Text

Final Rept on Inservice Insps Conducted During 1980 Refueling Outage,Vols 1 & 2
	ML19344E318
Person / Time
Site:	Pilgrim
Issue date:	04/30/1980
From:	; BOSTON EDISON CO.
To:	;
Shared Package
ML19344E317	List: ML19344E316; ML19344E318;
References
	NUDOCS 8008280380
	Download: ML19344E318 (750)
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. . _ _ _ _ _ _ - . . _. _

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j 1980 INSERVICE INSPECTION OF PILGRIM NUCLEAR POWER STATION UNIT 1 VOLUME 1 Prepared for

Boston Edison Company l 800 Boylston Street Boston, Massachusetts 02199 April 1980 o e PeabTdy bsinc Services

,8008280340

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FORM NIS-1 (back)

8. Examination Dates 1/5/80- to 5 /20/80,, lospection Inter,al from 12 /9 /72 o 12 /9 /82 t

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. Refer to abstract in Final Report.

11. Abstract of Conditions Noted. Refer to Summary and Conclusions in Final

Report.

12. Abstract of Corrective Meuures Recommended and Taken None We certify that the statements made in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code,Section XI.

[ Signed /I M l

Date

'/ '

19 Certifieste of Authorization No.(if applicable)

BostonOwner N/A Edison Co.sy/

Expiration Date N /A

[ee l

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel j Inspectors and/or the State or Province of Mass. and employed by

Factory Mutual of Waltham. MA have 55'N0the - components descnbed in this Owners' Data Report during the period 1/5/80 to and state that to the best of my knowledge and belief, the Owner has performed examinations and taken ortretive measures desenbed in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

By signing this cernficate neither the inspector nor his employer makes any warranty, expressed or impl; ,

concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the inspector nor his employer s5all be liable in any manner for any personal injury or property damage or a loss of any kind arismg from or connected wirh this inspection.

Date 8 19 88

. ,, du . Commissions 88 78N8

inspector's Signature Nanonal Board, State, Province and No.

Arkwright - Boston Insurance Mutual Boiler and Machinery Division A

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O FORM NIS-1 OWNERS

DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. owner Boston Edison Co., 800 Boylston Street, Boston, MA (Name and Address of Owner)

2. Plant Pilgrim Nuclear Power Station, RFD #1, Rocky Hill Rd., Plymout a, MA (Name and Address of Plant)

3. Plant Unic #1 4. Owner Cernficate of Authorization (if required) N/A

5. Commercial Service Date 12 /9 /7 2 6. Nadonal Board Number for Unit 20763

7. Components Inspected Manufacturer Component or Manufacturer or Insta!!ct State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Vessel Combustion Eng. 66107 66207 20763 Pipine Bechtel Corp. N /A N/A 7572 O

i Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,

(2) information in items 1 through 6 on this data rewrt is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

W.

Peabody Testing Servic:s 1 a division of Magnaflux Corporation 7300 West Lawrence Avenue l Chic go, IL 60356 i Tel; phone 312 867-8000 O

SCOPE

-)eacocy esanc Services An inservice examination of selected components of Boston Edison's Pilgrim Nuclear Power Station, Unit #1 was performed from Jan. 7, 1980 thru May 5, 1980. These components were selected by Boston Ed-ison in accordance with the 1974 edition of the ASME Boiler and Pres-sure Vessel Code,Section XI, " Rules for Inservice Inspection of Nu-clear Power Plant Components," with all addenda through the Summer of 1975, and the examination schedule. specified in Tables 3.6.G and 4.6.

Q G of the technical specification for the Pilgrim Nuclear Power Station, Unit #1. (See technical specifications contained in Volume I).

Manual Ultrasonic, Liquid Penetrant, Magnetic Particle, Radiographic, and Visual Techniques were utilized in the performance of this inser-vice examination in accordance with ASME Boiler and Pressure Vessel Code,1974 Edition with all addenda through the Sumer of 1975. All ASME code references are the 1974 Edition including all addenda thru Summer of 1975 unless otherwise specified.

The nondestructive examination procedures utilized during the inser-vide examinations are contained in the NDE procedure section of Vol-ume I.

The Peabody Testing Services Quality Assurance Manual, Rev. 6028-1 was utilized during this project tc outline the Quality Assurance func-O tions to he Performed 8y eeedody Testin9 s on-site auelity Assurence Engineer.

A Unit of Peabody International Corporation

Peabedy Tc;. ting l

Th2 proj:ct plan for this ins:rvice examination was ammended after the initiation of examinations. These changes are reflected in the ammended project plan (Volume II). As the outage progressed, certain selected l components were found to be inaccessible or inspected during previous g outages. Many Class 2 system items selected for examination do not ex-ist (eg. long seams in piping), or permanent obstructions prevent exami-nation. Substitutions were made by Boston Edison for these items when components of the proper category existed within the system. Additions to the program were made by Boston Edison so that components previously taken exception to could be examined during this outage. These changes, deletions, and additions are annotated in the anmended project plan.

A summary of all nondestructive examinations performed is contained in the inservice examination table contained in the Abstract, (Volume I).

This table contains the ASME Section XI category and item number for each component, the NDE method and procedure used, the data sheet numbers for each component and the evaluation of the examination data.

The Peabody Testing Quality Assurance section was represented on site by the Peabody Testing Project Q.A. Engineer who was present for 100% of the examination period. The Q.A. Engineer conducted daily surveillances which h monitored compliance to: a. Administrative Procedures

b. Personnel Qualifications and Records

c. Equipment Calibration

d. Test and Inspection Procedures

e. Proper Preparation of Test Reports

f. Receiving Inspection and Storage of Pro-cedures

g. Audits, Surveillance and Nonconformance/

Corrective Action.

In addition, Q.A. overchecks were performed on each ultrasonic shear wave crew, and each procedure utilized was surveyed during process.

The corporate Quality Assurance Manager from Peabody Testing performed periodic audits of the project.

Magnaflux PS-702A ultrasonic units were used to perform the manual volu-metric examinations. A Krautkramer-Branson DM-1 digital thickness mea-i surement ultrasonic unit was also utilized. Transducers from various manufacturers were used in conjunction with these units. Ultragel was h used as the primary coupling agent during ultrasonic examinations.

