ML20081F337
| ML20081F337 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/31/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20081F344 | List: |
| References | |
| 91-218, NUDOCS 9106100009 | |
| Download: ML20081F337 (17) | |
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}{ l C ll bl o N Is. Vi tull N I A 2112 01 May 31, 1991 U.S. Nuclear Regulatory Commission Serial No. 91 218 l Attention: Document Control Desk NL&P/JBL: R1 Washington, D.C. 20555 Docket No. 50 338 License No. NPF 4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY RQRTH ANNA POWER STATION UNIT 1 SECOND TEN-YEAR INSERVICE INSPECTION PROGRAM RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION By letter Serial No. 90 716, dated November 21,1990, Virginia Electric and Power Company submitted Revision 1 to the North Anna Unit 1 Second Ten Year Interval inservice inspection Program for NRC review and approval. By letter dated April 11, 1991, the NRC requested additionalinformation in order to complete their review and evaluation of the our inspection program. Attachment 1 to this letter provides our formal response to the NRC's request for additionalinformation. Several aspects of our inspection program were discussed by telephone with the NRC staff and its contractor, Idaho National Engineering Laboratory, to clarify issues inferred by the requested information. in response to the NRC's comments, appropriate changes to the North Anna Unit 1 Inservice inspection program have been made. The revised second interval program and program plan are provided as Attachments 2 and 3, respectively. Should you have any questions or require additional information, please contact us at your earliest convenience. 7 Verystulyy ts? ,
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W. L7 Stew' art Senior Vice President Nuclear . Attachment <
- 1. Response to NRC Request for Additional Information
- 2. North Anna Unit 1 Second Interval inservice inspection Program, Revision 2
- 3. North Anna Unit 1 Second Intervalinservice inspection Program Plan NO $0b? NNN33 Ib Q PDR (O
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cc: U.S. Nuclear Regulatory Commission Region ll 101 Mariotta Street, N.W. Suito 2900 Atlanta, Georgia 30323 Mr. M. S, Lessor NRC Senior Resident inspector North Anna Power Station l l 1 I 1 l l
11TTAflitiERT___1 A) HEC: Please provide a listing of all Class 2 systems at North Anna Power Station Unit 1, that are classified as (1) Residual lleat Removal ( RilR) , (2) Emergency Core Cooling (ECC), (3) Containment IIcat Removal (CilR) systems. For each of t!'e systems listed above, state the number and percentage of the Class 2 piping welds that will receive surface examination during the second 10-year inspection interval, y1EQ: (1) Residual licat Removal system: Portions of Residual IIcat Removal ( RilR) , line numbers designated Hil. (2) Emergency Core Cooling system: Portions of Chemical Volume and Control (CVCS), line numbers designated Cll. system: Safety Injection (SI), line numbers designated SI. (3) Containment lleat Removal system: Portions of Quench Spray (QS), line numbers designated QS. system: Recirculation Spray (RS), line numbers designated RS. Surface examinations schedeled: RllR: 11, 6.8% of nonexempt system wolds. CVCS: 0, 0% of nonexempt system welds. SI: 38, 7.6% of nonexempt system welds. QS: 10, 6.7% of nonommpt nystem welds. RS: 7, 8.8% of nonexempt systeN welds. Note: Per agreement furing telecon on April 25, 1991 with ' A r. G. Johnson (HRC), a revision will be cado, which selects 7.5% (nonexempt volds) of each system by Code Case N-408 item number. Items C5.21 and C5.22 will be submitted by the third period. B) HRC: 10CPR 50. 55a (b) (2) (iv) requires that pipe welds in RilR, ECC, and CllR systems be examined. The extent of these examinations shall be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, and paragraph IWC-2411 in the 1974 Edition and Addenda through Sumlaer 1975 of Section XI of the ASME Code. Verify that the
" temperature /presnure" and " chemistry control" exclusions of IWC-1220(a) and IWC-1220(c), respectively, will not be used to exclude wolds of these systems from inservice 1
a
