ML20052E655
| ML20052E655 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/05/1982 |
| From: | Morisi A BOSTON EDISON CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| 82-113, NUDOCS 8205110311 | |
| Download: ML20052E655 (54) | |
Text
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9-BOETON ED150 N COMPANY GENERAL Orrects 800 BayLaTON STREET BOSTON, MASSACHUSETTS 02199 A. V. M O RISI MANAGER fiay 5,1982 NUCLE AR OPERATIONS BUPPORT DEPARTMENT BECo. Ltr. #82-113 i
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conmission Washington, D. C.
20555 Li cens e' o. ! DPR -f Doc e't':No750-293 Request for Additional Information for N'
Pilgrim Nuclear Power Station's ISI Program l
.gf g 1 Reference a) NRC Letter dated February 22, 1982,
)
' C [ #[ N i
Mr. D. B. Vassallo to Mr. A. V. Morisi(.
ecy;,
ch
Dear Sir:
A Q
In response to your letter Reference a) requesting Boston Edison Company (BECo) to submit additional information concerning the Inservice Inspection Program for Pilgrim Nuclear Power Station, BECo would like to submit the following in-formation:
1.
Code Relief #2 This code relief request applies to a total of 15 pipe welds of category B-J, l
item B4.5, in the following systems:
i Main Steam Reactor Core Isolation Coolant Feed Water Core Spray Residual Heat Removal High Pressure Coolant Injection Reactor Water Cleanup The ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition throuch the Summer 1975 Addenda, requires that these Class I welds be volumetrically exami ned.
Relief is requested from volumetrically examining these 15 pipe welds because they are located in triple-flued heads and are inaccessible.
l At the time of design there were no examination requirements for these welds.
These 15 pipe welds are part of 495 pipe welds of category B-J, item B4.5, g
in the above systems, and all of the other pipe welds are inspected as part of the Inservice Inspection Program.
The following additional information is requested:
(a) Please clarify in the program table where this particular code relief is requested. For the Residual Heat Removal System, the lines as l
identified in Code Relief #2 description do not totally agree with the tabl e.
8205110311 820505 i
PDR ADOCK 05000293 G
PDR l
1 C D ",TO N EDCON COMPANY Mr. Domenic B. Vassallo, Chief May 5, 1982 Page 2~
(b) Describe-the leak detection systems that would serve, and their proximity to, the areas in which these 15 pipe welds are located.
(c) Discuss the capability of the bellows sleeve to withstand the full dynamic effects of a longitudinal or circumferential break of the enclosed process pipe, including jet impingement, pipe whip impact, and environmental effects.
If previously discussed in submittals to NRC, document by reference.
(d) Do any of the 15 pipe welds involve the welding of dissimilar metals?
1.
Response to questions concerning Code Relief #2 (a) The table has been corrected to reflect where the particular code relief is being requested.
The tables for the Residual Heat Removal System have also been revised to agree with the code relief #2 description.
(b) In response to questions concerning the leakage detection system BECo is providing copies of the Final Safety Analysis Report which describes the function of the leak detection system.
(Attachment 1)
Incl uded with the description are the system diagrams (Fig. 4.10-1 and Fig. 4.10-2) which depict the location of the floor and equipment drain sumps.
(c) In response to the question about the capability of the bellows sleeve to withstand the full dynamic effects of a longitudinal _or circumferen-tial break of the enclosed process pipe.
An engineering evaluation _is in progress and the results will be forwarded to your office upon completion.
(d) In response to the question concerning dissimilar metal welds; there are none located within these penetrations.
A review of the ISI drawings will l
substantiate that material classification on either side of containment are similar metals.
Examples:
ISI M-252 - Core spray A & B - Material classification 10 "-DC-14 l
l
- Clean-up system - Material classification 6"-EA-12
- Residual heat removal - Material classification 18"-DC-10
- Residual heat removal - Material classification 20 "-EL-10 In addition to your questions, BECo has also revised the table to include one main steam drain line penetration that should have been included in the original program. Also, a revised copy of the piping penetration drawing is being submitted along with the requested information.
t CO~, TON EDICON COMPANY Mr. Domenic B. Vassallo, Chief May 5, 1982 Page 3 2.
Code Relief #5 This code relief request applies to the calibration block used in the per-formance of ultrasonic examinations of the reactor vessel. Relief is re-quested from changing standards from the present unclad calibration block to clad blocks.
The following additional infonnation is requested:
(a) What experimental evidence will support the premise that the use of an unclad calibration does not significantly affect the validity of the examination results?
(b) Identify in program table by Section XI category number and by Section XI item number, where this relief is requested.
2.
Response to questions concerning Code Relief #5 The request for code relief concerning the use of an unclad calibration standard for the ultrasonic examinations of the reactor vessel is withdrawn by BECo.
3.
Code Relief #6 This code relief request applies to the calibration blocks used in the performance of ultrasonic examinations. Relief is requested from machined notches in the calibration block.
The following additional information is requested:
(a) Identify in program table by Section XI category number and by Section XI item number, where this relief is requested.
1 (b) Discuss your capability to detect planar and near surface flaws.
3.
Response to questions concerning Code Relief #6 (a) Attachment (2), Program Table, has been marked to indicate where the code relief is being applied.
(b) Attachment (3) is a memo prepared by Magnaflux Quality Services discussing the capability of BECo to detect planar and near surface flaws.
4.
Code Exenption #1 This code exemption applies to pressure retaining welds and support components, Categories B-0, B-J, and B-K-2, pursuant to IWB-1220(b) (1) (Surmier 1975 Addenda), in the following systems:
COSTON Eos QN COMPANY Mr. Domenic B. Vassallo, Chief May 5, 1982 Page 4 Reactor Pressure Vessel Main Steam Reactor Recirculation Stand-by Liquid Control Exemption'from examination for line sizes 3-irches and under is claimed.
The following additional information is requested:
Pursuant to IWB-1220(b) (1), show that under the postulated conditions of loss of coolant from the component (for which exemption is claimed) during normal reactor operation, tne reactor can be shut down and cooled down in an orderly manner assuming makeup is provided by the reactor coolant makeup system only, and the makeup system is using onsite power.
If previously discussed in submittals to NRC, document by reference.
4.
Response to question concerning Code Relief #1 Attachment (4) is the calculation sheets that allow for the exemption of pipe 3 inches and smaller for inspection.
We trust the above information is responsive to your needs; however, should you require any additional information please do not hesitate to contact us.
Very truly yours, I
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ATTACHMENT 1 PNPS 4.10 NUCLEAR SYSTEM LEAKAGE RATE LIMITS Total Icalage rate consista of all leakage, identified and unidentified which flows to the drywell floor drain and 4.10.1 Safety Objective equipment drain suinps.
Nuc! car system leakage rate limita are established so The criterion for utablishing the total leakage rate that appropriate action can be taken before the integrity of limit is based on the makeup capability of the control rad the nuclear system process barrier is unduly compromised.
drive (CRD) system. The CRD system supplies 63 gpm into the bottom of the reactor vessel using either one of the two 4.10.2 Safety Des.gn Bases CRD pumps. The total leakage rate limit is therefore The safety des.ign bases for nuclear system leakage rate e=tablished at 63 gpm.
limita are as follows:
The total Icakage rate m set low enough to prevent 1.
The nuclear system leakage rate limita shall be set so 1
f the drywell sumps. The equipment drain surap
'"U w that corrective action can be taken:
(capacity 500 gallons) and the floor drain sump (capacity Before the nuc! car system process barrier is
.500 gallons), which collert all Icalage, are rach dramed 3 a.
tw 50 gpm pumps. The totalleakage rate limit is therefore threatened with significant compromise.
below the remosal capacity of the two pumps m ca h b.
Before the rate of leakage exceeds the coolant nump. Further,,t is unlikely that the totallrakage would di i
3, makeup capability.
g, Before the total leakage rate within the drywell c.
exceeds the capability for leakage removal from Each pump has an alarm system and automatic pump the drywell.
starting acquence on rising water lesel, which act> as follows: At the first high water lesel wtting ("high"), tv 2.
Means shall be provided for the detection of leakage rates so that corrective action can be taken before the MM d M d 6 p ie h a automatic pump selector Eitch) is automatically started.
7 mtegnty of the nuc! car system pmcess barner is d.
unduly compromised.
..On off" lights indicate the operational status of each pump. If the water lesel runtinuc* to rig. a higher water lesel netting ("high high") starts the nerond pump. A 4.10.3 Description further ric in water lesel to the final high water lesel The leakage considered in this subsection is limited to
<t ting ("high-high-high") actuates an alarm.
that water and steam released from the nuclear system Hy obsersing the sump disc harge now meteringinstr.s-process barrier inside the primary containment. This mentation, a high level alarm can be ascribed to either D
released water and steam, after condensation,is rollected in failure of one or both pump or to excessise leakage in'o the drywell Coor drain and/or equipment drain sumps.
the sump. On decreasing lesel, * 'ow"lewel and " low-low" O
Nuricar system Irakage inside'the dry well is treated here lesel witche, shut-down pump, and actuate alarm if purrp separately from leakage el rwhere in the station because it fail, to hut.down. respertisely.
O can not be invntigated locally or imlated from the reartor b the water which has been rollerted m the sumps in O
vessel during power operation.
- pumped out, the diu harge flow from carh ump i.
Figurn 4.10-1 and 4.10 2 are diagrams of the drywell indisidually metered by now integrator >.Totalleakage ra.e leak detection e3 stem and of the dry well sumps, resper-i periodically ralculated from these now integratorn and a tisely. As shown in the figurn, there arr two drywell record i, maintained in order to detect increases in total sumps. One sump, the dn well equipment drain sump, leakage rate.
receives drainage from pump seat leak-offs, reactor vnsel head Gange seal leak.off, selected valve. tem leak off 4.10.3.1 Identified Leakage Rate.
including recirculation loop and main steam isolation The identified leakage rate i, the sum of s!I rompo.
valves, and other equipment drains through directly con-nrnt leakage rol!<cted from identified mourcem. In general, nected dnin lines. The second sump, the Door drain.
these murce. drain to the dr> well equipment drain sump collector sump, reccises leakage etc., from the dr>well which has a coser and a rai cd curb to present floer coolers, control rod drives, other sehr stems and Danges, drainage from intermixing with the equipment drainage.