I

Peabedy Testing Pen:;trantmaterialswereprovidedtoPeabodyTdstingbyBostonEdison.

The documentation of certification of the ultrasonic, penetrant, and mag-O)

L netic particle materials is found in the material certification section of Volume I.

The equipment and materials used for each examination is listed on each calibration or technique sheet. All required examinations performed du-ring this inservice examination are documented in the data (ISI and base-line) sections of this report. Each data sheet references the calibration or technique sheets and calibration sheets cross reverence respective data sheets. A detailed explanation of the ultrasonic calibration.and data sheets is found in the definition section of Volume III.

A cross reference and index listing the calibration / technique sheets and data sheets for each component examined prefaces the inservice and base-line data sections.

D) c O

Peabody Testing Services I a division of Magnaflux Corporation 7300 West Lawrence Avc,nue l Chicago, IL 60656 i Tc!: pheno 312 867-8000 ABSTRACT

(]

v 3eacocy es:nc Services All visual examinations perfonned in accordance with Peabody Testing Services visual procedure 26.A.1, Rev. 9 and prior to issuance of 26.A.1, Rev. 1 dated January 30, 1980, were repeated to ensure con-formance to the specific requirements of Rev.1.

During the L-Wave attenuation check on welds 6-A-11, 6-A-12, 6-B-11, 6-B-12, 6-B-13, a significant difference in attenuation was noted be-Q tween the calibration block and the component. This attenuation dif-ference ran between 4 db and 14 db.

During the shear wave examinations performed, the units were cali-brated on the calibration block,11 db was added to compensate for the attenuation factor and all reflectors were evaluated at this ele-vated db settino. The welds were scanned at a minimum of +6 db over the elevated evaluating gain.

With the exception of the Recirculation System, and Class 2 systems (Ref.6028-NCR-008),L-Wave,45 and 60 shear wave examinations were conducted on all Class I components requiring ultrasonic examination.

Manual ultrasonic inspection was performed on the Recirculation Sy-stem pipe welds outlined in the ammended project plan. A 2.25 MHz straight beam exam and a 1.5 MHz 60 shear wave exam were performed.

lj u The 45 exam was deleted. Boston Edison and Peabody Testing judged the 600angle and the 1.5 MHz frc-quency to be the best possible ex-am, with available equipment, to detect stress corrosion cracking in A Unit cf Peabody Intemational Corporation

Peabody Testing stainless steel piping. The high radiation levels of the Recirculation System was another consideration in deleting the 45 0exam.

O Since stress corrosion cracking begins on the I.D. of the weld and heat affected zone, a 20% DAC recording / reporting level was used. Indications from stress corrosion cracking may appear at this low amplitude in its initial stages. All indications 20% of DAC and over were evaluated. (Ref:

6028-NCR-004).

The recirculation pump integrally welded support welds were examined from the attachment side only. An ASME calibration block for the exami-nation from the pump body was not available. The pump body was scanned with the attachment calibration for information only.

The Class 2 components requiring manual ultrasonic were examined using 0

a L-Wave and 45 shear wave to complete the required volumetric examina-tion. The Boston Edison calibration blocks for the Class 2 ultrasonic examinations were painted to represent the condition of the components, which are ciso painted.

O A comparison, painted vs. unpainted, was performed on the calibration block designated Pil-45. The difference in amplitude from the is "T" hole in this block from the painted and the unpainted side was negligible.

Reflectors were resolved out to the 14/8 node at an amplitude of 30%

FSH when the primary reference (6/8 node) was set at 80% of FSH.

A special magnetic particle technique was required to perform the sur-face examination on the RPV closure stubs that were removed because of the residual longitudinal field that exists in all the RPV closure studs.

This technique is explained on sheet MTT-6020.

Weld 14-A-3 was examined using a m diographic technique to complete the volumetric examination. The use of radiography was necessitated since this was the NDE method used to establish the baseline for this component.

All calibration / technique and data sheets are found in the appropriate sections of this report (Volumes II, III).

Pcabody Testing All nonconformance and deficiency reports ganerated during this outaga ,

precede the ISI calibration and technique sheets. Each calibration, technique and data sheet that is involved in a nonconformance or deff- r ciency has the NCR number referenced on the data sheet.

The results of all examinations are tabulated in the inservice exami-nation table which follows.

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1 10-B-26 tlTL-722 (1T5-727 X i

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llTL -703 i ,

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- 2 s

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C-E-2 C2.5 H-10-1-136 VT 26.A.1 j Rev. 1 VTE-530 X f

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Rev. 1 VTE-479 X ll-13-1-45R VTE-481 X i

ll- 13-1-27 , VTE-480 X 1

11-13-1-29 VTE-482 X l

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C-G C2.1 14-A-55 UT 22.A.16 UTL-375 Rev. 2 UTS-355 X Weld Crown 4

1 14-A-56 UTL-376 UTS-356 X 14-A-57 UTL-377 UTS-357 X

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C-G C2.1 14-BTL-1 UT 22.A.16 UTL-370 Rev. 2 UTS-361 X Weld Crown 14-BTL-2 UTL-371 UTS-362 X Weld Crown l

I 14-BTL-3 UTL-372 UTS-363 X 9, 14-BTL-6 UTL-373 '

UTS-360 X l

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l' Rev. 2 UTS-365 X l i ;

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cas 2 :i i

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! Rev. 2 UTS-320 X 4

t 23-S-4 UTL-283 UTS-319 X i

4 23-S-5 UTL-285

. UTS-318 X Root Geometry i .

l 23-S-7 UTL-282 UTS-314 X

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, lUTS-316 X f I l .

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, $stlasan i 5sce4=a XI 8.Ja..al .

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Rev. 2 UTS-323 Mode Conversion i

! C-E-2 C2.6 ' H-23-1-13 t VT 26.A.1 VTE-561 X >

f Rev. 1 le i I

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VTE-562 X

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C-E-2 C2.6 11-23-1-24 VT 26.A.1 VTE-555 X Rev. 1 li-23-1-285 VTE-560 X ,

ll-23-1-32 VTE-557 X ll-23-1-33 VTE-558 X

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Peacocy Testini Services I a division o: Magnar:ux corporat;on 7300 Wcst Lawrence Av:nu3 l Chicago. IL 60656 l Te!ephone 312 867-8000 P) v

.(-

3eacocy esanc Services An inservice examination of selected components of Boston Edison's Pilgrim Nuclear Power Station, Unit # 1 was ptrformed from Jan. 7, 1980 thru May 2, 1980. These components were selected by Boston Edison in accordance with the 1974 edition of the ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," with all addenda through the Sumer of 1975, and the examination schedule specified in Tables MG and C.6.G of the technical soecification for the Pilgrim Nu-

clear. Power 3Tation, UnTt n.

