ML20214U771

From kanterella
Jump to navigation Jump to search
Inservice Insp Rept for Beaver Valley Power Station Unit 1, Outage 5 (First Interval,Third Period), on ASME Class 1 & 2 Components & Piping Examined Between Mar 1985 & Aug 1986
ML20214U771
Person / Time
Site: Beaver Valley
Issue date: 11/18/1986
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20214U728 List:
References
NUDOCS 8612090389
Download: ML20214U771 (35)
v • d • e


Text

{{#Wiki_filter:__ _ .s ~ INSERVICE INSPECTION REPORT POR BEAVER VALLY POVER STATION UNIT 1, OLITAGE 5 (First Interval, Third Period) November 18, 1986, OWNER: Duquesne Light company One Oxfo'rd Centre 301 Grant Street Pittsburgh, PA 15279 UNIT: Beaver Valley Power Station, Unit No. 1 Box 4 Shippingport, PA 15077 NRC DOCKET NUMBER: 50-334 REACTOR SUPPLIER: Vestinghouse Electric. Corporation GROSS GENERATING CAPABILITY: 852 NVe CONNERCIAL SERVICE DATE: September 1976 i 1 i 4 l 4 h 8612090389 861124 PDR ADOCK 05000334 G PDR

T e INSERVICE INSPECTION REPORT BEAVER VALLEY UNIT 1, OUTAGE 5 I TABLE OF CONTENTS h Number of Pages Cover Page 1 Table of contents 1 Form NIS-I 3 Summary 12 Appendix I - Class 1 Examination List 13 Appendix II - Class 2 Examination List 4 Appendix III - Disposition of Indications 1 0 i i: e l i su 73 ,t

Pegs 1 of 3 FORM NIS 1 OWNER'S REPORT FOR INSERVIG INSFECI1ONS As seguired by the Provisisse of the ASME Ceds Rules

1. Owne'r' Ducuesne Licht comoany, 301 Grant Street. Pittsburch. PA 15279 (Name and Address of Owner)
2. Pleac Beaver Valley Power Station, P.O. Box 4, Shippincoort, PA 15077-0004 (Name and Addreas of Plant)
3. Plast Unic 1-852 MWe
4. Owner <ertificate of Authorisation (if required) 26-05000*-
5. Coensmarcial Service Date 09/30/76 6. National Board Nurnber for Unic N/A
7. ComponentsInspected Manufacturer Component or Manufacturer or Installer State or National Appursemance or installer Serial No.

Province No. Board No. Reactor v... 1 rnut Combustion Engi: sering 69103 B-105642 21011** RV Closure Head Combustion Engineering 69203 N/A 21011** RV Internals Westinghouse DLW-Z305 N/A N/A Pressuriser Westinghouse 1311 PA434 676 68-50 N Steaar Generators Westinghouse Loop 1 1301 434 597 68-45 Loop 2 1302 434 598 68-46 Loon 3 1303 434 599 68-47 Reactor PA Spec No. c'aainne 94na nai+hv.me wahrtem*4na N/A 5390 N/A Auxiliary Pipe Class 1 Schneider Power Coro. N/A N/A N/A Reactor l coolant Pit =n Maatinahnuam Tyn 1 1 -K1 A.TQ'll f!A1 N/A N/A Loop 2 2-618J931G03 N/A N/A

Valves, Class 1 N/A N/A N/A

,l l

  • Dqsignates account number of arrangement with Authorized Inspection Agency to
i trovide iryspection services.
  • Conusonwea.ith of PA, Certificate of Boiler or Pressure Vessel' Operation,

.; l No. B105642. 't b

  • $~.

,c..- ~ _ _,

E* Page 2 of 3 FORMMB4 OWNER'5REFORTFORDWRYM3BEFECMMB ~ As segebed by she hovidose of the ASME Code Rules

1. Owne'r DEquesne Light C _-==v, 301 Grant straat. Dit*=h eah-na 15940 (Nases and Address of Owner) neaver valler Power station, P.O. Box 4, Shinnemanast. DA 1tnTT nana
2. Finer (Names and Addsess of FlesO
3. Fleet Unit-1-856 NNe-
4. Owner Cardficase of Am Of,sequbed) 26-05000*
5. Comunercial Service Date 9/10/76 4.Nadomal Board Nussbar for Unic N/A
7. e-
- _ts laspected Mamefacasrer c-
or Mammfacturer or lassauer Stateer National

. etlastaner Serial No. Province No. Board No. Reactor eaat.ne y11 *., AMF, Cuno 115 N/A SK11 Regenerative Beat Exchanger Joseph Ost & Sons 1831-10 Shell 1 434sas din shall 2 414sa7 41e N Shell 3 434688' 440 Residual u..e.m.,h.n .. Joseph Oat & Sons 1832-1 434s82 168 Safety Inject. Acctusulat. lA Delta Southern Co. N/A* 434sso 2710 Seal unter Inject. Filters Cousnercial Fil':er 538-10 M/A lies 539-10 N/A 1399 seal water naturn Filter AMF, Cudo 102 434723 2615 Piping c1... 2 geh==ider u r earn. w/a w /m u /m i i + ,t 1 ;

  • Designates account number of arrangement with Authorized. Inspection Agency to provide inspecticn services.

i J

    • Commaonwealth of PA, ceificate of. Boiler or Pressure Vessel Operation,

,. i No. ~81.05642. [4 I = s

...a.,.:......- . ~.. P gs 3 of 3 roam NIS 1(Bad)

8. kxamination Dates 3/22/85 to 8/23/86
9. Inspection Interval from e /1n / in to 9/20/87
10. Abstract of R=-instions. Include a list of examinations and a ara *===*at concerning status of work required for cumat imeerval.

See Appendices I-II. 11 Abstreet of Conditions Neeed 3 See text.

12. Abstract of Cometive Measures Recomunended and Taken Snee Appendix III.

We certify that the statements made in this report are correct and the examinations and cornctive mes-sures taken conform to the rules of the ASME Code, Section XI. 26-05000 Expiration Date N/A. Certificate of Authorisation No. (if applicable) //h 19 LSigned Duquesne Licht Co. By cz t.; Date / Owner CERTIFICATE OF INSERVICE ' INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boinst and Pressure Vessel Inspectors -k and the State or Province of and employed by of e - ted %e components described in this Owner's Report during the period /M to . and st' ate tha,t tothe best of,my knowledge and belief, the Owner has i f z f swaminations and taken corrective measums described la this Owner's Report la 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 e===8==Hans and corrective measures described in this Owner's Report. Furthermore, neither the l Inspector nor his employer shall be liable in'any manner l'or any personallajury or property damass or a loes of any kind or cosaected with this inspection. l Factory Mutual System / _JM Cosamassan.: __ MB R116 PA 2248 l i / spector's ture National Board, State, Province, and Endorsements ^ 621 l 19 $c Doet - ,y mmt

  • Arkwright-Boston Manufacturers Mutual Insurance Company, Waltham, Mass.

