ML19273B550
| ML19273B550 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/05/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Schwencer M Office of Nuclear Reactor Regulation |
| References | |
| 099, 99, NUDOCS 7904090161 | |
| Download: ML19273B550 (11) | |
Text
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VIItOINIA ELucritic ANi> I*ownie COMI%NY nacnwonn.viuonn:A uG261 April 5, 1979 Mr. Harold R. Denton, Director Serial No.
099 Office of Nuclear Reactor Regulation P0/KEB:scj Attn:
Mr. A. Schwencer, Chief Docket Nos.:
50-280 Operating Reactors Branch No. 1 50-281 Division of Operating Reactors License Nos.: DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C.
20555
Dear Mr. Denton:
Pursuant to Surry Power Station Technical Specification 6.6.3.a Virginia Electric and Power Company hereby submits its five year inservice inspection report for Units 1 and 2.
Vepco is presently preparing submittals for updating the Surry Units 1 and 2 inservice inspection programs for the final forty month periods of the first ten year intervals to the 1974 Edition of the ASME Section XI Code, with Addenda thru the Summer of 1975, as required by 10 CFR 50, Section 50.55a(g).
Examination requirements per the ASME Code are being reviewed in light of existing technology and requests for relief for those specific examinations determined to be impractical will be submitted pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
Very truly yours,
- h. b'), k$ C& Ly4 C. M. Stallings Vice President-Power Supply and Production Operations cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region 11 S\\%
9 7 9 0 4 0 9 01(c,I
VIRGIMf A EI.ECTPIC A :D l'0WER CXiPANY SURRY I'O'JER STATIOh UNITS 162 FTVE YEAR INSERVICE IMSPECTION
SUMMARY
REPORT Inservice inspections during the first five yeact of coime rc ial opera-tien at Surry Po'rer Statiou Units I and 2 vere performed in accordance with the Surry Technical Specifications with guidance provided by Section XI of the AStiE Boiler and Pressure Vescel Code, 1971 Edition with addenda thru the summer of 1972.
The arrangeuent and detail of Surry Units 1 and 2 piping systems and associated components were designed and f abricated before any of the examina--
tion requirements of Section XI of the Code were formalized. Consequently, the performance of the examinations has been limited to the extent practical due to accessibility, geometric configuration and metallurgical characteristics.
1:ach inspection outage is summarized herein along with exanination limitations and results.
Detailed reports of the inspections are availnble at Surry Power Station.
The examinat ions performed during this period revealed no indications which would af fect safe operation of the units.
Typical indications re port ed strikes, minor gouges, tust and were damaged and nicked bolt threads, arc corrosion.
The af fected components were either repaired or scheduled for future maintenance depending on significance.
. SURRY UNIT I ISI CONDUCTED FRO:1 FEBi;UARY ]1 THRU 13, 1974 An inservice inspection was performed by Ucst inghouse at Surry Unit 1 over the period of February 11 thru February 13, 1974.
Visual and Ultraconic Inspections performed during this outage were on the Loop "C" nain coolant punp flywheel, the bolt hole ligament areas, the internal pressure boundary and the main coolcr.t pump bolt s.
Inspection of the Loop "C" cold leg and hot leg stop valve studs and nuts was also accom-plished.
Tha visual inspections performed on the various items indicated the general condition of all but one item to be satisfactory.
One cold leg stop valve stud, heat nunber 24097, has a circumferential sau-cut of approxumately inch long by 1/8 inch deep.
The notch was cut in an attempt to nake an one ultrasonic angle beam standard.
This valve stud was replaced.
The ultrasonic inspections performed were in some cases limited to less than 100 percent of the item primarily due to gecaetric configuration.
The ultrasonic inspection of the stop valve studs, both h,,
and cold legs, were inspected for approximately fifty percent of their total area utilizing a straight beam inspection frcm the head end of the studs.
The center portion of the stud head is the only area where a back reflect ion f rom the opposite end could be maintained due to the geometric configuration of the opposite stud end.
An attempt to inspect the threaded area of the studs utilizing an angle beam inspection from the nonthreaded area of the item proved unsuccess-ful as the reflections from the stud threads were of such a high amplitude, as compared to the available notched standard, that th is inspection would not be meaningful.