Manual Ultrasonic, Liquid Penetrant, Magnetic Particle, Radiographic, and Visual techniques were utilized in the performance of this in-service examination in accordance with ASME Boiler and Pressure Ves-sel Code,1974 Edition with all addenda through the Sumer of 1975.

All ASME code references are the 1974 Edition including all addenda thru Sumer of 1975 unless otherwise specified.

All visual examinations performed in accordance with Peabody Testing Services visual procedure 26.A.1, Rev.9 and prior to issuance of 26.A.1, Rev. 1, Dated January 30, 1980, were repeated to ensure con-formance to the specific requirements of Rev. 1.

l During the L-Wave attenuation check on welds 6-A-11, 6-A-12, 6-B-11, ,

6-B-12, 6-B-13, a significant difference in attenuation was noted between the calibration block and the component. This attenuation i

i difference ran between 4 db and 14 db.

l During the shear wave examinations performed , the units were cali-I brated on the calibration block, 11 db was added to compensate for the attenuation factor and all reflectors were evaluated at this ele-vated db setting. The welds were scanned at a minimum of +6 db over l

the elevated evaluating gain.

I Of) l l

A Unit of Peabody International Ccrporation i

BASEST l 3.A.C and 4.6.C Structural Intecrity y- s

/ \ A preservice inspection of accessible components listed in Tab 1'e 4.6.1 vill be conducted before initial fuel loeding to assure the system is free of gross defects and as a reference base for later inspections. Construction orientated nondestructive testing is being conducted as systems are fabri-cated to ass'urc applicable code requirements are met. Prior In to operation,

~

addition,

- the primary sy' stem boundary will be free of gross defects.

the facility has been designed such that gross defects should not occur throughout the life of the station. The inspection program given in Tabic 4.6.1 is based on the requirements of Section IS-242; Table IS-261, compo-nents, Parts and Methods of Examination, and Table 15-251, Examination Categories, all of Section XI of the 1970 ASFE Boiler and Pressure Vessel Code, execpt' where accessibility for inspection was not provided and where it was impractical to modify the original design. The interin use of Sec-tion XI of the Summer Addenda of the 1971 ASME Boiler and Pressure Vcssel Code for the evaluation levels required for inspection of the nucicar 19 piping system, until the appropriate sections of the 1974 code are com-picted, assures that a more recent code than Section III of the 1968 edition of the ASME Code uhich uould otherwise be applicable, is in effect. The biological shielding surrounding the vessel was modified by providing openings in specific locations to permit access to selected len'gths of the reactor vessel shc11 welds. Also, modifications were made to vessel nozzle -

insulation and nozzle block-out removable shielding designs with the intent to mahc the inspection areas more accessibic.by reducing the personnel

radiation exposure required for inspection utilizing available equipment.

O

%s /

The inspectiow program and' the modifications described above verc developed Ihc scr-by the Boston Edison Company with' assistance from its contractors.

vices of Southwest Research Institute were retained to aid in developing the inspection program, provide advice on practical modifications to existing designs for improved inspectability and to perform the preservice inspection.

It is not possibic, houever, to make all changes that might be desired to in-sure literni compliance with all ' areas of the current inspection code. The arcas of exclusion and reasons for this exc1psion .are discussed below.

Category A Accessibility has bcon provided to perform the required examinations The shielding asand stated in-in Tabic 4.6.1 of sc1ceted lengths only of these welds.

sulation designs ucre modified to permit access to these areas and minimize The Coston Edison Company recognizes the importance of personnci exposure.this testing program and has and will continue to m.ske every reasonabi to comply. Although it is believed the ficxibility provided by.che desir.n util permit the inspections to be performed with presently availabic equip-cent, if cnperience revcsis these examinations to be impractical beenusn of high radiation c:tposure to personnel, an evaluatica vill be submittedI,e is thetoin- the AEC for approval of any variance from the specified program.

tent of the Dosten Edison Company to continue with its consultants to develop examination techniques to Icssen the radiation exposure to personnci during the examinations.

O 149 .

Amendment No. 19

. . =.% ...---e.

- -- - - - - .. % _ - ~ - - - , - _ . . ,

BASES:

3.6.C and 4.6.G

- Structural Integrity Category 3

.. l.

In addition to the exclusion bases stated for Category A welds, at the present time there is.no practical way to volumetrically inspect welds in the bottom head because of the combinatios of insulation and control rod and in-core monitor housings configuration on the outside of the vessel and jet pumps and core shroud on the inside of the vessel. ,

19 l Category D In addition to the exclusion bases stated for Category A welds, definitive volumetric examination by ultrasonic methods from external locations on noz-zie internal radii is expected to be limited to ten percent of its perimeter (those portions of the nozzle inner radius lying perpendicular to the reactor vessel centerline). However, these are believed to be the most highly stres-Modifications were made to the shielding sed areas on the nozzle inner radii.

and insulation designs around the nozzles with the intent to permit the in-spections to be performed with minimal radiation exposure to personnel using presently available equipment. ,

It is the intent of the Boston Edison Company to continue with its consultants .

in the development and i=plementation, if practicable, of new techniques so as to include any excluded areas within the inspection program.

s v

f Categen E-2 At the present time there is no practical way to volumetrically or visually inspect the bottom head penetrations or drain nozzle veld because of the combination of insulation and control rod and in-core monitor housings con-figuration. Also, the design of core differential pressure .and shell instrumentation nozzies is such that present day volumetric inspection tech-The combination of hydrostatic test niques are not practical to utilize.

and visual checks to be performed do provide reasonable assurance these examination areas are free of gross defects.

Category L-2 It is the intent that no internal examination be performed on the recircula-tion pu=ps unless they are disassembled for maintenance because of the high personnel radiation exposures which would be involved.

