*

2-C12-F101(46-11) Plug 80 dpm Repair (97-AGSB1)*

2-C12-F101(30-23) Plug 2 dpm Repair (97-AGSC1)*

2-C12-F102(18-07) Plug 20 dpm Repair (97-AGSD1)*

2-C12-F102(22-07) Plug 20 dpm Repair (97-AGSE1)*

2-C12-F102(14-31) Plug 20 dpm Repair (97-AGSA1)*

2-C12-F102(14-11) Plug 20 dpm Repair (97-AGSA1)*

2-821-V10 Packing 1dpm Heatup 2-C12-F102(06-15) Plug 20 dpm Repair (97-AGSA1)*

• = Recommended prior to Unit 2 startup.

ESR EVALUATION nnn eo% z Revd o esR 99 - o o 279 I LEAKAGE RESULTS INSIDE DRYWELL REV o '

pas y s E b . dth 2-E41-F002 Packing 1/16" stream Adjusted packing (97-AGRO1) l B11-CRD (06-23) Flange 30 dpm Acceptable risk that heatup will seal leakage based on previous operating experience.

B11-CRD (02-35) Flange 50 dpm Acceptable risk that heatup will seal leakage based on previous operating experience.

B11-CRD (06-19) Flange 20 dpm Acceptable risk that heatup will seal leakage based on previous operating experience.

B11-CRD (34-39) Flange Steady stream Flange bolt torque checked.

(<150 dpm) Indication of some leakage found at pipe connection. Acceptable risk that heatup will seal o<ing leakage based on previous operating experience.

2-832-F023B Body / Bonnet 1/8" stream Heatup 2-832-F031B Body / Bonnet 1/8" stream Heatup 2-832-V39 Packing 1dpm Heatup 2-832-V38 Packing 1dpm Fixed

/ 2-821-F011 A Packing 40 dpm Toolpouch work (ADM-NGGC-104)*

2-832-F043A Packing 60 dpm Toolpouch work (ADM-NGGC-104)*

2-E21-V40 Packing 1dpm Heatup 2-E21-V25 Packing 1dpm Heatup 2-E21-V26 Packing 5dpm Toolpouch work (ADM-NGGC-104)*

2-E21-V27 Packing 5dpm Toolpouch work (ADM-NGGC-104)*

2-E21-V28 Packing 5dpm Toolpouch work (ADM-NGGC-104)*

2-821-F022C Packing 12 dpm Heatup RCR Bypass Flange leak 1/8" stream Repair (97-AGRU1)*

Cleanout Flange l

• = Recommended prior to Unit 2 startup.

l l

-a l

i J

l

l l

A"lTAtakGC 3 ESR 9e,-oo 273 Rev 0 P A 6G ZL i 1

i l

Memo l l

To: Jerry Crider From: Ray Acomb- ANil l CC: L Wheatley insp. File Date: May 5,1999 Re: Section XI-IWA - 5250 Jerry:

Per a discussion with H. S. B.'s Home Office Engineering and RSES E. L. Farrow, it's our position that a packing gland does not constitute a bolted connection. Therefore if leakage is detected from a packing gland during a system pressure test the requirements of IWA - 5250 do not apply.

Please contact me if I can be of further assistance.

Ray Acomb - ANil O

e Page1

ESR 99-00279 Revision 0 Page 23 of

_A_ttachment 4 VISUAL EXAMINATION DATA SHEET Component: Exam Date:

Exam Method: O Direct O Remote NOTE: For all bolted connections with identified leakage, a general visual examination SHALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

O NO degradation noted.

O Localized general corrosion that appears to have reduce the bolt or stud cross-sectional by more than 5 percent.

O Bending, twisting, or deformation of bolts or studs.

O Missing bolts, studs, or nuts.

O Other damage, deformation, or degradation that may be detrimental to the material condition of the bolted connections.