Door drains, and clowd cooling water system drains.
l.calage from the reactor ses=1 head Dange gasket is piped Collection of leakage in excess of normal background to a co!!cetion chamber and then to the equipment drain amounts is potentially indicative of a reactor coolant leal..
. ump. The chamber filling time is periodically timed during The discharge lines from the equipment drain sump and station operation and the Gange gasket leakage rate can bc
)
Coor drain sump to the radwaste system are prosided with calculated. A more detailed discussion of this instrumenta.
How meters, prnsure indicators and samp!c points outside lion is in the subsection 7.8, "Heactor Veswl Instru-cf the primary containment.
mentation." Most vahes and the recirculation pumps in the 4.10 1 g.m.
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1 PNPS
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nuclear system inside the drywell are equipped with double 4.10.4 Safety Evaluation
)
seals. Ieakage from these seals is piped to the equipment The unidentified leakage rate limit is based, with an
/
drain sump. The recirculation pump scata are instrumented adequate margin for conting;encies, on the calculated as shown in the subsection 4.3, Reactor Recirculation Icakage from a crack farge enough to propagate rapidly.The System." Main steam relief valve leakage is identified by established limit is sufficiently low so that even if the entire temperature sensors in the valve discharge piping. Such unidentified leakage rate were' coming from a singic crack in leakage would collect in the suppression pool as steam the nuclear system process barrier, corrective action could leakage is condensed.
be taken before the integrity of the. barrier is threatened with significant compromise.
4.10.3.2 Uni:!cntified Leakage Rate The limit on total lealaf;e rate is established so that in The unidentified leakage rate is the sum of allicakage the absence of off. site a< power and feedwater, and collected from unidentified sources. These sources drain to without using the core standby cooling systems, the leakage the drywell floor drain sump.
lose from the nuclear system could be replaced. Either one A threat of significant compromir.c to the nuclear of the two CRD pumps can furnish the required makeup system process barrier exists if the barrier contains a crack flow rate. The limit on total leakage also allows a which is large enough to pmpagate rapidly. The unidenti.
reau nable margin below the discharge capability of either ficd Irakage rate is limited because of the possibility that the floor drain or equipment drain sump pumps. Thus, the rnost of the unidentified Irakage rate might be emitted established total ic4kage rate allows sufficient time fcr from a single crack in the nuc! car system proces barrier.
correctise action to be taken before either the nuclear A leakage rate of 150gpm has been consenatiseJy optem coolant makeup or the drywell sump re noval calculated to be the minimum liquid leakage from a crack capabilities are exceeded.
~
large enough to propagate rapidly. An allowance for Prosided in the description in a discussion of the re:3nnable Icakage which does not compromise barrier Ic4Lage detection instrumentation. With this information it integrity and la not identifiable is made for normal is shown that means are provided for the detection of 3
operation.
Icalage u> that corrective action can be taken before the The unidentified leakage rate limit is ntablished at integrity of the nuclear system process barrier is unduly 15 gpm which ia far enough helow the 150 gpm leslage rate compromiard. It is concluded that the safety design bases J
to cllow time for corrective action to be taken before the are met.
pmecan barrier is significantly compromiaed.
Condennation fmm the drywc!! atmosphere occun as 4.10.5 In9ection and Testing the atmosphere is circulated through the drywcIl coolers.
Ilecauw the sump pumps are automatically started ani o
This condensation is co!!ccted and piped to the divwc!!
their operation is verified by the alarms and discharge flow floor drain sump. Fluid leakage imm the priman presure in trumentation, no special inspection or testing during boundary will ecsult in merca ed cooling loads on the power operation of the station is necessary. The pumps an.1 dn well air coolers which will result n abnormal temper-controls are inspected and tested during schedule.1 O
ature measurements on the cooling units The condensation shutdow n..
on the coolen willincrece and abnormally high condennate p
flows to the floor drain sump will rnuit Condenaation on 4.10.6 Opcentional Nuclear Safe Requirements 0
the drywell walls and structures withm the priman
\\latrn 3 of 4ppendis G dmm. a requireme ic r containment will ahn collect m the floor dram sump. The nm lear prem leakage rate indication in
- tate. C. D ani integrated flooc drain sump flow, the dn well atmo.phere F during planned operation. Thi> matni enin il1 on the pec*ure and temperature. the dn wel! atmosphere humid.
matris under piem SI) indicate, that the leakage mdice ity, and the dn =ctl air coolet temperaturn are all tion
- mu-t be continunudy operable in ca.h state The employed as indicators of potent 2al leakage from the a<tual hmits ob ened within the priman contamment an-1 primary prewre boundarv.
the method, of indication are divuued in the per<cding de cription section.
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d 'LL E.QOIP M ENT OR FLocit B R. A LN 50MP (S et Fia. 9. 2.2 )
PILGRIE NUCLEAR POWER STATION
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FINAL SAFETY ANALYSIS REPORT Dnweu Samps, Disp.:n FIGUR E 4.10 2
- - - - ~ - -
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ATTACHMENT 2 1
Boston Pilprim.Nuc!c L l E(lison Power. Statio; l,
Company 1
INSERVICE INSPECTION PROGRAM Unit - 1 j
System:
REACTOR PRESSURE VESSEL Page 1 of 4 Rev.
Section P&iD Section XI No.
- e j
Line or Component and O
XI Item item of IIxam
$I J
Description Co-ord. 5 Category Number Description Itenn Method Ek Remarks 3
Pressure retaining welds 1
B-A Bl.1 longitudinal and circum-7 volu-Code Relief #6 in reactor vessel beltline ferential welds in core metric
+
[
region region j
j Pressure retaining welds 1
B-B Bl.2 longitudinal and circum-22 volu-Code Relief #6 1
in vessel ferential welds in shell metric l
and meridional and circum-j ferential seam welds in i
bottom head and closure 3l head l
Pressure retaining welds 1
B-C Bl.3 vessel to flange and head 2
volu-Code Relief #6 to flange and head to to flange metric flange f
Full penetration welds of l
1 B-D Bl.4 primary nozzle to vessel 34 volu-Code Relief #6 2
nozzles in vessel welds and nozzle inside metric Y
radiused section i
{
Pressure retaining partial 1
B-E Bl.5 vessel penetrations in-187 visual Note: Inspection conducted penetration welds in vessel cluding control rod drive (TWA in accordance with and instrumentation pene-5000 IWA 5000 i
trations 4
Pressure retaining welds -
l' f
1.)
Recirculation 252 1
B-F Bl.6 nozzle to safe end welds 12 volu-Code Relief #6 metric e
I 2.)
Core Spray 242 1
D-F Bl.6 nozzle to safe end welds 2
and f
sur-face N
i I
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5 Boston Pilgrim -Nucle-Edison Power-Statior:
Company INSERVICE INSPECTION PROGRAM Unit - I,
[V I
I' System: REACTOR PRESSURE VESSEL Page 2 of 4 Rev.
Section P&lD Section XI No.
W
[
Une or Component and G
XI Item Item of Exam
)
Description Comrd. N Category Number Description Items Method Ea Remarks I
Pressure retaining welds Code Relief #6
[
cont'd.
3.)
Main Steam (* Note 1) 252 1
B-F Bl.6 nozzle to safe end welds 4
volu-
- Note 1: These are not
(
metric dissimilar metal welds, but and for identification and sur-inspection requirements will face be classified as safe end welds 4.)
Feedwater (* Note 1) 252 1
B-F Bl.6 nozzle to safe end welds Code Relief #6 I
5.)
C.R.D. Return 252 1
B-F Bl.6 nozzle to safe end welds 1
Cut & capped
)
)
6.)
Jet Pump Inst.
252 1
B-F Bl.6 nozzle to safe end welds 1
Code Relief #6 I
Pressure retaining bolting 1
BC-1 Bl.7 reactor pressure vessel 56 volu-2" and larger in metric t
l 1
BG-1 Bl.7 closure studs and nuts when *
- Represents number removed t
removed
/
1 BG-1 Bl.7 ligaments between threaded Code Relief #6 0
stud holes
[
l BC-1 Bl.7 closure washers 56 visual L
1 BG-1 Bl.7 closure bushings 12 Visual examination for
(
bushings of removed studs
[
only.
U 0j 9
+ = = = =.
= +
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O
O Hoston Pilgrim. Nucle.
Edison Power. Station Company INSERVICE INSPECTION PROGRAM Unit, - 1 A
t i
e.
REACTOR PRESSURE VESSEL Page 3 of 4
.sey.
System:
Section P&ID Section XI No.
'M Line or Component and O
XI Item Item of Exam ikscription Co-ord. 5 Category Number Description items Methad Ea Remarks Pressure retaining bolting 1
BG42 Bl.ll pressure retaining 12 visual smaller than 2" in diameter L
(head spray)
(-
Vessel supports 1
B-H Bl.12 integrally welded vessel 1
volu-Code Relief #6 netric j
Interior clad surfaces 1
BI-l Bl.13 closure head cladding 6
aone CR3 of reactor vessel head i
Internal of vessel 1
BI-1 Bl.14 vessel cladding 6
aone CR3 f
Vessel interior 1
BN-1 Bl.15 interior of reactor vessel visual k
Vessel interior 1
BN-2 Bl.16 integrally welded core
'tisual i
l supports and interior
{
attachments to reactor g
vessel 1
l Removable core support 1
BN-3 Bl.17 N/A N/A y
structures o
A Pressure retaining welds 1
B-O Bl.18 Control rod drives 145'risual EX-]
in control rod drive housings
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4
(f Boston Pilgrim. Nucle Edison Power. StatioI Company INSERVICE INSPECTION PROGRAM Unit - 1 I
I of 4 System:
REACTOR PRESSURE VESSEL page Rev.
Section P&lD Section XI No.
- c Une or Component and G
XI Item item of Exam Category Number Description items Method E. 4 Remarks Ducription Co-ord.
t-p Control rod drive housing 1
B-P' Bl.19 C.R.D. housing bolting 145 visual *
- Visual during hydro only
- bolting r
Lines less than 1" EX2 Lines between 1" and 2" EX1 Steam lines between 1" and 3" t,
Drain line from C.R.D.
