ML18139B557
| ML18139B557 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1981 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML18139B554 | List: |
| References | |
| NUDOCS 8110060251 | |
| Download: ML18139B557 (8) | |
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INSERVICE INSPECTION REPORT OF THE SURRY UNIT NO. l NUCLEAR POWER STATION P. 0. BOX 315 SURRY, VIRGINIA 23883 FOR VIRGINIA ELECTRIC AND POWER COMPANY P. 0. BOX 26666 RICHMOND, VIRGINIA - 23201 COMMERCIAL SERVICE DATE: DECEMBER 22, 1972
' OPERATING CAPACITY:
REPORT DATE:
REFUELING OUTAGE:
822 MWe AUGUST 1981 V-VI PERFORMED BY:
WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR SERVICE DIVISION INSPECTION SERVICE P. 0. BOX 2728 PITTSBURGH, PENNSYLVANIA 15230
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FORM NIS-1 (back)
- 8. Examination Dates 9/20/80 to!.. /5/81 9. Inspection Interval from 12/22/72 to 12/22/82
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning sta*Us of work required for current interval. Reference Tab B and Tab C _
u~:..bstract of Conditions Noted Reference Tab B and Tab F 12.-1\.bstract of Corrective Measures Recommended and Taken Reference Tab 8 and Tab F We certify that the statements made in this report arc correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code.Section XI. ~
Date~ \Y 19~Signcd \.lE'fC,L)
--=......;;..;. ....0..-==w~ne_r____ By ~~ t)E Ccnificate of Authorization No. (if applicable) _ _ .;..~...L-jh'-""fr~---- Expiration Date _N__,,,..X-~~-------
CERTIFICATE OF INSERVICE INSPECTION i, the undersigned, holding a valid commission issued by the National Board of Boiler ancl Pr~surc Vessel
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Inspectors and/or t h e State or rovmce o f V*
, {at *1'1,, c.c...) d - I an c:mp oye db YBt,-J..*? Har-f-Jo,-.:P S"~~
() :z-* ,s: 4,;; p */VC <<!'., of HortJ,zJ <9,t!,{A) have inspected the com~nents described in this Owners' Data Report during the ;criod
,/ '2<2 / Ge? to 7 /;:jg-; , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this O,rners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
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FORM NJS-1 OWNEl{S' DATA REPOHT l*OH. JNSEl{\'ICE INSPECTIONS As required hy the Provi,;ions of the ASME Cude Rules Virqjnia Electric And Power CorilJ?.~.n:t..L.O, Box 26666.Richmond.VA~.261
- 1. Ownc, (Name and Acldrc:s~ of Owner)
- 2. l'lant _~urry #1, P.O.Box 315,_Su~Virg..:...i_n1.:....:*a"--=2~3-=-88:::.;3~-----=-:..::...*- - - - - - -
(N:une and Address of Plant)
- ' 3. Plant Unit _ _1____.__;_4. Owner Certificate of Authorization (ifrequircd) _ _ N.:.../_A_ _ _ __
- 5. Commercial Service Date ] 2/22/72 6. National Bl*ard Number for Unit _ ____.NCl.j/uA'4--------
- 7. Components Inspected Manufacturer Component or Manufacturt>r or Installer State or National Appurtenance or Install er Serial No. Province No. Board No.
Reactor Vessel Rotterdam RCPCRV 137-1 R. V. RCRIU1 Internals Allis-Chalmers RCRILI Pressurizer Westinghouse RCPCPR 1031 St. Gen. l Westinghouse 2981 681 St. Gen. 2 Westinghouse 2982 682 St. Gen. 3 Westinghouse 2983 683 Reactor Cool an Piping Southwest Fab. Cq.
Class l Piping Southwest Fab. CQ.
Class 2 Piping Southwest Fab. Co.
R.C. Pump l Westinahouse 458 R.C. Pumo 2 Westinahouse 459 R.C. Pumo 3 Westinahouse 460 Valve 1-595 Darling 1--------t-----=----------1--------1--------+---------
Va l ve 1-700 Copes Vulcan v_a_lv_e_l_-8_7_5_o____o_a_r_1,_*n_ia_________-_-_-_____
RRR HX lA Atlas Industrial 890 J~--:;-:;.._~----_-___. 740 Note: Supp!cmcntal shc:c:ts in form of lists, sketches, ,,r drawin1:s may l,c: used provided ( J) size is 8'1.i i!l. x 11 in.,
(2) inform3tion in itl*m:- I rhrout,h 6 on rhis Jara rcp11rr is induJcd 1Jn eal*h sheer, and (3) eal*h shc~c is numhcrcd and the numher of sl11.-e1s i'i u*nirJt*d at the hlft of this form .