+ I i i ..-.w, ._.,__,(_

INSERVICE INSPECTION REPORT BEAVER VALLEY UNIT li OUTAGE 5 P l

SUMMARY

During the Fifth Refueling (5R) Outage, an Inservice Inspection (ISI) examination of Class 1, 2, and 3 components was conducted at Beaver Valley Power Station (BVPS), Unit 91. This ISI examination.is the second inspection of the third period in the first ten year interval and included most of the end of interval examinations. The plan for this outage called for ' examinations of both the Reactor Vessel (RV) and the Balance-of-Plant (BOP) portion of the Ten Year Plan for i the first inspection interval. This plan reflects the ASME Code Section II requirements as defined in the 1974 Edition through the Summer 1975 Addenda amended by Plant Technical Specification Amendments 22, 27 and 48, required by Plant Technical Specification Section 4.0.5. The Babcock and Vilcox (MV) Company of Lynchburg, Virginia, was the primary vendor for the outage. All nondestructive examinations (NDE) performed by MV vere conducted in accordance with the procedures contained in the 1986 (MV) Technical Manual for Beaver Valley Unit 1. The examination procedures were approved by MV personnel qualified to SNf-TC-1A Level III. These procedures conform to the requirements of the applicable edition and addenda of the ASNI Boiler and Pressure Vessel Code, NRC regulatory guides, and Duquesne Light Company (DLCo) Technical Specifications. The examinations were performed by MV technicians qualified to SNT-TC-1A as required. Westinghouse Electric Corporation (V) conducted the post expansion eddy current examination of the expanded tubes in ."A" Steam Generator (see i page 7). The bobbin coil examination was performed to standard eddy current procedures as included in the Vestinghouse NSID report." Support Plate Tube Expansion Eddy Current Inspection Mechanical Plugging" of July 19-25, 1986. IEE examinations performed 'by DLCo. personnel and DLCo. sukontracted personnel.(other than MV and V) were conducted in accordance with the ~ procedures contained in the DLCo. Nuclear Group Inservice Inspection Manual. The procedures were approved by DLCo. personnel qualified to Level III in accordance with SNF-TC-1A and ANSI N45.'2.6. Personnel performing the examinations were qualified in accordance with requirements of SNf-TC-1A and/or ANSI N45.2.6 as required. All procedures used during the outage were revieved and approved for use !j by DLCo. prior to the commencement of examinations. 'I f i, .4 d 1 0 , s t.u

. _; n n

.r a I

IN8ERVICE INSPECTION. REPORT BEAVER VALLEY UNIT 1, OUTAGE 5, REACTOR VESSEL VELD EXAMINATION The reactor vessel velds were examined ultrasonically using the (B&V) Automated Reactor Inspection System (ARIS) tool. The velds including and above the lower head-to-shell veld were examined using the contact trr method. The velds below the lower head-to-shell veld were examined using the immersion technique.- h contact and immersion examinations were conducted utilising the multichanaal KB6000 UT instrument. The MV Automatic Data Acquisition and Analysis System (AD&S) was used during the contact examination to magnetically record the scan information. N examinations were conducted with the standard Code required angles of O' longitudinal wave, 45' and 60' shear wave sound. beams. In addition, these angles were supplemented with 70' longitudinal wave angle beams specifically designed to examine the near surface region of the vessel ID. A 30* longitudinal wave angle beam was also used to examine the nossle-to-shell velds from the nossle bore. The volume examined meets or, in most cases, exceeds the minimum requirements of the 1974 edition of ASME Section XI Boiler and Pressure Vessel Code with Addenda through the Summer of 1975. The lower head dollar plate veld (Veld #16) vs.s inaccessible due to incore instrumentation. The examination of the nossle-to-safe-end pipe velds was conducted from the interior of the nossle side of the veld only. This was done because of the inherent limitations ~ imposed by the material properties on the centrifugally cast stainless side of the veld. h code required examinations of these velds had been completed in the first and' second periods from the exterior surface. W examination this outage was supplemental to the code requirements. b examinations are summarized i'n Appendix I and are illustrated in Figures 1 and 2. A complete description of the results is contained in the B&W Report "1986 Examination Results of Reactor Vessel Velds for Duquesne Light Company Beaver Valley Unit 1" dated 9/30/86. h greater sensitivity of the contact UT method enabled the reactor vessel velds to be mapped and their position to be independently verified. i h results of this work are contained in the report "1986 Reactor Vessel Veld i Location Mapping for Duquesne Light Company Beaver Valley Unit la dated 9/30/86. h veld mapping confirmed the locations depicted on the vessel drawings. ~ I's r! 1 2 a

.- ~ _ -.-r i ~ INSERVICE INSPECTION REPORT e REAVER VALLET UNIT 1, OtfrAGE 5 The visual examination of reactor vessel clad patches (B1.14) and of the core support structure (B1.17) was limited by the failure of the primary camera on the ARIS equipment. The secondary camera on the ARIS equipment could not be positioned to verify resolution but was utilised during the entire ARIS examination and no, cladding deficiencies were noted. A visual examination (limited) of the lower vessel head cladding was conducted using the secondary camera (see VER 13292). The contact trf method provided a much more senaltive examination of the vessel cladding than that,which could have been achieved by the immersion technique (see B&V report "1986 Reactor vessel Examination Contact vs Immersion Comparison for. Duquesne Light Company Beaver Valley Unit 1" of 9/30/86). DLC considers tha.t this greater sensitivity coupled with.the limited visual examination is sufficient to satisfy the intent of the ASNE required visual examinations. During the inspection of the reactor vessel closure head welds, some confusion arose concerning the number and location of the head welds. The initial inspection. team mistakenly concluded that there were 6 (rather than 4) peel segment velds. Supplemental examinations and a record review indicated that the confusion was the result of the remnants of various handling and fit-up lugs used during fabrication of the head. DLCo. letter ND1ISI 0302 of 8/5/86, explains this and confirms the existence of only four (4) welds. This was followed by the NRC as Unresolved Item 86-09-01. As of this date, DLCo. action on this is complete and it is waiting formal NRC closure. ) 4 9 I a 3 i

Figuro 1 e Q

r p

e - w, jw to p _ _ _. (..,,_,y liL h 4 y i: f s

s,

.sp i Th .u 1 3 r n i 2' 8 a 3 llp

(.:::

3 U y?; f l l q q h V

  1. [

lsI_ nag s 4;g:;.lp* [; = 3 l >.E j-8 O, 0 + ,l *4 { 2 l ll + c I p p 3 i K q sj m, a k Q ,,/ l

".
::. :::,l 5

is ' i uA

f. W_i a,e4

~ a .u m t 4>. -: j' yl G t; g', d 2 e <t l D ) M d p g li. ._._A_____._.--.,; j' lm, ={ t y 5 4. ' q< e 9 /+ + 8,i 4, Q W d l; l> l 2e -x -.g _ 1. &V4Q ! WHZae.mxsswwow"w w 1 o i 1 ,(m f5 ? sn e s w 4 2.

Figure 2 IVELD EXAMINA776N TECHNIQUE DESIGNAT/eN ( LOWER HEA D_ M*[g q' 35 27* \\ 1 27 f / 03' B1.2.2 l 81.2.4 Bl.2.5 61.1.9 293* B1.2.10 87*i see ( NOTE I m m UI'1:5 y zy 1 -, g. N-1 Bl.2.8 267* Bl.2.5 Bl.1/. 81.2.7 I B/. 2. 2 233' 147* / \\- e 207* ,y 220' fg. l NeTE / : EAest a rac.51x McniatownL wcLas lectE EyAmMrb m IS% W ME WELDS M =IMMERStoN N 7b7AL LENGm. /Vt/WW 'r coNTAcr ~ f 5 1

INSERVICE INSFECTION REPORT BEAVER VALLEY UNIT 1, OUTAGE 5 p, STEAM GENERATOR EDDY CURRElfr EXAMINATIONS one hundred percent of the Inconel 600 tubes in all three recirculating steam generators (RSG) (A, B and C) was examined by eddy current (ET) techniques during May and June. This required the completion of the examinations from both legs of the RSG's for the innermost rows (Rows 1 through 4). The examinations were performed using frequencies of 400, 200, 100 and 35 i k5s. Both the differential and absolute modes were used for each frequency. The 400 and 200 kan frequencies in the differential mode were mixed to enhance detection of indications at the tube support plates. The absolute modes were used for tapered flaws, such as voar and possible Intergranular Attack (IGA). The 35 kEs was used for secondary side analysis (loose parts, sludge, debris, etc.). The eddy current analysis was performed using Zetec's DDA-4, Data Analysis System (Edition 18-1). Acquisition of the data was performed using i Zetec's NIZ-18 system. RESULTS: The results of the examination are summarized below. RSG-At Of the 3388 tubes, twenty-four (24) tubes had been previously removed from service. Eleven (11) of the 3364 tubes examined were found to contain indications of 40% through wall (TV), or greater, and were plugged (removed from service) (See Table 1). Thirty-six (36) additional tubes were found to contain indications of 20% TV or gretter, but less than 40% TV. An additional tube (Row 24, Column 62) was found to be plugged in the hotleg end but not in the coldleg end. Tube R25-C62 was found to be plugged in the coldleg end but not the hotleg end (see Licensee Event Report *86-006). RSG-B Of the 3388. tubes, two (2) tubes had been previously removed from service. Fourteen (14) of the 3386 tubes examined, were found to contain indications of 40% TV, or greater (See Table 1). Fifty-two (52) additional tubes were identified which contained indications of 20% TV or greater, but less than 40% TV. 1 i RSG-C: Of the 3388 tubes, seven (7) tubes had been previously removed from service. Six (6) of the 3381 tubes examined, were found to contain indications of 40% TV or greater (See Table 1). Twenty-six (26) additional tubes Vere identified which contained indications of 20% TV or greater, but less than 40% TV. 1 0 l' l 6 3 l L