EX2 return - 1"
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Boston Pilgrim. Nucle, i
Edison Poiver. Statior J
Company INSERVICE INSPECTION PROGRAM Unit - 1 System: MAIN STEAM Page 2 of 4 Rev.
I Section p&lD Section XI No.
p Line or Component and Q
XI Item item of Exam j g.
a Description Co-ord.
A Category Number LWeription Items Method n,
Remarks 1
1 Loop "B" (cont'd.)
252 1
B-J B4.5 longitudinal and cir-CR2 In accessible weld in cumferential pipe welds penetration i-
{
1 B-J B4.7 branch pipe connection 1
sur-welds 6" in diameter and face I
smaller 1
B-J B4.8 socket welds 3
EX2 f
'l B-K-2 154. 1 0 support components is visual 1
B-M-1 B6.6 pressure retaining welds N/A 1
in valve bodies 1
I 1
B-M-2 B6.7
- 1) valve bodies (main stean 2
visualCR7 i
q
{
isolation valves) i 4
1 B-G-2 B6.9 relief and safety valve, visual
- nember of valves with i
main isolation valve bolting bolting Loop "C" 252 1
B-F B4.1 safe end to pipe welds 1
volu-Code Relief #6 I
metric visual 4
1 B.i B4.5 longitudinal and circum-17 volu-R6 Code Relief #6 ferential pipe welds metric 3
2 1
B-J B4.5 longitudinal and circum-R2 In accessible weld in ferential pipe welds penetration
]
1 l
4
Pilgrim.Nucle Boston Edison Power. Station Company INSERVICE INSPECTION PROGRAM Unit, - 1 t
System:
MAIN STEAM Page 1 of 4 Rev.
Section P&lD Section XI No.
g_
q Line or Component and O
XI Item item of Exam
./
Description Coord. G Category Number Description Itenn Metliod 32, Remarks loop "A" 252 1
B-F B4.1 safe end to pipe welds 1
volu-Code Relief #6 metric visual 1
B-J B4.5 longitudinal and circum-19 volu-CR6 Code Relief #6 ferential pipe welds metric 1
B-J B4.5 longitudinal and circum-CR2 Inaccessible weld in a
ferential pipe welds penetration 1
B-J B4.7 branch pipe connection 2
surf-welds 6" in diameter and face smaller 1
B-J B4.8 socket welds 3
EX2 I
[
1 B-K-2 B4.10 support components 7
visual h
1 B-M-1 B6.6 N/A i;
1 B-M-2 B6.7
- 1) valve bodies ( main steam 2
visual CR7
)
isolation valves) 0 1
B-G-2 B6.9 relief and safety valve visual
- number of valves with bolting, main steam bolting isolation valve bolting Loop "B" 252 1
B-F B4.1 safe end to pipe welds 1
volu-Code relief #6 metric visual 1
B-J B4.5 longitudinal and circum-18 volu-CR6 Code relief #6 ferential pipe welds metric q
Edison Power. Station Company INSERVICE INSPECTION PROGRAM Unit - 1 t
System:
MAIN STEAM Page 3 of 4 Rev.
Section P&lD Section XI No.
W Line or Component and O
XI Item item of Exam Description Coord. O Category Number Description items Method E. ",
Remarks I
Loop "C" (cont'd) 252 1
B-J B4.7 branch pipe connection 2
sur-welds 6" in diameter and face smaller 1
B-J B4.8 socket welds 3
EX2 1
B-K-2 B4.10 support components 8
visual 1
B-M-1 B6.6 pressure retaining welds N/A in valve bodies i
l 1
B-M-2 B6.7
- 1) valve bodies (main 2
visual CR7 steam isolation valves) 1 B-G-2 B6.9 relief and safety and main visual
- number of valves with
}
steam isolation valve bolting bolting Loop "D" 252 1
B-F B4.1 safe end to pipe welds 1
volu-Code Relief #6 metric sur.
1 1
B-J B4.5 longitudinal and circum-22 In accessible weld in l
forential pipe welds penetration l
I 1
B-J B4.7 branch pipe connection 2
sur-welds 6" in diameter and face smaller k
3
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Boston Pilgrim Nucleat Edison Poict Station Company INSERVICE INSPECTION PROGHAM Unit - 1 t
Systam: MAIN STEAM Page Page 4 of 4 Rev.
Section P&lD Section XI No.
Line or Component and G
XI Item item of Exam $[
Dcscription Co-ord. $
Category Number Description items Method
?. 2, llemarks Loop "D" (Cont'd.)
252 1
B-J B4.8 socket welds 3
EX2 1
B-K-2 B4.10 support components 9
bisual 1
B-M-1 B6.6 pressure retaining welds N/A in valve bodies 1
B-M-2 B6.7
- 1) valve bodies (main 2
visual CR7 steam isolation valves) 1 B-G-2 B6.9 relief and safety, and visual
- number of valves with main steam isolation bolting valve bolting Drain Line 3" 252 1
B-J B4.5 longitudinal and cir-11 EX1 I
cumferential. pipe welds 1
B-J B4.5 longitudinal and cir-CR2 In accessible weld in cumferential pipe weld penetration 1
B-J B4.8 socket welds 5
EX1 1
B-M-2 B6.7 valve bodies - isolation 2
visualCR7 k
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Boston Pilgrim Noci;al Edison Poder Station i
INSERVICE INSPECTION PROGRAM Unit - 1 Company
~
System:
REACTOR RECIRCULATION Page 1 of 2 Rev.
Section P&ID Section XI No.
W Une or Component and O
XI Item item of Exam Description Co-ord. A Category Number Description items Method nA Remarks Loop "A" 252 1
B-J B4.1 safe end to pipe welds 6
volu-Code Relief #6 metric sur-face 1
B-J B4.5 circumferential and long-37 volu-Code Relief #6 itudinal pipe welds metric 1
B-J B4.6 branch pipe connection 7
volu-Code Relief #6 welds greater than 6" metric diameter 1
B-J B4.7 branch pipe connection 2
sur-welds 6" diameter and face smaller t
1 B-J B4.8 socket welds 7
EX1 1
B-J B4.10 support components 15 ' visual 1
B-G-1 B5.3 pressure retaining volts 18 volu-metric 1
B-K-1 B5.4 integrally welded supports 3
volu-(pump casing) metric 1
B-K-2 B5.5 support components 3
visual 1
B-L-1 B5.6 pump casing welds 1
CR 10 1
B-M-2 B6.7 valve bodies 4
visual CR7
/
Bosten Pilgrim. Nucle Edison Power.Statioi Company i
INSERVICE INSPECTION PROGRAM Unit, - 1
)
System: REACTOR RECIRCULATION Page 2 of 3 Rev.
Section P&lD Section XI No.
x
- Line or Component and O
XI Item Item of Exam g.
Description Co-ord.
Category Number Description items Method na Remarks Loop "B" 252 1
B-J B4.1 safe end to pipe welds 6
volu-Code Relief #6 metric sur-face
[
l B-J B4.5 cf.rcumferential and long-37 volu-Code Relief #6 itudinal pipe welds metric 1
B-J B4.6 branch pipe connection 6
volu-Code Relief #6.
welds exceeding 6" diamete r metric 1
B-J B4.7 branch pipe connection 2
sur-Code Relief #6 welds 6" diameter and face smaller 1
B-J B4.8 socket welds 7
EX1 e
i 1
B-K-2 B4.10 support components 15 sur-face 1
B-G-1 B5.3 pressure retaining bolts 18 volu-metric 1
_b-K-1 B5.4 integrally welded supports Code Relief #6 (pump casing)
.I 1
B-K-2 B5.5 support components 3
visual i
1 B-L-1 B5.6 pump casing weld 1
CR
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10 l
1 B-L-2 B5.7 pump casing 1
visual CR8' k
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Pilgrim b'tected Boston Power. Station Edison Company INSERVICE INSPECTION PROGRAM Unit - 1 System:
CONTROL ROD DRIVE Page 1 of 1 Rev.
Section P&lD Section XI No.
- e
'j Line or Component and O
XI Item item of Exam Description Co-ord. $
Category Number Description Itens Method 9,4 Remarks 6" Scram discharge 250 2
C-F C2.1 circumferential butt 3G volu-Code Relief #6 headers H-2 metric H-3 f
2 C-F C2.2 longitudinal pipe welds 16 volu-Code Relief #6 I
in fittings metric 2
C-F C2.3 branch pipe to pipe welds 2
volu-Code Relief #6 metric C. R. D. Return Line 250 1
B-J B4.'5 circumferential and 5
volu-Code Relief #6 longitudinal pipe welds metric 1
B-J B4.7 branch pipe connection 1
sur-welds 6" diameter and face l
smaller 1
B-M-2 B6.7 Valve bodies 2
CR7 EX2 1
B-J B4.8 socket welds 1
Visual 1.
k I
t l
I.
Pil, grim. Nucle Boston Edison Power. Sintio.
Company INSERVICE INSPECTION PROGRAM Unit - I
~
[
t
- System:
FEEDWATER Page 1 of 2 Rev.
Section Section XI No.
4 P&lD
$[
(
Line or Component and O
X!
Item Item of Exam l
Description Co-ord. 5 Category Number Description items Method E.a Remarks Ii l
Loop "A" 12" diameter 252 1
B-F B4.1 safe end to pipe welds 2
volu-Code Relief #6 metric y
surfac(
g 1
1 B-J B4.5 circumferential and long-20 volu-CR6 Code Relief #6 itudinal pipe welds metric I
1 B-J B4.6 branch pipe connection 1
volu-CR6 Code Relief #6 welds exceeding 6" dia-metric meter 1
B-K-2 B4.10 support components 4
visual Loop "A" 18" diameter 252 B-J B4.5 circumferential and long-14 volu-CR6 Code Relief #6
)
itudinal pipe welds metric 1
B-J B4.5 circumferential and long-CR2 Inaccessible weld in 1
itudinal pipe welds.