This form 11:00029) niay he c,l.,1c1i11cd Iron, tho Orclur D~pt** ASME, 345 E. '17th St** Now York, N.Y. 10017
FORM NIS*l OWNERS' DATA REPORT FOR IN.SERVICE INSPECTIONS As required by the Provi-:ions of the ASME Code Rules
- 1. owner *v;rginia Electric And Power Company P.O. Box 26666.Richmond,YA, 23261 (Name and Address of Owner)
- 2. Plant Surry #1, P.O.Box 315 1 SuJI1._,Virg...:...i_n.:....:ia:::.__:;2;.:c3..:;;.8.:::..83~----..:._ _ _ _ _ __
(Na.me and Address or Plant) -
J. Plant Unit _ _1______ 4. Owner Certificate or Authorization (if requi~d) _ _ N/:....A
- 5. Commercial Service Due 12/22/72 6. National Board Number for Unit _ ____,,N.l.4/"-'A;i._______
- 7. Components Inspected
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- Manufacturer Component or Manufacturer or Installer Stare or National Appurtenance or Installer . Serial No. Province No. Bo:i.rd No.
RHR HX lB Atlas Industrial 891 --- 741 Seal Water Heat Excn.
Regenerative Joseoh Oats &Sons 1817-2A --- 346 4195-A3-7 369 HX Sentrv 4195-A3-8 --- 370 4195-A3-9 371 Volume -
Control Tank Richmond Eng. L-8554 --- 57783 l.nargrng Pump lA Byron Jackson Pumps --- -- - ---
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Note: Supplemental sheets in form of lisrs, sketches, r,r drawings may be: l.lscd provided ( 1) size is 8'n in. x *It in.,
(2) inform:nion in irems I rhrou 6 h 6 on this J:ua rcp,>rt i!i included ,>n ca"*h sheet, anJ ( 3) eaL*h sheer is numoc:rc:d and the: number of sheets is rccor,kd a1 the: 1op of 1hii- form.
This form (E00029) may t>e 01Jtc1inod from tht, Order Dept., ASME, 345 E. 47t.h St., New York, N.Y. 10017
VIRGINIA ELECTRIC AND POWER COMPANY SURRY NUCLEAR POWER PLANT UNIT NO. l OUTAGE CORE V-VI
' }INTRODUCTION INSERVICE AND PRESERVICE INSPECTION EXAMINATION
SUMMARY
1980 - 1981 The following was perfonned by Westinghouse Nuclear Service Division and Virginia Electric and Power Company at the Surry Unit No. l Nuclear Power Plant from September 20, 1980 thru July 5, 1981.
- 1. Inservice examination was perfonned to Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition up to and including Sulllller 1975 Addenda and to the Plant Technical Specification on the following items.
A. Reactor Vessel Circumferential and Longitudinal Welds B. Reactor Vessel Upper and Lower Internals C. Reactor Vessel Core Barrel D. Pressurizer E. Class l and Clais 2 Piping and Supports F. Reactor Coolant Pumps G. Class l and Class 2 Components H. Class land Class 2 Valves
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Class 2 Pumps _
Sensitized Stainless Steel Piping High Energy Welds Change 13 Parts A and B Hydrostatic Test of Class l Systems
- 2. Preservice examination was performed to Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition up to and including Sulllller 1975 Addenda and to the Plant Technical Specification on the following items.
A. Steam Generators l, 2 and 3 Nozzle to Safe-End Welds B. Class l Reactor Coolant Piping.
These examinations were performed in accordance with an approved Program Plan located under Tab C of the final report.
Examination procedures were approved prior to the examinations and certification documents relative to personnel, equipment and materials were reviewed and detennined to be satisfactory.
Inspections, witnessing and surveillance of the examinations and related activities were conducted by personnel from: Hartford Steam Boiler Inspection and Insurance Company; Virginia Electric and Power company Non-Destructive Testing Personnel and Virginia Electric and Power Company Quality Assurance Departments.