INSERVICE INSPECTION REPORT BEAVER VALLEY UNIT 1, OUTAGE 5 DISCUSSION: All three RSGs exhibited tube degradation at the lower tube s.upport plates (TSP) on the coldleg side. These defects were located in only the outer 5 peripheral tubes. The majority of these indications occurred at the 1st and 2nd TSP locations up from the coldleg side tube sheet. The amplitude of the indication signals are comparable to the flat bottom holes in the ASNI calibration standard. Similar eddy current, signals have been documented by the Electric Power Research Institute (EPRI). Based on pulled tubes from other Vestinghouse 51 series generators, the indications have been attributed to vall " thinning" in this area of the generator. This phenomenon is believed to-originate from mechanically assisted chemical degradation. There were also cases of Anti-Vibration Bar.(AVB) voar indications in each of the generators. Since standard differential data incorporating the ASME calibration standard may be inaccurate, an AVB voar standard was used to better size the indications. The final, analysis of all AVB voar defects was based on an amplitude curve obtained using the AVB voar standard. The tube lane blocking device rubbing against the tube was responsible for a small number of indications. Several of the tubes containing indications c' 20% TV or greater were j subjected to a re-evaluation of their previous eddy current inspection data. A side by side comparison was made between the present data and the past data to determine if flav growth had occurred. Rasults of the evaluation indicate i that auch of the thinning type degradation observed at the lower coldlag TSP's did sh'ov significant growth from the previous inspection. Indications of AVB t voar did show some evidence of growth but not to the same extent as the thinning indications. Indications adjacent to the tube lane blocking device did not show significant growth. A complete description of the above results is contained in the B&V Report " Eddy Current Examination Re for Beaver Valley Unit 1 June 1986 Refueling Outage 95" dated 8/26/86.' port STIAN GENERATOR "A": l Because of the coldleg thinning identified (above), an examination of 142 tubes was conducted using the Babcock and Vilcox rotating pancake probe. Based upon this data, Duquesne Light utilised Vestinghouse to expand fifty tubes at the first and second support plates (coldleg) (See Table 2) in an effort to reduce tube motion and the consequent thinning (see VCAP-ll233). The results of this modification vill be monitored during subsequent refueling j outages. h L H il l 7 o'q ~,-.- -. - __ _. - -.-

INSERVICE INSPECTION REPORT ^ BEAVER VALLEY UNIT 1, OUTAGE 5 TABLE 1 STEAM GENERATOR TUBES VITH INDICATIONS 40% THROUGH-VALL AND GREATER STEAM GENERATOR A M COL IND %TV LOCATION 15 5 ODI 47 1C 21 8 ODI 45 1C 24 37 VEAR 40 AV1 29 11 ODI 47 1C 29 13 ODI 43 1C 30 83 ODI 45 3C 33 78 ODI 42 3C 34 77 ODI 52 1C 42 30 ODI 52 2C 44 35 ODI 42 2C 45 56 ODI 50 1C STEAM GENERATOR B ROV COL IND %TV LOCATION 15 90 ODI 47 2C 25 9 ODI 49 1C 25 11 ODI 45 1C 26 11 ODI 41 1C 26 86 ODI 41 1C 31 79 ODI 43 1C 32 17 ODI 51 1C 32 79 ODI-45 2C 33 77 ODI 51 2C 36 77 ODI 43 1C 40 45 VEAR 41 AV3 40 50 VEAR 45 AV2 40 51 VEAR 53 AV3 45 48 ODI 41 1C STEAM GENERATOR C ROV g IND %TV LOCATION 24 87 ODI 43 1C 32 78 ODI 40 1C 37 22 ODI 42 4C 41 28

ODI, 42 4C 44 40 ODI 41 3C J

45 49 ODI 42 2C .( I M 8 7 r . __er, p % a--wt-, -co.---* - - + - - - - - - - - - - - - - --+-:-~--- - - -

i INSERVICE INSFECTION REPORT BEAVER VALLEY UNIT 1, OtFTAGE 5 TABLE 2 "A" STEAM GENERATOR EXPANDED TUBES ROV CINM ROV CLMN 33 79 36 22 45 39 27 85 42 31 24 8 3C 13 30 16 31* 81 36 75 32 16 42 38 34 17 42 32 35 19 43 30 36 20 45 45 39 26 9 2 41 30 14 5 42 34 45 36 43 31 11 4 40 28 12 4 44 60 23 8 30 12 14 92 34 16 17 90 38 21 21 88 41* 66 28 85 41* 67 22 8 39* 71 25 11 40 71 '31 16 44 57 26 9 45* 57 35 18 44 62 45* 49 Tube plugged after expansion due to violation of the acceptance criteria established for the expansion effort. I i l l 9 I t

    • '[

INSERVICE INSPECTION REPORT REAVER VALLEY UNIT 1, OUTAGE 5 r, \\ BALANCE OF PLANT (BOP) EXAMINATIONS l One hundred fifty (150) examinations were performed on class 1 and 2 components other than the automated reactor vessel examination and the stean generator tubing examination. B&V personnel performed 109 examinations on Class 1 ccaponents and 33 examinations on Class 2 components. Duquesne Light personnel performed 2 examinations of Class 2 components during the outage and 6 examinations prior to the refueling outage but after the submittal of the 4R outage report. These examinations are tabulated in Attachments I (Class 1) and II (Class 2). A complete description of the B&V performed examinations is contained in l the report "1986 Inservice Inspection Report for Beaver Valley Unit 1, Outage 5", dated 8/15/86. The DI4o. performed examination results are contained in the DLCo. files. Examinations were conducted to review as such of the examination zone as was practical, within geometric, metallurgical and physical limitations. Examinations in limited areas were accomplished as a best effort attempt to cover as such of the code required area or volume (generally, the veld and base metal for 1 "T" on each side) as possible. The principal basis for the limited examination notation is to identify the inability to examine 100% of the required base metal volume for the 1 "T" distance beyond the edge of the veld on a fitting or component. An example is IFT examination of a pipe to elbow assembly, where scanning the entire volume on the fitting or component side is limited by configuration. The resulting coverage is such.that examination of the veld, heat affected zone and base metal for 1 "T" on the pipe side can be ach'ieved by scanning from the pipe side of the veld. An indeterminate coverage of the base metal on the fitting or component side any be achieved during this pipe side scan depending on the calibration sweep length, attenuation, joint configuration, etc. Bovaver, the volume on the fitting or component side cannot be scanned completely for transverse indications as required by code. In either case, 100% of this 1 "T" volume cannot be assured, thus a limited examination notation is used as a disclaimer to having satisfied code requirements, albeit the code is satisfied to the extent practical. Certain piping welds were examined in accordance with the 1974 Edition of Section II, Vinter 1975 Addenda, Appendix III, due to calibration standard configuration (permissible per Amendment 22 of Tech. Spec.). These velds contain the note " Notch Calibration" in the comments column on the examination list (Appendix II). Rejectable conditions identified and the associated corrective action ar's I listed in Appendix III. i f 10 1 1 .--.~..,1m,,.,