B-J B4.7 branch pipe connection 1
EX2 I
welds 6" in diameter and smaller 5
3 1
B-J B4.8 socket welds 1
EX2 l
1 B-K-2 B4.10 support components 6
visual I
1 B-M-2 B6.7 valve bodies 3
visual CR7 1
t
Pilgrim Nucich Boston Edison Poder Station i
INSERVICE INSPECTION PROGRAM Unit,- 1 Company System:
FEEDWATER Page 2 of 2 Rev.
Section P&lD Section XI No.
- c une or Component and O
XI
- Item Item of Exam Description Co-ord.
Category Number Description Itenn Mctliod E2, Remarks Loop "B" - 12" diameter 252 1
B-F B4.1 safe end to pipe welds 2
volu-Code Relief #6 metric and sur-face 1
B-J B4.5 circumferential and long-20 volu-CR6 Code Relief #6 itudinal pipe welds metric 1
B-J B4.6 branch pipe connection 1
volu-CR6 Code Relief #6 welds exceeding 6" diamerc r metric 1
B-K-2 B4.10 supports components 4
visual Loop "B" - 18" diameter 1
B-J B4.5 circumferential and long-16 volu-CR6 Code Relief #6
}
itudinal pipe welds metric 1
B-J B4.5 circumferential and long-CR2 Inaccessible weld in itudinal pipe welds penetration 1
B-J B4.6 branch pipe connection 2
volu-CR6 Code Relief #6 welds exceeding 6" diameter metric 1
B-J B4.8 socket welds 1
EX2 1
B-K-2 B4.10 support components 6
visual 1
B-M-2 B6.7 valve bodies 2
visual CR-Examine when disassembled for maintenance or repairs l
Boston Pi!2 rim Nucleg iidison Power Station Company INSERVICE INSPECTION, PROGRAM Unit - 1 System: RESIDUAL HEAT REMOVAL Page 1 of 14 Rev.
1 Section P&lD Section XI No.-
.:c.
Line or Component and Q
XI Item
!!cm of Exam g
Description Co-ord.
Category Number Description llenn Method n:1 Remarks RHR "in" - LPCI-LOOP "A"
'241 1
B-J' B4.5 circumferential and 14 volu-CR6 Code Relief #6 from M0 1001-29A to 28" C-6 lonnitudinal welds metric main recire. disch. Loop A 1
B-J B4.5 circumferential and CR2 Inaccessible weld in longitudinal welds penetration-1 B-J B4.8 socket welds 7
EX2 1
B-K-2 B4.10 support components 5
visual 1
B-M-2 B6.7 valve bodies 3
visualCR7 l RHR "in" - LPCI-LOOP "B" 241 1
B-J B4.5 circumferential and 17 volu-CR6 Code Relief #6 from MO 1001-29B to 28" C-4 longitudinal welds metric main recire, disch. Loop B 1i B-J B4.5 circumferential and CR2 Inaccessible weld in longitudinal penetration 1
B-J B4.8 socket welds 7
EX2 1
B-K-2 B4.10 support components 5
visual RHR Heat Exchangers 241 2
C-A C1.1 circumferential butt welds 8
volu-CR6 Code Relief #6 A-7 (vessel to flange) metric 2
C-B C1.1 s nozzle to vessel welds 4
volu-
~R6 Code Relief #6 A
metric i
2 G-C C1.3 intergrally welded supports 8
surfac e 2
C-D Cl.4 pressure retaining bolts 64 none 3R9 Note: visual inspection of bolts will be conducted during hydro "A" Pump discharge (12")
241 2
C-G C2.1 Circumferential butt welds 12 volu-R6 Code Relief #6 A-6 met ric
~
~
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longitudinal weld joints 1
volu-
- R6 Code Relief #6 2
C-G C2.2 in pipe fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-4 metric 1
2 C-E-2 C2.6 support components 2
visual i
e e.mm T
Pilgrim Nacleal
- oston Powcr Station.
1:51ison Company INSERVICE INSPECTION PROGRAM Unit - t i
System:
RESIDUAL HEAT REMOVAL Pat:c 2of14 Rev.1 l
Section P&lD Section XI No.
E Line or Component and O
XI Item Item of Exam
-@ g.
Description Co-ord. 5 Category Number Description items Method E. P..
Remarks "C" pump discharge (12")
241 2
C-G' C2.1 circumferential butt welds 12 volu-Code Relief #6 B-4 metric 2
C-G C2.2 longitudinal weld joints 1
volu-Code Relief #6 in pipe fittings me tric 2
C-G C2.3 branch pipe to pipe welds 0
volu-netric 2
C-E-2 C2.6 support components 2
visual "B" pump disch. (12")
241 2
C-G C2.1 circumferential butt welds 12 volu-Code Relief #6 A-4 metric 2
C-G C2.2 longitudinal pipe welds 1
volu-Code Relief #6 in-fitting metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-metric 2
C-E-2 C2.6 support components 2
visual "D" pump disch. (12")
2,41 2
C-G C2.1 circumferential butt welds 12 volu-Code Relief #6 R-4 metric I
2 C-G C2.2 longitudinal pipe welds 1
volu-Code Relief #6 in-fitting metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-motric 2
C-E-2 C2.6 support components 2
visual 16" to E-207A 241 2
C-G C2.1 circumferential. butt welds 11 volu-Code Relief #6 B-6 metric 2
C-G C2.2 longitudinal pipe welds 1
volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 2
visual
Pi!rilm Nuclead itost on l'ower Stitti liltson Unit - 1 company INSERVICE INSPECTION PROGRAM h
i System:
RESIDUAL HEAT REMOVAL Page 3 of 14 Rev. 1 Section P&lD Section XI No.
..L Une or Component and O
XI Item Item of Exam i$
Description Co-ord. N Category Number Description items Method E.2 Remarks 16" to E-207B 241 2
C-C C2.1 circumferential butt welds 12 volu-Code Relief #6 B-4 metric 2
C-G C2.2 longitudinal pipe welds 1
volu-in fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-metric 2
C-E-2 C2.6 support components 3
visual 16" From E-207A 241 2
C-G C2.1 circumferential butt welds 4
volu-Code Relief #6 B-6 metrle 2
C-G C2.2 longitudinal weld joints 1
volu-Code Relief #6 in fi ttin gs metric 2
C-G C2.3 branch pipe to pipe welds 1
volu-Code Re11e1 Fb metric 2
C-E-2 C2.6 support components 0
visual 16" From E-207B 241 2
C-G C2.1 circumferential butt welds 4
volu-Code Relief #6 B-4 metric 2
C-G C2.2 longitudinal weld joints 1
volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support cdmponents 1
visual 18" "A" Loop discharge 241 2
C-G C2.1 circumferential butt welds 28 volu-Code Relief #6 M-3 metric to 2
C-G C2.2 longitudinal pipe welds 3
volu-Code Relief #6 A4Z in fittings netric 2
C-G C2.3 branch pipe to pipe welds 3
volu-Code Relief F6 metric 2
C-E-2 C2.6 support components 13 visual i
n a
re-m Pil rim Nucicat f
lioston 14tison Power Flation -
Company INSERVICE INSPECTION PROGRAM Uni' o I t
lRev.
i 1
. System:
RESIDUAL HEAT REMOVAL Page 4 of 14 Section P&lD Section XI No.
- c une or Component and Q
XI Itciii Item of Exam Description Co-ord. O Category Number Description items Metliod E f.,
Remarks 18" "B" Loop discharge 241 2
C-C '
C2.1 circumferential butt welds 29 volu-Code Relief #6 in to MD-1001-29A M-3 metric to 2
C-G C2.2 longitudinal pipe welds 3
volu-Code Relief fl6 A-2 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 3
volu-Code Relief #6 metric l2 C-E-2 C2.6 support components 10 visual "A" Suction 241 2
C-G C2.1 circumferential butt welds 24 EX3 6
2 C-G C2.2 longitudinal pipe welds S
EX3 in fittings 2
C-G C2.3 branch pipe to pipe welds 0
EX3 2
C-E-2 C2.6 support components 9
EX3 "C" Suction 2,41 2
C-G C2.1 circumferential butt welds 21 EX3 Af6 2
C-G C2.2 longitudinal pipe welds 3
Pl3 in fitting 2
C-G C2.3 branch pipe to pipe welr' O
TX3 2
C-E-2 C2.6 support components 6
EX3 "3" Suction 241 2
C-G C2.1 circumferential butt welds 21
?X3 A-4 2
C-G C2.2 longitudinal pipe welds 4
sX3 in fittings 2
C-G C2.3 branch pipe to pipe welds O
EX3 2
C-E-2 C2.6 support components 6
EX3
w Pill' rim Nuclead 11oston Power Sfalion litison Company INSERVICE INSPECTION PROGRAM Unil. *l t
t Sya.icm:
RESIDUAL HEAT REMOVAL l'.tgo 5 of 14 llev.
I Section P&ID Section XI No.
.:e Une or Comhn:nt and O
XI Item item of Exam Description Co-ord. 5 Category Number Description items Method
?. 2, Remarks "D" suction 241 2
C-G C2.1 circumferential butt welds
'25 EX3 B-4 2
C-C C2.2 longitudinal pipe welds 6
EX3 in fittings 2
C-G C2.3 branch pipe to pipe welds O
EX3 i
2 C-E-2 C2.6 support components 9
EX3 18" from "A" suction to 241 2
C-G C2.1 circumferential butt welds 6
volu-Code Relief #6 20" X 18" reducer B-5 metric and 2
C-G C2.2 longitudinal pipe welds 3
volu-Code Relief #6 A-6 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 1
volu-Code Keliet Fb metric 2
C-E-2 C2.6 support components 2
visual 20" suction cross con-441 2
C-G C2.1 circumferential butt welds 34 volu-Code Relief #6 nection to Loop "B" from B-5 metric loop "A" 20" X 18" reducer A-5 2
.C-G C2.2
. longitudinal pipe welds 15 volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-metric 2
C-E-2 C2.6 support components 20 visual 18" from "C" suction 241 2
C-G C2.1 circumferential butt welds 4
volu-Code Relief #6 to branch connectiotr T-5 metric 2
C-G C2.2 longitudinal pipe welds in 3
volu-Code Relief #6 fitting metric 2
C-G C2.3 branch pipe to pipe welds 2
volu-Code Relief F6 metric 2
C-E-2 C2.6 support components 2
visual
~,
Pilt rim N aoston l'ower.StLiion Pdison Company INSERVICE INSPECTION PROGRAM Unit - 1 j
t System:
RESIDUAL llEAT REMOVAL l' age 6 of 14 Rev. 1 Section PAID Section XI No.
