ML20199C897
| ML20199C897 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/13/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| SBN-1110, NUDOCS 8606180360 | |
| Download: ML20199C897 (39) | |
Text
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SEABROOK STATION Engineering Offica MI
.r June 13, 1986 PubdC Service of New Hampshire NEW HAMPSHIRE YANKEE DIVISION B7.1.2 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-1072), dated May 28, 1986, "Preservice Inspection Program (PSI) (SER Outstanding Issue No. 4), Relief Requests",
J. DeVincentis to V. S. Noonan Subj ect :
Preservice Inspection Program (PSI) (SER Outstanding Issue No. 4):
Revised Relief Requests
Dear Sir:
Enclosed, herestth, please find revised Seabrook Station Unit 1 PSI Relief Requests for examinations determined to be impractical pursuant to 10CFR50.55(a)(g)S(iii). These revisions are in accordance with our ' dis-l cussions with the Staff on June 11, 1986 regarding the relief requests submitted by Reference (b). Tne revised relief requests included herewith are listed below by number en: subj ect.
l l
PR-2 P er. cir and Steam Generator Welds (Class 1)
!~
PR-4 Cla s 1./.ptng Welds l
PR-5 Pump and Valve Internal Pressure Boundary Surfaces PR-6 Steam Generator, Residual Heat Removal, and Letdown Heat Exchanger Welds
.7 PR-7 RHR Heat Exchanger Nozzles PR-9 Class 2 Piping Welds I
8606180360 860613
{~DR ADOCK 05000443' PDR_
AoV1 Seabrook Station Construction Field OfSco. P.O. Box 700. Seabrook, NH O3874 l
l f..-
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United States Nuclear Regulatory Commission Attention:
Mr. Vincent S. Noonan Page 2 These revised relief requests will become a part of the final PSI Report.
In accordance with previous discussion with the Staf f, the final report will be submitted by July 15, 1986.
We-trust that the enclosed is acceptable and request that the reso-lution of this-issue be reflected in the next supplement to Seabrook's SER.
Very trulv yours,
/
S John DeVincentis Director of Engineering Enclosure cc:
Atomic Safety and Licensing Board Service List 1
- o Diane Curran, Esquire Calvin A. Canney
'Harmon & Weiss City Manager 2001 S. Street. W.W.
City Hall Buite 430 126 Daniel Street l
Washington, D.C.
20009 Portsmouth, NH 03801 Sherwin E. Turk, Esq.
Stephen E. Merrill, Esquire Office of the Executive Legal Director Attorney General U$S. Nuclear Regulatory Commission George Dana Bisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 Office of the Attorney General 25 Capitol Street Robert A. Backus, Esquire Concord, NH 03301-6397 116 Lowell Street P.O. Box 516 Mr. J. P. Nadeau Manchester, NH 03105 Selectmen's office 10 Central Road Philip Ahrens, Esquire Rye, NH 03870 Assistant Attorney General Department of The Attorney General Mr. Angie Machiros Statehouse Station #6 Chairman of the Board of Selectmen Augusta, NE 04333 Town of Newbury Newbury, MA 01950 Mrs. Sandra Gavutis Chairman, Board of Selectmen Mr. William S. Lord RFD 1 - Box 1154 Board of Selectmen Kennsington, NH 03827 Town Hall - Friend Street Amesbury, MA 01913 Carol S. Sneider, Esquire Assistant Attorney General Senator Gordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place, 19th Floor Concord, NH 03301 Boston, MA 02108 (ATTN: Herb Boynton) l Senator Gordon J. Humphrey H. Joseph Flynn, Esquire U.S. Senate Office of General Counsel Washington, DC 20510 Federal Emergency Hanagement Agency (ATTN: Tom Burack) 500 C Street, SW Washington, DC 20472 Richard A. Hampe, Esq.
Hampe and McNicholas Paul McEachern, Esquire 35 Pleasant Street Matthew T. Brock, Esquire Concord, NH 03301 Shaines & McEachern 25 Maplewood Avenue Thomas F. Powers, III P.O. Box 360 Portsmouth, NH 03801 Town Manager
-~
Town of Exeter 10 Front Street Gary W. Holmes, Esq.