INSERVICE INSPECTION REPORT BEAVER VALLEY UNIT 1, OtffAGE 5 COMPONEfrf SUPPORTS 1 Six hundred fifty-four Class 3 supports and hangers for components exceeding four-inch nominal pipe size were examined in accordance with IVD-2600. These examinations were conducted to DLCo. procedures by DLCo. subcontractors. All deficiencies were appropriately addressed by the ISID Deficiency Report System. Snubber visual inspecticns were performed in accordance with Technical Specification 3/4.7.12. All safety related snubbers were found to be I operable. The visual examination reports are contained in the DLCo. files. 4 INSTRUNINTED INSPECTION TECHNIQUE PRESSURE TESTING During SR, the Instrumented Inspection Technique (IIT) was applie'd to several plant systems as an alternative method to hydrostatic testing. This alternative was approved'for use at BVPS Unit 1 by the NRC in D. Mcdonald's letter dated May 15, 1986. The Residual Beat Removal System and Quench Spray System were tested l using IIT. A portion of the Safety Injection System (SI), specifically the SI Accumulator Tank discharge piping, and the Gaseous Vaste System Decay Tanks (GV-TK-1A, 18 and' 1C) and associated piping were tested using the IIT methodology. (See the following examination. reports: Residual Beat Removal V13218-227; Quench Spray V13261-267; Safety

  • Injection V13277 and 278; Geseous Vaste IIT 19.1-19.3).

All of the above systems met the IIT acceptance criteria. Also during SR, testing of the "B" hiver Vater Header'was attempted using IIT. The results of this test were inconclusive because the pressurising medium could not introduce adequate flow / pressure to the system to effect a measurable change from the initial, background conditions. An improved test i method will be employed during 6R that will provide an adequate pre'asure source to obtain the necessary test conditions. i BYDR0 STATIC PRESSURE TESTING During April, 1986, the Lov Head Safety Injection Pumps (SI-P-1A and 15) and their associated piping were hydrostatically tested to meet the end of interval hydrostatic testing requirements. In May, 1986, the Puel Fool Cooling and Purification Systes lines from the discharge of the Puel Fool Cooling Pumps, through the Puel Pool Heat Exchangers, up the the last isolation valve before the Spent Puel Fool were also tested. (See the 4 following examination reports: Low Head Safety Injection V13090, 091 and 094; j Puel Fool Cooling V13092 and 093). The accompanying visual inspections (VT-2) found no rejectable conditions. I i 11 -er ' N' eg ap w.$ e J

INSERVICE INSPECTION REPORT BRAVER VALLEY UNIT 1, OUTAGE 5 SYSTEM LEAKAGE EXAMINATIONS A system leakage examination vas' conducted upon reaching Mode 3. (See visual examination reports V13280 through V13288 contained in the DLCo. examination files). The deficiencies found are listed in Appendix III and were corrected prior to entering Mode 2. AUGNENTED IIAMINATIONS Some examinations in excess of the ASME II requirements were performed. The "A" Reactor Coolant Pump Flywheel was examined both ultrasonically and by The load bearing penetrant per the guidance of Regulatory Guide 1.14, Rev. 1. velds on the special lifting devices were examined by magnetic particle techniques in response to NUREG-0612 (on the control of heavy loads). Additionally, an eddy current egamination of the "C" Recirculation Spray Heat Exchanger was conducted. RESOLUTION OF DEFICIENCIES All rejectable indications were evaluated and reported by Inservice Inspection Department (ISID) Deficiency Reports (D.R.). Resolution was documented by Maintenance Vork. Request (MVR), by Quality Control Report (OCR), or by Engineering Memorandum (RM). Appendix III is a disposition matrix of the ASME II Class 1 and 2 reportable indications found this outage. + L 12 N t0 1 s ^ ^ ^ - ~.. ,, L Z_, _, _ _, _ _ _,; _

  • ^

a

m. __ c... ~ ~ ' '- ~ i, APPEDIX I LIST OF CLASS 1 EXAMINATIONS PAGE 1 B2072 t twett MLLD, AltEA 10 PROCE-EXM. CAL. N0 OR PARTS NO, SKETCM ETH00 OURE MhT'L THICK DIM BLOCK

COBOGITS----------.

l 81.1.1 LONG. SHELL

  1. 3 ER1-1 UT 131 CS 7.9 DWL-HJE-EXMIK FRIBE 0* TO 51*(0* PERPEN-001 DICULAR Als ANACENT TO WELO 2).

(ARIS INSPECTION) 51.1.2 LONG. SHELL

  1. 4 ER1*-1 UT 131 CS 7.9 OWL-HJE-EXAll!K Fret 0" TO 51*(0* PERPEN-

~ 001 DICRAR AIS ANACENT TO WELD 2). (ARIS INSPECTION) 81.1.3 CIRC. SHELL,

  1. 5 ER1-1 UT 131 CS 7.9 DWL-HJE-EXAMIK CLOCKWISE BETWEEN YESSEL 001 AXIS 0* Als 180* (247 INCHES).

(ARIS INSPECTION) 81.1.4 LONG. SELL M KR1-1 UT 131' CS 7.9 DWL-NJE-EXAltIK FADM 0" TO 51*(0* PERPEN-001 DICULAR AND ADJACENT TO WELD 5). (ARIS INSPECTION) ~ 81.1.5 LONG. SHELL

  1. 7 ERI-1 UT 131 CS 7.9 DWL-NJE-EXAMI K FR61 0" TO 51*(0* PERPEN-L 001 DICULA" AIS AthlACENT TO WELO 5).

i' P (ARIS INSPECTION) B1.2.1 CIRC. SHELL. f2 ERI-1 UT 131 CS 7.9 DWL-HJE-EXMIK A MINIMUM OF 24.4 CLOCK-001 WISE FRtM YESSEL AXIS 0* TO 18*. (ARIS INSPECTION) 81.2.2 CIRC. SHELL

  1. 8 ERI-1 UT 131 CS 5.1 DWL-HJE-EXAMINE A MINIMim 0F 24.4 CLOCK-001 WISE FROM VESSEL AXIS 0* TO 18*.

(ARIS INSPECTION) g B1.2.3 CIRC. SHELL

  1. 9 ER1-1 UT 131 CS 5.1 DWL-HJE-AMENDMDIT 22 (ARIS IN3PECT10N) 001 '

/ Bl.2.4 LOWER HEAD

  1. 10 ERI-4 UT 131 CS 5.1 DWL.HJE-AME, M 22 001 (0 REFERENCE IS WELD #16)

(ARIS INSPECTION) B1.2.5 LOWER EAD

  1. 11 ER1-4 UT 131 CS 5.1 DWL-HJE-AMDIDMDIT 22 001 (O REFERDetE IS WELD #16)

(ARIS INSPECTION) 81.2.6 LOWER HEAD

  1. 12 ER1-4 UT 131 CS 5.1 OWL-NJE-AMO WEENT 22 (ARis INSPECTION) 001 (0 REFERDICE 15 WELD #16) 81.2.7 LOWER HEAD
  2. 13 ER1-4 UT 131 CS 5.1 DWL-HJE-AMDDIDff 22 ( ARIS" INSPECTION) 001 81.2.8 LOWER HEAD
  3. 14 E R1-4 UT 131 CS 5.1 OWL-HJE -

AMD etENT 22 001 (O REFDtDICE IS WELD #16) ( ARIS INSPECT 10ll) O

camac>p APPEN0lX I

  • PAGE 2 B2072 EXAM.

CAL. t AwnL NELD AREA ID rum.t- . THICK OIAM BLOCK NO OR PARTS NO. SKETCH ETH00 00K MRT'L M NTS--------------- Bl.2.3 LONER EAD

  1. 15 E R1-4 UT 131 CS 5.1 ONL-HJE-smanamT 22 001 (O REF mrmrr IS E LO #16)

(ARIS INSPECTION) 81.2.11 CLOSURE E AD"#1 ER1-8 UT 130 CS 6.6 BV1-23 EIANIE 0* TO 12' (0* A!UACENT 10 WELO 5). PEEL SE94ENT 51.2.12 CLOSURE HEAD f2 ER1-4 UT 130 CS 6.6 BV1-23 EXAMIE 0* TO 12" (0* ADJACENT TO WELO 5). PEEL SE99ENT 4 51.2.13 CLOSURE HEAD

  1. 3 ER1-4 UT 130 CS 6.6 BV1-23 EIAMIK 0* TO 12" (0* ADJACENT PEEL SE99ENT TO WELD 5)..