- c Line or Component and G
XI Item item of Exam Description Co-ord. M Category Number Description items Metlied 32 Remarks 18" from "B" suction to 241 2
C-G C2.1 circumferential butt welds 4
volu-Code Relief #6 branch connection A-5 metric 2
C-G C2.2 longitudinal pipe welds 3
volu-Code Relief #6 in fitting metric 2
C-G C2.3 branch pipe to pipe welds 2
volu,
Code Relief #6 metrid 2
C-E-2 C2.6 support components 2
visual 18" from "D" suction 241 2
C-G C2.1 circumferential butt welds 6
volu-Code Relief #6 to 20" X 18" reducer A metric 2
C-G C2.2 longitudinal pipe welds 3
volu-Code Relief #6 in fitting metric 2
C-G C2.3 branch pipe to pipe welds 1
volu-Code Relief #6 metric j
2 C-E-2 C2.6 support components 2
visual s
4" flushing line "A" 241 2
C-G C2.1 circumferential butt welds 6
EX4 suction to N29K A-5 2
C-G C2.2 longitudinal pipe welds 2
EX4 in fittings 2
C-G '
C2.3 branch pipe to pipe welds 1
EX4 7
4" flushing line "C" 241 2
C-G C2.1 circumferential butt welds 2
EX4 suction to N29K
-B-5 2
C-C C2.2 longitudinal pipe welds 2
EX4 in fitt: ngs 2
C-C C2.3 branch pipe to pipe welds
]
EX4 i
e
- , Y
- Ir.
P
Pilgrilli Niidicar
};e.s(int I:. ti. n n Power.Stiilion Company INSERVICE INSPECTION PitOGRAM Unit - i t
Page 7 of 14 Rev. 1 stem:
RESIDUAL HEAT REMOVAL Section PalD Section XI No.
W Line or Component and O
XI Item item of Exam Description Co-ord. $
Category Number Description items Method E"
Remarks 4" flushing line "B" 241 2
C-G C2.1 circumferential butt welds 2
EX4 suction to N29K A-5 2
C-G C2.2 longitudinal pipe welds 2
EX4 in fittings 2
C-G C2.3 branch pipe to pipe welds 1
EX4 4" flushing line "D" 241 2
C-G C2.1 circumferential butt welds 2
EX4 suction to N29K B-5 2
C-G C2.2 longitudinal pipe welds 2
EX4 in fittings 2
C-G C2.3 branch pipe to pipe welds 1
EX4 "RHR" "OUT" from 241 2
C-G C2.1 circumferential butt welds 3
volu-Code Relief #6 mo-1001-47 to suction crosac-5 metric connection 2
C-G C2.2 longitudinal pipe welds 2
volu-Code Relief #6 in fittings metric
{
2 C-G C2.3 branch pipe to pipe welds 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 2
visual Code Relief #6 10" containment spray loop 241 2
C-G C2.1 circumferential butt. welds 20 volu-Code Relief #6 "A"
D-4 metric C-3 2
C-G C2.2 longitudinal pipe welds 10 volu-Code Relief #6 C-4 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-2 C-E-2 C2.6 support components
/
visual s
i
l'ilr. rim N,itelcar{
U.stoi l'4li:.nin l'O Wdr.S,taljoH Company INSEllVICE INSPECTION PitOGilAM lhill - I t
{
System:
RESIDUAL HEAT REMOVAL P3Ce 8of14 Rev.
1 Section w
P&lD Section XI No.
_g$
{
i _.
Line or Component and O
XI Item Item of Exam Description Co ord. 5 Category Number Description Items Method E?
Remarks 10" containment spray 241 2
C-G C2.1 circumferential butt welds 31 volu-CR6 Code Relief #6 loop "B" metric 2
C-G C2.2 longitudinal pipe welds 15 volu-CR6 Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe welds 0
volu-metric 2
C-E-2 C2.6 support components 14 visual 4" head spray nozzle 241 2
C-G C2.1 circumferential butt welds 33 EX4 flange from MO-1001-60 D-6 2
C-G C2.2 longitudinal pipe welds 18 EX4 in fittings 2
C-G C2.3 branch pipe to pipe welds 1
EX4 2
C-E-2 C2.6 support components 21 EX4 2
C-D C2.4 pressure retaining bolting EX4 g
4" head spray nozzle 241 1
B-J B4.5 circumferential and long-42 volu-CR6 Code Relief #6 flange from MD-1001-60 D-6 itudinal pipe welds metric i
1 B-J B4.5 circumferential and long-1 CR2 Inaccessible weld in
{
itudinal pipe welds penetration i
1 B-K-2 B4.10 support components 4
visual 1
B-M-2 B6.7 valve bodies 3
visualGR/
{
1 B-G-2 B4.12 pressure retaining bolting 16 visual surface 1
i RHR "out" to MO-1001-47 241 1
B-J B4.5 circumferential and long-34 volu-CR6 Code Relief #6 C-5 itudinal pipe welds metric l
1 B-J B4.5 circumferential and long-CR2 Inaccessible weld in
~
itudinal pipe welds penetration 1
1 B-K-2 B4.10 support components 4
visual 1
B-M-2 Bb. 7 valve bodies 3
visual CR]
t i
Pilgriin Nitelearl 11osten Power Stittien Edison Company INSERVICE INSPECTION PROGRAM Unit - i System:
RESIDUAL HEAT REMOVAL Page 9 of 14 Rev. 1 Section P&lD Section XI No.
p_,
Line or Component and Q
XI Item item of Exam jj; Description Co-ord. n Category N imber Description items Method
- r. ",
itemarks Loop "A" 12" line to torus 241 2
C-G C2.1 circumferential butt welds 28 EX3 test line C-6 C-7 2
C-G C2.2 longitudinal weld joints 10 EX3 2
C-G C2.3 branch pipe to pipe weld 2
EX3 2
C-E-2 C2.6 support components 9
EX3 Loop "A" 6" line to torus 241 2
C-G C2.1 circumferential butt welds 17 EX3 spray C-6 C-7 2
C-G C2.2 longitudinal weld joints 8
EX3 2
C-E-2 C2.6 support components 5
EX3 Loop "B" 12" line to torus 241 2
C-G C2.1 circumferential butt welds 25 EX3 test line d6 p
C-7 2
C-C C2.2 longitudinal weld joints 9
EX3 2
C-G C2.3 branch pipe to pipe weld 1
EX3 2
C-E-1 C2.6 support components 6
EX3 Loop "B" 6" line to torus 2
C-C C2.1 circumferential butt welds 11 EX3 spray 2
C-C C2.2 longitudinal weld joints 5
EX3 2
C-G C2.3 branch pipe to pipe weld 1
EX3 2
C-E-2 C2.6 support components 2
EX3 d
h sto n Pilgrim Niidear Edison Power Stntion Company INSERVICE INSPECTION PROGRAM Unit - !
System:
RESIDUAL HEAT REMOVAL Page 10 of 14 Rev.
1 Section PalD Section XI No-
.. _g$
-j Line or Component and Q
XI Item item of Exam Description Co ord. 3 Category Number Description
!! cms Method na Remarks 18" tie line Loop "A" to 241 2
C-G C2.1 circumferential butt welds 29 volu-Code Relief #6 Loop "B" B-3 metric 2
C-G C2.2 longitudinal weld joints 7 volu-Code Relief #6 7
metric 2
C-G C2.3 branch pipe to pipe welds 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 6
visual 6" fuel pool connection 241 2
C-G C2.1 circumferential butt welds 23 volu-Code Relief #6 from 18" tie line to N26 B-4 metric 2
C-G C2.2 longitudinal weld joints 13 volu-Code Relief #6 in fittings metric i
k 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 15 visual 4" chemwaste receiver 241 2
C-G C2.1 circumferential butt welds 3
EX4 line to MD-1001-32 B-4 2
C-G C2.2 longitudinal weld joints 1
EX4 2
C-G C2.3 branch pipe to pipe weld 1
IX4 2
C-E-2 C2.6 support components 1
IX4
-eummmI
it...tiin l'ilgilm Nihicat Power Siniion nti.on Company INSEltVICE INSI)E(TI'lON l'ilOGitAM Unit o 1 t
System:
RESIDUAL HEAT REMOVAL Page 11 of 14 Rev. 1 Section PalD Section XI No.
-@y Une or Component and Q
XI Item Item of Exam g
Description Co-ord. 5 Category Number Description items Method E2, itemarks 6" Line from RHR "out" to 241 2
C-G C2.1 circumferential butt welds 20 volu-Code Relief #6 fuel pool N29 metric 2
C-G C2.2 longitudinal weld joints 10 volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support cusponents 9
visual 6" torus make-up from 241 2
C-G C2.1 circumferential butt welds 7
EX3 condensate to A0-8000 C-3 2
C-G C2.2 longitudinal weld joints 2
volu-'
Code Relief #6 metric 1
{
2 C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric 18" Service water to dis-M-241 2
C-G C2.1 circumferential butt welds 34 volu-Code Relief #6 charge cross connection H-5 metric 2
C-G C2.2 longitudinal weld joints 19 volu-Code Relief #6 in fitting metric 2
-C-E-2 C2.6 support components 11 visual
=-
I'll; tim Nudeaf l'. c.t o n t
1:du>n Ib w er sihii.in Company INSERVICE INSPECTION PROGRAM Unit - I
~
t System:
RESIDUAL HEAT REMOVAL Page 12 of 14 Rev.
Section PalD Section XI No..