4 y examinations. It appears that Class 2 residual heat removal, chemical and volume control, and containment spray system piping welds may be lacking volumetric examinations. The staff has previously determined that a 7.5% augmented l volumetric sample constitutes an acceptable resolution at i other plants. Verify that volumetric examination of at least i a 7.5% samp)ing of the Class 2 piping welds in these systems will be performed. VEPCO: The "tomparature/ pressure" and " chemistry control" exclusions of IWC-1220(a) and IWC-1220(c) were not used for wolds composing the RHR, ECC, and CHR systems. The orig!nal selection used Code Case N-408 in determining which welds would be examined. The Code case requires for items C5.11 and C5.12 that the wold thickness be greater than or equal to .3751n. fnr examination. Additionally note 2a of table 1 in Code caso N-408 requires that the examinations be distributed by prorating the systems by the number of nonexempt welds in each system. The original selection used the .3751n. limitation in the proration. As such, a uniform distribution of tJ 1d examinations at the 7.5% level for each system was n6t planned. As agreed in the telecon with Mr. G. Johnson (NRC), dated April 25, 1991, a revision will be supplied which will select we]4 examinations on the R11R, CCC, and CHR systems based upon the item requirements of table 1 Code Case N-408 with the following changes;
- 1) Items C5.11 cnii CS.12 require that the weld thickness be
.3751n. or greater, however if the 7.5% (nonexempt welds) requirement for each system has not been met, additional welds less than .3751n. thick will be selected in that system until the 7.5% is met.
- 2) Items C5.21 and C5.22 (high pressure safety injection) will be submitted at a later date for implomontation in the third period.
c) UBg: Augmented examinations are required by the NRC when added assurance of structural reliability is deemed necessary. Plans for inservice-examination of the reactor pressure vessel welds should address the degree of compliance with NRC Regulatory Guide 1.150," Ultrasonic Testing of Reactor Vessel Wolds During preservice and Inservice Examinations." Verity that North Anna Power Station Unit 1, is in compliance with NRC Regulatory Guide
-1.150.
VEPCO: Westinghouse Electric Corporation purforms the examinations on our reactor vessels. West)ngnouse has based their examination program on Appendix A of USNRC Regulatory guide 1.150 Revision 1, " Ultrasonic Testing of Beactor Vessel Welds During preservice and Inservice Examinations." L 2 l ' l
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i Appendix A has boon adopted by the Electric Power Research Instituto Ad Hoc Committoo as an acceptable approach to the positions recommended in the baso document. Westinghouse complies with the requiroments of USNRC Regulatory Guido : 1.150, Revision 1, Appendix A with the exception of paragraph 7.a. This exception is subject to withdrawal as now techniques, proceduros, and equipment for reflector sizing are assessed with the intent of providing a , quantitativo databaso for estimating the tolerancos in sizing the flaw. D) HEC: Roquest for Rollef HDE-1: Rollef is requested from performing the Codo required volumotric examination of the pressurizer surgo nozzlo-to-vossel wold. It is stated that, if a partial examination were performed, only 3 to 8% of the wolds are accessible for volumotric examination. Other similar plants have stated that approximately 30% of the wolds are accessible for volumetric oxamination and have committed to perform volumetric examination of the accessible portion. Verify that a larger percentago is not accessible for the required examination and discuss the impracticality of performing a volumotric oxamination of the accessible portion. ELECQ: We are presently pursuing detailed drawings, which depict the surgo lino nozzlo with respect to the location of the heater penetrations. Those drawings are nooded to accurately determino the extent of oxamination possible for the surgo line nozzle. Tho 3 to 8 percent ostimato of the examination volume previously reported was based upon a field estimato. Since the unit is currently operating, this estimato cannot be verified. Thorofore we will withdraw this rolief request pending the ovaluation of the detailed drawings. E) HEs: Roquest for relief HDE-2: pleaso provido sketches showing the pressurizar and steam generator nozzle insido radius geometry that precludes the Codo-roquired volumetric examination. VEPCQ: We are currently evaluating an alternativo ultrasonic examination technique developed under the provisions of IWA-2240 which may provido a meaningful examination of the following nozzlo inner radli: DRAWING NUMBEB UIR IDENTIFICATIOl{ 11715-WMKS-RC-E-2 10NIR, 11NIR, 12NIR, 13NIR, 14NIR (PRESSURIZER) 11715-WMKS-RC-E-1A.2 09NIR & 10NIR (STEAM GENERATOR A) 3 l 1
