ML20237C434

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Requests Relief from Some Requirements of ASME BPV Code as Described in Attached Relief Requests98-002 & 98-003.Relief Is Requested from Performing Regenerative Heat Exchanger Volumetric Exams & Requirements of 1989 ASME BPV Code
ML20237C434
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 08/13/1998
From: Barron H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9808210164
Download: ML20237C434 (18)
v • d • e


Text

{{#Wiki_filter:_ _ _ _ _. _ _ _ - _ _ _ _ - _ _ _ _ _ - _ l l (' g gg Duks EnerCy Corpor;thn f # Energy. McGuire Nudear Station l 12700 Hagers Ferry Road HuntersviUe, NC 28078-9340 H, B. Barron (704) 875-4800 omCE Yice President (704) 875 4809 Mx I August 13, 1998 1 I U. S. Nuclear Regulatory Commission I i Document Control Desk Washington, D.C. 20555-0001

Subject:

McGuire Nuclear Station Docket Nos. 50-369, 370 Relief Requests 98-002 and 98-003 Pursuant to 10CFR50. 55a (a) (3 ) (ii), Duke Energy Corporation requests relief from some requirements of the ASME Boiler and Pressure Vessel Code as described in the attached Relief Requests 98-002 and 98-003. These requests are submitted together since Relief Request 98-002 is used as the basic for approval of Relief Request 98-003. Specifically, Relief Request 98-002 requests relief from performing Unit 1 and Unit 2 Regenerative Heat Exchanger volumetric examinations required by the 1989 ASME Boiler and Pressure Vessel Code, Section XI, Table IWC-2500-1, Examination Category C-A Pressure Retaining Welds in ] Pressure Vessels, Items Numbers C1.20 and C1.30, Figures j IWC-2500-1 and IWC-2500-2 and Note (1). Relief Request 98-l 003 requests relief from the requirements of 1989 ASME Boiler and Pressure Vessel Code, Section XI, paragraph IWC-l 2412 and Table IWC-2412-1 as a result of Relief Request 98-j 002. J l Questions should be directed to Julius Bryant, McGuire Licensing and Compliance, at (704) 875-4162. Sincerely, D r H. B. Barron, Vi e President McGuire Nuclear Station } /) Attachments L v -s U 9808210164 980813 PDR ADOCK 05000369 P PDR

i l i U.S. Nuclear Regulatory Commission j Aug,ust 13, 1998 Page 2 l cc: Mr. L. A Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. F. Rinaldi, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 9H3 Washington, D.C. 20555 S. M. Shaeffer Senior NRC Resident Inspector McGuire Nuclear Station { 1 i i I 1 i 1 i

a Serial No. 98-002 Page 1 of 7 i Duke Energy Corporation L l Station McGuire Unit 1 & 2 f SECOND 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 98-002 Pursuant to 10CFR50.55a (a)(3) (ii), Duke Energy Corporation has determined that compliance with the specified code requirements results in hardship or i unusual difficulty and conformance with the examination requirements of the ASME Section XI requirements is not practical. This requirement would present hardship or unusual difficulty without a compensating increase in the level of 1 quality and safety. Accordingly information is being submitted in support of our determination and a request is being sought for relief from the applicable ASME Section XI requirement (s). 1. System / Component (s) for Which Reliefis Reauested: Safety-related ASME Section XI Code Class 2 Regenerative Heat Exchanger Head Circumferential and Tubesheet-to-Shell welds in Table IWC-2500-1 (Examination Category C-A). There are a total of twelve (12) welds per unit. l UNIT 1 l Weld Numbers Item Numbers Description End Of Cycle i 5141.-1-HD1 C01.020.070 Nozzle Belt to Head 12 l. (Shell 1) 5141-1-HD2 C01.020.071 Shell to Head (Shell 1) 12 5141-2-HDI C01.020.072 Nozzle Belt to Head 13 (Shell 2) 5141-2-HD2 C01.020.073 Shell to Head (Shell 2) 13 5141-3-HD1 C01.020.074 Nozzle Belt to Head 14 (Shell 3) 5141-3-HD2 C01.020.075 Shell to Head (Shell 3) 14 5141-1-NB-TS C01.030.020 Nozzle Belt to Tubesheet 12 (Shell 1) 5141-1-TS-SH C01.030.021 Tubesheet to Shell 12 (Shell 1) 5141-2-NB-TS C01.030.022 Nozzle Belt to Tubesheet 13 (Shell 2) l

