ML20236Y548

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Rev 1 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20236Y548
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 08/03/1998
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20236Y537 List:
References
PROC-980803, NUDOCS 9808120292
Download: ML20236Y548 (46)
v • d • e


Text

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Revision 1 l

i BRAIDWOOD STATION UNITS 1 AND 2 SECOND INTERVAL INSERVICE INSPECTION PROGRAM PLAN-NRC SUBMITTAL l

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BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL i

REVISION

SUMMARY

l Effective Pane (s) Revision Date i-il 1 7/28/98 iii 0 2/20/)8 1-1 to 1-3 0 2/20/98 2-I to 2-27 0 2/20/98 3-1 to 3-6 0 2/20/98 4-1 to 4-2 0 2/20/98 5-1 to 5-3 0 2/20/98 6-I to 6-3 0 2/20/98 6-4 1 7/28/98 6-5 0 2/20/98 6-6 1 7/28/98 6 7 to 6-15 0 2/20/98 7-I to 7-4 0 2/20/98 7-5 1 7/28/98 7-6 0 2/20/98 7-7 to 7-8 1 7/28/98 7-9 to 7-12 0 2/20/98 7-13 1 7/28/98 7-14 to 7-21 0 2/20/98 7-22 1 7/28/98 7-23 0 2/20/98 7-24 1 7/28/98 7-25 0 2/20/98 7-26 to 7-27 1 7/28/98 7-29 to 7-31 0 2/20/98 7-32 1 7/28/98 7-33 to 7-34 0 2/20/98 7-35 1 7/28/98 7-36 to 7-39 0 2/20/98 8-1 0 2/20/98 8-2 to 8-4 1 7/28/98 8-5 to 8-8 0 2/20/98 8-9 to 8-13 1 7/28/98 8-14 to 8-48 0 2/20/98 8-49 to 8-56 1 7/28/98 8-57 to 8-63 0 2/20/98 8-64 to 8-69 1 7/28/98 8-70 to 8-107 0 2/20/98 8-108 to 8-109 1 7/28/98 8-110 to 8-113 0 2/20/98 8-114 to 8-121 1 7/28/98 9-I to 9-26 0 2/20/98 10-1 to 10-2 0 2/20/98 l

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Revision 1 l HRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL i

6.1 BASIS FOR CONTAINMENT INSERVICE INSPECTION PROGRAM 6.1.1 ASME Section XI Examination Requirements Per the requirements of the Code Of Federal Regulations, Title 10, Part 50, Section 55a, (10 CFR 50.55a), this Containment ISI Program Plan was developed in accordance with the requirements delineated in the 1992 Edition, 1992 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsections IWE and IWL, as modified by 10 CFR 50.55a(b)(2)(ix) and 10 CFR 50.55a(b)(2)(x) and Inspection Program B of IWE-2412 and IWL-2410, except as follows:

l 6.1.1.1 10 CFR 50 Appendix J leak testing will be performed on gaskets and seals in lieu of VT-3 Visual Examinations required by IWE. Relief Request 12R-23 of Section 8.0 has been developed to employ these alternative rules.

6.1.1.2 When performing the visual examinations required by IWL-2510

, remotely, the maximum direct examination distance specified in Table IWA-2210-1 may be extended and the minimum illumination requirements specified may be decreased provided tilat the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination. Request I2R-24 of Section 8.0 has been developed to employ these alternative rules.

6.1.1.3 The paint and coatings in the containment will be examined in accordance with the existing Braidwood Station painting and coating requirements. If degradation of the coating is identified, additional measures will be applied to determine if the containment pressure boundary is affected. Relief request 12R-25 and I2R-26 of Section 8.0 have been developed to employ these alternative rules.

6.1.1.4 Relief Request I2R-27 of Section 8.0 has been deleted.

6.1.1.5 Examination of repairs will be performed in accordance with the requirements ofIWA-4150. Relief Request I2R-28 of Section 8.0 has been developed to employ these alternative rules.

6-4 u__ _______ - . . _ . _ _ .- _

l.' .

Revision ! l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL Table 6.1.4-1 COMPONENT CLASSIFICATIONS Design Construction Containment Part Code Reference Braidwood Code

< Spec.

1. Containment Concrete CC UFSAR F/L-2722 ACI-ASME-359, Sec. 3.8.1 1974
2. Post-Tensioning Sfstem CC UFSAR F/L-2721 ACI-318-71 Sec. 3.8.1
3. Steel Liner CC UFSAR F/L-2725 CC Sec. 3.8.1
4. Equipment Hatch Air MC UFSAR F/L-2725 MC Lock Sec. 3.8.2
5. Emergency Personne! Air MC UFSAR F/L-2725 MC Lock Sec. 3.8.2 l 6. Electrical Penetrations MC UFSAR F/L-2725 MC, Summer 78 Sec. 3.8.2 F/L-2804 IEEE-317 F/L-2804-01 l
7. Mechanical Pipe Penetration l
a. Type I Head Fittings ASME UFSAR F/L-2725 ASME Section III (MS & FW Lines) Section Sec. 3.8.2 F/L-2787 III F/L-2739 l Sleeve MC UFSAR F/L-2725 MC,1974 l Sec. 3.8.2 F/L-2787 l b. With Type II Head MC UFSAR F/L-2725 MC,1974 l

Fitting Sec. 3.8.2 F/L-2787

c. With Type III Head MC UFSAR F/L-2725 MC,1974 l

! Fitting Sec. 3.8.2 F/L-2787 t

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d. Fuel Transfer Canal MC UFSAR F/L-2725 MC,1974 Sec. 3.8.2 F/L-2787
c. Recirculation Sump MC UFSAR F/L-2725 MC,1974 Piping Sec. 3.8.2 F/L-2787
8. Polar Crane Bracket CC UFSAR F/L-2725 CC Integral Attachment Plate Sec. 3.8.1 to Liner
9. Other Integral Attachments CC UFSAR F/L-2725 CC l to Liner Sec. 3.8.1 6-6 f

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Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL TABLE 8.0 ISI PROGRAM RELIEF REQUEST INDEX 1