EXAMIK 0" 12" (0* ADJACENT B1.2.14 CLOSURE HEAD M ER1-4 UT 130 CS 6.6 PY1-23 TO WELD 5),TO PEEL CE94ENT 81.3.1. FLANGE TO

  1. 1 ER1-1 UT 131 CS 9.1 BV1-31 EXAMIK 163* CLOCKWISE FROM C OF VESSEL

~ STUO MOLES #33 THROUGH #56. (ARIS INSPECTION) B1.3.2 CLOSURE E AD ER1-B UT 130 CS 6.6 BV1-23 EXAMIK 1005 TO FLANGE B1.4.1 INLET N0ZZLE

  1. 17 ERI-2 UT 131 CS 9.1 BV1-29.31 1005 PER IWS-25000.

TO SHELL (ARis INSPECTION) 81.4.2 INLET N0ZZLE fl9 ER1-2 UT 131 CS 9.1 BY1-29.D1 1001 PER IWB-25000. TO SHELL (AR15 INSPECTION) 81.4.3 INLET N0ZILE

  1. 21 ER1-2 UT 131 CS 9.1 BV1-29.31 1001 PER IWS-25000.

TO SHELL (ARIS INSPECTION) i 81.4.4 OUTLET N0ZZLE

  1. 1B ER1-2 UT 131 CS 9.1 BV1-29.31 (ARIS INSPECTION)

TO SHELL B1.4.5 0UTLET N0ZZLE #40 ER1-2 UT 131 CS 9.1 . BV1-29.31 (ARIS INSPECTION) TO SHELL I i 81.4.6 0UTLET N0ZZLE

  1. 22 ER1-2 UT -

131 CS 9.1 BV1-29.31 (ARIS INSPECTION) 1 TO SE LL I Bl.6.1 INLET TO FW-1 LOOP 1-1 UT l'31 CS/S$ 3.25 BV1-30 (ARIS INSPECTION) l N0ZZLE SAFE W/ CLAD END I

.,. - w. - _=. - -..... ~. -. 5 APPENDIX 1 PAGE 3 I. 82072 I t Awnt KLD, AREA ID PitOCL. EKAFI-CAL. 4 NO OR PARTS NO. SKETCH ETN00 DURE .MRT'l THICK DIAM SLOCK

COIt"'NT S----- - - - ------

e 81.6.2 IIILET T0 FW-24 LOOP 2-1 UT 131 CS/S$ 3.25 BV1-30 ' (ARIS INSPECTION) N0ZZLE SAFE W/ CLAD ENO B1.6.3 INLET TO FW-N 'LD0P3-1 UT 131 CS/S$ 3.25 SY1-30 (ARIS INSPECTION) NDZZLE SAFE W/ CLAD EM 31.6.4 OUTLET 70 FW-1 LOOP 1-1 UT 131 CS/SS 3.25 8V1-30 (ARIS INSPECTION) N0ZZLE SAFE W/ CLAD EM a 31.6.5 0UTLET TO FW-13 L00(2-1 UT 131 CS/S$ 3.25 ~ BV1-30 (ARIS INSPECTION) i NDZZLE SAFE W/ CLAD ENO Bl.6.6 0UTLET TO FW-25 LOOP 3-1 UT 131 CS/S$ 3.25 BV1-30 (ARIS INSPECTION) NDZZLE SAFE W/ CLAD END e i 31.8.1.1 CLOSURE

  1. 39 ER1-10 MT 270 CS

? STU0i 4 NUTS TIAL q

  1. 58 81.9.1 VESSEL FLANGE SEE KR1-2 UT 104 CS 10.0 ID MO. f2 THRU #8, #13 THRU fl8, LI6MENTS CGOENTS
  2. 33 Tietu #40, Als #52 THRU #56 31.10.1 CLOSURE E AD
  3. 39 RCR1-10 YT 350 CS WASERS THRt
  4. 58 B1.11.1 CONOSEAL RCR1-8 YT 350.

CS EXAMINED WHILE DISASSEMBLED 00LTIIIG 81.13.1.1 CLOSURE HEAD CP-1 RCR1-8 YT 354 SS ( AfEINDIENT 27) OletE PER INTERVAL WEN MADE ACCESSIBLE. REMOTE CLA0 DING THRU CP-6 CAfqERA. Bl.14.1 VESSEL CLAD 0!NE KR1-7 YT 354 SS SE TEXT PATCHES 81.15.1 VESSEL KR1-5 & YT 354 RENDTE CAf4EllA. INTERNALS KR1-4 LONER INTERNALS. 81.15.2 VESSEL RCR1-5 & VT 354 SS RENDTE CAleERA. INTERNALS KR1-6 UPPER INTERNALS. RCR1-6 YT 350 SS SEE TEXT 4 81.17.1 CORE SUPPORT i STRUCTURE Bl.18.1 CONTROL R00

  1. 34 KRI-8 8 VT 350 SS EXAMIK TIMEE (3) ACCESSIBLE DRIVE HOUSIIIE
  2. 54 ER1-9 DRIVE BElWSIIIG WELDS BETWEEN
  3. 58 VESSEL AXIS 0* 8 90'.

. -. a - i j APPE21X ! PAGE 4 82072 l sKLit.H ist Exan vu. FIGURE NO ) ELD. AREA. OR PART ID (151-) NOT PROCEDURE MAT'L THCK DIAM BLOCK

C000E NT S ------

b -PRESSURIZER-82.1.1 LONGW5LD

  1. 2' RCTK1 UT 130 CS 4.0 92.4 BV1-28 EXAMINE 5" FROM 15* TO 20" FMM 0 REFERENCE

~ (A!WACENT TO WELD 5) 82.1.2 LONG WELD

  1. 1 RCTK1 UT 130 CS 4.0 92.4 BY1-28 EXAMINE 5" FROM 100* TO

~ 105"(+15" FROM TRANSI-i TION IN INSULATION) FROP 0 REF.( AIM TO WELD 7) 82.1.3 CIRC. WELD

  1. 7 RCTK1 UT 130 CS 4.0 92.4 BVI-28 EXAMIME 5" FROM 10* TO 15" FROM 0 REFERENCE (CENTERLINE OF MANWAT)

AMENDMENT 22 82.2.1 N0ZZLE TO VESSEL

  1. 1 RCTK1 YT 354 SS RADI USED SECTION THRU
  2. 5 82.8.1 SUPPORT SKIRT
  3. 8 RCTK1 UT 130 CS 1.5 BV1-26 EXAMINE 30* UNDER INSU-LATION PANEL fRIP-PS-A-6 CIRCLE WELD AMEN 0 MENT 27 82.9.1 CLADDING CP-1 RCTK1

'5T 350 SS 6 NRC UNRESOLVED ITEM 82.11.1 MANWAY RCTK1 YT 350 CS

  1. 85-12-01 (MANWAi, SEAL-ING SURFACE & BOLT HOLES 82.11.2 MANWAY

,RCTK1 MT 276 CS l e f'T e

r._,_ m - -. .o s l;e APPElIDIX ! B2072 i PAGE 5 ) 4j FIGURE 110 ELD, AREA. OR PART ID (ISI-) WT PROCEDURE MAT'l THCK OIAM SLOCK

C000ENTS -----

_1 3ELIUM 1h1 LJIJWE UJtL. -STEAM GE ERATORS-83.8.3 VESSEL CLA00!M -CP-5 RCEl-1 YT 354 SS B3.8.4 VESSEL'CLA0 DIN CP-6 ACEL-1 VT 354 SS -PIPIM SAFE END EIRCLE Sf#S-