l Serial No. 98-002 Page 2 of 7 l UNIT I (Continued) Weld Numbers Item Numbers Description End Of Cycle 5141-2-TS-SH C01.030.023 Tubesheet to Shell 13 (Shell 2) 5141-3-NB-TS C01.030.024 Nozzle Belt to Tubesheet 14 (Shell 3) 5141-3-TS-SH C01.030.025 Tubesheet to Shell 14 (Shell 3) UNIT 2 Weld Numbers Item Numbers Description End Of Cycle 514 1-HDI C01.020.070 Nozzle Belt to Head 10 (Shell 1) 5141-1-HD2 C01.020.071 Shell to Head (Shell 1) 10 5141-2-HD1 C01.020.072 Nozzle Belt to Head 12 (Shell 2) 5141-2-HD2 C01.020.073 Shell to Head (Shell 2) 12 5141-3-HDI C01.020.074 Nozzle Belt to Head 14 (Shell 3) 5141-3-HD2 C01.020.075 Shell to Head (Shell 3) 14 5141-1-NB-TS C01.030.020 Nozzle Belt to 7 ubesheet 10 (Shell 1) 5141-1-TS-SH C01.030.021 Tubesheet to Shell 10 (Shell 1) 5141-2-NB-TS C01.030.022 Nozzle Belt to Tubesheet 12 I (Shell 2) 5141-2-TS-SH C01.030.023 Tubesheet to Shell 12 (Shell 2) l 5141-3-NB-TS C01.030.024 Nozzle Belt to Tubesheet 14 (Shell 3) 5141-3-TS-SH C01.030.025 Tubesheet to Shell 14 (Shell 3) i I

Serial No. 98-002 Page 3 of 7 II. Code Requirement: The 1989 Section XI ASME Boiler and Pressure Vessel Code, Table IWC-2500-1, Examination Category C-A (Pressure Retaining Welds in Pressure Vessels) requires a volumetric examination of the weld during each inspection interval, included in this requirement are Item Number (s) C1.20 and C1.30, Figure Number (s) IWC-2500-1 and IWC-2500-2 and Note (1) which states " Includes essentially 100% of the weld length." III. Code Requirement from which Reliefis Requested: Reliefis requested from performing the volumetric examination required by the 1989 ASME Boiler and Pressure Vessel Section XI Code requirements of Table IWC-2500-1, Examination Category C-A Pressure Retaining Welds in Pressure Vessels for Item Number (s) C1.20 and C1.30, figure Number (s) IWC-2500-1 and IWC-2500-2 and Note (1) which states " Includes essentially 100% of the weld i length." IV. Basis for Relief: Due to ALARA concerns of high radiation in the area of the heat exchangers, it is station management's recommendation that these welds not be examined. Per ALARA calculations, to complete the examination (s) on the Regenerative Heat Exchanger an estimated dose of 12038 mrem would be expected for each unit. Listed below are the dose estimates received from the McGuire Radiation Protection ALARA Specialist of the radiation exposure expected for these examinations. The estimates listed below assume dose rates at the time of examination will be comparable to dose rates measured during previous outages. However, it is likely that the dose rates in the Regenerative Heat Exchanger will l be higher during the next few refueling outages due to higher cobalt activity in the coolant system resulting from operation of new Steam Generators. Plants that have replaced Steam Generators (including Catawba Nuclear Station) have reported higher radioactivity in the coolant system during outages following replacement of their Steam Generators, causing higher dose rates in piping and I components associated with the coolant system. l f E_ _ __