.- _g[
i Line or Component and O
XI Item item of Exam Description Co-ord. N Category Number Description items Method E 2, Remarks 16" heat exchanger line 241 2
C-G C2.1 circumferential butt welds 5
volu-Code Relief #6 diccharge loop "A" B-7 metric (E 207A) 2 C-G C2.2 longitudinal weld joints 1
volu-Code Relief #6 metric 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric 16" heat exchanger line 2
C-G C2.1 circumferential butt welds 5
volu-Code Relief #6 discharge loop "B" metric (E-207B) 2 C-G C2.2 longitudinal pipe welds 1
volu-Code Relief #6 metric
'g 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric Loop "A" 12" line to torus 241 2
C-G C2.1 circumferential butt welds 28 EX3 test line C-6 10 EX3 C-7 2
C-G C2.2 longitudinal weld joints 2
C-G C2.3 branch pipe to pipe weld 2
EX3 2
..C-E-2
.C2.6 support components 9
EX3 Loop "A" 6" line to torus 241 2
C-G C2.1 circumferential butt welds 17 EX3 spray C-6 C-7 2
C-G C2.2 longitudinal weld joints 8
EX3 2
C-E-2 C2.6 support components 5
EX3 i
i
ik; ton Pilgritu Nudcar 1:dison Power Station Company INSERVICE INSPECTION PROGRAM Uriit i
System:
RESIDUAL HEAT REMOVAL Page 13 of 14 Rev.
Section P&1D Section XI No.
W f$
Line or Component and XI Item Item of Eum Description Comrd.
Category Number Description Items Method n 2, Remarks Loop "B" 12" line to torus 241 2
C-G C2.1 circumferential butt welds 25 EX3 test line C-6 C-7 2
C-G C2.2 longitudinal weld joints 9
EX3 2
C-G C2.3 branch pipe to pipe weld 1
EX3 2
C-E-1 C2.6 support components 6
EX3 Loop "B" 6" line to torus 241 2
C-G C2.1 circumferential butt welds 11 EX3 spray C-6 C-7 2
C-G C2.2 longitudinal weld joints 5
EX3 2
C-G C2.3 branch pipe to pipe weld 1
EX3 2
C-E-2 C2.6 support components 2
EX3 18" tie line Loop "A" to 2'41 2
C-G C2.1 circumferential butt welds 33 volu-Code Relief #6 Loop "B" B-3 metric to B-7 2
C-G C2.2 longitudinal weld joints 7
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 6
visual 6" fuel pool connect _ ion.,
,_241 2
. C--G.
C2.1 circumferential butt welds 24 volu-Code Relief #6 from 18" tie line to N26 B-4 metric 2
C-G C2.2 longitudinal weld joints 13 volu-Code Relief #6 in fittings metric
. Baston Pilgdm Nucicar liti. son Power Sthfion Company INSERVICE INSPECTION, PROGRAM Unit - I r
System:
RESIDUAL HEAT REMOVAL Page 14 of 14 Rev.
1 SCClion i
P&lD Section XI No_
.. -4 Line or Component and O
XI Item item of Exam i g.
l Description Co-ord. 5 Category Number Description items Method E. ",
Remarks 6" fuel pool connection 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 from 18" tie line to N26 metric (continued) 2 C-E-2 C2.6 support components 15 visual 4" chemwaste receiver 241 2
C-G C2.1 circumferential butt welds 3
EX4 line to MO-1001-32 B-4 2
C-G C2.2 longitudinal weld joints 1
EX4 2
C-G C2.3 branch pipe to pipe weld 1
EX4 i
i 2
C-E-2 C2.6 support components 1
EX4 6" line from RHR "out" to 241 2
C-G C2.1 circumferential butt welds 21 volu-Code Relief #6 fuel pool N29 g5 metric
{
2 C-G C2.2 longitudinal weld joints 10 volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric i
)
2 C-E-2 C2.6 support components 9
visual 6" torus make-up from i
condensate to AO-8000
,241 2
..C -G.
C2.1 circumferential butt welds 7
EX3 C-3 2
C-G C2.2 longitudinal weld joints 2
volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric
Boston Pilgrim Nudcal Edison Power,Slation Company INSERVICE INSPECTION PROGRAM Unit o 1 t
System:
REACTOR WATER CLEAN-UP Page 1 of 1 Rev.
Section P&ID Section XI
,No.
g _,
Une or Componu t and O
XI Item Item of Exam E. g Description Co-ord. 3 Category Number Description items Method P.,
Remarks Reactor water clean-up 247 1
B-J B4.5 circumferential and long-42 volu-CR6 Code Relief #6 water in from MO-1201-80 D-4 itudinal pipe welds metric (4" to 6" line) to D-7 1
B-J B4.7 branch pipe connection 1
sur-welds 6" diameter and face smaller 1
B-K-2 B4.10 support components 8
visual 1
B-M-2 B4.7 valve bodies 3
visual CR7 Reactor water clean-up 247 1
B-J B4.5 circumferential and 39 volu-CR6 Code Relief #6 "out" to 1201-5'(6" line) longitudinal pipe welds metric 1
B-J B4.5 circumferential and:
CR2 Inaccessible weld in longitudinal pipe welds penetration 1
B-J B4.7 branch pipe connection 1
sur-welds 6" diameter and face smaller 1
B-K-2 B4.10 support components 2
visual 1
B-M-2 B6.7 valve bodies 3
visual CR7 i
130ston Pilgrim Noeled Edison Pawer Station Company INSERVICE INSPECTION PROGRAM Unit - l t
System:
REACTOR CORE ISOLATION COOLANT Page 1 of 2 Rev. 1 i'
Section PAID Section XI No.
Ss.
Line or Component and O
XI Item item of Exam i $
Description Co-ord.
Category Number Description items Method E 2, Remarks Steam supply line main 245 1
B-J B4.5 circumferential and long-25 volu-CR6 Code Relief #6 steam J ine "C" to 1301-17 C-6 itudinal pipe welds metric C-7 1
B-J B4.5 circumferential and long-CR2 Inaccessible weld in
~
itudinal pipe welds penetration 1
B-J B4.7 branch pipe connections 1
sur-6" and smaller face 1
B-K-2 B4.10_
support components 2
visual Pump discharge f rom 1301-245 1
B-J B4.5 circumferential and long-l'8 volu-CR6 Code Relief #6 49 to reactor water clean-C-5 itudinal pipe welds metric up (4" line) 1 B-J B4.7 branch pipe connections 1
volu-R6 Code Relief #6 smaller than 6" metric g
I 1
B-K-2 B4.10 support components 2
, visual Turbine exhaust - from 245 2
C-C C2.1 circumferential butt. welds 4
volu-CR6 Code Relief #6 1301-64 to torus (8")
B-5 metric A-5 2
C-G C2.2 longitudinal pipe welds in 1
volu-CR6 Code Relief #6 fittings metric 2
C-E-2
.C2.6 support components 1
visual 3
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I!oston Pilgrim Nudcas Edison POW'r S.tation Company INSERVICE INSPECTION PROGRAM Unit - 1 t
System:
CORE SPRAY Page 1 of 3 Rev.
I Section PalD Section XI No.
.. q$
Line or Component and O
XI Item Item of Exam Description Co-ord. M Category Number Description llems Method E ",,
Remarks Loop "A" 10" from 242 1
B-J B4.5 circumferential and long-25 volu-CR6 Code Relief #6 MO-1400-25A to reactor C-6 itudinal pipe welds metric C-7 1
B-J B4.5 circumferential and long-CR2 Inaccessible weld in itudinal pipe welds penetration 1
B-K-2 B4.10 support components 3
visual 1
B-F B4.1 safe end to pipe and 3
volu-CR6 Code Relief #6 dissimilar metal welds metric surf.
Loop "B" - 10"'from 242 1
B-J B4.5 circumferential and long-27 volu-CR6 Code Relief #6 MO-1400-25B to reactor C-6 itudinal pipe welds metric C-7 1
B-J B4.5 circumferential and long-CR2 Inaccessible weld in itudinal pipe welds penetration 1
B-K-2 B4.10 support components 3
visual 1
B-F B4.1 safe end to pipe and 3
volu-dissimilar metal welds metric surf.
, "A" in to MO-1400-25A 242 2
C-G C2.1 circumferential butt welds 38 volu-CR6 Code Relief #6 metric.
from pump 215A 2
C-G C2.2 longitudinal weld joints in fittings 17 volu-CR6 Code Relief #6 metric 2
.C-D C2.4 pressure retaining bolting CR9 2
C-E-2 C2.6 support components 11 visual e
Pilgrim Nuclead thiston Power Statism tiggson Company INSERVICE INSPECTION PROGRAM Unit - I t
System:
CORE SPRAY Page 2 of 3
, IIcy.
Section P&lD Section XI No.
gi,.
Line or Component and O
XI Item llem of Exam E.g Description Co-ord. 5 Category Nuniber Description items Method Rer.iarks "B" in to MO-1400-25B 242 2
C-G C2.1 circumferential butt welds 30 volu-Code Relief #6 B-4 metric
- 4' 2
C-G C2.2 longitudinal weld joints 11 volu-Code Relief #6
-5 in ittings metric C-6 2
C-D C2.4 pressure retaining bolt-CR9 ing 7
C-E-2 C2.6 support components 9
visual Loop "A" - MO-1400-25A, C-6 1
B-M-2 B6.7 valve bodies.
3 CR7 A0-9A, 1400-6A C-7 Loop "B" - MD-1400-25B, C-6 1
B-M-2 B4.7 valve bodies 3
CR7 A0-9B, 1400-6B C-7 i
Loop "A" torus to pump d,42 2
C-G C2.1 circumferential butt welds 18 EX3 215A-18" line B-5 2
C-G C2.2 longitudinal weld joints 5
EX3 in fittings 2
C-E-2 C2.6 support components 5
EX3 Loop "B" torus to pump 242 2
C-G C2.1 circumferential butt welds 18 EX3 215B - 18" line 2
C--G C2.2 longitudinal weld joints 6
EX3 in fittings 2
C-E-2 C2,6 support components 5
EX3 e
f i;,,. ton l'iintim Nucleas i
g,t.on l'ower Station Company INSERVICE INSPECTION PROGRAM Unit - l Systern:
CORE SPRAY Page 3 of 3 Rev.
Section P&lD Section XI No.
4@g.
Line or Component and O
XI Item item of Exam Description Co-ord.
