ML20097D170

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Forwards Revised ISI Relief Request NDE-18,including Omitted Terminal End Piping Welds Connected to Facilities Regenerative HX
ML20097D170
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 02/07/1996
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-032, 96-32, NUDOCS 9602120226
Download: ML20097D170 (42)
v • d • e


Text

{{#Wiki_filter:VIHOINIA ELucTHIC AND POWER COMPANY Ricnwonn,ViaorwiA 20261 February 7, 1996 U.S. Nuclear Regulatory Commission Serial No. 96-032 Attention: Document Control Desk NL&OS/EJW Washington, D.C. 20555 Docket No. 50-338 50-339 License No. NPF-4 NPF-7 i Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 INSERVICE INSPECTION REQUEST FOR RELIEF By letter Serial No. 93-018, dated February 16,1993, we submitted Relief Request NDE-18 for North Anna Unit 1 and Unit 2 inservice inspection (ISI) examinations. Relief Request NDE-18 was conditionally granted by letters dated August 7,1995, "Evalua5zsn of the Second Ten-Year Interval Inspection program Plan, Revision 4 and AssWated Requests for Relief / North Anna Power Station, Unit No.1 (NA-1) (TAC No. M89620)," end August 8,1995, " Evaluation of the Second Ten-Year interval Inspection program Pian, Revision 3 and Associated Requests for Relief / North Anna Power Station, Unit No. 2 (NA-2) (TAC No M89740)." Due to the omission of certain terminal end piping welds connected to each unit's regenerative heat exchanger, we are submitting revised relief requests (Attachments 1 and 2) to include these welds. The alterr.ative requirements proposed for these welds are similar to the guidelines established by your previous evaluation of the regenerative heat exchanger. The revised relief requests are submitted pursuant to 10 CFR 50.55a(g)(5) and have been approved by the North Anna Station Nuclear Safety and Operating Committee. North Anna Power Station Unit 1 is currently in the second period of its second ten year interval. The interval is scheduled to end December 24,1998. The Code of reference for North, Anna Unit 1 is the 1983 Edition, Summer 1983 Addendum of ASME Section XI. North Anna Unit 2 is presently in the second period of the second ten-year interval. Examinations are being conducted in accordance with the requirements of Section XI of the 1986 Edition of the ASME Boiler and Pressure Vessel Code. 120056 v4 9602120226 960207 PDR ADOCK 0500033G g $ G PDR ( J

I If you have any further questions, please contact us. Very truly yours, / J. P. O'Hanlon Senior Vice President - Nuclear Attachments cc: U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 R. D. McWhorter NRC Senior Resident inspector North Anna Power Station

i i i i i i .i 4 i - I I i ATTACHMENT 1 NORTH ANNA UNIT 1 RELIEF REQUEST NDE-18 (REVISED)

NORTH ANNA UNIT 1 RELIEF REQUEST NDE-18 (REVISED)

1. IDENTIFICATION OF COMPONENTS System:

Chemical and Volume Control (CH) Component: Regenerative Heat Exchanger (1-CH-E-3) Connecting Circumferential Piping Welds l Welds / Components Description Code item # Class 3 tubesheet-to-head 82.60 1 7 tubesheet-to-head B2.60 1 11 tubesheet-to-head B2.60 1 4 circumferential head B2.51 1 8 circumferential head 82.51 1 12 circumferential head B2.51 1 13 nozzle-to-vessel B3.150 1 14 nozzle-to-vessel B3.150 1 15 nozzle-to-vessel B3.150 1 16 nozzle-to-vessel B3.150 1 17 nozzle-to-vessel B3.150 1 18 nozzle-to-vessel B3.150 1 l 13NIR nozzle inside radius B3.160 1 14NIR nozzle inside radius B3.160 1 15NIR nozzle inside radius B3.160 1 16NIR nozzle inside radius 83.160 1 17NIR nozzle inside radius B3.160 1 18NIR nozzle inside radius 83.160 1 19 terminal end weld B9.21 1 20 terminal end weld B9.21 1 21 terminal end weld B9.21 1 22 terminal end weld B9.21 1 WS-1 welded attachment B8.40 1 WS-2 welded attachment B8.40 WS-3 welded attachment B8.40 1 WS-4 welded attachment B8.40 1 WS-5 welded attachment B8.40 1 WS-6 welded attachment B8.40 1 1 circumferential head C1.20 2 5 circumferential head C1.20 2 9 circumferential head C1.20 2 2 tubesheet-to-shell C1.30 2 6 tubesheet-to-shell C1.30 2 10 tubesheet-to-shell C1.30 2 1 of 4