An ultrasonic angle beam inspection of the main coolant pump bolts upper four inches of the threaded area appeared to be a very useful inspec-tion.
The calibration for this inspection was cccomplished using the bo lt notched standard supplied by Vepco and a procedure for the optional angle beam inspection.
A straight beam inspection from the threaded end of the bolt was also performed to insure 100 per cent coverage of the bolt threaded area.
The ultrasonic inspection of the main coolant pump ligament arcas between the bolt holes was perforned frca the flange face only.
The supplemen-tary examination from the bore side of the pump casing was not performed because the pump casing was half full of primary coolant water.
The ultrasonic inspections performed indicated all items tested were in satisfactory condition.
3 I SI C0!m0CTED ' RC:t t'0VE!!iW: 1 THRU DECE!H;ER 31, 1974 (lct REFil! l.l k. OUTAGIO A suanary report of this inspection (Report No. ISI 75-3) was sent to the NRC via lett er serial no. 409 dated liay 5, 1975.
ISI CONDUCTED FRO: F0VE:fiiER 4 TilRU 9, 1975 (2nd REFUEll!L OUTAGE)
A sumna ry re;iort of this inspection (Report No. ISL 75-0) was sent to the NRC via letter serial no. 873 dated February 4, 1976.
ISI CONDUCTED FRO?! OCT0"ER 17, 1976 THRU JANUARY 21, 1977 (3rd IM. FUELING OUTAGE' INTRODUCTION _
An inservice examination of the react or vessel, Class I conponents, certain auxiliary piping systens, sensitized stainless steel piping and designated welds of high energy lines was conducted at Surry Unit I fron October 17, 1976 thru January 21, 1977.
Examinations were performed in acordance with the Examination Program for Refueling Outage Core III-IV.
Examinat ion precedures were approved prior to the examinations, and certifica-t ions relative to personnel, equipment and viat e rials we re reviewed and determined to be satisfactory.
Examinations were witnessed by a Code Authorized inspector from The Hartford Steam Iloiler Inspection and Insurance Company.
RI: SUI.TS Vepco examinations resulted in numerous indications of arc strikes, weld splatter, rust and corrosion being found by visual methods en the low head SIS piping (T.S. Item 7.2) and the sensitized stainless stee' piping (T.S.
Item 8.1.2).
These indications were not judged to be seriou: enough for ina.3diate corrective action; therefore were schedulc.d for remwal during future maintenance.
West inghouse examinat ions resulted in a total of 52 reportabic indications being noted.
The term " reportable indication", as applied to Westinghouse inservice inspection, is a broad term reference to which the following classification has been assigned to clarify usage.
Indications are classified as follows:
Class 1 - Flaw indication.
Exceeds reportable requirements.
This classifi-cation requires a repair.
A total of 10 indications were in this classification and all were
.r
- repaired to a no indication (NI) condit ion.
Six were due to damaged threads on bolts and four were surface indications that were removed by light blending or grinding.
Refer t o Table 1 for details.
Class 2 - Flaw ind icat ion.
Exceeds reportable requirements and is acceptable.
This classification requires a disposit ica.
A total of 38 indica-tions are in this classification and the dispositions have been satisfied.
Refer to Table 1 for details.
Class 3 - Flaw indication.
Less than reportable requirements --
noted for reference univ.
This classificat ion is applied to note flaw areas that might be of interest to future examiners. There is one indication in this classification.
Refer to Table 1 for details.
Class 4 - Ccometric indication.
Noted for reference only, this classifica-tion is applied to note geometric indication areas that might cause interpretation difficulty for future examiners.
There are two indications in this classification.
Both areas were detected ultrasonically with a 45* beam angle and investigated with 45* and 60* beam angles, and with 5 MHZ and were dual element high resolution straight be mq transducers to confirm the lack of flaws.
The weld crown was removed from the indication area of weld 10 on the 4" pressurizer spray line (T.S. iable 4.2-1, Item No. 8.1.1, U ISO VPA044/S) to allow scanning across the weld and half node investigation.
The indication areas on weld 18 of Loop 2 main steam line (T.S.
4.15, W ISO VpA102) produce sicultaneous reficctions from the I.D.
and 0.D. with an apparent finw indication between these two.