Remarks:

QC Examiner: Date:

ESR 99-00279 Revision 0 Page%f ATTACHMENT 5 OPT-80.1 RPV Leakane Test Bolted Connection Leakane Evaluation Data Sheet

' Refueling outage: B214RI Date: 12MAY99 OPT-80.l Attachment i, Figure 10, Page 54

1. Location and description of Bolted Connection Leakage:

2-B32 F031 A, Recirc Loop A Discharge Valve; RB2, EL014, DW Az 11I The valve was observed leaking less than 1 Drop per minute at the body to bonnet bolted connection.  ;

( See attached the General Visual Examination Data Sheet)

2. Other References (P&lD, system drawings, vendor foreign prints etc):

C-02409 (shs 00019-1 and 0020-1), Tech Manual FP-50274, DBD-02, D-02548 sh0002B, D-02548 sh002A,1/2 FP-5363, D-02518 (sh0001 A and 0001B)

3. The number and service age of the bolts :

28 studs and nuts greater than 10 years old

4. Bolt and component material :

Body to bonnet studs A193 grade B7 Bonnet nuts A194 grade 8

5. Corrosiveness of the process fluid that is leaking:

The corrosiveness of the reactor coolant is described in the Evaluation section of ESR 99-00279.

6. System function of the leaking bolted connection:

Recire discharge valves close to isolate the loop on a LOCA ECCS signal to prevent LPCI flow diversion, pressure retaining boundary, isolation for pump and valve maintenance.

7. Leakage history at the connection or other system components:

2-B32-F031B body to bonnet leak the last two hydros. 'Ihere was no leakage for the 2-B32-F031 A during the last two cycles identified.

Evaluation:

Inspection results indicate only light corrosion on the studs for the body to bonnet leak identified.

The one drop per minute leakage identified for this bolted conr.ection during the RPV leakage test is insignificant and will seal up during the plant heatup and operations as has been shown for other similar valves located in the Drywell on the recire system. No corrective action is required for this condition.

Joint integrity is acceptablefor this connection based on thefollowing:

• No significant corrosion or other degradation ofthe bolting uns observed e Plant experience with this botting andflange material on primary system connections confirms that sigmficant degradation will not occur with minor leakage.

• Plant operational history indicates that leakage will be reduced or eliminated duringplant heatup.

• General corrosion rates are very lowfor this bolting material when exposed to reactor coolant.

• Plant andindustry experience with this botting material in BWR service confirms that service age is not a

. significantfactor in degradation.

Accordingly, nofurther evaluation is warranted Reviewer:

r

[V Date: hb

w-- ,

ESR 99 00279 Revision 0 Page6of Attachment 4 I

VISUAL EXAMINATION DATA SHEET Component: 2 -OMA Exam Date: 5-12-9 9 Exam Method: @irect O Remote NOTE: For all bolted connections with identified leakage, a general visual examination SHALL be performed ,

either DIRECFLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable i for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

j

[ NO degradation noted.

O Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more than 5 percent.

O Bending, twisting, or deformation of bolts or studs.

O Missing bolts, studs, or nuts. j 1

0 ' Other damage, deformation, or degradation that may be detrimental to the material condition of the i bolted connections.

Remarks:

J AL.slE. dAs REfPih M 604Et t TO b o O4 . LES S THAc3 044. j DeoA Pa t. M.ca0Tk. LIGHT - P o s T ne] 5rdel.

QC Examiner: ) Date: I'd ~3 $

\

rp r

ESR 99-00279 I Revision 0 Pageit,of

, . OPT-80.1 RPV Leakane Test Bolted Connection Leakane Evaluation Data Sheet i Refueling outage: B214RI Date: 12MAY99 OPT-80.1. Attachment I, Figure 4 page 7 l

1. Location and description of Bolted Connection Leakage:

2-B32 F031B, Recire Loop B, Discharge Valve; RB2, El 015, DW Az 291 The valve was observed leaking 120 drops per minute from the body to bonnet bolted connection.