Exeter, NH 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03842
~RFD Dalton Road Brentwood, NH 03833 Mr. Ed Thomas FEMA Region I Peter J. Mathews, Mayor 442 John W. McCormack PO & Courthouse City Hall Boston, MA 02109 Newburyport, MA 01950 Robert Carrigg i
Town Office d
Atlantic Avenue North Hampton, NH 03862
~
SBN-1110 e
I Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-2 Component Identification:
Pressurizer and Steam Generator Welds Code Class:
1 Examination Category:
B-B and B-D Code Requirement:
For Seabrook Unit No. I a volumetric (ultrasonic) examination of 100 percent of the weld length and 100 percent of the nozzle inner radius areas shall be con-ducted for the following items in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum, Subarticle IWB-2500:
Item Description B2.11 Circumferential Shell-to-Head Welds (Pressurizer)
"2.12 L: ;itudir:1 Sh:11 L'cid: ("..... lecc)
B2.40 Tube Sheet-to-Head Welds (Steam Generators)
B3.30 Nozzle-to-Vessel Welds (Pressurizer)
B3.40 Nozzle Inside Radius Section (Pressurizer)
- 33. EO NOZILE To S.HLU wen t1( STnM GEk1ES.NTcP1)
Code Relief Request:
Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portions of the subject vessel welds and inner radius areas.
Basis for Relief:
Geometric configuration and permanent obstructions prohibit performance of a 100 percent volumetric examination of each of the subject welds. The PSI limitations and the specific relief as they apply to each weld, are noted in the attached table for each component.
Support for Relief / Alternate Examinations:
A.
The subject welds received both volumetric examination by radiography and surface examinations during fabrication, in accordance with ASME Section III requirements, which provide adequate assurance of the struc-tural integrity of the welds.
B.
A construction hydrostatic test was conducted successfully on the Class 1 pressure boundary, of which these welds are a part thereof, in accordance with the requirements of ASME Section III.
C.
In-service system leakage tests will be performed per Category B-P, Table IWB-2500-1 each refueling outage.
Relief Request: PR-2 Table 1 Page 2 of 5 Pressurizer Liuitations Weld Data Code Exam Technique Configuration / Limitation-CRV Identification Sheet Item Angle Coverage Number (1)
Number RC-E-10-A-NZ 6466-11.
B 3.30 45" l Vee Nozzle to Shell 75%
RC-E-10 A-NZ 6466-10 B 3.30 60*
1 Vee Nozzle toShell/#
75%
Shel1[g 75%
RC-E-10-B-NZ 6466-11 B 3.30 45*
1 Vee Nozzle to toShell/f 75%
RC-E'10-B-NZ 6466-10 B 3,30 60*
1 Vee Nozzle toShel1[g 75%
j RC-E-10-C-NZ 6466-11 B 3.30 45*
} Vee Nozzle toShel1[jf-75%
RC-E-10-C-NZ 6466-10 B 3.30 60 i Vee Nozzle toShel1[g RC-E-10-D-NZ 6466-11 B 3.30 45*
1 Vee Nozzle 75%
Shel1[g RC-E-10-D-NZ 6466-10 D 3.30 60*
i Vee Nozzle to 75%
RC-E-10-SP-NZ 6466-11 B 3.30 45*
1 Vee Nozzle to Shel1[J(L 75%
toShel1[g RC-E-10-SP-NZ 6466-10 B 3.30 60*
i Vee Nozzle 75%
-)(- Gecurve._I.L.Ct. m m e.
Relief R:qusst PR-2 Table 1 P g2 3 of 5 Pressurizer Linitations a
Technique Configuration / Limitation Co age Ang Ident i ation Number (1)
Number ShelltoShel1[#g 96%
1-RC-E-10-4 6466-6 B2.11 0*
0*
1-RC-E-10-4 6466-8 B2.11 45' Circ and Axial ShelltoShel1[f f 96%
1-RC-E-10-4 6466-7 B2.11 60*
Circ. and Axial ShelltoShell[fg 96%
1-RC-E-10-9 6466-15 B2.11 0*
0*
ShelltoUpperHead/kg 95%
1-RC-E-10-9 6466-8 B2.11 45*
Cire, and Axial Shellto-UpperHead[fi 95%
1-RC-E-10-9 6466-13 B2.11 60*
Circ, and Axial ShelltoUpperHead[f, 95%
1-RC-E-10-1 6466-9 B2.11 0*
O' LowerHeadtoShell[f 99%
i LowerHeadtoShell[Ns 79%
1-RC-E.10-1 6466-8 B2.11 45*
Cire. and Axial LowerHeadtoShell!Y, 80%
1-RC-E-10-1 6466-10 B2.11 60*
Circ, and Axial 1-RC-E-10-S-NZ 6466-15 B3.30 0*
0*
SurgeNozzletoLowerHead/.j(g 74%
1-RC-E-10-S-NZ 6466-14 B3.30 45*
Circ. and Axial SurgeNozzletoLowerHead/#g_
74%
1-RC-E-10-S-NZ 6466-13 B3.30 60*
Circ. and Axial SurgeNozzletoLowerHead[#c 74%
Surge Nozzle to Lower Head [f K.