Relief Request Summary Revision 12R-01 Alternative Examination for Branch Pipe Connections Designed 0 with Reinforcement Saddles i 12R-02 Limited Surface Examination of Centrifugal Charging Pump, I Residual Heat Removal Pump, and Containment Spray Pump Integral Attachment Welds I2R-03 Limited Examination of Reactor Coolant System Piping Weld 0 Due to Whip Restraint Obstructions 12R-04 Limited Volumetric Examination of Main Steam and Feedwater 0 System Welds Due to Ultrasonic Scanning Obstructions 12R-05 Alternate Hydrostatic Pressure Test Requirements for ASME O Class 1,2 and 3 Repaired / Replaced Components - Use of Code Case N-416-1 12R-06 Alternative Rules for Hydrostatic Testing of Class 3 Components 0

- Use of Code Case N-498-1 12R-07 Limited Volumetric Examination of Residual Heat Removal Heat 0 Exchanger Nozzle-to-Shell Welds and Nozzle Inner Radii I2R-08 Volumetric Examination of the Pressurizer Surge Nozzle-to- 0 Vessel Head Weld and Surge Nozzle Inside Radius Section 12R-09 Limited Surface Examination of the Pressurizer Seismic Lug 0 Welds l 12R-10 Limited Surface Examination of Piping Penetration Integral 1 Attachment Welds 12R-11 Alternate Rules to Table IWC-2500-1, Category C-H: Pressure 0 t Testing of Containment Penetration Piping With Attached Nonclassed Piping 12R-12 Alternative Rules for Insulation Removal at Bolted Connections 0 in Systems Borated for the Purpose of Controlling Reactivity 12R-13 Alternative Rules for Corrective Measures ifleakage Occurs at 0 Bolted Connections 12R-14 Alternative Rules to IWF-5000 Inservice Inspection 1 Requirements l

s., l

Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL 1 ISI PROGRAM PLAN-NRC SUHMilTAL 1 I

TABLE 8.0 ISI PROGRAM RELIEF REOUEST INDEX (Cont'd)

Relief Request Summary Revision 12R-15 Alternative Rules For the Selection and Examination of Class 1, 1 2 and 3 Integrally Welded Attachments - Use of Code Case N-509 12R-16 Alternative Rules for Deferral ofInspections on Nozzle-to- 0 Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End '

Welds of the Reactor Vessel - Use of Code Case N-521 12R-17 Alternate Examination Requirements for Longitudinal Welds in 0 Class 2 Piping - Use of Code Case N-524 12R-18 Limited Volumetric Examination of Reactor Pressure Vessel 0 Circumferential Shell Welds and Lower Head Circumferential Welds 12R-19 Use of Alternative Examination Requirements, Examination 0 Method, and Acceptance Standard for Reactor Vessel Closure IIead Nuts 12R-20 Limited Volumetric Examination of Reactor Pressure Vessel 0 (RPV) IIead-to-Flange Weld 12R-21 Alternate Rules for the Deferral of Inspectior s on the Reactor 0 Pressure Vessel (RPV) Shell-to-Flange Weld s) l J

I2R-22 Limited Volumetric Examination of Reactor l'ressure Vessel 0 l

Nozzle-to-Vessel Welds 12R-23 Alternative Examination Requirements For Seals and Gaskets 0 12R-24 Alternative Visual Examination Requirements for Minimum 0 l Illumination and Maximum Direct Examination Distance of Class CC Components l

I2.R-25 Alternative Requirements for Preservice Examination of Paints 0 l and Coatings I2R-26 Alternative Requirements for Examination of Paints and 0 Coatings Prior to Removal 12R-27 Deleted 1 i i l l 8-3 I

,- o Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL TABLE 8.0 ISI PROGRAM RELIEF REQUEST INDEX (Cont'd)

Relief Request Summary Revision 12R-28 Alternative Requirements for Successive Examination of Class 0 MC & CC Components 12R-29 Alternative Requirements for Torque and Tension Testing of 0 Class MC Pressure Retaining Bolting 12R-30 Alternative Rules for Insulation Removal at Bolted Connections 1 in Systems Borated for the Purpose of Controlling Reactivity Based on Material Types I2R-31 Alternative Rules for Insulation Removal at Bolted Connections 1 on The Reactor Vessel and Steam Generator Primary Manways I

l 1

J I

8-4 I

,- .- Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-02 (Page 1 of 5)

COMPONENT IDENTIFICATION Code Class: 2

References:

Table -2500-1, of Code Case N-509 Examination Categories: C-C Item Numbers: C3.30

Description:

Limited Surface Examination of Centrifugal Charging Pump, Residual Heat Removal Pump, and Containment Spray Pump Integral Attachment Welds Component Numbers: CVP-01*, CVP-02, CVP-03, CVP-04 [ Pumps 1(2)CV01PA]

CVP-01, CVP-02, CVP-03, CVP-04 [ Pumps 1(2)CV01PB]

RHP-Ol*, RHP-02, RHP-03 [ Pumps 1(2)RH01PA]

RHP-01, RHP-02, RHP-03 [ Pumps 1(2)RH01PB]

CSP-Ol**, CSP-02, CSP-03, [ Pumps 1(2)CS01PA]

CSP-04***, CSP-05, CSP-06, [ Pumps 1(2)CS01PB]

(*) Denotes welds selected for inspection during the interval

(**) "A" Pump selected only for Unit 2

(***) "B" Pump selected only for Unit 1 Drawing Numbers: 1RHP-01 (Unit 1), 2RHP-01 (Unit 2)

ICSP-01 (Unit 1), 2 CSP-01 (Unit 2)

CODE REQUIREMENTS Note: Braidwood Station is using Code Case N-509 as an alternative to the requirements of Table IWC-2500-1, Category C-C of the 1989 Edition of Section XI.

Table -2500-1 of Code Case N-509, Category C-C, Item Number C3.30 requires a 100%

surface examination of Pump Integrally Welded Attachments per Figure IWC-2500-5. Per

)

i Note 5, a 10% sample of the welded attachments associated with the component supports j selected for examination under the 1990 Addenda, IWF-2510 shall be examined. Note:

)

Braidwood Station is employing Code Case N-491 for selection of supports for examination.

The requirements of Code Case N-491 -2510, are the same as those in 1990 Addenda, IWF-2510.