    • REACTbt C00UusT B4.1.1 CIRC. WELO

'LohP LOOP 3-1 UT 119 CS/SS 2.375 31.0 BV1-1 TO TE EXTENT PRACTICAL 3-2 (NetENOMDfT 22) FW 2a B4.1.1.1 CIRC. WELD LOOP LOOP 3-1 PT 240 CS/SS 29.0 PT SUPPLEMENTS UT 3-2 FW 28 (#eIDIDMENT 22) 84.1.2 CIRC. ELD LOOP LOOP 3-1 UT 119 CS/S$ 2.375 31.0 Bil-1 TO THE EXTENT PRACTICAL '3-3 FW 29 (MetENDMENT 22) B4.1.2.1 CIRC. ELD LOOP LOOP 3-1 PT 240 CS/S$ 31.0 PT SUPPLEMENTS UT 3-3 (MetENDMENT 22) FW 29

    • PRESS. SPRAY & 5AFETY RE11EF 84.1.3 N0ZZLE TO SAFE E-72 348-4 UT 120 CS/S$

4.0 BV1-19 END -7EW1

  • N0ZZLE 0.8" TO 0.92*

4 THICK WELD 1.3" THICK 84.1.3.1 N0ZZLE TO SAFE RC-72 348-4 PT 240 CS/SS SAFE END 0.85" TO 1.0* 4.0 THICK END -7EW1 -PIPIM ELDS-

    • REACTOR COOLANT 84.5.2 CIRC. WELO LOOP LOOP 3-1 UT 119 SS 2.375 27.5 BV-1 3-7 1

e l l e Y

j a o 6 E T T G S U U A T S) S) - n P T2 T2 N2 N2 e E E po MT MT C EN EN LE LE PM PM P0 PO UN UN SE SE M M TA TA P( P( 4 4 7' 7 8 8 8 K 1 1 1 1 1 1 1 C 1 LO 1 1 1 1 1 1 1 V V Y V V V V Y AL B B B B B B B B CB MM 5 - 5 5 0 0 0 0 0 0 0 AA XI 7 7 7 4 4 ED 2 2 2 1 1 8 8 6 6 6 C 7 2 2 1 2 5 5 5 K 5 4 4 2 1 6 6 6 H 3 4 4 8 8 7 7 7 T 2 1 1 L 'TS S S S S S S S S S I S S S S S S S S S ER 1D 0 9 0 0 0 0 0 0 0 0 U 5E 4 1 4 2 2 2 2 2 2 2 1C 2 1 2' 1 1 1 1 1 1 1 O R P b' T T T . T T T T T T T T O P U P U U U U U U U N 1 1 1 H) C - 3 3 3 3 3 6 2 2 T1 E5 P P P 1 '1 4 K1 O O O 9 9 5 3 3 S( O O O 4 4 9 9 7 2 2 L L L 7 7 9 9 3 2 2 3 0 0 P P P P P 7 3 3 O7 O7* O7 2 2 M O9 O9 7 S O - O - O - L H-H - E O O-I6W I3 I4W 0 L31 L32 L32 A R13 R12 T L3t L31 SF S - 1 S F 1 V S T e S _T 6 lA E 0 A T R T P N N 1 A T A T R L A L C O O E O E SO H O J DC C N E ER L L L A L L R l , D I D D D A L D D D L D D b L L L L R WO E E E U E E O E E T E f E A T W W W D W W T V W T W V W GC I C E NA S A F D IE C C C E C C E C C A C C C L PR R R R R R R R R R S R R R I* I I I I I I I I I I I C C C C C C E P* C C C C I O 0 N 1 1 0 N2 3 9 1 E7 E 2 3 3 4 5 6 7 P2 U 5 5 5 5 5 5 5 5 5 5 P0 R A8 G I 4 4 4 4 4 4 4 4 4 4 F 8 8 8 8 8 8 8 8 8 8 t l

.e APPEISIX ! S2072 I SKETCH 151 EXAM CAL FIGURE NO ELD. AREA. OR PAET 10 (ISI-) NOT PROCEDURE MAT'L THCK DIAM SLOCK

C0fGENTS ------

    • SdFETYINJECT106 84.5.10.1 CI K. WELD

$5-30 223-2 PT 240 6.0 PT SIFPLEMENTS UT -4 (AMENBMENT 22) FWS B4.5.11 CIK. WELD $1-30 223-2 UT 120 SS .765 6.0 BV1-18 -4 Sr 84.5.11.1 CIRC. WELD $1-30 223-2 PT 240 SS 6.0 -4 5 B4.5.12 CIRC. WELD S1-30 223-2 UT 120 SS 765 6.0 BV1-18 -4 4 B4.5.12.1 CIRC. WELD S1-30 223-2 PT '240 6.0 -4 4 84.5.13 CIRC. WELD $1-30 223-2 UT 120 SS 765 6.0 BV1-18 -4 1 6.0 B4.5.13.1 CIRC. WELD $1-30 223-2 PT 240 SS -4 1 84.5.14 CIRC. WELD E-99 350-2 UT 120 SS 765 6.0 BV1-18 -1 7 6.0 34.5.14.1 CIE. WELD E-99 350-2 PT 240 SS -1 7 84.5.15 CIRC. WELD E-99 350-2 UT 120 55 765 6.0 BV1-18 -1 6 84.5.15.1 CIRC. WELD E-99 350-2 PT 240 6.0' -1 6

z' iD C.C....... -.. ~~ z. ~.e '..:1 'e t .f

-{
]

a .APN,MDIX 1 PAu 8 1; ~

t s

ldi F18uRE no utLD. AAEA. 08 P 50 hNI$ NDT P90 b MT'L TER E b'

N NTS ---- '

~ 1 .,,m.s,.T 8 A,m,& m g. s - 1 84.5.16 CIRC." WELD K-350-1 , UT 120 SS .765 6.0 541-18 1898-1 pyg - s ?,. 84.5.15.1 CIK. WELD E-350-1 PT 240 SS 6.0 i 104-1 i .' a ~ FW1 i I B4.5.17 CIRC. WELD E-71 344-1 UT-119 SS 437 4,0 N 1-19 d -3 l yi g q 4.0 PT SUPPLEMENTS UTl.v ~ il' ~, - 84.5.17.1 CIRC. WELD K-71 348-1 PT 240' SS 3

  • ( AMENDMENT 22) 5 j

84.5.18 CI K. WELD E-7 L 348-2

  • UT 120

.437 4.0 W1-19 / -S 2 O 84.5.18.1 CIRC. WELD E-71 348-2 '.f. PT 240 4.0 i'l -8 2 b' 84.5.19 CipC. WCLD E-71 348-2 UT 120 .437 4.0 N1-19 4 l! 3 /. / ) 84.5.19.1 CIRC. WELD K-71 348-2 PT 240 SS 4.0 j- -8 1 3 34.5.20 CIRC. WELD K-71 348-2 UT 120 . SS .437 4.0 W1-19 a -8 I FW9 4.0 i B4.5.20.1 CIRC. WELD K-71 348-2 PT 240 SS 1- -S f: M

    • REkCTORCOOLANT 84.5.21 CIRC. WELD E-33 353-3 UT 120 SS

.440 3.0 W1-20 l -1 3 3.0 l4 84.5.21.1 CIRC. WELD E-33 353-3 PT 240 1 i 3 1

e -) i-e. wo m a E l ~ I 2 2 2 2 2. S 5 4 a A A 4 A 5W E E I E I E ( E E 'o

  • o l5 o

o o e E .4 J J t J J l J M 3 3 3 3 3 g E ~. I a. ~. ~. I a. .>1 .3 3 N N N a G N N 3 N I s-s. E aaea s a a a a a 1 W t t

  • W 2

B 't . B C B 2 W g c z. s 7 7 7 7 7 7 7 La 7 7 7 7 NO a a R R R R R R R 2 R "n n n n n n n n n n n n ~. e e e e w eE e e n e e 7 7 e 7 7 7 7 m 7 m A* A* 7. 7 T Te Te a* av av a?E a?e a7 a7 a7E ave at o y 3-W 1a 5 E 2 E E E E E E E mE oS eS mE mE e5 S.mE mE S a o a a s dw we wo w a a sw s g y W-go gr go o o yg zo zr zr zg r r .y 5