(See attached the General Visual Examination Data Sheet)

2. Other References (P&lD, system drawings, vendor foreign prints etc)

l. C-02409 (shs 00019-1 and 0020-1), Tech Manual FP-50274, DBD-02, D-02548 sh0002B, D-02548 sh002A, l/2 FP-5363, D-02518 (sh0001 A and 0001B)

3. The number and service age of the bolts 28 studs and nuts greater than 10 years old

4. Bolt and component material

. Body to bonnet studs A193 grade B7 Bonnet nuts A194 grade 8 l S. Corrosiveness of the process fluid that is leaking:

l The corrosiveness of the reactor coolant is described in the Evahiation section of ESR 99-00279.

6. System function of the leaking bolted connection l' Recire discharge valves close to isolate the loop on a LOCA ECCS signal to prevent LPCI flow diversion, pressure retaining boundary, isolation for pump and valve maintenance

7. Leakage history at the connection or other system components 2-B32-F031B body to bonnet leak the last two hydros.

Evaluation:

The 2-B32 F031B valve was observed leaking 120 drops per minute during the RPV leakage test. The bolted connection General Visual Inspection data sheet found a light corrosion on the studs, and no degradation was noted. His valve historically has seen a steady 1/8 inch stream ofleakage during the last two leakage tests, and has been visually inspected during heatup to seal for normal plant operation. Historical retorquing of the  !

body to bonnet bolts for this valve has not reduced the leakage. With the emergent work associated with the 1 body to bonnet bolted connection on the 2-B32-F023B Recire Suction Valve of the same Anchor Darling pattern during this B214R1 outage, WR/JO 99-ADKA 1 was initiated to work this valve during the next refueling outage B215RI. His will provide sufficient time to develop a detailed work plan in a high dose area in the drywell. No corrective actions are required at this time.

Joint integrity is acceptablefor this connection based on thefollowing:

e No sigmficant corrosion or other degradation ofthe bolting was observed e Plant experience with this bolting andflange materia! on primary system connections confirms that sigmficant degradation will not occur with minor leakage.

• Plant operational history indicates that leakage will be reduced or eliminated during plant heatup.

• General corrosion rates are very lowfor this botting material when exposed to reactor coolant.

• ' Plant andindustry experience with this bolting materialin BWR service confirms that service age is not a signficantfactorin degradation.

Accordingly, nofurther evaluation is warranted l

p Reviewer: /s Date: I f l

m -m ._, ,

/ OF 1 f Q' h65 ,-

ESA $3.o003

. . 1sv o VISUAL EXAMINATION DATA SHEET l Component: 2B32- Fo a I a exam Date: 5- /o- W Exam Method: hirect O Remote NOTE: For all bolted connections with identified leakage, a general visual l examinatien SHALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local {

environmental conditions) using the examination attributes listed below. J Check, as applicable:

I NO degradation noted.

O Localized general corrosion that appears to have reduce the bolt or stud cross-sectional by more than 5 percent.

O Bending, twisting, or deformation of bolts or studs.

O Missing bolts, studs, or nuts.

O Other damage, deformation, or degradation that may be detrimental to the material condition of the bolted connections.

Remarks:

/4wr $cMosY od Gn/Ps.

/ja 5-m-w QL i

'J L , G s-i z - i l Q C_.

F l-

\

ESR 99-00279 Revision 0

! Pagedgf ATTACHMENT 5 OPT-80.1 RPV Leakare Test Bolted Connection Leakane Evaluation Data Sheet Refueling outage: B214R1 Date: 12MAY99 OPT-80.1 Atta:hment 1, Figure 4, page 7

1. Location and description of Bolted Connection Leakage:

2-B32-F044B, Recirc Pump 2B Equalizer Bypass Valve; RB2, El 035, DW Az 197 The valve was observed to leak 4 drop per minute at the body to bonnet bolted connection l

( See attach the General Visual Examination Data Sheet)

2. Other References (P&lD, system drawings, vendor foreign prints etc): j D-02548 sh002A l

3. The number and service age of the bolts 8 studs and nuts greater than 10 years old l

4. Bolt and component material i Body to bonnet studs A193 grade B7 Bonnet nuts A194 grade 8

5. Corrosiveness of the process Guid that is leaking-The corrosiveness of the reactor coolant is described in the Evaluation section of ESR 99-00279.