Table IWC-2500-1, Examination Category C-H, Item Numbers C7.50 and C7.60 requite pressure retaining pumps to be pressure tested and VT-2 examined.

CODE REQUIREMENTS FROM WHICH RELIEF IS REOUESTED Relief is requested for Table -2500-1, of Code Case N-509, Category C-C, Item Number C3.30 which requires a 100% surface examination of Pump Integrally Welded Attachments per

. Figure IWC-2500-5.

8-9

l t

Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITI'AL RELIEF REQUEST 12R-02 (Page 2 of 5)

BASIS FOR RELIEF i

Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.

The design of the Centrifugal Charging Pump, Residual Heat Removal Pump and Containment Spray Pump support lugs obstruct portions of the associated integral attachment welds from the code required surface examination. The obstructed areas are shown in Figures 1,2 and 3. As detailed in these Figures, the portion of the subject weld within the recess between the pumps and the support does not provide sufficient clearance to perform a surface examination. The approximate amount from field measurements and First Interval inspection data of accessible weld length per lug that can be surface examined is as follows: 77% for the CV pump,76%

l for the RH pump, and 65% for the CS pump.

Reasonable assurance of the continued inservice structural integrity of the subject weld (s) will be achieved without performing the complete Code examination based on the following. When

j. a pump has a lug scheduled for inspection, all the lugs on that pump will be inspected to the l maximum extent possible. The Code required surface examination will be performed for the l subject pump on all the accessible portions of all pump lug welds. A visual VT-1 inspection l will be performed on the portions of the subject welds which are obstructed. Performance of the alternative Visual, VT-1 examination of the obstructed weld length will provide an acceptable level of quality and safety. These are not full penetration welds, but surface fillet welds. In addition, a VT-2 examination during system pressure testing per Category C-H is also performed on these pumps each inspection period to verify leaktight integrity.

PROPOSED ALTERNATE PROVISIONS l

l When a pump has a lug scheduled for inspection, all the lugs on that pump will be inspected to the maximum extent possible per the below requirements:

(1) The Code required surface examination will be performed for the subject pump on all I the accessible portions of all pump lug welds.

l (2) A Visual, VT-1 examination will be performed on the portions of the subject welds I

which are obstructed.

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit I and Unit 2.  ;

l l

8 - 10

\

b E_--_--__--.-_.- . . _

I

," Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-02 (Page 3 of 5)

Figure 1

-r4 . .

ii lil ii 5

PUMP CASING - INACCESSIBLE VIEW A-A VIEW B-B CVP-01 p CVP-02 7

O O g.: _ _ _ _ _ _

/ ... ...

l O 0 CVP-03 d -

g-CVP-04 d h e CV PUMP 1(2)CV01 PA 1(2)CV01PB l

8 - 11 l

L______________ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ . . _ _ _ _ .__ _ _ _ . _ . . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-02 (Page 4 of 5)

Figure 2 s

WELDED ATTACHMENT l'l (TYP)

PUMP CASING .

l

' CONCRETE SUPPORT

{

' INACCESSIBLE j VIEW A-A o ,, I s, o h RHP-01 - - -

RHP-02 I

PUMP CASING I _

DISCHARGE

/ N0ZZLE RHP-03 o RHR PUMP 1(2)RH01PA 1(2)RH01PB l

8-12 L______________

,- ,- Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL t

RELIEF REQUEST I2R-02 (Pay 5 of 5) l Figure 2 fwELDED ATTACHMENT

,hl-  !' / (TYP)

, i PUMP CASING -

((

CONCRETE SUPPORT

-INACCESSIBLE VIEW A-A-1 0/ I \O CSP-01 _

CSP-02 PUMP i) _ i CASING I ~

DISCHARGE

/ N0ZZLE

~'

CSP-03 O i

CS PUMP 1(2)CS01 PA ,

1(2)CS01 PB  !

9 8 - 13 i

l ,- ,. Revision 1 l CRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL l

ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-10 (Page 1 of 8)

COMPONENT IDENTIFICATION Code Class: 2

References:

Table -2500-1, of Code Case N-509 Examination Categories: C-C Item Numbers: C3.20

Description:

Limited Surface Examination of Piping Penetration Integral Attachment Welds Component Numbers: Unit 1 Welds.  ;

1CV-19-23 & 24, 1RH-03-37 & 37B, IRH-04-73 & 73A,1RH-05-21B & 22*

1RH-07-25 & 25A,1RH-08-02A & 2B,1RH-09-45 & 45A ISD-01-19 & 20*, ISD-02-21 & 22, ISD-03-25 & 26 ISD-04-22 & 23 ISI-04-02 & 02A, ISI-12-23 & 23A, ISI-26-09 & 09A ISI-37-02 & 03,1S1-39-18 & 19 I ISX-01-02 & 03, ISX-04-02 & 03, ISX-07-41 & 42 ISX-10-28 & 29 Unit 2 Welds:

2FW-06-01 & 01A,2FW-10-24 & 24A,2FW-11-25 & 25A 2FW-12-25 & 25A* l 2RH-04-03 & 03A,2RH-05-35 & 35A,2RH-08-03 & 04 l

2RH-09-28 & 28A 2SI-04-02 & 03, 2SI-12-19 & 19A, 2SI-26-02 & 03 2SI-39-21 & 22 2SX-01-02 & 03,2SX-04-02 & 03*,2SX-07-37 & 38 l 2SX-10-26 & 27

  • Denotes penetration welds selected for inspection during the interval Drawing Numbers: Unit 1:

I CV- 19, 1 RH-03, 1 RH-04, 1 RH -05, 1 RH-07, 1 RH-08, 1 RH-09, ISD-01, ISD-02, ISD-03, ISD-04, ISI-04, ISI-12, ISI-26, ISI-37, ISI-39, ISX-01, ISX-04, ISX-07, ISX-10 Unit 2: l 2FW-06, 2FW-10, 2FW-11, 2FW-12, 2RH-04, 2RH-05, 2RH- l 08, 2RH-09, 2SI-04, 2SI-12, 2SI-26, 2SI-39, 2SX-01, 2SX-04,  !

2SX-07, 2SX-10 CODE REQUIREMENTS Note: Braidwood Station is using Code Case N-509 as an alternative to the requirements of

. Table IWC-2500-1, Category C-C of the 1989 Edition of Section XI.

