ML20069G829

Requests NRC Review & Approval of Proposed Relief Requests Applicable to Unit 1 Second Ten-Yr Interval ISI Program. Listed Relief Requests Attached for Review

ML20069G829
Person / Time
Site:	Beaver Valley
Issue date:	05/23/1994
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9406100178
Download: ML20069G829 (22)

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Bea r a ey Power Station Shippingport, PA 15077-0004 Sen or Vice P es dent arid Cheef Nuclear Officer May 23, 1994 Nuclear Power Division U.

S.

Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Subject:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 ISI (Inservice Inspection) Program:

Relief Request 3 The purpose of this submittal is to request NRC review and approval of proposed relief requests applicable to the Unit No. 1 Second Ten-Year Interval ISI Program.

The following relief requests are attached for review:

No. BV1-B5.40-1, Rev. O No. BV1-B9.11-2, Rev. O No. BV1-RC-P-1-1, Rev. O No. BV1-RC-P-1-2, Rev. O No. BV1-CS.11-2, Rev. O No. BV1-C6.10-1, Rev. O No. BV1-CH-E-4-1, Rev. O No. BV1-CH-FL-4-1, Rev. O No. BV1-RH-E-1-1, Rev. O The examinations represented by these relief requests have been completed to the extent possible.

Complete coverage of the welds could not be obtained for the reasons identified within each relief request.

These limited examinations require review and approval by the NRC as required by 10 CFR 50.55a.

It is requested that this review be completed before February 1,

1995, in order to allow sufficient time to plan and prepare for any follow-up examinations that may be required during the eleventh refueling outage tentatively scheduled to begin February 9, 1996.

If you have any questions regarding this issue, please contact Mr. Steve Sovick at (412) 393-5211.

Sincerely, Y I N Y

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Sieber DEllVERING Rossbach,Sr.ResidentInshector 0 U blII Y cc:

Mr.

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Mr. T. T. Martin, NRC Region I Administrator ENERGV Mr.

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Edison, Project Manager 9406100170 940523 O

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l DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-B5.40-1, Rev. O Components Pressurizer Nozzle to Safe-end Weld, RC-98-1-E-02 Section XI Reauirement (83S83)

Item B5.40 (Table IWB-2500-1, Category B-F) requires a surface and a volumetric examination.

Basis for Relief The ultrasonic examination of this weld was limited due to search unit lift off on the nozzle curvature when scanning from the nozzle side.

The weld crown and diameter change prevent coverage from the safe-end-side.

See attached sketch.

This exam was performed using a 45 degree refracted longitudinal scan angle as recommended in NRC Information Notice 90-30.

Approximately 70%

of the required volume was covered by this ultrasonic examination.

The surface exam was completed without limitation.

Alternative Examination Perform the volumetric exam to the maximum extent practicable using the refracted longitudinal scan angle as noted.

The surface exam and the normal leakage exams will be performed as scheduled.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-B9.11-2. Rev. O Components RC-98-1-F-01 i

RC-72-5-F-06 l

RC-72-5-S-06 l

SI-73-8-F-11 SI-101-2-S-02 e

SI-101-2-S-06 RH-24-1A-F-06 j

Section XI Recuirement (83S83) 4 Item B9.11 (Table IWB-2500-1, Category B-J) requires a surface and a j

volumetric examination.

Basis for Relief The following list ilentifies the weld, the percentage of required coverage that can be performed, and the specific obstruction for each weld.

RC-98-1-F-01 80%

Ultrasonic examination is limited due to steep O.D.

taper on the safe-end. side of the weld preventing scanning of required volume.

The 45 deg.

angle scan was supplemented with a 60 deg. angle scan.

1 The surface exam was completed without limitation.

RC-72-5-F-06 78%

Ultrasonic examination is limited due to the elbow to valve weld configuration and the intrados of the elbow preventing i

scanning of the required-volume.

The 45 deg.

angle scan was supplemented with a 60 degree scan.

The surface exam was completed without limitation.

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RC-72-5-S-06 0%

Ultrasonic examination is completely limited on one side of the weld by the tee configuration of-the fitting and on the other side of the weld by a welded support.

The surface exam was completed I

I without limitation.