Category M-2 There are several valves in the primary pressure boundary which cannot be

' inspected unless the reactor fuel is removed and reactor water level lowered to the level of the entrance to the jet pump mixer assembly resulting in high personnel radiation exposures from the loss of shielding from the water.

Therefore, those valves which would require the reactor water levelare to be ex-lowered below the low-low water level protection system trip point O, cluded from the requirement of visual inspection of internals.

l 150 Amendment No.19

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b)

V EXAMINATION CATEGORIES AREAS SU8 JECT TO EXAMINATIONS EXTENT AND FREQUENCY OF EXAMINATIONS

-- B-A PRESSURE RETAINING WELDS IN REACTCR VESSEL BELTLINE REGION The areas srtall include the shellionptudinal and circumferential Examination of the shell tonptudinal and circumferential welds welds in the reactor vessel wall opposite the length of the reactor may be performed at or near the end of each inspection mtervat vessel thermal shield, where used, or opposite the effective and shall cover at least 10", of the length cf each longitudinal length of reactor fuel where thermal shield is not used. The weld, and 5". of the length of each circumt'arential weld, with volume to be exammed is shown in Fieures IWB-3510.1 and the mmimum length of weld examined equi to one wall thick-IWB-3510.2- ness.

Material that has been repatred by welding shall be examined The length of weld to be examined shall be increased to at Icast

, wtten the repur depth exceeds IM of the nominal wall thick- 50". of the length when the longtudini.i and circumferential ness. If the location of the repair is not positively and accurately weld have received an exposure to neutron t1uence in excess of known, then the individual shell plate, forpng, or shell course 10 nvt (En of I MeV or above).

positively known to contain the repair shall be exammed.

The extent of the examination of repaired areas shall be at least 50". of the repaired areas when the repured areas have received an exposure to neutron ticx in excess of 10 nyt (En of I MeV or above), but m any case, no later than at the end of the second inspection interval Examination shall be contmued in the suc-ceeding intervals in accordance with IWB-2420.

B8 PRESSURE RETAINING WELDS IN VESSELS I The areas shall include the tonstudinal and circumferential The examinations performed dunng each inspection intetval welds in the vessel shcIl and mendional and circumferential shall cover at least 10", of the length of each longitudinal shell welds m vessel heads. This includes weld metal and base metal weld and mendional head weld and 5", of the length of each for one plate thickness beyond the edge of weld. circumferential shell weld and head weld.

For welds on the reactor vessel, examinations may be performed at or near the end of each inspection interval BC PRESSURE RETAINING WELCS, VESSEL TO. FLANGE. AND HEAO-TO. FLANGE The areas shall melude the vessel-to tlange and head-to tlartse The exammanons performed dunr.g each mspection interval weids, shall cumulauvely cover 100". of each circumferential weld.

BD FULt.PENETR ATION WELOS OF NOZZLES IN VESSELS The areas shall melude the nozzle-to vessel weld and adjacent The extent of examination of each nozzle shall cover 10% of areas as shown m Figure IWB 2500D. the volume to be inspected as shown m Figure IWB MOOD. All nozales shall be examined during each mspection interval B-E PRESSURE. RETAINING PARTI AL PENETRATION WELCS IN VESSELS The ares surrounding each penetration shall be examined for The exa ntna: ions performed dunns each inspection interval

~%

i evidence ofleakage dunng pressure test (IWA 5000). shall cumulatively cover at least 25". of each group of pene.

[O tratiers of comparable size and function.

EXAMINATICN CATEGCRIES AREAS SUBJECT TO EXAMINATIONS EXTENT AND FRECUENCY OF EXAMINATIONS 3-F PRESSURE RETAINING OISSIMILAR METAL WELOS The areas shall include dissirndar metal welds (e.g., safe-end ne examinations performed dunns each inspection interval welds) between combinations of carbon, low alloy, or high sh:11 cover the circumference of 100% of te welds.

tensde stects and stainless stee!s, nacks!-chromium-tron alloys, ruckel-copper alloys. This shall Mciude the base matenal for, at least, one wall thickness beyond the edge of weld.

B-G 1 PRESSURE RETAINING SOLTING,2 INCHES ANO LARGER IN OI AMETER The areas mali mctude bolts studs, nuts, bushings, wuhers, and The examinations performed dunns each mspaction intetval threads d base matenal and flange ligsments between threaded shall cover 100% of the bolts, studs, nuts, bushings, and threads stud holes, in base matenal and tlangs ligaments between treaded stud holes.

Bushings, threads, and ligaments in bue matene of tlanges are required to be examined only when the connection is dis-usemblei Bolting may be examined etther in place under tensten, when the connect:on is disassembled, or when te bolt:ng is removed.

B-G 2 PRESSURE.3ETAINING SCLTING. SM ALLER THAN 2 IN. IN CI AMETER The areas shallinclude bolts, studs, and nuts. The excznmatons performed dunng each uuptction tnterval shall cover 100% of the bolts studs, and nuts.

Boltzng may be examined either ta place under te.uton, when the connection is disassembled, or when the boltmg ts removet B-H VESSEL SUPPORTS The areas shad include te intepsily-welded support attachment In the esse of vessel sucport sk2rts. Se eummation performed (e g., support skirts). Thas includes the welds to the vessel and during each inspection nterval shall cover, at least.10% of the the base metal beneath me weld tone and along the support circumference of the eeld to the vessel In de case of support attachment member for a distance of two support thicknesses. ltig attachments.100% cf the welding to the vesset shad be ex.

amanel Integral support pads on nozzles are excluded.

B-I-1 INTERICR CLAO SURF ACES OF REACTCR VESSELS l

The aress shall include at least six patches (esch 36 sq. in.) The examinations performed during each utspection interval evenly distnbuted, in the etcsure head, and six patches'esch 36 shall cover 100% of de patch areas.

sq. ut.). evenly distnbuted in accessible sections of vessel shell.

Bt2 INTERIC A CLAO SURF ACES CF VESSELS OTHER TH AN AEACTOR VESSELS The areas shall include at ' east one patch (36 sq. in.) near each The exammations performed tunns each mscection interval manway in the pnmary side of the vessel shall cover 100% of ce patch areas.