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.- ,. Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND LNTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-10 (Page 2 of 8) l l

Table -2500-1, of Code Case N-509, Category C-C, Item Number C3.20 requires a 100%

l surface examination of Piping Integrally Welded Attachments per Figure IWC-2500-5.

, Table IWC-2500-1, Examination Category C-H, Item Numbers C7.30 and C7.40 require pres.sure retaining piping components to be pressure tested and VT-2 examined.

CODE REQUIREMENTS FROM WHICH RELIEF IS REOUESTED Relief is requested for the surface examination of Piping Integrally Welded Attachments l required by Code Case N-509, Table -2500-1, Category C-C, Item Number C3.20.

BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is being requested on the basis that compliance with the specified Code requirement has been determined to be impractical.

l Some penetrations at Braidwood were originally designed where one of the integral attachment welds is inside the penetration assembly, thus making the welds inaccessible for inservice inspection. Access from outside of the closed end of the penetration assembly for examiners is prohibited by the integral attachment. Access from the open end of the penetration is severely l

restrained due to geometry and clearance. See Figures 1,2,3,4 and 5 for penetration details.

The integral attachment weld is set back some distance inside the penetration assembly and the clearance between the pipe and penetration sleeve is small, see Table 1, Figure 6.

To satisfy the Code requirement to perform a surface examination of this weld, modification to the penetration assembly and/or piping to allow access would be required. Braidwood would incur significant engineering and installation costs to perform such a modification without a l compensating increase in the level of quality and safety to justify such modifications.

l PROPOSED ALTERNATE PROVISIONS When a weld is scheduled for inspection, a surface examination of the accessible weld on the l exposed outside surface of the penetration will be performed. In conjunction with the above l proposed alternative technique, the periodic VT-2 examinations in accordance with the j requirements of ASME Section XI, Table IWC-2500-1, Examination Category C-H will j j provide reasonable assurance of continued strue: ural integrity of the piping systems.

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit 1 and Unit 2.

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. o- Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN NRC SUBMITTAL RELIEF REQUEST 12R-10 (Page 3 of 8)

Figure 1 (Drawing not to scale) l l

l CONTAINMENT WALL i

=13  :

r - j e

Tcw  :

! b I

Q' See Detail A I PRESSURE RETAINING PIPE (Figure 2, Page 4) v a INACCESSIBLE WELD pg w .

- ACCESSIBLE WELD ANCHOR  :

l PLATE 1/2" r

TYPICAL TYPE 2 PENETRATION l

\

CONTAINMENT WALL c =13  :

~

1 w

Tcw  :

See Detail A

s PRESSURE RETAINING PIPE (Figure 2, Page 4) vv a

\ INACCESSIBLE WELD pg l _-  !

i l ACCESSIBLE WELD ' ANCHOR  : l +-- j PLATE 1/ 2,,

TYPICAL TYPE 3 PENETRATION

~8 - 51 i

w_-___-__-_ - - _ _ .

I

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Figure 2 (Drawing not to scale)

I -

I l

PENETRATION l ATTACHMENT l = T, =

1 i

l' i

i 45 1

t PROCESS PIPE WALL Tv i

4 l

DETAIL A 8 - 52

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Figure 3 (Drawing not to scale)

. CONCRETE WALL

~ 3~  :  :

3'  :

See Detail B , .

I i Pc (Figure 5, Page 7) (]

PRESSURE RETAINING PIPE I

) INACCESSIBLE WELDS PRESSURE RETAINING PIPE PRESSURE RETAINING PIPE ANCHOR PLATE ACCESSIBLE WELDS TXdICAL PENETRATION (DETAIL 26)

? CONCRETE WALL

^

4--- 6"

- 1 I

" Pc Q

F gu e Page 7) PRESSURE RETAINING PIPE INACCESSIBLE WELD m

~ywe~ _A _i i s ' oef__ ~5 w j _b ~ I j I.

g ~ [l0 w

l'1

' I I

! ACCESSIBLE WELD TYPICAL PENETRATION (DETAIL 27) 8 - 53 t

Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECONT R :. :AL ISI PROGRAM PLAN-NRC SUBMITi.O RELIEF REQUEST I2R-10 (Page 6 of 8) l Figure 4 l (Drawing not to scale) l l

l CONCRETE WALL ..

4" or 6"

[-

F 9 -

3' :l See Detail B f (rigure 5, Page 7) PRESSURE RETAINING PIPE l vv JL INACCESSIBLE WELD pc ACCESSIBLE WELD . . _ . .,

, p' ,

ANCHOR PLATE , . ,

s

>j TYPICAL PENETRATION (DETAIL 4)

(-

8 54

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Figure 5 (Drawing not to scale)

PENETRATION ATTACHMENT l

l

T,  :

I 45 i

l t

PROCESS PIPE WALL rp, 4

DETAIL B 8 - 55

Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-10 (Page 8 of 8) l Figure 6

{

TABLE 1 Weld ID Pipe Pipe Attachment Thickness Penet. Penet.

Size Thickness Thickness Concrete Size Clearance Tw T. Tcw Pc l

l TYPE 2 PENETRATIONS (HGURE 1) l IRil-04 73 & 73A 12" 0.375" 2.0" J 3*6" 24" 4.9" 1RII4)8-02A & O2B 12" 0.375" 2.0" 3'6" 24" 4.9" ISI-04-02 & O2A 8" 0.906" 2.0* 3'6" 24" 7.0" 15112-23 & 23A 12" 1.125" 2.0" 3*6" 24" 4.9" ISX-01-02 & 03 16" 0.375" 2.0" 3'6" 30" 6.0" ISX-04-02 & 03 16" 0.375" 2.0" 3'6" 30" 6.0" ISX-07-41 & 42 16" 0.375" 2.0" 3'6" 30" 6.0" ISX-10-28 & 29 16" 0.375" 2.0" 3'6" 30" 6.0" 2RII4)4-03 & O3A 12" 0.375" 2.0" 3*6" 24" 4.9" 2RII-08 03 & O4 12" 0.375" 2.0" 3'6" 24" 4.9" 251-04-02 & 03 8" 0.906" 2.0" 3'6" 24" 7.0" 2SI-1219 & 19A 12" 1.125" 2.0" 3'6" 24" 4.9" 2SX-01-02 & 03 16" 0.375" 2.0" 3*6" 30" 6.0" 2SX-04-02 & O3 16" 0.375" 2.0" 3'6" 30" 6.0" 2SX-07 37 & 38 16" 0.375" 2.0" 3'6" 30" 6.0" 2SX-10-26 & 27 16" 0.375" 2.0" 3'6" 30" 6.0" TYPE 3 PENETRATIONS (FIGURE 1)