11715-WHKS-ItC-E- 111. 2 0 914111 & 1 011111 (STEAM gel (1:llATolt II) 11715-WMKS-HC-E-1C.2 0 911111 & 1 011114 (STEAM GE!4EllATOlt C) Thorofore wo winh to withdraw this relief requent pending the results of our ovaluation. Alno, wo intend to submit poparato requesto to indopondently addroup the pronourizor surgo lino nozzlo, 911111, and the utonm generator channel hond innor radiun noctions. F) tillC With regard to paragraph 2.1.2 of the ISI program and lloquest for Italief liDE-4 (Clanu 1 piping wold coloction n"i nample alzo), verify that all terminni ondo will bo includod in the 25% samplo of the woldn to be examined. VIIT.Qt The original polection procoon did not include terminal ends as a criterin. If terminal endn woro colected it van to the critoria stated in 11DE-4, nu nuch not all terminal ondo are included. A revision will be nupplied, which solects Category ll-J wolds to tho following critorin;
- 1) Selection will be connervatively applied to terminal ondu as they appear on the isometrica na no corronponding strono cniculationa exint (ref. IlUREG-0000, llTp . 3.6.2-13).
- 2) Solection will includo terminni onds at major componento, which provido rigid support to piping (eg. voucolo, pumpu, valvon) . Tho doulgn at 11 orth Anna in most instancon terminaten the piping run at_n dioalmilar metal wold for thoue typo componento. Those wolds will then bo
-examined to the requiremonta of Category ll-F vico ll-J.- _
- 3) Selection will include woldo next to and on either nido of an integral attachment, that are accoualble for examination, when the integral attachment in attached to a rigid typo support. This would excludo unubborn, upring hangers, and comprennion upring typo supporto attachod to integrn1 attachmento.
- 4) Selection will includo 100% of the branch connectiono nu required by itomo 119.31 and 139.32 in Category 13-J .
S).Solection will include terminni onda annociated with valves, normally cloned, prosaurized at RCS normal operating ptoanuco on ono nido and utatically filled or dry on the other side. Tho selected wolds will bo on the 1108 prosaurized side of the valvo.
- 6) The remainder of the wolda nolected will be distributed 4
to the extent practicable based upon lino sizo, line function, and lino deuign. The total selected will not exceed 25% of categorf B-J. This critoria was discussed with Mr. G. Johnson (HRC) on May 2,-1991, and was agrood to in principlo. NDE-4 will be revised accordingly. G) HEC: Roquest for Roliof NDE-7: Pleano provido clarification of the proposed alternativo examination. Should tho alternative road "... associated with each branch connection vold..." instead of "... associated with ono branch connection wold..."? VEPCO: The selection of carbon stool branch connections was to the rules of ASME Section XI 1974 Edition, Summer 1975 Addendum. There are throo banks of safety valvoa on this class 2 system. Multiple streaming allows selection to be limited to the number on one bank. Additionally Category C-G of the 1974 Edition, Summer 1975 Addendum requires only 50% of the components bo examined in nonroactor coolant systems. There are five branch connections on each bank. Throo are required to be examined to the requirements of Category C-G. Thic requirement is spread over 40 years. One branch connoition wold was selected (SW-55), using theso guidelinos for this interval. Both fillet wolds (SW-62 and SW-69) on the reinforcement pad will roccivo a surface examination. Expansion to other branch connection wold reinforcement pads would only occur if relevant indications occur at eithor SW-62 or SW-69. It is our position that the relief is correct as written.
- 11) HRQ Roquest for Roliof NDE-10: please discuss the impracticality of performing the VT-3 visual examination of the Class 3 integral attachment wolds (1-inch NPS and umaller) in the Auxiliary Foodwater system.