Finger damping of the weld crown affects both the 0.D.
signal and the apparent mid-wall flaw indication.
The mid-wall signal is caused by a mode conversion ( ard the resulting velocity change) due to the 1.D.
surface configuration.
A review of the appropriate construction radiographa revealed no flaws in or near the areas producing these re flec tors.
Class 5 - Minor indications. Typical or characteristic.
Condition is acceptable. This classification is applied to light surface corrosion or oxidation, light scratches or grinding marks, small rounded dents, etc.
There are no indications in this classification.
Class 6 - Indications outside of examination zone.
Noted for assistance only. This classification is applied to indications outside of the 1 "T" examination area that are noted or reported as aid or assistance to the construction contractor or owner. There was one indication in this classification that was repaired to a no indication condition.
Refer to Table 1 for details.
-m
-S-
- 1. IMITATIONS Sone of the arrangement s and details of the piping cystem and components designed and fabricated before the acce - and examination requirements were of Section XI of the Code could he applied; consequently nome examinations are limited or nct pract ical due to geor'etric configuration or accessibility.
Generally these limitations exist at all fitting to fitting joints such as elbow to tee, elbou to valve, reducer to valve etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.
'he limitations exist to a lesser degree at pipo to fitting assemblies, particularly where the weld is not ground flush with the pipe 0.D.
surface.
At these joints examin.it ions can be conducted f rom the pipe side, however, the fitting again limits or precludou examination from the opposite side.
When the weld surfacc is flat, the fitting side exanunation is replaced by a calibrated ntraight berm examination on the weld as allowed by the Code.
For the reactor coolant pump integrally welded supports visual and surface e:: amination was substituted for the volumetric examination required by Section Xi of the Code.
This is allowable for Category K items as amplified on T.S.
page 4.2-13 and Table 4.2-1, item no. 5.6.
For the angr.ented inspection of thee high energy line outs ide the containment as required by T.S. 4.15, examination of three (3) main steam line welds was not perforced due to location within the wall penetration and determination of inaccessability by inspection personnel.
EXAMINATIONS Examinations were conducted to review as much of thee examinat ion zone as pract ical, within geouetrical, metallurgical and physical limitations.
was When 100% c,f the required examination could not be achieved, the examination was considered to be part ial (PAR) and so noted.
Generally PAR's are noted et fitt ing-to-fitt ing acsemblies (as explained under LIMITATIONS) and in areas where integrally velded supports, lugs, or hangers, etc., preclude access to sorae part of the excmination area.
Ultrasonic examinations that produced greater than reference level sensitivity, from reflectors th a t are characteristic of metallurgical structure or th e I.D. and 0.D.
surfaces of an item were acknowledged only.
Examples of areas that generally produce such geometric indications:
(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 the cast main coolant piping.
(4) responses from the thread areas of bolt ing.
Geometric responses from these areas are charact eristic of the examination and are not considered relevant for report ing lengt h or depth.
TA3LE 1 T.S. TABLE 4.2-1
'J CLASS
/>RCA EXAMII;ED ITEi! I;0.
U ISO ITEM DESCRIPTIO!;
CONDITIO!!S 1
Reactor vessel closure 1.11 VPA151 Marca clamp cssembly missing base r.etal he.2d conoscal bolting 1
Steam generator manway 3.5 VPA154 bolts 32,B2,D27,C3 & C7 damnged threads, bolting nicks en chreads and bolt heads 1
2" CVCS letdown piping 8.2.2 VPA59/S piece 18 1/8" linear indica-tion 1
8" containment spray 8.2.1 VPA74/S piece 32 are strike ring #1 1
8" containment spray 8.2.1 VPA75/S piece 6B two linear indica-ring #2 tiens 2
Reactor vessel closure 1.11 VPA151 jacking screw accecblu small nicks head conoscal bolting 2
Pressurizer nanway bolting 2.6 VPA153 bolts 1-16 minor nicks and goures on bolt heads 2
Steam generator manway 3.5 VPA154 bolts A4,5,8,21,22,23, ninor nicks on bolting 24,25,26;B4,5.6,25,26; threads C2,4,5,6,18,20,22 3
Loop A 6" 6 2" SIS 8.2.2 VPA71/S piece 30 small hole in grind car hot leg piping 6
Loop A 2" SIS cold leg 8.2.2 VPA68/S piece 54 are strike piping i
_7_
S U R RY U N I_T _2._
ISI CO ! DUCTED FROM IUY 13 TllRU 15, 1974 It1SPECT10Il SUMMAhY An inservice inspection was performed by U:stinghous, at Surry Unit 2 over the period of May 13, thru Ilay 15, 1974.