ISD-01-19 & 20 6" 0.432" 2.0" 4'6" 16" 3.8" ISD-02-21 & 22 6" 0.432" 2.0" 4*6" 16" 3.8" ISD 03-25 & 26 6" 0.432" 2 ,0" 4'6" 16" 3.8" ISD-04-22 & 23 6" 0.432" 2.0" ~

4'6" 16" 3.3" 1SI-26-09 & 09A 8" 0.906" 2.0" 3'6" 24" 7.0" 1SI-39-18 & 19 3" 0.438" 1.625" 3'6" 12.75" 4.2" 2FW-06-01 & OI A 6" 0.432" 2.0" 4'6" 16" 3.8" 2FW-10-24 & 24A 6" 0.432" 2.0" 4'6" 16" 3.8*

2FW-1125 & 25A 6" 0.432" 2.0" 4'6" 16" 3.8" 2FW-12-25 & 25A 6" 0.432" 2.0" 4'6" 16" 3.8" 251-26-02 & 03 8" 0.906" 2.0" 3'6" 24" 7.0" 251-39-21 & 22 3" 0.438" 1.625" 3'6" 12.75" '4.2" DETAIL 4 PENETRATIONS (FIGURE 4) 1RH4)3-37 & 37B 8" 0.375" 1.0" 3 '0" !8" 4.3" 1Ril4)7-25 & 25A 8" 0.375" 1.0" 3 '0" 18" 4.3" DETAIL 27 PENETRATIONS (FIGURE 3) 1Ril-05-21B & 22 8" 0.375" 1.0" 3'0" 20" 5.2" 1RH 09-45 & 45A 8" 0.375" 1.0" 3'0" 20" 5.2" 2RH-05-35 & 35A 8" 0.375" 1.0" 3'0" 20" 5.2" 2Ril 09-28 & 28A 8" 0.375" 1.0' 3'0" 20" 5.2" DETAIL 26 PENETRATIONS (FIGURE 3) 1CW19-23 & 24 6" 0.280" 0.75" 3'0" 13"x34" 2.7" ISI-37 02 & O3 6" 0.280" 0.75" 3'0" 13"x34" 2.7" l 8 - 56 L_______________________ _ _ _ _ _ _ _ _ _ _

Revision 1 l l

BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-14 (Page 1 of 3) l l . .

i COMPONENT IDENTIFICATION Code Class: 1,2 and 3 i

Refereaces: IWF-5000

. Examination Category: Not Applicable-Item Number: Not' Applicable

Description:

Alternative Rules to IWF-5000 Inservice Inspection Requirements .

CODE REQUIREMENT Inservice Inspection of snubbers shall be performed as follows:

. Preservice examination per IWF-5200(a) and Inservice examination per IWF-5300(a) in accordance with the first addenda to ASME/ ANSI OM-1987 Edition, Part 4, published in 1988 (OMa-1988 Part 4).

Repair and replacement of snubbers per IWF-5400 in accordance with the first addenda to ASME/ ANSI OM-1987 Edition, Part 4, published in 1988 (OMa-1988 Part 4).

l CODE REQUIREMENTS FROM WHICH RELIEF IS REOUESTED Relief is requested for the inservice examination of snubbers per IWF-5300(a) in accordance with ASME/ ANSI OM-1987 Edition, Part 4, published in 1988 (OMa-1988 Part 4).

BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives provide an acceptable level of quality and safety.

Braidwood Station Technical Specification (TS) 3/4.7.8 includes a comprehensive program

( for visual examination of all safety related hydraulic and mechanical snubbers. The program scope encompasses all ASME Code Class 1,2, and 3 snubbers, safety related non-code class snubbers, and non safety related snubbers whose failure could adversely affect a safety related system. Currently, Braidwood Station TS 4.0.5 also includes

[ requirements for visral examination of Code Class 1,2 and 3 snubbers per ASME Section XI and ASME/ ANSI OMa-1988, Part 4. Upon the implementation of Improved Technical Specifications (ITS), the requirements for visua' examination of snubbers will be relocated I' to the ITS Technical Requirements Manual. Current Technical Specifications 3/4.7.8 and 4.0.5 will no longer exist.

. Because the existing Braidwood Station Technical Specifications ( TS ) and the Improved Technical Specifications Technical Requirements Manual ( TRM ) require visual 8 - 64 c ___ _ _ _ _ _ - _ _ _ __ __ .-

. , . , , Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBM11TAL RELIEF REQUEST I2R-14 (Page 2 of 3) examination of all ASME Code Class 1,2,3 safety related snubbers, safety related non-code snubbers, and non safety related snubber whose failure could adversely affect a safety related system, the overlap of the programs per TS, TRM, md ASME Section XI for the Code Class snubbers presents an unnecessary redundancy. The program requirements detailed in the TS and TRM are as rigorous and conservative as the program presented in OMa 1988, Part 4 per IWF 5200. The TS / TRM snubber programs and the program presented in OMa-1988, Part 4 per IWF-5200(a) and IWF 5300(a) are similar in content.

All of the programs have consistent requirements for visua. examination, examination frequency. examination sample size, examination failure evaluation, examination corrective actions, and examination documentation.

It is Braidwood Station's position that the snubber visual examinations required per the current Technical Specifications and the Improved Technical Specification Technical Requirements Manual meets the intent of the program required by OMa-1988, Part 4. No plant safety benefits will be realized by imposing both programs on the Code Class snubbers at Braidwood Station.

Based on the preceding information, Braidwood Station requests relief from the ASME Section XI requirements for visual examination, repair and replacement of Code Class snubbers.