.s PAGE 2 OF 2 RELIEF REQUEST BV1-B9.11-2 SI-73-8-F-11 85%

Ultrasonic examination is limited due to the 90 deg.

intrados curvature of the elbow-to-branch nozzle weld causing the search unit to lose contact with the pipe surface.

A 45 deg.

refracted longitudinal scan supplemented by a 60 deg.

shear angle scan were used to enhance this examination.

The surface exam was completed without limitation.

SI-101-2-S-02 85%

Ultrasonic examination is limited on one side of the weld by the configuration of the tee fitting and on the other side by the 90 degree intrados curvature of the adjacent elbow fitting.

A 60 degree shear angle scan was used to supplement this exam.

The surface exam on this weld was completed without limitation.

SI-101-2-S-06 25%

Ultrasonic examination is limited by a box restraint located around this weld.

The surface examination covered 90% of the required area.

RH-24-1A-F-06 50%

Ultrasonic examination is limited due to a

support plate welded over the elbow and the elbow to valve weld configuration.

A 60 degree scan was attempted without success due to the same reasons.

The surface exam was completed without limitation.

Alternative Examination Perform the volumetric examination to the maximum extent practicable, using the supplemental scans noted above.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-RC-P-1-1, Rev. O Compo_REDtg Reactor Coolant Pumps RC-P-1A(B) (C) Weld C-1 Section XI Recuirement (83S83)

Item B12.10 (Table IWB-2500-1, Category B-L-1) requires a volumetric examination.

Relief Request BV1-B12.10-1, Rev.

O proposed as an alternative to the volumetric examination of this weld, a surface exam from the outside surface of the pump.

NRC Safety Evaluation dated August 7, 1991 granted this relief.

Hasis for Relief The penetrant examination on the Reactor Coolant Pump casing circ weld was limited by the three support leg structures.

Insufficient space between the support legs and the pump casing does not allow l

access to the circ weld.

Three areas, each approximately 8 inches

wide, behind the support legs were inaccessible.

Therefore only 88%

of the circ weld was examined.

Alternative Examination None.

Perform the surface examination to the maximum extent practicable.

The normal leakage exams will continue to be performed as scheduled.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-RC-P-1-2, Rev. O Components Reactor Coclant Pumps RC-P-1 A(B) (C) Welded Supports WS-1,

-2,

-3 i

Section XI Reouirement (83S83)

Item B10.20 (Table IWB-2500-1, Category B-K-1) requires a surface examination.

Basis for Relief The penetrant examinations on the Reactor Coolant Pump support attachment welds were limited by the supporting structure around the pump.

Insufficient

space, between the supporting structure and the attachment

welds, limits access for the examination.

Attachment welds WS-1 and WS-3 have the additional limitation of the close proximity of the pump's discharge piping to the attachment welds.

Approximately 42%

of welds WS-1 and WS-3 hudf examined.

Approximately 63% of weld WS-2 was examined.

/d'd hiternative Examination None.

Perform the surface examination to the maximum extent i

practicable.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-C5.11-2. Rev. 0 9

Components QS-2-1-F-02 t.

Section XI Recuirement (83S83 / Code Case N-408)

Item C5.11 (Table IWC-2500-1, Category C-F-1) requires a surface and a volumetric examinations.

Basis for Relief j

The following list identifies the weld, the percentage of required coverage that EaB be performed, and the specific obstruction.

QS-2-1-F-02 84%

Ultrasonic examination is limited cn1 one side of the weld by the valve to elbow weld configuration and on the other side by the intrados of the elbow fitting.

A 60 degree shear angle scan was used to supplement this exam.

The surface exam was performed without limitation.

Alternative ExaminatioD Perform the volumetric examination to the maximum extent practicable using the supplemental scan noted above.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-C6.10-1. Rev. O Components Recirculation Spray Pumps-RS-P-1A(1B),-2A(2B) - Pump Casing Welds Safety Injection Pumps-SI-P-1A(1B) - Pump Casing WeldsSection XI Reauirement (83S83)

Item C6.10 (Table IWC-2500-1, Category C-G) requires a

surface examination.

Basis for Relief The specific limitation, along with the percentage of the required surface area that can be examined, is listed below.