  • E 3

W W D W,s Wa W W WW WE We W WE W G G M G5 G5 Um Gw GE. GE Gd Gs G M 9 9 g= R 9 9 9 9 n n m e ~ ~ o gg W 9 N. 9 9 9 9 9

  • f

'i 9 9 9 Re S 9 9 9 9 i E 3 I E 1 X X X 3 3 t h O t l k --"-~-----A

t e APPENDIX 1 PAGE 10 82072 ^ ,5KLIUM 151 E KAN ' CAL FIGURE N0 lELD, AREA, 0R P ID (151-)

  • leT PROCEDURE MAT'l THCK DIAM BLOCK

COME NTS ------

84.5.28.1 CIRC' WELD SI-74 375-3 PT 240 SS PIPE TO PIPE -4 3 84.5.29 CIRC.NELD, 51-74 375-3 UT 120 SS .766 6.0 BVI-18 PIPE TO ELBOW -4 1 84.5.29.1 CIRC. WELD S1-74 375-3 PT 240 SS 1 PIPE TO ELBOW -4 1 84.5.30 CIRC. WELD SI-74 375-3 UT 120 SS .766 BVI-18 ELBOW TO PIPE -4 j 2 ~ B4.5.30.1 CIRC. WELD S1-74 375-3 PT 240 SS ELBOW TO PIPE -i 2 3 -BRANCH CONNECTION WELDS-4.0 84.7.1 BRANCil RC-72 348-3 , PT 240 55 CONNECTION -1 6 T i \\ 84.7.2 BRANCH DLW-LOOP 2-1 . PT 240 SS 2.0 CONNECTION LOOP 2-7 LOOP 2-2 ~ 3 -SOCKET WELDS-

    • LH SAFETY INJEC110N 2.0 f

84.8.1 SOCKET WELD S1-74 375-3 PT 240 -5 FW6A i

    • CHEM & VOLUME CC iTROL 2.0 84.8.10 SOCKET WELO CH-245 PT 240 SS 142-5 1

2.0 84.8.11 SOCKET WELD CH-245 PT 240 SS 142-5 2 e

. ~ w -

I o APPENDIX 1 PAGE 11 j B2072 j 1 l

  • L I L,n 151 ExAn cM.

FIGURE NO WELD. AREA. OR PAff 10 (ISI-) NOT PROCEDURE MAT'L THCK DIAM BLOCK

COM4ENTS ------

i 84.h.12 SOCKET WELD CH- '245 PT 240 SS 2.0 2 -142-5 h I B4.8.13 SOCKET WELD CH-245 PT 240 SS 2.0 142-5 4 245 PT 240 SS ? B4.8.14 SOCKET WELD CH-2.0 1'42-5 5

    • REACTOR COOLANT 84.8.15 SOCKET WELD RC-35 354-3 PT 240 SS 2.0 1-FW1 4

84.8.16 SOCKET WELD RC-35 354-3 PT 240 SS 2.0 -1 FW2 84.8.17 SOCKET WELD pc-35 354-3 PT 240 SS 2.0 -2A i fv3 2.0 84.8.18 SOCKET WELD RC-35 354-3 PT 240 SS -28 FW3A .,a e G

-- - m-4 O APPENDIX l' PAGE 12 82072 l NKLILM lhi LKAM LAL FIGURE NO WELD, AREA, OR PART ID (151-) leT PROCEDURE MAT'L THCK DIAM BLOCK

COMENT S ------

- PRESSURE RETAIN BOLTINE 84.12.1 BOLTING BETW. 3 54 -3 YT 350 CS 2.0 RC-35 -2 " FW4 & RC-35 -3 FWS 6.0 84.12.2 FLANGE VALVE 350-2 VT 350 CS BOLTING 551A 6.0 84.12.3 FLANGE VALVE 350-2 YT 350 CS BOLTING 551C - PUMP PRESSURE BC 20ARY - 4.35 BVI-68 24 BOLTS IN PLACE 85.1.1 REACTOR COOLANT RC-P-18 RCP 1-2 UT 305 CS PUMP FLANCE BOLTING 2.0 Byl-70 12 BOLTS REMOVED 85.2.1 SEAL HOUSE RC-P-18 RCP 1-2 'UT 104 'CS BOLTING 2.0 BYI-70 12 BOLTS REM 0YED 85.3.1 SEAL HOUSE RC-P-1A RCP 1-2 UT 104 CS BOLTING - VALYtS - ~ 86.1.1 LOOP STOP VALVE MOV VLV-1 UT 305 CS 18.0 2.8" BVI-67 23 STUDS IN PLACE BONNET ENO RC-591 86.2.1 LOOP STOP VALVE MOV VLV-1 UT 305 CS 18.0 2.8" 8VI-67 1 STUD REMOVED CLOSURE STUDS RC-591 2 SPARES 2.8" 86.2.1.1 LOOP STDP VALVE MOV YLV-1 NT 270 CS CLOSURE STUDS RC-591 2.8" 86.3.1 LOOP STDP VALVE MOV YLV-1 YT 350 CS CLOSURE STUDS RC-591

~ -- m ..' s APPENDIX 1 PAGE 13 B2072 l 5KL rcM 151 EXAR CAL FIGURE NO ELD. AREA. OR PAC 10 (ISI-) NDT PROCEDURE MAT'l THCK DIAM BLOCK

C0 fee NTS -----

l [ 86.7.4 LOOP.STOP VALVE ley LOOP 1-1 VT 354 SS 900Y RC-591 I 6.0 86.9.1 PRESSURE $1-10 375-3 VT 350 CS RETAINING l BOLTING 6.0 $1-25 375-3 VT 350 CS 86.9.2 PRESSURE RETAINING-BOLTING 6.0 86.9.3 PRESSURE $1-17 223-2 VT 350 CS RETAINING BOLTING 350 CS 6.0 56.9.4 BOLTING SI-22 223-2 YT 5 9 1 i = s l e

y-- u-.- -. : i

  • 8 APPENDIX 11 LIST OF CLASS 2 EXAMINATIONS PAGE 1 B2072 5KL Net 151 EXAM CAL FIGURE NO WELD. AREA, OR PART ID (151-)

NOT PROCEDURE MAT *L THCK DIAM BLOCK

C0pe4ENTS ------

- PRES!URE VESSEL

    • STEAM GENERATOR!

C1.1.1 CIRC. BUTT WELD 2-5 RCEl-2 UT 130 CS 3.68 BV1-55 EXMINE 7.1" CLOCXVISE FROM 282.8" TO 289.9* C1.1.2 CIRC. BUTT WELD 2-6 RCEl-2 UT 130 CS 3.62 BV1-55 EXAMINE 81.2" CLOCKWISE FROM 286.1" TO 377.3* C1.1.3 CIRC. BUTT WELD 3-8 RCEI-2 UT 130 CS 3.68 BVI-55 EXAMINE 9.2" CLOCKWISE FROM 368.1" TO 377.3"

    • REGENERATIVE EAT Ex.

i C1.1.4 CIRC. BUTT WELD 2-2 CHE3 UT 130 SS 0.9 9.55 BV1-54 CH-E-3

    • SEAL WATER INJECTION FILTERS A & 8 DLC EXAM OF 3/22/85 C1.1.5 CIRCLE SEAM 1-1 CWL4 PT LP101 SS 0.875 10.75 DLC EXAM OF 3/22/85 C1.1.6 CIRCLE SEAM 1-2 CW L4 PT LP101 SS 0.875 10.75 DLC EXAM OF 4/17/85 C1.1.7 CIRCLE SEAM 2-1 CHFL4 PT LP101 SS 0.875 10.75 DLC EXAM OF 4/17/85 C1.1.8 CIRCLE SEAM 2-2 CWL4 PT LP101 SS 0.87 5 10.75
    • REACTOR COOLANT FILTER C1.1.9 CIRCLE SEAM 1