1. IDENTIFICATION OF COMPONENTS (Continued):

Welds / Components Description Code item # Class J (Drawing 11715-WMKS-0103CD) 21A terminal end weld B9.21 1 l (Drawing 11715-WMKS-0111H) 32 terminal end weld B9.21 1

11. IMPRACTICAL CODE REQUIREMENTS Examination Categories B-B, B-D (Inspection Program B), B-H, B-J, and C-A l

require that volumetric and surface examinations be performed as indicated by the Code item numbers above. Ill. BASIS FOR RELIEF The regenerative heat exchanger (1-CH-E-3) provides preheat for the normal charging water going into the reactor coolant system (RCS). The preheat is derived from normal letdown water coming from the RCS. Charging and letdown constitute the normal chemical and volume control within the RCS. The heat exchanger itself is actually three heat exchangers in series, interconnected with piping. This fact was previously utilized in limiting examinations to one of the heat exchangers as allowed by the Code. The heat exchanger has an outside shell diameter of 9.55 inches. The shells were manufactured with ASTM A351 CF8 type material. The heads were manufactured with ASTM A240 TP304 material. The 3 inch nozzle necks were manufactured with ASTM A182 F304 material. Until very recently the regenerative heat exchanger was entirely classified ASME Class 2 for inservice inspection activities. However, a reanalysis changed the classification of the letdown side of the heat exchanger to ASME Class 1. This action significantly increases the examination requirements associated with this heat exchanger. Nozzles, which were previously exempt under Class 2 requirements are now required to be examined. Additionally, all Class 1 nozzles are required to be examined, and the examinations are not limited to one heat exchanger. The nozzle-to-vessel welds and nozzle inside radius sections for this vessel were not designed for ultrasonic examination from the outside diameter of the vessel. The small diameter of the vessel and nozzles along with the cast stainless steel vessel shell prevents a meaningful ultrasonic examination of these components. 2 of 4

Ill. BASIS FOR RELIEF (Continued): 1 The Code required volumetric examination on the vessel head circumferential welds is limited due to the weld crown, radius of the closure caps, and the nozzles. The Code required volumetric examination of the tubesheet welds is limited by the weld crown and is obstructed by a support clamp. This clamp must be mechanically removed prior to the welds' examination. Additionally weld 11 is j partially obscured by the six integral attachments, which are themselves butted up against a clamp. It is estimated that between 21 and 42 percent of the circumferential welds could be examined, and 42 percent of the tubesheet welds could be examined, if the clamps are removed. Weld 11 would be significantly less due to the integral attachment location. Previous partial examinations completed on these welds have identified no problems. An ALARA evaluation has been conducted on each activity associated with these examinations. A table is provided documenting these results, it is estimated that more than 26 man-rem will be required to complete these examinations over the interval. This estimate assumes optimum inspection and preparation times. If difficulties are encountered, a corresponding increase in dose would be expected. Shielding is not considered practical since the source of radiation is the component receiving the examinations. Considering the examination limitations previously discussed, expending this much dose is deemed impractical. This relief request was originally submitted by letter Serial No. 93-018, dated February 16,1993. The relief was granted ("provided that the lower regenerative heat exchanger receives the Code-required examinations to the extent possible") by letter dated August 7,1995, and its associated safety evaluation report. This request is being revised to add four of six terminal end piping-to-vessel welds which are required to be selected for examination under Category B-J note 1(a) under item B9.21. These welds were omitted from the original request and need to be addressed in this relief request in addition to those already evaluated. New survey maps of the regenerative heat exchanger indicate higher dose rates than previously estimated (survey attached). Performing these surface examinations would result in approximately 10.5 man-rem of exposure and would negate, to a large degree, the exposure reduction of the original relief request. This is due to the close proximity of the regenerative heat exchanger to these welds and the need for scaffolding and insulation removal, which were previously eliminated for the regenerative heat exchanger in our original relief request. I 3 of 4

IV. ALTERNATE - REQUIREMENTS Technical Specifications require that the RCS Leak Rate be limited to 1 gallon per 1 minute unidentified leakage. This value is calculated every 72 hours in i accordance with Technical Specification requirements. Additionally, the containment atmosphere particulate radioactivity is monitored every 12 hours per Technical Specification requirements. As a result, new leakage is rapidly identified and located during operation. Leakage identified from these components can be easily isolated by two upstream valves with manual operation from within the control room. The valves also receive an automatic control signal to close on inventory loss based on pressurizer level. However, these valves could not be used as the Class 1 boundary valves due to their nonsafety-related actuation. Correspondingly, as a result of the reclassification to Class 1, these components will receive a system leakage test prior to start up after each refueling outage. During this system leakage test the components will receive a visual (VT-

2) examination. The support structures will receive a visual (VT-3) examination to the extent required by the Code without insulation removal.