6. System function of the leaking bolted connection Valve is closed and no longer used for pleni manipulation. Pressure retaining boundary

7. Leakage history at the connection or other system components l Body to bonnet leak the B212RI hydros. j Evaluation:

Inspection results indicate only light corrosion on the studs for the body to bonnet leak identified.

i The four drop per minute leakage identified for this bolted connection during the RPV leakage test is l insignificant and will seal up during the plant heatup and operations as has been shown for other similar valves located in the Drywell on the recirc system. No corrective action is required for this condition.

Joint integrity is acceptablefor this connection based on thefollowing:

• No sigmficant corrosion or other degradation ofthe bolting was observed e Plant experience with this bolting andflange material onprimary system connections confirms that sigmficant degradation will not occur with minor leakage.

• Plant operational history indicates that leakage will be reduced or eliminated during plant heatup.

• General corrosion rates are very lowfor this bolting material when exposed to reactor coolant.

• Plant andindustry experience with this bolting materialin BWR service confirms that service age is not a sigmficantfactorin degradation.

Accordingly, nofurther evaluation is warranted Reviewer:

r M Date: 7I .

1

T:-

ESR 99-C0279 Revision 0 Page W 19 l Attachment 4 l VISUAL EXAMINATION DATA SHEET {

Component: 2 EfA FOll'fII Exam Date: /A!ff Exam Method: Remote '

NOTE: For all bolted connections with identified leakage, a general visual examination SHALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

NO degradation noted.

O Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more 1 than 5 percent.

Bending, twisting, or deformation of bolts or studs.

Missing bolts, studs, or nuts.

Other damage, deformation, or degradation that may be detrimental to the material condition of the bolted connections.

i Remarks l a J ., L_ L ~ . M I...,._ l ~ b D n L, -

~

QC Examiner: WI (b, Date: b

l l

ESR 99-00279 Revision 0 j Page3aaf ATTACHMENT 5 OPT-80.1 RPV Leakane Test Bolted Connection Leakane Evaluation Data Sheet l Refueling outage: B214RI Date: 12MAY99 OPT-80.1 Attachment I, Figure (A) 21, page 26 (B)25 page 30

( C),29 page 34

1. Location and description of Bolted Connection Leakage:

2-B21-F028A, Main Steam Outboard Isolation Valve, RB2, El 020, WW 1121 R,2DPM 2-B21-F028B, Main Steam Outboard Isolation Valve, RB2, El 020, WW 1121R,2 DPM i 2-B21-F028C, Main Steam Outboard Isolation Valve, RB2, El 020, WW 1121R,10 DPM '

nese valves were observed leaking from the body to bonnet connections

- (See attached the General Visual Examination Data Sheets)

2. Other References (P&lD, system drawings, vendor foreign prints etc):

1/2 FP-55013 sh013, FP-50554, DBD-25,0FP-05101 l

3. The number and service age of the bolts i 20 studs and nuts required. No studs or nuts changed in last 3 years

4. Bolt and component material ,

Body to bonnet studs ASTM-540 grade B23 l Body to bonnet nuts ASTM-194 grade 7

5. Corrosiveness of the process fluid that is leaking:

The corrosiveness of the reactor coolant is described in the Evaluation section of ESR 99-00279. I

6. System function of the leaking bolted connection MSIVs fail closed with a variety of primary containment isolation signals. Pressure retaining boundary.

7. Leakage history at the connection or other system components J 2-B21 F028B, and 2-B21-F028C were observed leaking B213RI.

Evaluation:

Inspection results indicate only light corrosion on the studs for the body to bonnet leak identified. l The three observed leaks, with rates from two to ten drops per minute, identified for these bolted connections during the RPV leakage test is insignificant and will seal up during the plant heatup and operations as has been shown previously by plant history. ne valves are located in the MSIV pit which is an enclosure which has limited air flows during operation and is subject to high ambient temperatures as a result of the waste heat from the main steam lines passing through the pit from the reactor vessel to the turbine building. No corrective action is required for this condition.