VEPCO: This roller request addressed piping, which our company had no corresponding isometrics. The investment required to develop the drawings for the inspection program appeared impractical, when you considor that ASME Class 1 components are exempt from examination at 1 NPS and smaller. A preliminary field walkdown has boon performed on the linos in question, and isometrica will bo developed for inclusion in our inspection program by the second period. This will include additional IWD integral attachments and IWF component supports. This relief request shall be withdrawn. I) . ERC: Request for Relief NDE-11: What specifically are the differences betwoon the existing calibration blocks and-those required by the Codo? Is the roguest for relief only asking for approval to use ASME Codo Case N-4617 5
. 1 VEPCO In addition to Codo Case N461, relief request NDE-11 was submitted to address the following North Anna Unit 1 _
calibration blocks. It has been our experience that a valid UT calibration can be obtained using those blocks. Reference calibration block drawings are attached. VRA-15 This block is used to examino 12 inch schedulo 40S piping welds. Circumferential notch "B" is 0.004 inchos less than the minimum depth specified by ASME Section XI, Appendix III, Supplement 7. YRA-27 This block is used to examine wolds on the boron injection tank and 2 1/2 inch thick pressurizer wolds. The notch on the clad side of the block is 0.0034" over the maximum depth specified by ASME Section V, Figure T-431.1. The 3/4 T holo used for straight beam calibration in 1/4 inch closer to the edge of the block than specified. In addition, the block is not the same material specification as the pressurizor, but
-it is considorod an equivalent material under the rules of Section V, Article 5.
VRA-21 This block is used for the steam generator secondary sido welds and the pressurizar skirt attachment wold. The block is 4 inches wide versos the 6 inch minimum width specified by Section V, Figure T-431.1. The 3/4 T hole used for straight beam calibration is 1/2 inch closer to the block edge than specified. In addition, the block is not the simo material specification as the steam generator or pressuriter skirt but it is the ramo carbon steel P-number as the stoa.1 generator. The block is considered an equivalent material for both components under the rules of Section V, Article 5. VGB-20 This block is used for the Roactor Vessel closure head-to-flange wold and the steam generator channel head-to-tube sheet weld. The block is partially clad, however a 5/4 T calibration required by Section V, Article 4 can be accomplished from the unclad portion of the clad side of the block. Instructions-for this calibration are in the examination procedure. In addition, the block is not the same product form or material specification as the steam generator channel head but it is the same material specification as the reactor vencel head to flange and steam generator tube sheet. A new calibration block is being fabricated for the Unit i replacement steam generators which are scheduled for. installation in the second period of interval two. VGB-21 6 l
\
t This block is usod for the 4 inch thick wolds on the prousurizer. The block is 4 inches wide versos tho 6 inch minimum width upacified by Section V, Figure T-431.1 Tho , 3/4 T holo used for straight beam calibration in 1/2 inch closer to the block odge than specified. The block is partially clad, however a 5/4 T calibration required by Section V, Article 4 can be accomplished from the unclad portion of the clad side of tho block. Instructions for l this calibration are in tho examination proceduto. In addition, the block is not the unmo product form or material , specification as the prosaurizer head but it in the samo matorial specification as the pressurizer sho11 section. VRA-01 This block is used to examino the 27 1/2 inch ID, 29 inch ID, and 31 inch ID reactor coolant loop piping wolds. The block was originally designed for use with a captivated water column longitudinal wave fixture and thoroforo doou not-contain an axial notch. Wo have cubsequently developed , an examination procedure utilizing a duel olomont focused 1 longitudinal wave search unit. Wo intend to replace this , block with two blocks (27 1/2 inch ID and 31 inch ID) which contain axial notches. Wo do not plan to obtain a 29 inch ID block. Instead, wo request to uso the 31 inch ID block to perform calibrations to examine the 29 inch reactor coolant icop piping wolds. Wo bo11ovo that this is an adoquato alternativo to the requiremonto of ASME Soction XI, Appendix III for the following reasons:
- 1. The thickness of the 29 inch loop piping varios by approximately 5% from that of the 31 inch piping (2.590 inches vornos 2.440 inchos) ,
- 2. The search unit designed for the 31 inch ID piping will focus within 1/2 inch from the ID when used on the 29 inch piping. This is within the focal longth roquirements specified by the examination proceduro. ;