Your evaluation of our original relief request, dated August 7,1995, added alternative requirements. The appropriate portion of the Technical Evaluation Report follows: Based on the statement by the licensee that previous partial examinations have been completed on these welds, it is concluded that a best effort volumetric examination of the lower RHX, in addition to system radiation monitoring and the Code required visual examinations, would provide a reasonable assurance of the system's inservice structural integrity. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), it is recommended that relief be granted provided the lower RHX vessel receives Code-required volumetric examinations to the extent possible. We would also request that this philosophy of inspection be extended to the vessel-to-piping terminal end welds on the regenerative heat exchanger. The two lower RHX vessel-to-piping terminal end welds (22 & 21 A) will be examined by the surface method as required by the Code, l 4 of 4

I NORTH ANNA UNIT 1 1 -C H-E-3 EXAMINATIONS MAN-REM ESTIMATE Work Task Man Hours (hrs) Dose Rate (R/hr) Man-Rem insulation Remove / Install 5.3 0.500 2.650 Scaffolding install / Remove 1.0 0.350 0.350 Clamp Remove / Install 2.0 1.000 2.000 Weld Prep. 3.5 1.000 3.500 HP Coverage 31.0 0.010 0.310 Nozzle-to-Vessel Inspection (UT) 6.0 1.000 6.000 Nozzle inside Radius Inspection (UT) 4.5 1.000 4.500 Circumferential/Tubesheet Inspection (UT) 4.0 1.000 4.000 Welded Attachment inspection (PT) 3.0 1.000 3.000 Total Estimate = 26.310 1 of 1

NORTH ANNA UNIT 1 1-CH-E-3 PIPING TERMINAL ENDS EXAMINATIONS MAN-REM ESTIMATE 6 Terminal End Welds Wgrk Task Man-Hours (hrs) Dose Rate (R/hr) Man-Rem Insulation Remove / Install 2.0 2.000 4.0 Scaffolding Install / Remove 1.0 1.500 1.5 Weld Prep. 1.0 2.000 2.0 PT Exam 6 Welds 1.5 2.000 _34 Total Estimate = 10.5 2 of 1

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i ATTACHMENT 2 NORTH ANNA UNIT 2 RELIEF REQUEST NDE-18 (REVISED) I

NORTH ANNA UNIT 2 RELIEF REQUEST NDE-18 (REVISED) 1. IDENTIFICATION OF COMPONENTS System: Chemical and Volume Control (CH) Component: Regenerative Heat Exchanger (1-CH-E-3) Connecting Circumferential Piping Welds l (Drawing 12050-WMKS-CH-E-3) l Welds / Components Description Code item # Class 8 tubesheet-to-head B2.60 1 10 tubesheet-to-head B2.60 1 12 tubesheet-to-head B2.60 1 2 circumferential head B2.51 1 4 circumferential head B2.51 1 6 circumferential head B2.51 1 13 nozzle-to-vessel B3.150 1 14 nozzle-to-vessel B3.150 1 15 nozzle-to-vessel B3.150 1 16 nozzle-to-vessel B3.150 1 17 nozzle-to-vessel B3.150 1 18 nozzle-to-vessel B3.150 1 13NIR nozzle inside radius B3.160 1 14NIR nozzle inside radius B3.160 1 15NIR nozzle inside radius B3.160 1 16NIR nozzle inside radius B3.160 1 17NIR nozzle inside radius B3.160 1 18NIR nozzle inside radius B3.160 1 19 terminal end weld 89.21 1 20 terminal end weld B9.21 1 21 terminal end weld B9.21 1 22 terminal end weld B9.21 1 WS-1 welded attachment B8.40 1 WS-2 welded attachment B8.40 1 WS-3 welded attachment B8.40 1 WS-4 welded attachment B8.40 1 WS-5 welded attachment B8.40 1 WS6 welded attachment B8.40 1 1 circumferential head C1.20 2 3 circumferential head C1.20 2 5 circumferential head C1.20 2 7 tubesheet-to-shell C1.30 2 9 tubesheet-to-shell C1.30 2 11 tubesheet-to-shell C1.30 2 Page 1 of 4 1