Joint integrity is acceptablefor this connection based on thefollowing:

• No sigmficant corrosion or other degradation ofthe bolting was observed e Plant aperience with this bolting andflange material on primary system connections confirms that significant degradation will not occur with minor leakage.

• Plan: operational history indicates that leakage will be reduced or eliminated during plant heatup.

e General corrosion rates are vs.ry lowfor this bolting material when exposed to reactor coolant.

• Plant and industry experience with this bolting materialin BWR service confirms that service age is not a sigmficantfactor in degradation.

l Accordingly, nofurther evaluation is w nted Reviewer: _

6k E UmhA40 Date: 0%N

p-ESR 99-00279 Revision 0 PageNof Attachment 4 VISUAL EXAMINATION DATA S11EET Component: So MA Exam Date: .$2/2-9 9 Exam Method: E Direct Remote NOTE: For all bolted connections with identified leakage, a general visual examination SIIALL be performed I cither DIRELTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

NO degradation noted.

Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more

, than 5 percent.

l l

i Bending, twisting, or deformation of bolts or studs.

l Missing bolts, studs, or nuts.

Other damage, deformation, or degradation that may be detrimental to the material condition of the bolted connections.

Remarks:

l*5N $u37 m An/fa, nY F/w a/ Aob, 75 A /

L 54 sr A, L / 90 * - 4 ".N B,n, N L r sea to w l me-7Y S b /s M l

l QC Examiner: -

_e-Date: 6/E*fi f

L

4 ESR 99-00279 Revision 0 Pagc32pf Attachment 4 VISUAL EXAMINATION DATA SilEET Component: #o2*A Exam Date: SVE-f 1 I Exam Method: @ Direct Remote NOTE. For all bolted connections with identified leakage, a general visual examination SHALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

C NO degradation noted.

Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more than 5 percent.

Bending, twisting, or deformation of bolts or studs.

Missing bolts, studs, or nuts.

Other damage, deformation, or degradation that may be detrimental to the material condition of the  ;

bolted connections. l l

Remarks: I

$4)$~Aou7

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AY AsJfun WO**

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l QC Examiner: # Date: f/.2 #7 l

l l

l L.

ESR 99-00279 Revision 0 PageBof l

Attachment 4 VISUAL EXAMINATION DATA SHEET Component: po;2T C Exam Date: SV2-ff l

Exam Method: EDirect Remote NOTE: For all bolted connections with identified leakage, a general visual examination SHALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

O NO degradation noted.

Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more l

than 5 percent.

Bending, twisting, or deformation of bolts or studs.

O Missins bolts, studs, or nuts. l 1

0 Other damage, deformation, or degradation that may be detrimental to the material condition of the bolted connections.

Remarks:

$4/7 hs7 eao de/M, novel p/ m ,p g ,/,y; L 9 7_ ),,hac

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QC Examiner: A Date: SVE- M i

l l

l

ESR 99-00279 Revision 0 PageNof ATTACHMENT 5 OPT-80.1 RPV Leaksee Test Bolted Connection Leakage Evaluation Data Sheet Refuelingoutage: B214RI Date: 12MAY99 OPT-80.1 Attachment , Figure 58, Page 73 and 74

1. Location and description of Bolted Connection Leakage:

2-B11-CRD(02-19), Control Rod Drive Assembly, RB2, El 023, DW Az 000,100 DPM 2-B11-CRD(06-23), Control Rod Drive Assembly, RB2, El 023, DW Az 000,4 DPM 2-B11-CRD(06-35), Control Rod Drive Assembly, RB2, El 023, DW Az 000,4 DPM 2-BIl-CRD(14-47), Control Rod Drive Assembly, RB2, El 023, DW Az 000,15 DPM 2-B11-CRD(26-07), Control Rod Drive Assembly, RB2, El 023, DW Az 000,15 DPM