PROPOSED ALTERNATE PROVISIONS Braidwood Station will perform visual examination of Code Class snubbers in accordance with Technical Specifications in lieu of the requirements of ASME/ ANSI OMa-1988, Part 4 until the Improved Technical Specifications Technical Requirements Manual is implemented. Braidwood Station will then perform visual examination of Code Class snubbers in accordance with the ITS Technical Requirements Manual. The visual l

examination boundary will include the snubber structural attachment to the foundation'or supporting structure up to and including the fasteners for connecting the snubbers to the pipe attachment or component attachment. Personnel performing the snubber visual j examinations will be qualified and certified to perform Visual, VT-3 examinations per j l

i IWA-2300.

As required by IWF-5200(c) and IWF-5300(c) the examination of snubber integral and l nonintegral attachments will be performed in accordance with Subsection IWF. In ,

l addition, Braidwood Station will visually examine (VT-3) any component support steel including ASME Section III NF steel connected to the snubber structural attachment.

If any component included in the visual examination boundary cannot be verified to be properly aligned, tight, and functional during the VT-3 examination due to insulation interference, the insulation will be removed from the component prior to executing the exam.

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BRAIDWOOD STATION UNITS I & 2 SECOND LNTERVAL ISI PROGRAh! PLAN-NRC SUBAlllTAL RELIEF REQUEST I2R-14 (Page 3 of 3)

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit I and Unit 2.

(

l

)

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, , , , , Revision 1 l BilAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-15 (Page 1 of 3)

COMPONENT IDENTIFICATION Code Classes: 1, 2 and 3 i

References:

Table IWB-2500-1, Table IWC-2500-1, Table IWD-2500-1 Examination Categories: B-H, B-K-1, C-C, D-A, D-B, D-C Item Numbers: B8.10, B8.20, B8.30, B10.10, B10.20, B10.30, C3.10, C3.20, C3.30, C3.40 D1.20, D1.30, D1.40, D1.50, D1.60, D2.20, D2.30, D2.40, D2.50, D2.60 l

Description:

Alternative Rules for the Selection and Examination of Class 1,2 and 3 Integrally Welded Attachments - Use of Code Case N-509 Component Numbers: All Class 1,2 and 3 Integral Attachments Subject to Inservice Inspection CODE REQUIREMENTS Class 1 Attachments Table IWB-2500-1, Examination Categories B-H and B-K-1 require the performance of surface or volumetric examinations, as applicable, on integral attachments with a design thickness of 5/8 inch or greater.

Class 2 Attachments Table IWC-2500-1, Examination Category C-C requires the performance of a surface examination on integral attachments with a design thickness of 3/4 inch or greater.

Class 3 Attachments Table IWD-2500-1, Examination Categories D-A, D-B and D-C require the performance of a visual VT-3 examination on integral attachments.

For complete details on ASME Section XI Code examination requirements, see Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1.

CODE REQUIREMENTS FROM WHICH RELIEF IS REOUESTED Relief is requested for the selection of components for examination, and examinations required by Table IWB-2500-1, Categories B-H and B-K-1 on integral attachments with a design i

thickness of 5/8 inch or greater. j l

Relief is requested for the selection of components for examination, and examinations required

- by Table IWC-2500-1, Category C-C on integral attachments with a design thickness of 3/4 I l

inch or greater.

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. ,, , Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBhlllTAL RELIEF REQUEST I2R-15 (Page 2 of 3)

Relief is requested for the selection of components for examination, and examinations required by Table IWD-2500-1, Categories D-A, D-B and D-C. 1 l

BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives provide an acceptable level of quality and safety.

Relief is being requested to allow the use of alternate requirements for the examination and selection of Class 1, 2 and 3 integral attachments detailed in Code Case N-509, with exception to the requirement to inspect the integrally welded attaciunents associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 (P.eference footnote 5 of Category B-K and Category C-C Code Case N-509 tables). The basis for this request is as follows:

1) No Inservice flaws which would affect the structural integrity of any component or piping system have been detected as a result of the integrally welded attachment exams performed during the first interval at Braidwood Station.
2) Integral attachment failures Itave been very rare within the commercial nuclear power industry. Failures and inservice defects that have been detected are usually associated with support damage caused by a system transient or other abnormal events during operational periods. Therefore, degradation is typically identified during inspections that are performed after a system transient or other abnormal events which have occurred. Code Case N-509 requires the examination of integral attachments when deformation of the associated component support members is identified. This requirement will ensure degraded integral attachments are identified and therefore increase the level of quality and safety provided by these alternatives rules, as compared to the rules of the 1989 Edition of Section XI.
3) Significant amount of man-rem exposure and cost associated with the scheduled examination of Class 1,2, and 3 integral attachments would be saved.
4) Contrary to the requirements specified in ASME Section X~ 1989 Edition, the alternate .

selection criteria of Code Case N-509 does not impose a minimum thickness l '

requirement for the examination of an integral attachment. Therefore, a larger population of integral attachments will be available for examination because the selection population will not be limited to those above an arbitrary thickness. This provision improves the quality and safety level established by these examinations.

5) The alternate rules of Code Case N-509 provide an acceptable level of quality and safety.

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6) The selection of component supports for examination per Code Case N-491 is an acceptable alternative approved by the NRC on Regulatory Guide 1.147.

PROPOSED ALTERNATE PROVISIONS The requirements of Code Case N-509 will be used to select and examine integrally welded attachments, with exception to the requirement to inspect the integrally welded attachments associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 (Reference footnote 5 of Category B-K and Category C-C Code Case N-509 tables).

Braidwood is implementing Code Case N-491 for support selections and will inspect the l integrally welded attachments associated with the component supports selected for examination i under Code Case N-491. For piping, pumps, and valves, a minimum sample of 10% of the welded attaclunents associated with the component supports selected for examination will be inspected. This percentage sample shall be distributed proportionally by system among the total number of nonexempt integrally welded attachments connected to the piping, pumps, and l valves subjected to these examinations.