The examination cf the patet es may be performed at or near the end of the inspection eterval

~ . _ . - - . _ . _ . _ _ ___.,_ _

s) EXAMINATION CATEGORIES AREAS SUBJECT TO EXAMINATIONS EXTE T AND FREQUENCY OF EXAMINATIONS B-J PRESSURE RETAINING WELOS IN PIPING The areas shall include longitudinal and circumferential welds The examinations performed during each inspection interval and the base metal for one wall thickness beyond the edge of the shall cover all of the area of 25% of the circumferentialjoints weld. Longitudinal welds shall be examined for at Icast I ft from including the adjoining I ft sections of longitudinaljoints and the intersection with the edge of the circumferential weld 25% of the pipe branch connection joints.

wiected for examination.

In the case of pipe branch connections, the areas shallinclude the weld metal, the base metal for one pipe wall thickness be-yond the edge of the weld on the main pipe run, and at least 2 in. of the base metal along the branch run.

B-K 1 SUPPORT MEMBERS FOR PIPING, VALVES AND PUMPS The areas shall include the integrally-welded extemal support The examinations performed during each inspection interval attachments. This includes the welds to the pressure-retaining shall cover 25% of the integrally-welded supports.

boundary and the base metal beneath the weld zone and along the support attachment member for a distance of two support thicknesses.

B-K 2 p%Y SUPPORT COMPONENTS FOR PIPING, VALVES AND PUMPS The areas shall include the support componenu that extend The examination performed during esch inspecuon inte: val shall from the pipmg, valve, and pump attachment to and including cover all support components.

the attachment to the supportmg structure.

The support setungs of constant and vanable spnns type hangers, snubbers, and shock absorbers shall be vent'ied.

B-L-1 PRESSU9E RETAINING WELOS IN PUMP CASING The areas shallinclude the weld metal and the base metal for one The examinations performed dunng each inspection interval wall thickness beyond the edge of the weld. shall include 100% of the pressure retaining welds m at least one pump in each group of pumps performing similar functions in system (e.g., recirculating coolant pumpst The examinations may be performed at or near the end of the inspection interval.

BL2 PUMP CASINGS The areas shall include the internal pressure boundary surfaces. One pumpin each of the group of pumps performing simdar func-tions in the system shall be examined during each inspection interval. This examination may be performed on the same pump selected for the Category B-L 1 examir tions.

' The examinations may be performed at or near the end of the

( inspection interval.

C/

- - - -~. .-.

EXAMIN ATION CATEGO RIES AREAS SUBJECT TO EXAMINATIONS EXTENT AND PREQUENCY OF EXAMINATIONS BM1 PRESSUAE RETAINING WELCS IN VALVE SCOtES The areaa shallinclude the weid metal and the base metal for one The examinations performed dunns eacn mspection mterval wall thickness beyond the edge of the weld. shall include 100". of the pressure retaining welds in at least one valve within esca group of valves that are of the same con-structwnal design. (e.g., globe, gate, or check valve), manu-factunns method and manufacturet and that are performing stmalar fJncuons in the system (e.g., ;ontalament isolation.

system overpressure protection, etc.L The examinations may be performed at or c. car he end of the inspecton intetvat B-M-2 V ALVE SColES The areas shall melude the internal pressure boundary surfaces, One valve in each grouo of valves of the sarne constructional on valves exceeding 4 in. nominal pipe size. design, e.g., globe. gate. or checit valve manufactunng method and manufacturer that performs similar functions in the system shall be exammed during each mspection interval. This eurnina-son may be performed on the same vaave selected for the Cate.

gory S-M 1 eumination.

The exammations may be performed at or near he end of the inspection intervsl.

B-N-1 INTEAICA CF AEACTCA VESSELS The areas shall include the space above and below the reactor The examinations shall be performed at the :ltst refuelms outage core that is made accessible for examination oy the removal of and subsequent efuetirig cutages at approx 1rnately three year components durmg normal refueimg outages. In tervals.

B-N 2 INTEGA ALLY WELCED CORE. SUPPORT STAUCTURES ANO INTERIOR ATTACHMENTS TO REACTOR VESSELS The areas shall include attachments and core-support structures The exarnmations during each mspection interval shall ine:ude welded to the vessel wall of the direct cycle boibng water type. 100*. of the visually accesuble attachment we:ds and visually accessible surfaces of the core support structure. This examination may be performed at or ner.t the end of the inspection interval.

B N-3 AEMOVABLE CCRE SUPPCRT STRUCTURES The areas shall include removable structures of the pressurtzed The examinations durmg the mspection tnterval shall metude water reactor vessel. 100", o( tne visually accessible attachmes

elds arid visually aceeuible surtases of the core support struerure and may be pert'ormed at or near ths end of the inspe. tion interval.

The structure shall be removed from the reactor venet for this eummation.

O ~

COMPONENTS, PARTS, AND METHOOS OF EXAMINATION Examination Category item Table No. lW8 2500 Components and Parts to be Examined Method Reactor Vessel 81.1 8A Longitudinal and circumferential snell welds in core region Volumetric 81.2 88 Longitudinal and circumferential welds in snell tothe than Volumetric those of Category 8-A and 84) and meridional and circumferential seam welds in bottom head and closure head (other than those of Category 84) 81.3 84 Vessel to-flange and head-to-ftange circumferential welds Volumetric 81.4 80 Primary nozzfe-to vesset welds and nozzle inside radiused Volumetric section 81.5 8-E Vessel penetrations, including control rod drive and instru- Visual (IWA.5000) mentation penetrations 81.6 8.F frozzfe.to-safe end welds Volumetric and Surface 81.7 8<" Closure studs,in place Volumetric 81.8 84 1 Closure studs and nuts, wnen removed Volumetric and Surface 81.9 8G1 Ligaments between threaded stud holes Volumetric B1.10 841 Closure washers, bushings Visual 81.11 84 2 Pressure <etaining botting Visual 81.12 8.H integrally-weided vessel supports Volumetric B1.13 8-11 C:osure Head Cladding 1) Visual and Surface. or

2) Volumetric 81.14 8-81 Vessel Cladding Visual 81.15 8N1 Vessel intenor Visual 81.16 8 N-2 Interior attachments and core suoport structures Visual 8N3 Core-support structures Visuai O

b' B 1.17 81.18 B1.19 84 8#

Control rod drive housings Exempted comoonents Volumetric Visual (IWA-5000)