} 1. IDENTIFICATION OF COMPONENTS (Continued): Welds / Components Description Code item # Class (Drawing 12050-WMKS-0111ST) 1A terminal end weld 89.21 1 (Drawing 12050-WMKS-0111Z) 46 terminal end weld 89.21 1 II. IMPRACTICAL CODE REQUIREMENTS Examination Categories B-B, B-D (Inspection Program B), B-H, B-J, and C-A l require that volumetric and surface examinations be performed as indicated by the Code item numbers above. UNIT 2 RELIEF REQUEST NDE-18 Continued: lil. BASIS FOR RELIEF The regenerative heat exchanger (2-CH-E-3) provides preheat for the normal charging water going into the Reactor Coolant System (RCS). The preheat is j derived from normal letdown water coming from the RCS. Charging and letdown constitute the normal chemical and volume control within the RCS. The heat exchanger itself is actually three heat exchangers in series interconnected with piping. This fact was previously utilized in limiting examinations to one of the heat exchangers as allowed by the Code. The heat exchanger has an outside shell diameter of 9.55 inches. The shells were manufactured with ASTM A351 CF8 type material. The heads were manufactured with ASTM A240 TP304 material. The 3 inch nozzle necks were manufactured with ASTM A182 F304 material. Until very recently the regenerative heat exchanger was entirely classified ASME Class 2 for inservice inspection activities. However, a reanalysis changed the classification of the letdown side of the heat exchanger to ASME Class 1. This action significantly increases the examination requirements associated with this heat exchanger. Nozzles which were previously exempt under Class 2 requirements are now i required to be examined. Additionally all Class 1 nozzles are required to be examined, and the examinations are not limited to one heat exchanger. The nozzle-to vessel welds and nozzle inside radius sections for this vessel were not designed for ultrasonic examination from the outside diameter of the vessel. The small diameter of the vessel and nozzles along with the cast stainless steel vessel shell prevents a meaningful ultrasonic examination of these components. l Page 2 of 4

The volumetric examination on the vessel head circumferential welds as required by the Code is limited due to the weld crown, radius of the closure caps, and the nozzles. The Code required volumetric examination of the tubesheet welds is limited by the weld crown and is obstructed by a support clamp. This clamp must be mechanically removed prior to the welds' examination. Additionally weld 12 is partially obscured by the six integral attachments which are themselves butted up against a clamp. It is estimated that between 21 and 42 percent of the l circumferential welds could be examined, and 42 percent of the tubesheet welds could be examined, if the clamps are removed. Weld 12 would be significantly less due to the integral attachment location. Previous partial examinations completed on these welds have identified no problems. An ALARA evaluation has been conducted on each activity associated with these examinations. A table is provided documenting these results. It is estimated that more than 32 man-rem will be required to complete these examinations over the interval. This estimate assumes optimum inspection and preparation times. If difficulties are encountered, a corresponding increase in dose would be expected. Shielding is not considered practical since the source of radiation is the component receiving the examinations. Considering the examination limitations previously discussed, expending this much dose is deemed impractical. This relief request was originally submitted by letter Serial No. 93-018, dated February 16,1993. The relief was granted ("provided that the lower regenerative j heat exchanger receives the Code-required examinations to the extent possible") by letter dated August 7,1995, and its associated safety evaluation report. This request is being revised to add four of six terminal end piping-to-vessel welds which are required to be selected for examination under Category B-J note 1(a) under item B9.21. These welds were omitted from the original request and need to be addressed in this relief request in addition to those already evaluated. New survey maps of the regenerative heat exchanger indicate higher dose rates than previously estimated (survey attached). Performing these surface examinations i would result in approximately 10.5 man-rem of exposure and would negate, to a large degree, the exposure reduction of the original relief request. This is due to the close proximity of the regenerative heat exchanger to these welds and the need for scaffolding and insulation removal, which were previously eliminated for the regenerative heat exchanger in our original relief request. Page 3 of 4

UNIT 2 RELIEF REQUEST NDE-18 Continued: IV. ALTERNATE REQUIREMENTS Technical Specifications require that the RCS Leak Rate be limited to 1 gallon per minute unidentified leakage. This value is calculated every 72 hours in accordance with Technical Specification requirements. Additionally, the containment atmosphere particulate radioactivity is monitored every 12 hours per Technical Specification requirements. As a result, new leakage is rapidly identified and located during operation. Leakage identified from these components can be easily isolated by two upstream valves with manual operation from within the control room. The valves also receive an automatic control signal to close on inventory loss based on pressurizer level. However, these valves could not be used as the Class 1 boundary valves due to their nonsafety-related actuation. Correspondingly, as a result of the reclassification to Class 1, these components will receive a system leakage test prior to start up after each refueling outage. During this system leakage test the components will receive a visual (VT-

2) examination. The support structures will receive a visual (VT-3) examination to the extent required by the Code without insulation removal.