Category Number Description items Metliod Ea Remarks 12" line to condensate 242 2
C-G C2.1 circumferential butt welds 1
EX3 storage from 18" suction B-5 to valve 29K-Loop A 2
C-G C2.3 branch pipe to pipe weld 1
EX3 12" to condensate stor-242 2
C-G C2.1 circumferential butt weld 1
EX3 age to valve 29K fr'om 18" A-3 suction Loop "B" 2
C-G C2.3 branch pipe to pipe weld 1
EX3 6" test line to RHR test 242 2
C-G C2.1 circumferential butt welds 13 volu-Code Relief #6 lina from Loop "A" dis-C-5 metric charge B-5 B-6 2
C-G C2.2 longitudinal weld joints 2
volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe weld 2
volu-Code Relief #6 joints metric 2
C-E-2 C2.6 support components 1
visual 6" test line to RHR test 242 2
C-G C2.1 circumferential butt welds 13 volu-Code Relief #6 line from Loop "B" dis-C-5 metric charge B-5 B-6 2
C-G C2.2 longitudinal weld joints 2
volu-Code Relief #6 in fittings metric
~
~
2 C-G
'C2.3 branch pipe to pipe veld 2
volu-Code Relief #6 joints metric
l'ill'.iiiii Nutled i t..,t o n i,n:.n l'.nwr.si.ainn Company INSEltVICE INSPECTION PitOGitAM Unit l
~
t System:
HIGH PRESSURE COOLANT INJECTION.
hge 1 of 3 Rev. 1 J
Section PAID Section XI No.
4 Line or Component and G
XI Item llem cf Exam
-@ g.
Description Co-ord. 5 Category Number Description llems Method E.2 Remarks 14" line to feedwater 243 1
B-J B4.5 circumferential and long-23 volu-CR6 Code Relief #6 Loop "B" - water in from B-6 itudinal pipe welds metric MO-2301-8 1
B-J B4.6 branch pipe to pipe weld 1
volu-CR6 Code Relief #6 metric 1
B-K-2 B4.10 support components 6
visual 1
B-M-2 B6.7 valve bodies 2
visual CR7 10" steam supply line from 243-1 B-J B4.5 circumferential and long-23 volu-CR6 Code Relief #6 main steam line "D" to C-6 itudinal pipe welds metric MD-2301-5 1
B-J B4.5 circumferential and long-CR2 Inaccessibic weld in itudinal pipe welds penetration 1
B-J B4.6 branch pipe to pipe weld volu-CR6 Coda Relief #6 metric 1
B-K-2 B4.10 support components visual 1
B-M-2 B6.7 valve bodies visual CR7 10" steam supply to turbinc 243 2
C-F C2.1 circumferential butt welds 30 volu-CR6 Code Relief #6 from MO-2301-5 C-3 metric C-5
,C-,4 2
C.- F C2.2 longitudinal pipe welds in 12 volu-CR6 Code Relief #6 B-3 fittings metric 2
C-F-C2.3 branch pipe to pipe weld 1
volu-CR6 Code Relief #6 metric 2
C-E-2 C2.6 support components 8
visual a
Pil: rim NtideauJ lioston i
i:.dison l' wer Station Company INSERVICE INSPECTION PROGRAM Unit - I t
System: HIGH PRESSURE COOLANT INJECTION P3EC 2 of 3 Rev. I Section P&lD Section XI No.
_. - -.g$
Une or Component and O
XI Item Item of Exam Description Co-ord. 5 Category Number Description items Method E2, Remarks 20" Turbine exhaust 243 2
C-F C2.1 circuraferential butt welds 36 volu-Code Relief #6 B-4 metric to 2
C-F C2.2 longitudinal pipe welds 12 volu-Code Relief #6 B-7 metric i
2 C-F C2.3 branc.' pipe to pipe weld 2
volu '
Code Relief #6 metric 2
C-E-2 C2.6 support components 7
visual Water in f rom pump to 243 2
C-G C2.1 circumferential butt welds 33 volu-Code Relief #6 2301-8 B-5 me tric B-6 2
C-G C2.2 longitudinal pipe welds in 15 volu-Code Relief #6 fitting metric i
k 2
C-D C2.4 pressure retaining bolts 18 visual surface 2
C-E-2 C2.6 support components 11 visual Suction from torus to 243 2
C-F C2.1 circumferential butt welds 29 EX1 Pump P-205 A-5 to 2
C-F C2.2 longitudinal pipe welds in 10 EX:
A-7 fitting
~
1r-5 2
C-D C2.4 pressure retaining bolts 16 EX]
C-4 C-5 2
C-E-2 C2.6 support components 5
EXJ 3
I'll, tim Nucleac l
1:,..! o n l'elima Power Station Company INSERVICE INSPECTION PROGRAM Unit.1 r
System:. IIIGil PRESSURE COOLANT INJECTION Page 3 or 3 Rev.1 Section PalD Section XI No.
4 Line or Component and O
Xi Item llem of Exam i g.
Description Co-ord. $
Category Number Description items Mettiod E. 2, Remarks Condensate storage to 243 2
C-F C2.1 circumferential butt welds 12 EX3 suction branch connection C-4 from MO-2301-6 2
C-F C2.2 longitudinal pipe welds in 5
EX3 fittings 2
C-F C2.3 branch pipe to pipe weld 1
i EX3 2
C-E-2 C2.6 support components 4
EX3 4" f rom water "in" RIIR 243 2
C-F C2.1 circumferential butt welds 22 EX3 test line B-5 A-5 2
C-F C2.3 branch pipe to pipe weld 2
EX3 2
C-E-2 C2.6 support components 5
EX3 10" from 2301-10 (RCIC ff3 2
C-G C2.1 circumferential butt welds 10 volu-Code Relief #6 test line-to "IIPCI" water C-G metric "in" 2
C-G C2.2 longitudinal pipe welds 4
volu-Code Relief #6 in fittings metric 2
C-G C2.3 branch pipe to pipe weld 1
volu-Code Relief #6 metric 2
C-D C2.4 pressure retaining bolting 16 visual surfac e 2
C-E-2 C2.6 support components 3
visual
Boston Pilgrim Niideas Edison Power Station Company INSERVICE INSPECTION PROGRAM Unit - 1 t
I, Rev.
System:
STAND-BY LIQUID CONTROL Page 1 of 1 Section PalD Section XI No.
.._.h Une or Coraponent and O
XI Item item of Exam eg.
Description Co-ord. !!
Category Number Description
!! ems Method E.4 Remarks 1 " line from 1106-A 249 1
B-J B4.8 socket welds 36 EX1 and 1106-B (squib valves)
C-7 to reactor vessel B-7 1
B-J B4.1 safe end to pipe welds 1
EX1 i
1 B-K-2 B4.10 support components 2
i EX1 l
1 B-M-2 B6.7 valve bodies 2
visual CR7 2 " suction to pump "A"
249 2
C-G welds 16 EX4 2 " suction to pump "B" 249 2
C-G welds 7
EX4 Discharge to Squib Valves 249 2
C-G welds 44 EX4 2 " to T-206 2'A9 2
C-G welds 3
EX4 3" to collection system 249 2
C-G welds 13 EX4 1
ae ease e me*
4
Pilgrim Nucle:
Bostoit l'dison Powcr Station Company INSERVICE INSPECTION PROGRAM Unit - l System:
CONTAINMENT ATMOSPilERIC CONTROL SYSTEM Page 1 of 2 Rev.
Section PalD Section XI No.
'g._,
Line or Component and O
XI Item item of Exam i$
Description Co-ord. 5 Category Number Descriptica items Method E"
Remarks 4" Nitrogen Purge supply M-227 2 C-G C2.1 circumferential butt welds 17 volu-Code Relief #6 line D-2 metric 2
C-G C2.2 longitudinal weld joints 11 volu-Code Relief #6 in fittings metric i
2 C-G C2.3 branch pipe to pipe welds 1
volu-Code Relief #6 metric 2
C-E-2 C2.6 support components 6
visual Drywell Purge Air to M-227 2 C-G C2.1 circumferen,tial butt welds 4
volu-Code Relief #6 Penetration X-25 metric 2
C-G C2.2 longitudinal weld joints 2
volu-Code Relief 76 in fittings metric j
2' C-G C2.6 support components visual Drywell Purge Air to M-227 2
C-G C2.1 circumferential butt welds 10 volu-Code Relief #6 Penetration metric 2
C-G C2.2 longitudinal weld joints in 4
volu-Code Relief #6 fittings metric 2
C-E-2 C2.6 support components 1
visual
Boston Pilgrim Nude:
Edison PJwer Station Contpany INSERVICE INSPECTION PROGRAM Unit
- 1 2
System:
CONTAINMENT ATMOSPHERIC CONTROL SYSTEM Page 2 of 2 Rev.
Section P&ID Section XI No.
.p.
j$
Une or Component and Q
XI Item item of Exam Category Number Description Items Method n 2, Remarks Description Co-ord.
20" Lone to torus penetra-M-22]
2 C-G C2.1 circumferential butt welds 10 volu-Code Relief #6 tion X-205 C-2 metric C-3' C-4 2
C-G C2.2 longitudinal weld joints ir 4
volu-Code Relief #6 fittings metric 2
C-E-2 C2.6 support components 1
visual 20" line to torus penetra-M-227 2
C-G C2.1 circumferential butt welds 16 volu-Code Relief #6 tion D-6 metric D-7 C-6 2
C-G C2.2 longitudinal weld joints 4
volu-Code Relief #6 C-7 in fittings metric 2
C-E-2 C2.6 support components 2
visual 1
\\
t
..y[g g M AGNAFLUX Corporation l 230 Murphy Road l Hirtford. CT 06114 l Td; phon 3203 522-3253 ATTACHMENT 3
~
MSNAFLUX O.uclhyServices To:
F. N. Famulari Date: March 17, 1982 RE: Docket No. 50-293 Request for additional information Paragraph 3 Code Relief #6 (b)
Ultrasonic examinations at Pilgrim Nuclear Power Station have been conducted using side drilled holes to form the Distance Amplitude Correction Curve during the first inspection interval. During this interval, there has been one documented unacceptable indica-tion (weld 3-I-3, CRD Re-route).