Pressurizer l 82.1 8-8 Longitudinal and circurnferential welds Volumetric l 82.2 8-0 Nozzle-to vessel welds and nozzle-to vessel radiused section Volumetric 82.3 8-E Hester penetrations Visual (IWA 5000) l 82.4 8F Nozzle-to-safe end welds Volumetric and Surface 82.5 BG1 Pressure retaining bolts and studs, in place Volumetric B2.6 8 G.1 Pressurwetaining bolts and studs, when removed Volumetric and Surface 82.7 8-G.1 Pressure <etaining botting Visual 82.8 8H integrally welded vessel supports Volumetric 82.9 8-82 Vessel cladding Visual l 82.10 8# Exempted components Visual (IWA 5000) i 82.11 84-2 Pressure-retaating botting Visual Heat Exchangers and Steem Generators 83.1 88 Longitudinal and circumferential wetos, including tube sheet- Volumetric to head or shell welds on the primary side 83.2 0-0 Nozzle-to-head welds and nozzle inside rad used section on Volumetric the primary side 83.3 8F Nozzle.to-safe end welds Volumetric and Surf ace 83.4 8G1 Pressure <etaining bolts and studs, in place Volumetric 83.$ 8G1 Pressure-retaining bolts and studs. when removed Volumetric and Surf ace 83.6 8-G 1 Pressure retaining boinng Visual 83.7 B-H Integrally weided vesset sucoorts Volumetric 83.8 8-1-2 Vessel C! adding Visual 83.9 8# Exemoted components Visual (IWA 5000) 83.10 8 G-2 Pressurwetaining bolting Visual b

EXAMINATION CATEGORIES 9'

AREAS SUBJECT TO EXAMINATIONS EXTENT AND FRECUENCY OF EXAMINATIONS BO PRESSURE.AETAINING WELOS IN CONTROL ACO ORIVE wCUSINGS Tho a:ea stiaJ metude the weld metal and base metal for one =all The exa:ntaanons perfermed dunns each inspection interval thickness beyond ?e edge of the weld, shall include 100". of the welds :n 10* of the per:phers' :entrot rod detve housmgs. The exarnmations may be perior.aed at or near the end of the inspecson intesal.

B-P COkF INENTS EXEMPTEC FROM EXAMINATION SY IW81220 The components snail include these exeinpted from votarnett:c All components shall be exarntned in accordance with IWA 5000 and sarface exmtmanon by IWB-t:23. dunns the system hydrostauc pressure tests required by IWB.5000.

O

D O COMPONENTS, PARTS, AND METHOOS OF EXAMINATION Examination Category item Tabie No. lWB 2500 Components and Parts to be Examined Method Piping Pressure Boundary 84.1 8-F Safe-end to piping welds and safe-end in branch pioing welds Volumetric and Surface 84.2 84 1 Pressure-retaming bolts and studs,in place Volumetric 84.3 8 G-1 Pressure-retaird.1g bolts and studs, when removed Volumetric and Surface 84.4 8 G-1 Pressure reteining bolting Visual 84.5 BJ Circumferential and longitudinal pipe weids Volumetric 846 8J Branch pioe connection welds exceeding six in. diameter Volumetric B 4.7 8J Branch pipe connection welds six m diameter and smaller Surface 84.8 B-J Socket welds Surface 84.9 8-K 1 Integrally welded supoorts Volumetric 84.10 8K2 Support comoonents Visual 84.11 8 -P Exempted components Visual (lWA 5000) 34.12 8-G 2 Pressure-retaining bolting Visual Pumo Pressure Boundary B 5.1 8-G 1 Pressure-retaining bolts and studs, in place Volumetric 85.2 8-G 1 Pressure-retainmg bolts and studs, when removed Volumetric and Surface 85.3 84 1 Pressure-retaining bolting Visual 85.4 6-K-1 Integrally-welded succerts Volumetric 85.5 8 -K-2 Supoort cornponents Visual nf 85.6 85.7 8L1 8 L-2 Pump casing welds Pump casings Volumetric Visual 85.8 8 -P E xempted components Visual (lWA-5000) 85.9 8-G-2 Pressure-retaming bolting Visual Valve Pressure Boundary 86.1 8 G-1 Pressure retaming bolts and studs, in place Volumetric 86.2 84 1 Pressure-retaining boats and studs, when removed Volumetric and Surface 86.3 8-G 1 Pressure retaining botting Visual 86.4 8K1 Integrally welded sucoorts Volumetric 86.5 8.K-2 Support components Visual 86.6 8-M 1 Valv=-body welds Volumetric 96.7 BM2 Valve bodies Visual 868 8# Exempted components Visual (f WA-5000) 86.9 84-2 Pressure-retaining bolting Visual l

1 I

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I

_.__ . _ _ ~ - . . - .

rO EXAMINATION CATEGORIES AREAS SUSJECT TO EXAMINATION EXTEN1 OF EXAMINATIONS C.F PRES $URE RETAINING WELOS IN PIPING, PUMPS, AND VALVES IN SYSTEMS WHICH CIRCULATE REACTOR COOLANT The areas shallinclude: The examinations shall cover 100% of the weld.

a. circumferential butt welds at structural discontinuities.'

b.circumferential butt welds in piping within 3 pipe diameters of the centerline of rigid pipe anchors, or anchors at tt:e pene-tration of the pnmary reactor containment. or at rigidly anchored components. ,

c. longitudinal weld joints in pipe fittmgs (i.e.,in tees, elbows, reducers).

1

d. branch connection weld joints.

! e. pump casms and valve body weld joints.

This includes the weld metal and base tretal for one wall thick-ness beyond the edge of weld.

l l

C-G PRESSUR E-RETAINING WELOS IN PIPING, PUMPS, ANO VALVES IN SYSTEMS WHICH CIRCULATE OTHER THAN REACTOR COOLANT The tress shall include 50% of the totalnumber of the followmg The examination shall cover 100", of the weld.

welds:

a. circumferential butt welds at structural discontinuities.'

b.strcumferenttal butt welds in ptpmg within 3 pipe diameters d of the centerline of rigid pipe anchers, or anchors at the pene-tration of the pnmary reactor contamment, or at ngidly anshored compenents.

c. longitudinal weld jomts in pipe fittings (i.e., in tees, elbows, reducers).

d. branch connection weld joints.

e. pump casing and valve 61y weld joints.