Serial No. 98-002 Page 4 of 7 The radiation levels in the general area of the heat exchanger are 600 mrem per hour. Activity Top Middle Bottom Total i InstMI/ remove scaffolding 900 900 0 1800 i mrem Remove / replace insulation 900 900 900 2700 mrem Prep (assumes no grinding) 600 600 600 1800 l mrem NDE 1800 1800 1800 5400 l mrem RP support 113 113 113 338 mrem Total 4313 4313 3413 12038 mrem Additionally it is possible that the structural steel supporting the heat exchangers 1 would have to be removed to facilitate the examination process. The estimate shown above does not include removal and replacement of any structural steel. The use of temporary shielding has been considered. However, preliminary temporary shielding evaluations using typical temporary shielding methods and I materials suggest that the amount of exposure that would be incurred to install and remove the shielding would be equal to or greater than the amount of exposure that would be saved. The use of chemical backflushes of the letdown header, which includes the Regenerative Heat Exchanger, have been performed in the past. The goal of these - l flushes is to reduce dose rates on the letdown header by removing residual radioactivity ' trapped' in the piping during unit cooldowns in preparation for refueling outages. Dose rate data collected before and after these flushes has shown, on average, a 10% to 20% reduction in letdown header piping dose rates. However, no data has been collected to measure the impact of flushing on dose rates in the vicinity of the Regenerative Heat Exchanger. The dose estimate above assumes that the letdown header has been backflushed and comparable dose rate reduction factors in the vicinity of the Regenerative Heat Exchanger are achieved. As of this time, no other viable optiens for flushing the Regenerative Heat Exchanger have been identified. 1_______.____________________

Serial No. 98-002 Page 5 of 7 V. Alternate Examination or Testing: Given there is no alternative beyond that already required by Code, in lieu of implementing the requirements of the 1989 ASME Boiler and Pressure Vessel Section XI Code Examination Category C-A, it is proposed that the inservice examination and testing being currently performed under the Examination Category C-H (vist.al, VT-2) "All Pressure Retaining Components" be taken into consideration as a basis for approval for this request. VI. Justification for the Grantine of Relief: Approval of the alternative testing provided by this request for relief would significantly save company resources and reduce unnecessary radiological exposure to plant personnel when complying with the volumetric examination requirements without decreasing the confidence level in the operability of the Regenerative Heat Exchanger. The alternative testing would not result in reduction in the safety oflife or property for the following reasons: The Regenerative Heat Exchanger and associated system piping are designed and constructed to have a low probability of failure throughout their design life. The heat exchanger is constructed to ASME Section III requirements, and its associated system piping is constructed to Duke Class B, ASME Class 2 requirements. McGuire Technical Specifications place conservative limits on the amount of reactor coolant leakage allowed during system operation. The reactor coolant leak detection system is in place to detect any variation in the reactor coolant water inventory, including the water present in both the tube and shell side of the Regenerative Heat Exchanger, as well as its associated piping. Any weld failure would be detected by the reactor coolant leak detection system, and procedures and automatic system actions are in place to assure that the heat exchanger would be isolated.

1 l l l Serial No. 98-002 Page 6 of 7 The Regenerative Heat Exchanger is isolable from the reactor coolant by valves operated from the Control Room, several of which receive automatic closure signals. The shell side of the heat exchanger is isolable from the reactor coolant l system by two fail closed air operated gate valves in series. These valves are l operated from the Control Room and also automatically close on a low reactor coolant system pressurizer level, which would be present with u significant leak. The tube side is isolable from the reactor coolant system by two flowpaths each with check valves in series with an air operated gate valve controlled from the l Control Room. The tube side is isolable from the high pressure charp,ing system i by two motor operated gate valves in series, which are controlled from the Control l Room and automatically close on a Safety Injection Signal, which would be present with a significant leak. The Regenerative Heat Exchanger is located inside the Containment Building, which is de. signed to contain any leak. VII. Implementation Schedule: During the second interval, the Regenerative Heat Exchanger Pressure testing examinations will be scheduled and performed in accordance with the requirements of Table IWC-2500-1 Examination Category C-H. The Pressure Testing examination schedules are shown below. UNIT 1 TEST ITEM INSPECTION END OF PERIOD NUMBER DATE CYCLE Leak Test C07.030.016 10/01/94 9 1" Period Leak Test C07.030.016 01/23/96 10 2"d Period Hydro Test C07.040.007 To Be Done 13 and 14 3'd Period UNIT 2 TEST ITEM INSPECTION END OF PERIOD l NUMBER DATE CYCLE Leak Test C07.030.039 05/09/96 9 and 10 1" Period l Leak Test C07.030.039 To Be Done 14 and 15 3'd Period Hydro Test C07.040.007 To Be Done 11,12 or 13 2"d Period i I

o Serial No. 98-002 Page 7 of 7 The following individuals were involved in the development of this request for relief. James R. Puckett (ALARA Specialist) developed dose estimates for Regenerative Heat. Pete L. Schuerger (Design Engineering McGuire) gave design justification for granting of relief. Gary Underwood (Inservice Inspection McGuire) wrote request for relief and addressed code requirements.