( See attached General Visual Examination Data Sheet)

2. Other References (P&lD, system drawings, vendor foreign prints etc):

RICSIL No,019, SIL 483 rev 1 and 2, GE Dwg 36242107A, FP-05920, DBD-08, EER 91-0324, EER 90-0059, SEEF 94-009, GE Memo dated 3AUG93 Control Rod Drive Flange Leakage Guidelines

3. The number and service age of the bohs 8 cap screws required. All cap screws replaced between 1991 and 1993. Cap screws are replaced every time the CRD mechanism is replaced or rebuilt.

2-B11-CRD(02-19) and 2-B11-CRD(06-23) were replaced in 1997 with AISI-4340 bolting material.

4. Bolt and component material Cap screws were SA-193 Grade B7 (AISI 4140 steel) as originally supplied by GE. Per EER 91-0324, U2 CRD Flange Bolt Evaluation, all original cap screws were replaced with new original bolting material.

SEEF 94-0009 approved use of ASTM 540 grade B23 (AISI-4340) bolting material as equivalent on 21Feb94. Greater than 50% of the cap screws have been replaced with the improved corrosion resistant material since then. Here are no nuts installed in this designed use of cap screws. The fasteners thread directly into the reactor Vessel CRD flange housings in a blind threaded hole.

5. Corrosiveness of the process fluid that is leaking:

The corrosiveness of the reactor coolant is described in the Evaluation section of ESR 99-00279.

6. System function of the leaking bolted connection Insert and withdrawal of the control rod blades for reactivity control. Pressure retaining boundary.

7. Leakage history at the connection or other system components Typically, there are several CRD assemblies which exhibit leakage during each hydrotest.

2-B11-CRD(06-23) leaked 30 DPM during the B213R1 outage as compared to 4 DPM this outage. 2-B1l-CRD(14-47) leaked 8 DPM during the B212RI outage, did not leak during B214RI and leaked 4 DPM this outage. He other CRD's found leaking did not exhibit leakage during the last two refueling outages.

Evaluation:

In the late 1980's, GE observed a cap screw susceptibility to stress corrosion of the CRD bolting. The original material was upgraded to a high strength more stress corrosion resistant material by GE SIL 483 revisions I and 2. CP&L replaced all the original bolting with new original bolting material between 1991 and 1993, and performed a VT 1 examination for each bolt insalled. Since 1994 we have replaced car screws with the new upgraded material each time that a CRD assembly is removed for replacemer,r Currently there are greater than 50% of the cap screws which have been upgraded to the new material. Between 1989 and 1991 three evaluations on CRD bolting were performed by the HE&EC to evaluate pitting and stress corrosion cracking l

l

ESR 99-00279 Revision 0 Pagegf on cap screws which had been in service in Unit 2 for 16+ years. They found that the tensile testing results indicated that the pitting and stress corrosion did not significantly affect the tensile strength of the bolting, and that the transition zone between the bolt head and shank was the area of greatest susceptibility to corrosion and pitting.

He CRD's routinely exhibit leaking flange connections during the RPV hydrotest performed each refueling outage. CP&L has established guidelines which follow the general guidance specified in the GE Memo dated 3 Aug93 for system manipulations to reduce leakage flow to less than 30 drops per minute. Historical inspections have verified that during plant startup/ heatup to normal operating conditions the CRD flange leaks seal up.

The General Visual Inspection performed per this ESR to identify bolted connection leakage is limited to only i the top of ti,e CRD cap screw since the CRD assembly is fastened to the RPV guidetube flange using blind threaded holet inspection of the cap screw transition zone between the head and the shank of the bolt which  ;

is the most seraitive to pitting and corrosion cannot be performed unless the cap screw is removed. The l General Visual laspection preformed indicated no degradation noted.