This includes the weld .neral and base metal for one will thick-ness beyond the edge of weld.

i l The welds selected shall provide a representative samptmg among the total number of welds covered by (a) to (c) above.

' Structural discontmuities melude weld joints at pipe-to vessel nozzie, pipe.to-valve body, pipe to-pump casmg. pipe-to titungs ti.e.,

elbows, tees, reducers, t1anges), and pipe to-pipe of different schedule wall thickness.

a m

, . . . , _ . .m._ _ _ _ . , , , . _ - _

EXAMINATlON CATEGORIES AREAS SUBJECT TO EXAMINATION EXTENT OF EXAMINATIONS C.A PRESSURE.AETAINING WELOS IN PRESSURE VESSELS The areas shall include sheil and head strcumferencal

elds The exarninations shall cover at least 20% of each circum-wnich are gross structural disconunutues.' This ncludes weld

. ferential weld. uniformly distnbuted among :nres areas around me:a! and base metal for one plate thick. ness beyond the edge of the vessel ctrcumference.

te weid jomt.

C8

?AESSU AE RETAINING NCZZLE WELOS IN VESSELS The areas shad include :he notale to vessel attachment welds. The examinatten shall cover 100% of me norne.to-vessei attach-ment weld.

C-C INTEGRALLY WELCEO SUP*CRT AT"pACHMENTS TO VESSELS The sters shall mctudc the welds of external sucport at:achtnent. The exammations sha;1 cover 100% of me meld.

brackets. lugs, etc.

CO PRESSUAE AETAINING SOLTING EXCEEQiNG t INCH IN OI AMETER The 4reas shad metade bolts, s:uds. auta. bushings, wuners. at:d Visual exarntnanons :4rformed dunng each mspecuon inte-val threads in base ma:ensi and tlange ligarnen:s between dreaded shall cover 100% of the bolts. stads. nuts. bushings, and mreads stud hcies. in base matenal and t1ange ligarnents be: ween dreaded stuJ holes.

Nondestructive summanons shdl be pertermed on 10% of the bolting m each joint but not 'ess

tan two botts cr studs per jomt.

Bushings, threads and ligaments m base matenal of :langes are required to be examined only

hen the connecnon ts dis-assemble 1 Solung may be exarnined either in place under :ension when the connecnon is disassembled, or when the botting is remove 1 C.6 1 SUPPCAT MEMBERS PC A MPING, V ALVES AND PUMPS The areas shad include me external su port attachments. D.is The examinations ;erformed dunng each mspection inter <al j

mcludes the welds to :nc pressare-retaining boundary and the shall cover 100% of the major !oad beanns etements of tne suo-j base metal beneath the *eid tone and along the support attaca- port structure and hanger.

ment member for a distance cf :wo support tatekrtesses.

C.E 2 SUPpC AT CCVPCNENTS PC A 8' PING, V ALVES ANO PUMPS l

The areas shall inctude me support components which extend The exar imation performed danni exh :nspeenon interval shh!

from :re piping, valve. and pump attachment. and inctedmg me cover ad support componen:s.

at:achtnent to me supper:m; structure.

The support iet:Ings et ;onstant and vanacle spring type hangers, snubcers. and shocx absoreers inall be ventiet

Cross struc urat disconnnuity is derined in NB M13.2.

l I

d COMPONENTS, PARTS, AND METHOD OF EXAMINATION E xamination Category item Tatile Components and Parts to NA IWC-2520 be Examined IL * %od PRESSURE VESSELS C1.1 CA Circumferential butt weids Volumetric C1.2 C-8 Nozzie-to-vessel welds Volumetric C1.3 C4 integraily.weiced succorts surface C1.4 C4 Pressure <etaining botting Visual and eitner surf ace or volumetric PIPING C2.1 CF,C4 Circumferential butt w=ics Volumetric C2.2 C F C4 Longitudinal we:d joints in fittings vclumetric C2.3 C 7.C4 Branen pipe to oice weid icints volumetric C2.4 CO Pressure'<etaining botting Visual and either surface or volumetric C2.5 C.E 1 Integrallyweided sucoorts Surface C2.6 C-E 2 Sucoort comoonents Visuai PUMPS 03.1 C-F, C.G Pumo casing weids Volurnetric C3.2 C4 Pressure <etaining botting Viswat and either surface or volumetric C3.3 -

C41 Integrativweided susoorts Surface C3.4 CE2 Succort comooneots Visual VALVES C4.1 C F,C G valve bocy weids Volumetric C4.2 CO Pressure <etainmg botting Visual and either surface or volumetric

[ _

(s C4 3 CE1 Integrally 4veided susoorts Surface visuai C4.4 C.E 2 Sucocrt comoonents l

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Table of Contents Figure flo. Page No.

C-1 RPV Examination Areas C-1 C-la Location of Areas of RPV Cladding Visually C-2 Examined C-2 Closure Head Examination Areas C-3 C-3 Main Steam System General Arrangement C-4 C-4 Main Steam-Loop A-Inside Containment C-5 C-5

C-6 C-6 Main Steam-Loop B-Inside Containment C-7 C-7

C-8 C-8 Main Steam-Loop C-Inside Containment C-9 pJ C-9

C-10 C-10 Main Steam-Loop D-Inside Containment C-11 C-11

C-12 C-12 .va in Steam Drain Manifold C-13 C-13 Reactor Recirculation System General Arrangement C-14 C-14 Reactor Recirculation System-Loop A C-15 C-15 Reactor Recirculation System-Loop B C-16 C-16 Control Rod Drive Hydraulic Return Line C-17 C-17 Feedwater System Loop A-12-inch Diameter C-18 C-18 Feedwater System Loop A-18-inch Diameter C-19 C-19 Feedwater System Loop B-12-inch Diameter C-20 C-20 Feedwater System Loop B-18-inch Diameter C-21 O C-21 Res4 duel Heat Removal (in)-Lect-' cop A C-22 C-22 Residual Heat Removal (in)-LPCI-Loop B C-23