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit 1 and Unit 2.

i l

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Revision 1 l l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRASI PLAN-NRC SUBS 11TTAL RELIEF REQUEST 12R-30 (Page 1 of 4)

COMPONENT IDENTIFICATION Code Class: 1

References:

IWA-5242(a) j Examination Category: B-P Examination Item Numbers: B15.70 nnd B15.71

Description:

Alternative Requirements for Insulation Removal at Bolted Connections in Systems Borated for the Purpose of Controlling Reactivity Component Number: Valve Numbers (24 Total Each Unit) l r

1(2)SI8948A-D 1(2)RC8002A-D

! 1(2)SI8949A-D 1(2)RC8003A-D

' 1(2)RC8001A-D 1(2)RH8702A-B 1(2)RH8701A-B l

Reference:

1) " Materials Handbook for Nuclear Plant Pressure Boundary i

Applications," EPRI TR-109668-SI, WO4382-01, Final Report, l

Revision 0, December 1997 (EPRI Proprietary)

CODE REQUIREMENT i

l IWA-5242(a), states "For systems borated for the purpose of controlling reactivity, i insulation shall be removed from pressure retaining bolted connections for visual examination VT-2".

p CODE REQUIREMENTS FROM WHICH RELIEF IS REOUESTED l Relief is requested for the IWA-5242(a) requirement to remove insulation on all bolted connections in systems borated for the purpose of controlling reactivity.

l BASIS FOR RELIEF l

Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed

alternative would provide an acceptable level of quality and safety. Specifically, relief is requested from the requirement to remove insulation for the Class I components listed above for VT-2 on the fregtency specified in Tables IWB-2500, Category B-P, (each refueling outage). The following supports a reduced inspection frequency

l 8-114 1

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Revision 1 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL l

RELIEF REQUEST I2R-30 l (Page 2 of 4)

1. ASME Section XI paragraph IWA-5242(a) requires the removal of insulation from pressure retaining bolted connections for VT-2 visual examinations when the system is borated for the purpose of controlling reactivity. Paragraph IWA-l 5242(a) requires this for all bolting, regardless of material type, when the l

system is borated for the purpose of controlling reactivity. For all materials of construction, when the system is not borated for the purpose of controlling reacti *ity, insulation removal is not required by paragraph IWA-5242(a) for VT-2 visu- 1 examinations.

Comed believes that by the Code only requiring insulation removal for borated systems, the intent of this requirement is to address early detection of boric acid wastage of the bolting materials. In either borated or non-borated systems, if leakage results in wetting of the bolting material, the required VT-2 visual examinations would not be effective at detection of incipient stress corrosion cracking if it occurs; only the volumetric examinations of IWB-2500 Categories B-G-1 would be effective. For this reason, if the bolting material of construction is resistant to boric acid wastage, there is no reduction in margin of safety if the required VT-2 visual examinations are performed without insulation removal each refueling outage as they would be for other Class 1 non-borated systems. The proposed alternative provision of inspecting these components on a once per year 10 year interval basis will provide sufficient assurance that these highly corrosion resistant components have not degraded.

2. For the valves listed above both the stud / bolt material and closure nut material utilize SA-453 Grade 660 Class B. Also known as alloy A-286, the nominal composition of this ferrous alloy is 25Ni-15Cr-2Ti-A1. According to Reference 1, the "high chromium content of alloy A-286 gives it similar resistance to general corrosion in boric acid as possessed by stainless steel, which is essentially immune to the wastage or erosion-corrosion problems." Reference 1 determines that for A-286 material stress corrosion cracking is only a concern if bolting material is loaded to 100 ksi or higher. For the valves listed above, l review of the installation procedures shows that none of the bolting is loaded to more than 65 ksi. Therefore, stress corrosion cracking is not a concern. Also,  ;

Reference 1 states that a review of available NRC Public Documentation j revealed no reports of failures of alloy A-286 used for external reactor vessel bolting service in B&W units over a service period of greater that 20 years. ]

l 3. The valves listed above are among the highest radiation level components in the Borated bolting Inspection Program. Insulation removal combined with scaffolding erection and inspection time are expected to contribute significantly 8 - 115 i

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TRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBSIITTAL RELIEF REQUEST 12R-30 (Page 3 of 4)

(approximately 1.5 person-rem) to the overall dose received. As discussed above, there is no significant increase in plant safety to be gained by performing VT-2 inspection of these materials on an every refueling outage frequency.

The following Braidwood Station bolting examination commitments and material control programs in conjumtion with the Proposed Alternative Provisions provide an acceptable level of safety and quality for bolted connections in systems borated for the purpose of controlling reactivity,

. In response to NRC Generic Letter 88-05, Braidwood Station has established a l program for Engineering to inspect all boric acid leaks discovered in the l

containment building and to evaluate the impact of those leaks on carbon steel or l

low alloy steel components. Any evidence of leakage, including dry boric acid crystals or residue, is inspected and evaluated regardless of whether the leak was discovered at power or during an outage. Issues such as the following are considered in the inspection and evaluation:

1) Evidence of corrosion or metal degradation
2) Effect the leak may have on the pressure boundary
3) Possibility of boric acid traveling along the inside of insulation on piping, and i 4) Possibility of dripping or spraying on other components. Based on this j l evaluation, Braidwood Engineering initiates appropriate corrective actions to

( prevent reoccurrence of the leak and to repair, if necessary, any degraded l materials or components.

. For systems borated for the purpose of controlling reactivity, when the bolting material is SA 453 Grade 660 and therefore immune to boric acid corrosion, l

Comed requests relief form the requirement of ASME Section XI paragraph IWA-5242(a) that insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination. Volumetric examinations as applicable to IWB-2500 ,

Categories B-G-1 will continue to be performed. ]

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! l PROPOSED ALTERNATE PROVISIONS

! For ASME Class 1 systems borated for the purpose of controlling reactivity, a system inservice leakage test shall be performed in accordance with the frequency required in

' table IWB-2500 (each refueling outage), without the removal of insulation from the bolted connections. The requirements for inservice leak tests shall be augmented with a minimum 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time at system normal operating pressure prior to the VT-2 visual l l

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L___ ___ _ _ . _ _ _ _ _ _ _ - _ _ _.

_ - _ - - - __--__ _________ _ ___ _-_ . _ - _ _ _ _ _ _ _ _ _ _ = _

Resision ! l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL 151 PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-30 (Page 4 of 4) examination to allow for leakage propardon from the insulation. If evidence of leakage is detected on the above list::d valves, the insulation shall be removed and the evaluations for corrective measures performed in accordance with IWA-5250 (as modified for Braidwood by pending Relief Request 12R-13).