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RESULTS Examinations resulted in a total of twenty-three_{23) .recordable indication items being noted on the basis of procedure recording criteri~, while are
~ generally more critical than specified ASME Acceptance standards. Four {4)
( i-tems were found to be acceptable which *the remaining nineteen {19) were 1 dispositioned by plant maintenance personnel.
- A summary of the indication items are as follows:
A. The reactor vessel lower and intermediate longitudinal welds 6, 7, 8 and 9 on VPA-1-1100 contained a total of twenty-two (22) separate recordable indications detected by the ultrasonic methods.
B. One {1) indication was noted during penetrant examination as a recordable linear indication in the area of the base metal examination area of a sensitized piping patch.
C. Eighteen {18) recordable indications were noted during visual examinations and consisted of the following.
- 1. Eleven {11) recordable indications were on Bolting consisting of rust and/or boric acid.
- 2. Two {2) recordable indications were gouges on the base metal adjacent support hangers.
- 3. One {1) recordable indication consisted of a bent hanger rod.
- 4. One (1) recordable indication consisted of a bent hanger rod with a loose bolt.
- 5. One (1) recordable indication consisted of rust and loose bolt on a valve bonnet bolting.
- 6. One (1) recordable indication consisted of weld spatter located on the adjacent scanning area of base metal of a weld.
- 7. One {1) indication consisted of an arc strike in the area of base metal examination of a sensitized piping patch.
- D. Specific data relative to the above indications is located under Tab F of Volume -2 of this report.
-=EXAMINATIONS Examinations were conducted to review as much of the examination zone as was practical, within geometric, metallurgical and physical limitations. When the required examination volume or area could not be examined 100%, the examination was considered to be partial (PAR) and so noted. Generally, PAR's are noted J\
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at fitting-to-fitting assemblies {as explained under LIMITATIONS) and in areas where integrally welded supports, lugs, hangers, etc., preclude access to some part of the examination area .
. Ultrasonic examinations that produced greater than reference revel sensi ti vi ty l from reflectors that are characteristic o.f metallurgical structure of the
- I.D./0.D. surfaces of an item were acknowledged for information only and were
/ noted as such on that data sheet. Examples of areas that generally produce
- -such geometric indications include:
(1) I.D. weld prep or root and/or the crown overlay or toe.
(2) The I.D. radius of the tube sheet on the channel head to tube sheet weld of steam generators, when examining from the tubesheet side.
(3) The metallurgical structure of cast materials.
(4) Responses from the thread areas of bolting.
Geometric responses from these areas are characteristic of the examination and are not considered relevant for reporting length or depth.
LIMITATIONS Some of the arrangements and details of the p1p1ng system and components were designed and fabricated before the access and examination requirements of Section XI of the 1971 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration or accessibility.
Generally, these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and some-times surface condition preclude ultrasonic coupling or access for the required scan length.
The limitations exist to a lesser degree at pipe fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface. At these joints examinations can be conducted from the pipe side, however, the fitting again limits or precludes examination from the opposite side. When the weld surface is flat, the fitting side examination is replaced by a calibrated straight beam examination on the weld.
- _In most cases, examinations in these areas were accomplished as a best effort 7attempt to cover as much of the code required area or volume {generally, the
':weld and base metal for l 11 T11 on each side) as is possible, howev.er, the extent
- ,of examination coverage in the base metal of the fitting or component cannot be specifically qualified.
Areas where complete examination of 100% of the required volume or area could not be achieved are indicated by a PAR (partial) notation on the examiner's data sheet, and the limiting cause is noted.
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The principal basis for PAR's is to identify the inability to examine 100%
of the required base metal volume for the l 11 T11 distance beyond the edge of the .weld on a fitting or component, such as: ultrasonic examination of
. a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam; or a pipe to flange or valve assembly, where
.scanning the entire vo l.ume on the fitting or component side i s-;1 imi ted by fconfi guration.
- The resulting coverage is such that examination of the weld, heat affected
- zone and base metal for l 11 T11 on the pipe side can be achieved by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side *scan depending on the calibrated sweep length, ~ttenuation, joint configuration, etc.; however, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by Code. In
- either case, 100% of this l 11!.11 volume cannot be assured, thus a PAR is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
Specific limitations and restricti9ns for all examinations are as indicated on the raw data sheets - Section D of the Final Report .
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