Radiographic investigation con-firmed the presence of the unacceptable planar flaw.
An informational ultrasonic examination, utilizing the side-drill-ed hole calibration, of the Class 2 Core Spray modification de-tected an unacceptable condition in one of the welds. Radiogra-phic investigation again confirmed the presence of the unacceptable planar flaw.
In addition, all Level II and Level III ultrasonic technicians utilized in manual ultrasonic examination of piping are trained on the EPRI IGSCC reference blocks before performing any examina-tions at Pilgrim Nuclear Power Station.
.. _.The ultrasonic procedure for volumetric examination of piping j,_.
welds at Pilgrim Nuclear Power Station for piping thickness 1 inch and less uses the 6/8 node side-drilled hole as the primary reference. hten the DAC curve is established on side-drilled holes, the amplitude response from a Code 4/8 node (I.D.) notch is greater than the primary reference of the side drilled hole.
This comparison 1, hows that the side-drilled hole calibration is more sensitive for the half-node examination of piping welds in this thickness range.
For pipe wall thicknesses over 1 inch in thickness and greater, the procedure establishes primary reference at the 5/8 node.
This exceeds the ASME Code,Section V requirement of 3/8 node.
s hten the DAC curve is established on side-drilled holes, the amplitude response from a code 4/8 node (I.D.) notch is greater than the primary reference.
This comparison shows that the side-drilled hole calibration is more sensitive when calibrated in this manner.
GEO interna
- cna' Corporat on
.y
~.,
...., - -. m.. ;
F. N. Famulari March 17, 1982 Page 2 Magnaflux Quality Services (formerly Peabody Testing) has performed examinations utilizing this procedure during the 1977, 1980, and 1981 refueling outages.
Based on the additional operator training, elevated sensitivity levels, and the demonstrated ability to detect unacceptable con-ditions, we feel that this Code Relief Request is jutified. Addi-tion.11y, a pre-service / inservice comparison of data shows no s'.gnificant change in indication amplitudes or linear extent in the manual examinations of Pilgrim Nticlear Power Station piping welds.
/
/
Michael F. Sherwin Quality Assurance Engineer MFS/lak JL._
~ --
Y r
O n*
ATTACHtfENT 4 er'ATTICHMENT
" arch 32, 1982 nutech UMC-82-051 San Jose, California Pilgrim Unit 1 (BOS-01) 87.701.0004 File Na p
Owner Boston Edison Company Cli:nt Boston Edison Company PURPOSE:
Determine the line size (s) which can be excluded from ISI Class I surface and volumetric examination in accordance with ASME Section XI, 1974 Edition thru Summer 1975 Addenda, Article IWB-1220 (b) (1).
(b)
Components may be exempted from examination (see IWB-1220 (c) ) if any of the following conditions are met:
(1)
Under the postulated conditions of loss of coolant from the com-ponent during normal reactor operation, the reactor cun be shut down and cooled down in an orderly manne'r assuming makeup system 5 only.
However, in no instance may the size exemption be more than 3 in. nominal pipe size.
5 ormal makeup system are those
~
N systems that have the capability to maintain reactor coolant inven-tory under the respective conditions of startup, hot standby, operation or cooldown, using onsite power.
dM (1)
Exclusion inside diameter in inches, water = D
=
g 17.8 2D (2)
Exclusion inside diameter in inches, steam = D
=
(3)
M = Total make-up flow rate in gr.11ons of water per minute (gpm) 0 70*F Equations (1), (2), and (3) are taken from G.E.
document 22A2750, Page 7.
RCIC flow = 400 gpm 49 gpm (CRD Cooling Water Flow)
CRD flow
=
Condensate Transfer /Feedwater flow = 1500 gpm D" =
/400 + 49 3 1500
= 2.48 inches 17.8 l
D 2D
= 2 (2.48) = 4.96 inches '
=
g Rcosion 0
1 PaBe y m. &. _
Prepared By/Date 3/,//62 d
I Checked By/Date
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' 00!8.!P.C ifATER RCACMR SYSTFJA5 CEPARTV.ENT 22A2750 mv:n
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. 3.3.2 ISI Code. 15 121, 2:4clusions fram System Beundary.
3.3.2.1 ISI Cede.
Paragra;hs (a) and (b) incl.; ding note 1 on page 3.
CE-3* Tv.)
~
h.* uords "re.:c:c. coclant =akeup ~ sys tco" and ".her:41 cake-u.p syste:".as
..deflae9 t
.z tha cace systcm..'. ! ;....s,ysten includhs-the..:ccre.ater ptr:ps, condensate /fcc..evcter
,y -.
, transfe r purp s, cen.rol. red -drive r u :ps,' and, ~r.i:i. :or'. c..ere 'isciation ecoling.s. s t en:.
pucps. "On-site pcuer" 'is defined as electric ;outr.ncr.211y availabic en site b"
during nor:a1 opers: ion includin:;:
startup, hat standby, cr.eration, cool-dovn or chut down of the pla.t.
This includes pevar availa.21e fro: outside lines.
~
3.3.2.2 Using the e.nc-up capability as described above it is possibic ta calculate the cize of liquid and :tesa lines which arc exclud?d frc: vole:.utric ext.=inatien.
lag,i' lina.; 2rc Je.dncJ ts the.se which penetra:e the cacter pecutura vcs wi G.P.')
b:lew th.: n:rre.1 vater level and stcan lines as those hleh panecrate the RIV s'cc ee the norn.11 vater icve 1.
ister flow rate:: fron a' ligeti line break are taken as 6:C')
pounds /sec/ft2 et 1J. psi.
Stes: f1rv rates ire: a s ca: line bras'< arc :: ken es 2000 poune.;/;ec/f 2 a: 100 psi. ::ake-up watar vairhs 8.33 pcuado per gclien at 73'F.,
On this basi.i the c.sclunica diarcters are as falicv:
G
- - - - - - ~ -
- ~ - - - -
Er.clesien inside di:::ctcr in inches, water. - Dg =
17.Sv Exclusica 1:.si.'c dic=cter in inches, sten: -D3=2y ITnere:
!! a Total n.t :a1 c'he-up f t:.w rate in salicas of water per cinute (g;=)
C:r:*ai: c 3 ficu states irc= ti.e ?.cs: tor Core -Iscintion Coolln. Sy.it..g,' the C:ntrol F.od *):ive Eyate-nnd the Tce *v..:er. Syst : are used to dete:-inu ::c:...1 ::ke-up capshill:y.
the condensa eti: edvater transfer 7::.; capac::y or gravity. feti cap acity rather than Icedvater p.::p capacity is used to r.ake this at:alysis becsusc the h :va:1 volute is 11-.ite. :.a. a icv : inutes of fec:vate: pu:p cperat ien a: =.uf:-2: fiev and :h-r 1.owell vole.e =ay be ins.4 than :c.;utrud ta brine; the Rp'.' devn to ::.spnaric p:essurt:
et maxt mn er rr.al:er flcus.
Cendensate stors;:e v2:er supr. lied by ti.c crn.icn: ster fer:Jeatcr t:ansfer pc p or by 3ravity fit w vill 1e required te e.2intain fes-hier pe.::p suc ticn b. c:.: in the hotevil In this casc.
Lbic 3.3.2.2 shows r.or.21 :ske 'sp rates f:r the CFJ) and F.Cic veste.s.
Ccndencate/feedea:cr tr:nsfer rates vill haee ce be detetr.ned for cach pl. tnt.
As en e..anple for a 233 plant, a tsuci':S 1000 c;:a cc.n-densste/icedunter tr.rs'< r r. petef ty.
s/? ;' + 7 00 - 1.
- f r. -
t'W ~
17.6
,.2.35 inches dicac:.ar a.
I 72 in:hes diancter D,* 2 x 2..%
lloto that the exclusien' di'.r.eter appites 'to th'c source of the Icakage fluid. In the c...irple, a 10 inch pipe att.'i:ed to a 2 in:h pipe h leu the nort.11 vater line vauld 1,e exclud..d.
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o Coll. NG t'N(ER 221.CTOR SY5TD25 DE!*A:lTME!!T 22).2750 e$
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TN1!.E 3".3.2.2 T pical I;or:ial P.ake *Cp Cape. city f
I Vessel.._.. ~
CPD
. p.CIC -
~-1
- (Inch ~c,s) pigu.
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pj '- -
(g..pa).
.(gpa)
. picy 183 44 500 201 53 530 218 61 600 239 72 100 251 78 E00 3.3.3 Further disece.sica of the ISI code for Class I cc:ponents are found in Tahics A,11, c.ad C in Apper.iix A.
7 - 3.4 -- _Cl a :.s 2 cc r e r.en : e..
(2..;cd en !!sy 1973 draft cf 197/. ISI Code)
-. ~.. -
3.4.1 ISI Cefc.
..'C 1: M. S'.s:en Esendary: Typie:11y Cro:p L cenpenen:s in the date. cht.e. F.i.;te :.- trr: stage: to Class 2 inspectica rules and the boundarics
.for Group 5 define th.: 5eunC:ric; for Class 2.
P 3.4.2 ISI Ced2.
~':0 !?2:. C; penents within !.c ;yste= boundaries ex:=pred frc :
voluretric inspec: ion.
3.4.2.1
!he deci n r.rcssurc ci th cc _':On r.: 1; lee; than 275 esig er the 3ccis n ter:peratt:c is le a than CGC'.F.
- cte: hFC ?.ep.ul.t:er e Ceide 2.51 D'.-71973) exci.:les compenent." enly where the de:!r,n pressure in le.c; : San 275 ;sig.mn.! r.hc cesign to:perature 1; less :han 20G'F.
3.4.2.2 Co:ponents dhich do not icnction during nar=al rcactor eperatien.
~j3.4.2.3 Cc:renents hich p2:(er...n e er:'nev cere ccaline, fen::fon, and the fluid chc:11stry in contro1Jcd liy ; cried:: sr.np!ing end tests.
- 3. 4. 2. '4 Cosponent schose si:o ic.<. 4 inch or Ic.s ns.-Inal s'1p : d t:.ne t er.
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