Your evaluation of our original relief request, dated August 7,1995, added alternative requirements. The appropriate portion of the Technical Evaluation Report states: The licensee stated that previous partial examinationshave been completed on these welds. Consequently, it is concluded that a best-effort volumetric examination of the lower RHX, in addition to system radiation monitoring and the Code-required visual examinations, would provide reasonable assurance of the system's inservice structural integrity. Therefore, it is recommended that relief be granted, pursuant to 10 CFR 50.55a(g)(6)(i), provided the lower RHX vessel receives Code-required volumetric examinations to the extent possible. We also request that this philosophy of inspection be extended to the vessel-to-piping terminal end welds on the regenerative heat exchanger (RHX). The two lower RHX vessel-to-piping terminal end welds (22 & 46) will be examined by the surface method as required by the Code. Page 4 of 4

2-CH-E-3 EXAMINATIONS MAN-REM ESTIMATE Work Task Man-Hours (hrs) Dose Rate (R/hr) Man-Rem Insulation Remove / Install 5.3 0.500 2.650 Scaffolding Install / Remove 0.0 0.000 0.000 Clamp Remove / Install 2.0 1.000 2.000 f Weld Prep. 3.5 1.000 3.500 HP Coverage 36.0 0.010 0.360 Nozzle-to-Vessel inspection (UT) 8.1 1.000 8.100 Nozzle Inside Radius Inspection (UT) 6.6 1.000 6.600 Circumferential/Tubesheet inspection (UT) 5.3 1.000 5.300 Welded Attachment inspection (PT) 3.0 1.000 3.000 Total Estimate = 32.305 Page 1 of 1

NORTH ANNA UNIT 2 2-CH-E-3 PIPING TERMINAL ENDS EXAMINATIONS MAN-REM ESTIMATE 6 Terminal End Welds Work Tasl( Man-Hours (hrs) Dose Rate (R/hr) Man-Rem insulation i Remove / Install 2.0 2.000 4.0 Scaffolding Install / Remove 1.0 1.500 1.5 l Weld Prep. 1.0 2.000 2.0 PT Exam 6 Welds 1.5 2.000 _1Q Total Estimate = 10.5 i l l i \\ Page 2 of 1 1

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JOB MAN-REM PROJECTION DATE:12/04/92 ) ALARA EVALUATION NUMBER: UNIT # 2 JOB DESCRIPTION: ISI/NDE REGEN HEAT EXCHANGER INSPECTIONS 1 WORK MAN DOSE MAN-REM / TASK TASK GROUP HOURS RATE WORKGROUP TOTAL TOP Hx: ISl/NDE - UT (2) NOZ TO VESSEL WELDS 2.7 1.000 2.700 - UT (2) INNER RADIUS WELDS 2.2 1.000 2.200 MID Hx: - UT (2) NOZ TO VESSEL WELDS 2.7 1.000 2.700 - UT (2) INNER RADIUS WELDS 2.2 1.000 2.200 BOTTOM Hx: - UT (2) NOZ TO VESSELWELDS 2.7 1.000 2.700 - UT (2) INNER RADIUS WELDS 2.2 1.000 2.200 - UT (4) CIRCUMFERENTIALWELDS 5.3 1.000 5.300 - PT (6) WELDED ATTACHMENT LUGS 3.0 1.000 3.000 23.000 SUPPORT ACTIVITIES: - INSUL RMVUINSTALL INSUL 5.3 0.650 3.445 - SCAFFOLDING INSTALL /RMVL CARP. 0.0 0.000 0.000 - WELD PREP PF 3.5 1.000 3.500 - HP COVERAGE HP 36.0 0.010 0.360 - (3) CLAMP RMVUINSTALL PF 2.0 1.000 2.000 9.305 NOTE: UT INSPECTION FOR CIRCUMFERENTIAL WELDS INCLUDE (3) PASSES: 0,45, AND 60 DEGREES MAN-REM TOTAL 32.305 REM MAN-HOUR TOTAL 70 HOURS U AL' ARA SIGNATURE

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