Attachment:

i 1. Sub-Assembly and Details Drawit of Regenerative Heat Exchanger l l Evaluated By: b ud Date 7 9 98 LA \\ ~ d_., L $2 >. w o D ate 7,[I3/98 Reviewed By: Approved By: --M h,a,M ) Date 7 I9 9

Serial No. 98-003 Page 1 of 3 Duke Energy Corporation Station McGuire Unit ! & 2 SECOND 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 98-003 Pursuant to 10CFR50.55a (a)(3) (ii), Duke Energy Corporation has determined that compliance with the specified code requirements results in hardship or unusual difficulty and conformance with the examination requirements of the ASME Section XI requirements is not practical. This requirement would present hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly information is being submitted in support of our determination and a request is being sought for relief from the applicable ASME Section XI requirement (s). I. System / Comnonent(s) for Which Relief is Reauested: Safety-related ASME Section XI Code Class 2 Regenerative Heat Exchanger Head Circumferential and Tubesheet-to-Shell welds. There are a total of twelve welds per unit as described in Request for Relief 98-002. II. Code Requirement: The 1989 ASME Boiler and Pressure Vessel Section XI Code, Subarticle IWC-2400, Inspection Schedule; Paragraph IWC-2412 Inspection Program B. "The required examinations in each examination category shall be completed during each inspection interval in accordance with Table IWC-2412-1". III. Code Requirement from which Reliefis Reauested: Relief is requested from the above requirements of paragraph IWC-2412 and Table IWC-2412-1 as a result of Request for Relief 98-002.

.-_._____--_--..-_---._------------_~J

e Serial No. 98-003 Page 2 of 3 IV. Basis for Relief - (Unit 1) Examination Category C-A Due to extremely high radiation in the area of the Regenerative Heat Exchanger (s), the minimum percentages for the second period and the end of.. interval totals can't be met. In Examination Category C-A, the Regenerative Heat-Exchanger involves twelve (12) of the twenty-three (23) exams scheduled for examination during the second interval. The Second Period minimum of 50 percent will not be' met due to' the elimination of 4 scheduled e 9 ms (9 complete /23 total =3913%). The Second Interval minimum of 100 percent will not be met due to the elimination of twelve (12) scheduled exams (9 complete + 2 more scheduled /23 total =47.82%). - For the Second Interval, excluding twelve (12) Regenerative Heat Exchanger exams, a total of eleven (11) examinations can be done for this code category. This examination total would leave the fmal percentage for Examination Category C-A at 11/23=47.82%, not 100% as required by the Section XI Code, Table IWC-2412-1. (Unit 2) Examination Cate:;ory C-A Due'to extremely high radiation in the area of the Regenerative Heat Exchanger (s), the minimum percentages for the second period and the end of interval totals can't be met. In Examination Category C-A, the Regenerative Heat Exchanger involves twehe (12) of the twenty-five (25) exams scheduled during the second interval. The Second Period minimum of 50 percent will not be met due to the elimination of 4 scheduled exams (3 complete + 5 more scheduled /25 total =32.00%). v L The Second Interval minimum of 100 percent will not be met due to the elimination of twelve (12) scheduled exams (3 complete + 10 more scheduled /25 total =52.00%).

-( Serial No. 98-003 Page 3 of 3 For the Second Interval, e eludine the twelve (12) Regenerative IIcat Exchanger J exams,a total of thirteen (13) examinations can be done for this code category. This examination total would leave the final percentage for Examination Category C-A at 13/25=52.00%, not 100% as required by the Section XI Code, Table IWC-2412-1. V. Alternate Examination or Testine: All examinations scheduled under the requirements of the 1989 ASME Boiler and Pressure Vessel Section XI Code, Table IWC-2500-1, Examination Category C-A will be done to these requirements witt. le exception of the Regenerative Heat Exchangers, therefore, no similar equipment welds can be examined as an alternative. In the case of the Regenerative Heat Exchangers it is proposed that the testing being performed u'nder Examination Category C-II "All Pressure Retaining Components" be taken into consideration as a basis for approval for this request, reference Request for Relief 98-002. VI~ Justification for the Grantine of Relief: Reference Request for Relief 98-002. VII. Implementation Schedule: Reference Request for Relief 98-002. I i i 7f 3 I% b Date Evaluated By: %x \\ \\ 7,//3,[92 w Date l Reviewed By: o> g-Approved By: Date 7 v L l ..__o

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