Visual and Ultrasonic Inspections perforra:d during this outage were on th e Loop "C" nain coolant pump flywheel, th-bolt hole lig. ment areas, the internal pressure boundary and the main coolant pump bolts.
Inspection of the Loop "C" cold leg and hot leg stop valve studs and nuts was also accom-plished.
The visual ins pect ions perforned on the various it e m indicated the general condition of all items to be sat is f ac tory.
The uttrasonic inspections performed were in some cases limited to less than 100 percent of the item prinarily due to geometric configuration.
The ultrasonic inspection of the stop valve studs, both hot and cold legs, were inspected for approximately fifty percent of their total area utilizing a st raight bene innpoct ion f rom the head end of the ;tuds.
The center port ion of the stud head is the only area where a back reflection frca the opposite end could be maintained due to the geometric configuration of the oppos it e stud end.
An ultrasonic angle beam inspection of the main coolant pump bolts upper four inches of th readed area was performed. The calibration for this inspection was accenplished using the bolt notched standard supplied by VEPCO and the procedure for the opt ional cogle beam inspection. A straight beam inspection from the threaded end o! the bolt was also performed to insure 100 percent coverage of ths. bolt threaded area.
The ultrasonic inspection of the main coolant pump lignment areas between the bolt holes was performed from the flange face only. The supplementary examinat ion f rom the bore side of the pump casing uas not performed because the pump casing was half full of primary coolant water.
The ultrasonic inspections performed indicated all items tested were in satinfactory condition.
ISI CONDUCTED FROM SEPTEMBER, 1974 THRU JULY, 1975 (OUTAGE CORE I-II)
A summary report of this inspect ion (11eport No. ISI 75-7) was sent to the NRC via letter serial no. 813 dated December 18, 1975.
T'
_g_
ISI ComiUC'I ED FP.DM APRII, 21, 1976 THRU JU:H: 1, 1976 (CD FAG'; CORE II-I]I)
SUI' MARY Inservice examinations were performed on Class I components, auxiliary piping systen;, sancitized stainle: s ctcel pipinc., component supports and support structurer at Sorry Unit 2 from April 21, 1976 thru June 1, 1976.
Visual, sur f ace and volunatric nondest ruct ive testing methods were utilined for the component inspections.
Review and approval of examination procedures, personnel qualifications, UT instruaunt and calibration, block certifications, couplant certifications, and liquid penetrant cert i fi cat ions, we re completed prior t o st art of the inservice inspection.
On the pressurizer spray line, ultrasonic examinat ions we re performed at reference sensitivity due to high noise level in this specinen.
All other ultrasonic examinations were performed at a mininma of 2X sensitivity.
LIli1TATIONS The piping syntens of the Surry Unit 2 plant contain welds and adjacent base material which are inaccessible f or 100 exami na t ion.
Componert configura-tions restricted angle Loam examination of weld and "lT" en each side as required by the Code.
These weldc. were examined (except uhcre noted other-wise) by the following techniques: (1) 100'4 angle beam of the weld and IT from the pipe nide; (2) longitudinal wave inspection of the pipe side, weld metal and cooponent areas where search unit contact is possible within th e one ucld thickness zone; and (3) part ial angle beam examination from the component side, search unit contact permitting. This technique satisfies code requiretants for inspection of the weld, but does not inspect base raet al for IT on component side of the wm ld.
For the react or coolant pump integrally welded support s visual examination substituted for the voltu etric exanination required by Section XI of the was Code.
This is allowable for Category K items as emplified on T.S.
page 4.2-13 and Table 4.2-1, item no. 5.6.
INDICATIONS Visual exaninations resulted in the following report able indications:
Stean Generator "A" Hot and cold nanway bolting inspected revealed thirteen (13) bolts with nicks on threads.