Summary: l Based on a minimum previously evaluated service life of 16+ years, and work practices which routinely 4 replace the cap screws with new corrosion resistant bolting since 1994, the probability of bolted connection I failure resulting in equipment damage is very low. Historical verification has confirmed that leaks less than 30 l drops per minute will seal up during startup/ heatup of the plant. He CRD was not found to exhibit significant corrosion when the General Visual Inspection was performed.

Joint integrity is acceptablefor this connection based on thefollowing:

• No sigmficant corrosion or other degradation ofthe bolting was observed e Plant experience with this bolting andflange material onprimary system connections confirms that sigmficant degradation will not occur with minor leakage.

• Plant operational history indicates that leakage will be reduced or eliminated during plant heatup.

• General corrosion rates are very lowfor this bolting material when exposed to reactor coolant.

• Plant and industry experience with this bolting material in BWR service confirms that service age is not a sigmficantfactor in degradation.

Accordingly, nofurther evaluation is warranted Reviewer M M Date: 8 9 1

ESR 99-00279 Resision 0 Page W 3(,

Attachment 4 VISUAL EXAMINATION DATA SilEET Component: Exam Date: I-/2*kk Exam Method: irect O Remote NOTE: For all bolted connections with identified leakage, a general visual examination SII ALL be performed either DIRECTLY or REMOTELY with sufficient illumination (natural or artificial) and resolution (suitable for the local environmental conditions) using the examination attributes listed below.

Check, as applicable:

. NO degradation noted.

O Localized general corrosion that appears to have reduced the bolt or stud cross-sectional area by more than 5 percent.

O Bending, twisting, or deformation or bolts or studs.

O Missing bolts, studs, or nuts.

I O Other damage, deformation, or degradation that may be detrimental to the material condition of the 1 bolted connections.

Remarks:

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FORM 2 E.SR % -oom l Sheet 1 of 1 ggy o j Generic ESR Comment Sheet 93,g 37 ESR No: 99-00279 Revision: 0 Reviewed by: Jerry W. Crider Organization: BESS leem # Comments ' - e -

Resolution '; -

1 Page 5, Design inputs, Relief Request 17 -

j

" June 1998" should be "May 1998". The requirements of the '89 Edition of Section LM j XI when in effect May 11,1998.

2 Page 6, Since we are not performing a VT-  % <A @ e r-e-A xaminat on, why is IWA 2213 included A  %

3 Page 7. Evaluation - Should be clarified that CP&L's position is that RR#17 does Wik M f.O M not apply to non-pressure retaining bolted connections, such as packing gland. This be A W.

position was discussed with the ANil and he agreed. The ANil concurrence is document in Attachment 3.

4 Corrective Action Level,2) - Recommend

/ changing "Retorque bolting..." to "Take C corrective action to reduce leakage" 5 Inspection Guideline, 6) - Recommend rewording as follows "If the General Visual Examination identifies unacceptable

., indications, one of the following actions must be taken: 1) evaluate the degraded bolting for structural integrity for continued service OR 2) remove the degraded bolt closest to the source of leakage and perform a VT 1 examination of the bolting using the following attributes:.

j 6 Attachment 4, Add a line for the examiner y to sign and date the data sheet.

7 Attachment 5,1. - Change " Attach OC y visual inspection report (VT-1)..." to "

Attach the Visual Examination Data Q

Sheet."

Comments h ve been satisfactorily resolved and incorporated in the ESR:

RE Date 13 %g l EGR-NGGC-005 l Rev. 9 l Page 92 Of 106 l

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{ ATTACHMENT 2 s-c l

Sheet 1 of 1 Cw 'o Record of Lead Review l

Design f5/2. 9966 M 7 Revision C I The signature below of the Lead Reviewer records that:

- I the review indicated below has been performed by the Lead Reviewer; appropriate reviews were performed and errors / deficiencies (for all reviews performed) have been resolved and these records are included in the design package; the review was performed in accordance with EGR-NGGC-0003.

@ Design Verification Review Engineering Review

@ Design Review Owner Review 0 Alternate Calculation '

O ouaiification Testing Spec ngineerin i S Records are anached.

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