- 3. The difference in the outsido diamator of the piping (36.1 inches versos 33.0 inches) is approximately 6%
J) UEg: Roquest for Rollef SPT-11 No alternative test is proposed. With regard to an alternativo test in lieu of the Codo . requiremet.t , what is the maximum hydrostatic test pressure that the subject Class 1 and 2 piping could be pressurized to without damaging the number one seal of the reactor coolant pumps? YEECQ: page 2-73, paragraph IV, provided that the system leakage test por IWB-5221 with the corresponding VT-2 oxamination be performed as an alternativo. It was omitted that the corresponding class 2 system nrosauro test at 7
nominal operating pronsure would also ba completod. Additionally, the rollof requent did not fully doucribo the design of the reactor coolant pump seal, and seal injection ; piping. The poal injection flow in provided from the charging pumps to the reactor coolant pump. This flow dividos in the pump with part of the flow being introduced to the RCS, and part of the flow panning over the pump scalu . and through tno various seal returna. Since the coal injection directly adds to the RCS inventory, and no intermediato isolation oxiota, any pronsurization abovo
- normal charging prosauro would require that the RCS bo ;
pressurized to that same amount. This would excoed the ASME ' class 1 hydrostatic tout prousure limits on-tho balanco of the reactor coolant syntom. The rollof request will be modified to include this information. K) HRQ Roquesta for Rollof SpT-2, SPT-5, and SPT-68 Daned on review of the drawings referenced in the relief requents, it appears that some valvo numborn listed in those relief " requests are incorrect. Pleano verify the correctnons of the valvo numbers or make the necessary revisions. VEECQ It appears that somo Unit 2 numbers woro inadvortently mixed within the Unit 1 program. These rollef requesta will be revised. L) URQt Roquent for Relief SPT-31 Justification for relief from the hydrontatic tent of Claan 1 RHR piping has not boon previded. It appears from the drawing referenced in the rollof requent that the Codo-required. hydrostatic test can be performed. Plonso discuss the possibility of opening valvo number 1-RH-MOV-1700 to perform the hydrostatic tout of this piping along with the adjacent Claus 1 piping. VEPCol Valvo 1-RH-MoV-1700 is pronouro interlocked for automatic closure to provent accidental ovorprennurization of tho attached RHR system. This safety feature would have to be bypassed to allow 1-RH-Mov-1700 to remain open during RCS proosurization. This would dofoat the designed safeguard, and therefore doomed impractical. M) HRC: Roquest for Reliot SpT-10: Discuso why the prosauro maapuring instruments cannot be placed such that the test boundary high point recoivon the hydrostatic test at a pressure as close to the Code-roquired test proasure ao possible without exceeding the 106% oystem test prosauro maximum at the test boundary low point. YEECQ This relief request will be withdrawn. It was assumed that tout boundary tout pressure correction for height could exceed the 106%. This was conservatively applied in our test procedures previously, however it appearn the Codo does not 8
. _ , , _ _ _ _ _ _ _ . _ _ _ _ ~ ~ . _ ._- _ . . _ . _ . _ . . . - ~ . _ _ _ _ -
mandate this requiremont, and your suggontion to make the tent presnure at the highout point be as closo as possible to test prosauro without exceeding 106% at the low point, will be followed, 11 ) l!RQt Roquent for relief SPT-lit Paragraph IWA-5241(b) of Section XI of the Codo states that, for compononto whone external surfacon are inaccenniblo for direct visual examination (VT-2), only the examination of the surrounding area for evidence of leakage, including floor arono or equipment surfacon located underneath the componento, shall be required. Could this statomont bo included in the proposed alternativo? If not, discusu the possibility of performing a remote visual examination in lieu of the direct visual examination. yfECQ SPT-11 doccribes the ditficulty in reaching the underside of the reactor vousel, when the containment is subatmospheric. A remoto visual means of monitoring thin aron is not currently established, and would be quantionable in unefulness. The aron would be subject to high temperatures and associated humidity, which combined with indirect lighting would probably yield inconclunivo renulto. This relief request was dincussed with Mr. G. Johnaon (11RC) on May 2, 1991, and it was pointed out that the commitment was made to perform a VT-2 examination of the aron at atmosphoric conditiona each refueling for evidence of boric acid corrosion. It is our opinion that enough justification exists in the relief requent an written. 9 i
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