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Y PILGRIM STATION UNIT 1 g ic==" Edison em. -
The ~igure C-29 isretric, as it is ncw drawn, d:es no e resen: :.e actual c nf-gur tien 'wnich new exists. A new is retri: is in t.e ::urse Of Ore;aration ::
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PILGR!M STATION UNIT 1 -
O'*" Edison c=--
The Figure C-30 isemetric, as it is now drawn, dces not re'present the actual conf-guration which new exists. A new isemetric is in the course of preparation to show the section of carbcn steel replacement in the "B" Core Spray Loop.
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PILGRIM STATION UNIT 1 -
@eabEyTestng CLASS 1 SUPPLEMENTARY ORAWINGS (IN ORYWELL)
P-1 Vessel Welds and Nozzles P-2 Vessel Head Welds and Nozzles P-3 Head Nozzle and Ligament Location P-3A Vessel Stud and Ligament Location P-4 Mainsteam A P-4A Mainsteam A P-6 Mainsteam B P-6A Mainsteam B P-8 Mainsteam C P-8A Mainsteam C P-10 Mainsteam 0 g P-10A Mainsteam 0 P-14 Recire. Outlet B P- 14A Recire. Outlet B P-145 Recirc. Loop'A P-146 Recirc. Inlet A P-lab Recire. Inlet B P-14c Recire. Inlet C l
Recire. Inlet 0 P-14d P-lae Recird. Inlet E P-15 Recire. Outlet A P-15A Recire. Outlet A P-15B Recirc. Loop B P-157 Recirc. Inlet F P-15g Recirc. Inlet G P-15h Recire. Inlet H
PILGRIM STATION UNIT 1 .
CPeabEyTestirg CtASS 1 SUPPLD1ENTARY DRAWINGS (IN DRYWELL)
P-15j Recire. Inlet J P '.5k Recird. Inlet K P-16 CRD Re-rcute P-17 Feedwater Loop A P-17A Feedwater A-Leg P- 3,75 Feedwater 5-Leg P-17C Ieedwater Leon A (outside drywell)
P-19 Feedwater Lace 3 P-19A Feedwater C-Leg P-193 Feedwater D-Leg P-19C Feedwater Loop 3 (cutside crywell)
P-21 RHR (in) - LPCI Lecp A
[V P-22 RHR (in) - L?CI Lce? B P-23 RHR (cut)
P-24A RHR -hcad spray P-24B RHR -head spray P-25 RWCU (in)
P-26 RWCU (in)
P-27 RCIC (in)
P-27a RWCU (in) to RCIC (in) - joining detail P-23 RCIC (cut)
. P-29A Core Spray A P-30A Core Spray 3 P-303 Core Spray 5 (outside drywell)
P-31 HPCI (in)
(v~\ P-32 HPCI (cut)
s' PILGRIM STATION UNIT 1 (vx P.eab_odyTestrg cuss 1 sumexenARY CRA'4INGS (IN cry'4 ELL)
P-50 Recirc. Outlet A - detail P-51 Recire. Outlet 3 - detail P-52 Recire. Lecp A to Lecp 3 - joining detail C
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O E PILGRIM STATICN UNIT 1 PeabTdyTe@g vesset wetos and nozztes e-1 3 3 3 3 3 3 0 3 3 3 0 3 3 0 330 300 270 2J0 210 130 150 120 30 60 30 0 I I I I I I i i i I I I i
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Peao~~dyTestrg vesset s.eae sgtas and t0ZZLES P-2
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O PeabEyTesting vesset sTuo and tigament Location P-3A I
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L PILGRIM STATION UNIT 1 -
O PeabTdyTesfrg mm STEM ' A P-4 1-A-1 1-A-3 h A e ii r rm ,
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V P!LGRIM STATION UNIT 1 -
C) PeabTdyTestrg ascracuunoN ouner B P-14 2-N18-1 (DMI I
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Peabiy reg O I RECIRCULATION INLET A P-14a 2-N2A-1 (O.M.)
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h PILGRIM STATION UNIT 1 _
O PeabEyTestirg RECIRCULATION INLET B P-14b 2-N28-1 (D.M.)
2-N2S-2 'h x
N2B 2-N2B-4 %
% y_
i k
i 2-N28-3 f .
C
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N' A
C
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~~4m t@A P!LGRIM STATION UNIT 1~~
~~O ~~~
9 P.ECIRCULATIC.'i I?iLET C P-lic 2-N2C-1 (D.M.)
2-12C-2 Y G R
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7 2-42C-2 0
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(t[5 j PILGRIM STATION UNIT 1 O PeabEyTesting RECIRCULATION INLET 0 P-14d 2-N2D-1 (D.M.)
2-N20-2 f N
N2D V
r x 2-N20-4 %
l k
2-N20-3 C'
l f
2-N20-6 2-N2D-5 t J N' 3
o h
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PILGRIM STATION UNIT 1 g p98 00\/.E Tg RECIRCULATION INLET E P-14e 2-N2E-1 (0.M.)
. L 2-N2E-2 .$
X '
a e i N2E P y :e , y, 2-N2E-4 u 4
2-N2E-3 0
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1 PtLGRIM STATION UNIT 1 -
O NaEM*G asctacutarioN ourter A P-1s 2-NIA-1 (D.M.)
2-NIA-3 y
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l 1
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h PILGRIM STATION UNIT 1 Pee 658yTestr.g ascracutArton tnter F e-1se N
2-N27-1 (o.M.)
L 2-N2F-2 ./
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RECIRCULA' ION INLET H P-15h 2-N2H-1 (0,gy 2-N2H-2 K%
i R N2H P il V
2-N2H-4 W 2-N2H-3 l
2-N2H-5LD L 2-N2H-5 2-N2H-6 2-H8-3
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e) PILGRIM STATION UNIT 1 Q Y b RECIRCULATION INLET K P 15k 2-N2K-1 (D.M.)
2-N2K-2 8/~
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,w, 7 ..
POECOGy WG REctacutATtoN INLET J P-15j 2-N2J-1 (0.M.)
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ML19344E318

Text

a

- = =

e c - b o== .E .- a

C t C S1 3 . E es ed E s =

> > e >e > > >s>s > . =.

* en a. 3 e == * =.=* t= 3 e == C == w

.

.

= .= b 6 - 6 C g. e t e e 3 e

t= e w == ec .

=

o "*.

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