Steara Gene rat or "B" Hot and cold manway holting inspected revealed two (2) bolts with nicks on threads.
9 Ste.-
Cenerat n "C" llot and cold. w ray bolt ing inspected revealed nine (9) bolts w i t. h nicks on th readt.
" chased" and cleaned up and bolts w re re-examinc.1 and The threads were det erni end acceptable.
Surface ex mai nat ion s resulted in the following, report able indication:
- 1. cop "C"
Hot Lee liigh !!ead ';IS Liquid penetreat c..ca i.na t i c a revealed a tepartable indication on weld
- 4.
Thia indicatian was later r,round, re examined and deteritined accept:ble.
Ult ra.4onic examinations resulted in no re po rt :1b l e indicalions.
ISI CONDUCTED FPret SEPTEMBER 13, 1977 THRU OC10HER 8, 1977 (OUTAC) C0!m III -l V )
I MTRf, DUCT IO.N-An innervice examinat ion of the reactor vessel, Class I components, certain senqitized st ainlesc steel piping and desinnated auxiliary piping c ya tt :,,
weldr. of high energy 1 inns was conducted at Surry Unit 2 from september 13, 1977 thru October 8, 1977.
Examinat ions were performed in accordance with the Exaninat ion Progran for Refueling Outage Cote III-IV.
E; amination procedures were approved prior to the examinations, and certifica-tionn relative to personnel, equipu:nt and r:m.c r i a l s were reviewed and witnet<;cd by a Code determined to be satisfactory.
Exrninations r re Aut hor ized Innpector f rom The llart ford Stean Boiler Inspection and Insurance Company.
RESULTS The only indicationr, reported within the areas examined during thin outage were on non-code itens, examined by plant personnel in accordance with th e Tech. Spec. Table 4.2-1, Item 7.2.
The indications were detected by visual examinationn and were all evaluated as being minor and not requiring ircediate correction.
LIMITATIO.NS So.ne of the arrangements and details of the piping sys tera and components were denigned and fabricated before the access and exanination requirements of Section XI of the Code could be applied; consequently some examinations are limited or not practical due to geonetric configuration or accessibility.
Generally these limitations exist at all fitt ing t o fitting joints such as elbow to tee, cibow to valve, reducer, to valve etc., where geometry and sometimes surface condition preclud" ultrasonic coupline or accesc for the required scan length.
. Tb-limit at inns exist to a lesser degree at pipe to litting asseublies, part icularly where the w"1d is a<er ground flu ;h with the pipe O.D.
curface.
At these joints examinutions can he c ondu c t e <' from the pipe side, h o'.m ve r,
the f i t t i n; a-iin lim ts o r p r e e l t N r.
examin.ition from the opposite
- c. i d e.
When the veld su,-face is flat, the fitting side exain; tion is repinced by a calibrated 4trai@ t bcr > excmination on the weld as allowed by the Code.
E X AMIN AT ION _S_
finminations ucre conducted to revi u as much of the cyamination zone as was prac tical, uith i n gem e t rical, net.il lurgical cod physical liuitations.
b'h e n 10fC of the rec uired examinalion ccmid not be achieved, the examination was i
considered to be pa rt i el (P.\\R) and ro noted.
Gen" rally PAR's are noted at f i t t ing-t o-f it t ing as sembliec (as explained under LIMITATIOUS) and in areas where inter, rally ucided supporte, luna, or hange rs, etc., preclude access to s er..e part of the exanination area.
Ultrasonic exnuinations that produced greater th an re fe rence level sensitivity, frou reflectors that are characteristic of metallurgical structure or the 1.D.
and or O.D.
surfaces of an iten were ackno.iledged only.
Examples of areas that penerclly pro 1uce such geometric indications:
(1)
I.D.
weld prep or root and or the croan overlay or toe.
(2) the 1.D.
radiur. of the tche sheet on the channel head to tube sheet weld of stean generators, vben examining from the tubesheet side.
(3) the retallurgical structure of the cast aain coolant piping.
(4) responses f rou the head Geometric responses fren these areas are charact eristic of the examination and are not considered relevant for reporting leny,th or depth.
Illtrasonic examinations resulted in no reportable indications.
.-