For the valves listed above, the insulation shall be removed from the bolted connections and a VT-2 examination shall be conducted, with the system depressurized on a once per 10 year interval frequency. These examinations shall be distributed throughout the inspection interval. If evidence of leakage is detected evaluations for corrective measures performed will be performed in accordance with IWA-5250 (as modified for Braidwood by pending Relief Request 12R-13). These inspections shall be implemented through application of the Braidwood Station predefined surveillance program to assure they are performed within the prescribed time periods.

Regardless of whether a component is scheduled for examination or not, any evidence of leakage will result in evaluations for corrective measures in accordance with IWA-5250 (as modified for Braidwood Station by pending Relief Request 12R-13).

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit I and Unit 2.

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..o Revision 1 l IRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-31 (Page 1 of 4) l CON 1PONENT IDENTIFICATION Code Class: 1

References:

IWA-5242(a)

Examination Category: B-P  ;

Examination Item Numbers: B15.10, B15.11, B15.30 And B15.31 l

Description:

Alternative Requirements for Visual Examination VT-2 I on Bolted Connections in Systems Borated for the i Purpose of Controlling Reactivity Component Number: 1(2)RC01R (Reactor Vessel Closure Studs and Nuts) 1(2)RC01BA-D (Steam Generator Closure Bolting /

Studs and Nuts)

CODE REOUIRENIENT IWA-5242(a), states "For systems horated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2".

CODE REOUIRENIENTS FRONI WHICH RELIEF IS REOUESTED Relief is requested from the IWA-5242(a) requirement to remove insulation when performing visual examination VT-2 on bolted connections in systems borated for the purpose of controlling reactivity during a system leakap rest.

BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.

As required by IWA-5242(a), the removal ofinsulation at operating pressure and temperature from the reactor vessel and steam generator primary side manways creates l a safety hazard and does not provide an increased level of safety conunensurate with the required actions because:

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e The components are located in high radiation areas, removal of insulation in these areas would be dose intensive.

  • As required by IWB-5221, the RCS is at normal operating pressure (= 2235 psig) and temperature (= 557 "F), personnel safety concerns exist when inspecting components in this condition with the insulation removed.

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_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ =

.. c, Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-31 l (Page 2 of 4) e Removal ofinsulation on the reactor vessel closure head requires use of the overhead crane to remove the large panels of mirror insulation. Work of this nature around the reactor vessel head while in Mode 3 could result in an unsafe condition.

The Staff has recognized that meeting the insulation removal requirement specified in IWA-5242(a) is a hardship to utilities. As an alternative to the requirements IWA-5242(a), the performance of a VT-2 visual examination at pressure and temperature with the insulation on, along with a VT-2 visual examination of the assembled connection depressurized in an uninsulated state has been an acceptable approach. This approach for ASME Class 1 components is consistent with the provisions of ASME Code Case N-533.

'At Braidwood Station, the subject bolted connections are typically disassembled during each refueling outage through normal maintenance practices. When the bolted connections are disassembled, critical bolting surface areas subject to accelerated corrosion due to boric acid attack become accessible for inspection by the maintenance organization. Braidwood proposes to utilize this inspection to identify degradation or wastage on the bolting surfaces. Upon completion of the inspection, the bolting condition will be documented and evaluated under the existing Station Problem Identification process. Applicable Section XI Acceptance Standards (i.e., IWA-3100) will be used to evaluate for bolting structural integrity. Appropriate maintenance procedures will be revised and enhanced as necessary to assure the aforementioned inspection and evaluation criteria are included.

The proposed inspection by the Station maintenance organization is a more informative assessment of the existing bolting condition compared to the VT-2 exams called for in IWA-5242(a) and Code Case N-533. It will allow a complete examination of bolting surfaces and will ensure that existing degradation is properly identified and evaluated, as required. In addition, performing the bolting inspection in the disassembled state is more consistent with current ALARA practices.

[ Braidwood Station has also implemented bolting examination and material control programs which provide additional assurance of maintaining structural integrity of bolted connections in borated systems:

  • In response to NRC Generic Letter 88-05, Braidwood Station has established a program for the periodic inspection of the containment building for boric acid leaks and to evaluate the impact of such leaks on carbon steel or low alloy steel components. Issues such as the following are considered in the inspection and evaluation:

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t . .o Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAh! PLAN-NRC SUBalI1TAL RELIEF REQUEST 12R-31 (Page 3 of 4)

1. Evidence of corrosion or metal degradation,
2. Effect the leak may have on the pressure boundary,
3. Possibility of boric acid traveling along the inside ofinsulation on piping, and
4. Possibility of dripping or spraying on other components.

Based on this evaluation, Braidwood Engineering initiates appropriate corrective actions to repair any degraded materials or components, as required, and to prevent reoccurrence of the leak.

The frequency of these inspections conducted by VT-2 qualified examiners are performed at the beginning and end of each refueling outage.

PROPOSED ALTERNATE PROVISIONS For the reactor vessel closure head and steam generator primary manway studs / bolting and closure nuts, a VT-2 visual examination shall be performed in accordance with the frequency required in table IWB-2500-1 without the removal of insulation from the bolted connections during the system leakage test. The hold time requirement for this system leakage tests shall be increased to 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time at system nominal operating pressure prior to the VT-2 visual examination to allow for leakage propagation from the insulation.

In addition to the above VT-2 visual examination, the following examination will be performed:

When the subject bolted connection (s) is(are) disassembled for normal maintenance during a refuel outages, an inspection for corrosion / wastage due to boric acid attack shall be conducted by the Station maintenance organization on all exposed bolting surface areas. If degraded condition is observed on the l bolting material, structural evaluation and/or repair / replacement will be conducted in accordance with the applicable rules of IWA-3100.

OR When the subject bolted connection (s) is(are) NOT disassembled for normal maintenance during a refuel outage, a VT-2 visual examination, with the bolted connection (s) assembled and with the insulation removed, will be conducted with the system depressurized. If necessary, corrective measures shall be performed in accordance with the requirements of IWA-5250 or approved alternative.

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Revision 1 l BRAIDWOOD STATION UNITS I & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-31 (Page 4 of 4)

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice l Inspection Program for Braidwood Unit 1 and Unit 2.

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