RS-P-2A(2B)-3 and -4 87%

Three (3) welded support plates are located on the welds preventing examination of approximately 13%

of the weld.

See enclosed photograph.

RS-P-2A(2B)-C-10 thru C-27 0%

The welds are located below RS-P-1A (IB) -C-5 thru C-10 0%

floor level in the pump's sump and are therefore inaccessible.

See attached drawings.

SI-P-1A(1B)-C-1 thru C-20 0%

The welds are located below floor level in the pump's sump and are therefore inaccessible.

See attached drawings.

Alternative Examination For welds limited by the support plates, the surface exam will be performed to the maximum extent possible.

For the inaccessible welds located in the pump sumps, the surface exam will be performed only if the pump casing is removed from the sump for maintanence purposes.

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e 1 ~ DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-CH-E-4-1. Rev. O Components Excess Letdown Heat Exchanger (CH-E-4) Weld C-1 Section XI Reauirement (83S83) Item C1.10 (Table IWC-2500-1, Category C-A) requires a volumetric examination of shell circumferential welds. Basis for Relief The close proximity of the 1" inlet and outlet nozzles and the .75" vent and drain connections to this weld physically obstruct the path of the search unit limiting the amount of UT coverage to 60% of the required volume. See attached drawing. f Alternative Examination None. The volumetric examination will be performed to the maximum extent practicable. The normal leakage exams for this component will l continue to be performed as scheduled.

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.s DUQUESNE LIGHT COMPANY Beaver Valley Power Station BELIEF REOUEST NO. BV1-CH-FL-4-1. Rev. O Components Seal Water Injection Filters CH-FL-4A(B) Welds C-1 and C-2 Seal Water Injection Filters CH-FL-4A(B) Weld N-4 Section XI Requirement (83S83) Item C1.10 (Table IWC-2500-1, Category C-A) requires a volumetric i examination of shell circumferential welds. Item C1.20 (Table IWC-2500-1, Category C-A) requires a volumetric examination of head circumferential welds. Item C2.21 (Table IWC-2500-1, Category C-B) requires surface and volun -ic examinations of nozzle-to-shell (of head) welds. Baals for Relief The weld, the percentage of UT coverage, and the specific obstruction are listed below. Refer to the attached drawing and sketches and the enclosed photograph for additional clarification. CH-FL-4B-C-1 64% Three welded angle supports are located over the weld. The inlet nozzle is located within 1.25" of this weld. The as-welded condition of the weld (weld crown) and the curvature of the lower head inhibit the beam path. CH-FL-4B-C-2 53% The examination is one-sided due to the flange. The attachment for the filter cover hinge obstructs the search unit movement in that area. The as-welded condition of this weld (weld crown) inhibits the beam path. CH-FL-4B-N-4 84% The configuration of the nozzle along with the proximity of a .75" drain line limit scan coverage. Alternative Examination None. The volumetric examination will be performed to the maxinum i extent practicable. The normal leakage exams for this component and the surface exam on N-4 will continue to be performed as scheduled. i N--

WS+t e i M P) eMETC) .N y ...os3a .v-1-z d /- g 1A p..,T norztE I / SECTION A-A / ws.3 , i* SECTION 6-9 \\ / 44 [ C3s4i m l I, _ _ t At NOTES:

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.i l i DUQUESNE LIGHT COMPANY Beaver Valley Power Station RELIEF REOUEST NO. BV1-RH-E-1-1. Rev. O Components Residual Heat Exchanger RH-E-1A(B) Welds C-1 and C-2 i i Section XI Reauirement (83S83) Item C1.10 (Table IWC-2500-1, Category C-A) requires a volumetric examination. Item C1.20 (Table IWC-2500-1, Category C-A) requires a volumetric examination. Easis for Relief The ultrasonic examination of these welds was limited by the physical interferences of the welded support plates and the inlet and outlet nozzle reinforcing saddles. See attached drawing. Exam coverage is also limited for weld C-1 due to the lower head curvature and weld crown. The 45 deg. axial angle scan was supplemented by a 60 deg. axial angle scan to extend exam volume. Approximately 84% of the required volume of C-1 and 80% of C-2 were covered by these examinations. Alternative Examination Perform the volumetric examination to the maximum extent practicable, using the supplemental scan as noted above. ( e m m - +

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