CHFL2 PT LP101 SS 0.165 10.75 OLC EXAH OF 4/5/85 j DLC EXAM OF 4/5/85 C1.1.10 CIRCLE SEAM 2 CHFL2 PT LP101 SS 0.165 10.75

    • SEAL WATER RETURN FILTER C1.1.11 CIRCLE SEAM 1

CHFL3 PT LP101 SS 0.188 16.0 CH-FL-3 (AMEN 0HENT 22) (D.L.C. REPORT LP-101-602 ) CH-FL-3 (AMEN 0 MENT 22) C1.1.12 CIRCLE SEAM 2 CWL3 PT LP101 SS 0.188 16.0 (D.L.C. REPORT LP-101-602) " RESIDUAL HEAT EXCHANGER RH-E-1A (AMEN 0 MENT 22) C1.2.1.1 N0ZZLE TO VESSEL 1-3 RHE1 VT 350 SS 0.875 124.88 WELD C1.2.2.1 N0ZZLE TO VESSEL 2-4 RHE1 VT 350 SS 0.875 124.88 RH-E-18 (AMENDMENT 22) WELD

a w cu n 's s. APPENDIX 11 LIST OF CLASS 2 EXAMINATIONS PACE 2 B2072 SKETCH ISI EXAM CAL FIGURE NO lELD, AREA, OR PART ID (ISI ) NDT PROCEDURE MAT'L THCK DIAM BLOCK

CopeENTS ------

  • SIS ACCIMULATOR C1.3.1 SUPPORT SKIRT 1-4 SITK1 per 270 CS 0*-37' CLOCKWISE FROM CENTER OF MANWAY

- PIPING -

    • RESIDUAL HEAT RE90 VAL C2.1.1 CIRC. BUTT RH-12 75-2 UT 120 SS

.406 12.0 BV1-51 WELD -4 1* C2.1.2 CIRC. BUTT RH-12 75-2 UT 120 55 .406 12.0 BVI-51 WELD -4 FW3 C2.1.3 CIRC. BUTT RH-12 75-2 UT 120 SS .406 12.0 BVI-51 WELD -5 FW4

    • RECIRCULATING SPRAV C2.1.4.1 FILLET WELD RS-3 81-4 PT 240 SS 12.0 AMENDMENT 22

-1B PT SUPPLEMENTS UT FW1A 12.0 AMENDMENT 22 C2.1.4.2 FILLET WELD RS-3 81-4 VT 3 50 SS -1B FW1A 12.0 AMENDMENT 22 C2.1.5.2 CIRC. BUTT RS-11 81-1 PT 240 SS WELD -3 PT SUPPLEMENTS UT 1 12.0 AMENDMENT 22 C2.1.5.3 CIRC. BUTT RS-11 81-1 VT 350 SS WELD -3 1 AMEN 0 MENT 22 C2.1.6.2 CIRC. BUTT RS-4 78-1 PT 240 SS 12.0 WELD -1B PT SUPPLEMENTS UT 2

- - - ~, - -. -. O e.'S i APPEN01X II LIST OF CLASS 2 EXAMINATIONS PAGE 3 B2072 k SKEILM 151 EXAM CAL l FIGURE NO ELD. AREA, OR PART 10 (151-) NOT PROCEDURE MAT'L THCK DIAM BLOCK

C000EN TS ------

i AMENOMENT 22 C2.1.6.3 CIRC. BUTT RS-4 78-1 VT 350 SS 12.0 WELD ' -1B 2 C2.1.7.2 CIRC. BUTT RS-12 78-4 PT 240 SS 12.0 AMENOMENT 22 WELD -5 PT SUPPLEMENTS UT 10 12.0 AMENOMENT 22 C2.1.7.3 CIRC. BUTT RS-12 78-4 YT 350 SS WELD -5 10

    • RESIDUAL HEAT RE# VAL C2.1.8 CIRC. BUTT RS-19 75-1 UT 120 SS

.365 10.0 BVI-52 PUMP TO ELBOW NELD -1 NOTCH pALIBRATION FW1

    • SAFETY INJECTIOt C2.1.9 CIRC. BUTT 51-15 109 UT 120 SS 1.00 10.0 BVI-16 WELD 1

FW1 I C2.1.10 CIRC. BUTT $1-16 109 UT 120 SS 1.00 10.0 BV1-16 AMEN 0 MENT 22 WELD -5 FW88 AMENOMENT 22 C2.1.10.1 CIRC. BUTT 51-16 109 PT 240 SS 10.0 WELD -5 PT SUPPLEMENTS UT Fw88 AMENOMENT 22 10.0 C2.1.10.2 CIRC. BUTT SI-16 109 VT 350 SS WELD -5 FW88 C2.1.11 CIRC. BUTT SI-26 109 UT 120 SS 365 10.0 BV1-52 AMEN 0 MENT 22' WELD 1A NOTCH CALIBRATION 2 AMENOMENT 22 10.0 C2.1.11.1 CIRC. BUTT 51-26 109 PT 240 SS WELD -1A PT SUPPLEMENTS UT 2

_ _ n =. O A ,'S k APPENoix 11 LIST OF CLASS 2 EKAMINATIONS PAGE 4 t B2072 5KL KH IM Lxan uu, r FIGURE NO ELD, AREA. OR PART 10 (151-) NOT PROCEDURE MAT'l THCK DIAM BLOCK

CO M NTS ------

    • SAFETY INJECTION C2.1.11.2 CIRC. BUTT SI-26 109 YT 350 SS 10.0 AMEN 0 MENT.22 WELD

-1A 2

    • RECIRCULATING SPRAY C2.1.12 CIRC. BUTT RS-21 81-5 UT 120 55

.322 8.0 Bv1-17 WELD -4 ' 1 C2.1.13 CIRC. BUTT RS-23 81-3 UT 120 SS .322 8.0 BVI-17 WELD -3 l FW2

    • MAIN STEAM CONFIGURATION PREVENTS UT C2.1.14.1 CIRC. BUTT SHP ISI MT 270 CS 1.0 32.0 WELD

-24 2-3 -1 FW1

    • SAFETY INJECTION C2.1.15 CIRC. BUTT 51-20 222-1 UT.

120 SS .718 6.0 BVI-18 WELD -1 FW1 C2.1.16 CIRC. BUTT 51-20 222-1 UT 120 55 .718 6.0 BVI-18 WLD -1 C2.1.17 CIRC. BUTT P-11 115 UT 120 SS 718 6.0 BV1-18 WELD -G FW9 C2.1.18 CIRC. BUTT P-11 115 UT 120 SS .718 6.0 BVI-18 WELD -G Q

^.: Poco oo. 1 FIrTa cErcaLImG OUTAoE Ar;Ea:Ix III CLA03 1 AN) 2 ASNE II DEFICIENCIES e wore DEFICIENCT MARE DEFICIENT REQUEST CLOSING BUNSER EUNSER CONDITION DISPOSITION BURSER DOCUMENT PIPING: Iten Number 34.8 86851 2*-s!-47 spool SI-74-5, weld tw-6A, has weld repaired 866578 7720 2457 two rejectable indications Item Numbert C2.1 86874 12*-RS-12 Spool RS-12-5, weld Sw-18, has weld' repaired 866571 PTRO 2458 f one rejectable indication 46184 12*-33-12 Spool R5-12-4 has a possible Thickness was found to 866575 064203 minimum wall violation upstream be satisfactory per of weld Fw-3 (located during ultrasonic measurement C2.1 esas) i VALVES: Item Numbers 56.7 86112 Nov-RC-591 Foreign object located in Loop Object removed Q62677 step Talve e i REACTOR VESSEL: Item Number 31.15 4 86170 BC-R-1 small foreign object ever lower Accepted by engineering EM61905 internals flow botes analysis node 3 LEAEAGE: Item number 315.70 86181 RT-RC-551C Steam leak from valve valve repaired 461328 v13290 86181 1Fw-314 Excessive leakage See D.R. 46183 861328 DRS6183 86183 IFw-314 Leaking 100 dpa Leak repaired 861328 v13290 _}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20214U771&oldid=3982072"