74%
1-RC-E-10-S, Nils 6467-11 B3.40 70* Inner J.,1, Radius 1.
Data sheet number refers to data sheet containing incomplete scan, d, L% n r_n h e. To OQ. Lw_ F E. a e o c.us
-# glimTen BM G Eo u.Exu_N/MEr a s.v._ h E r anmows,
Relief of Request: T R - 2 s ',
Table 2 Page 4 of 5 Steam Generator Limitations Weld-Data Code Exam Technique Configuration / Limitation CRV Identification Sheet Item Angle Coverage Number (1)
Number
$L 1-RC-E-11A-2A-NZ 6465-42 B 3.50 45*
Jts Ve e Nozzle to Shell 75%
1-RC-E-11A-2A-NZ 6465-48 B 3.50 60*
i Vee Nozzle to Shell 75%
1 RC-E-11A-2B-NZ 6465-42 B 3.50 45 i Vee Nozzle to Shell 75%
1-RC-E-11A-2B-NZ 6465-48 B 3.50 60*
} Vee Nozzle to Shell 75%
1-RC-E-11B-2A-NZ 6465-52 B 3.50 45" i Vee Nozzle to Shell 75%
1-RC-E-11B-2A-NZ 6465-44 B 3.50 60*
} Vee Nozzle to Shell 75%
1-RC-E-11B-2B-NZ 6465-52 B 3.50 45*
1 Vee Nozzle to Shell 75%
1-RC-E-11B-2B-NZ 6465-44 B 3.50 60*
} Vee Nozzle to Shell 75%
1-RC-E-11C-2A-N2 6465-49 B 3.50 45*
1 Vee Nozzle to Shell 75%
1-RC-E-11C-2A-NZ 6465-47 B 3.50 60 i Vee Nozzle to Shell 75%
1-RC-E-11C-2B-NZ 6465-49 B 3.50 45*
1 Vee Nozzle to Shell 75%
1-RC-E-11C-2B-NZ 6465-47 B 3.50 60*
1 Vee Nozzle to Shell 75%
1 -RC-E-11D-2 A -NZ 6465-46 B 3.50 45*
i Vee Nozzle to Shell 75%
1-RC E-11D-2A-NZ 6465-50 B 3.50 60*
1 Vee Nozzle to Shell 75%
1-RC-E-11D-2B-NZ 6465-46 B 3.50 45 i Vee Nozzle to Shell 75%
1-RC E-11D-2B-NZ 6465-50 B 3.50 60
} Vee Nozzle to Shell 75%
G co mas.-I - I. B C t. n h ce.
Ralief Riqu ntt PR-2 1.4 Pag 3 5 of 5 Steam Generator Limitations echn 4ue
' Con H guration M aitation Cov age Ang Idtnt ation Number (1)
Number 1-RC-E-11A Seam 1 6465-011 B2.40 0*
O' Tubesheet to lower head. */
pg S/G supports 1-RC-E-11A Seam 1 6465-008 B2.40 45' Circ. and Axial Tubesheet to lwoer head. X[
78%
S/G supports 1-RC-E-11A Seam 1 6465-007 B2.40 60*
Circ. and Axial Tubesheet to lower head. */
58%
S/G supports and surface contour.
78%
1-RC-E-11B Seam 1 6465-034 B2.40 0*
0*
Tubesheet to lower head 2 /-
S/G supports Tubesheet to lower head W [
78%
1-RC-E-11B Sean 1 6465-036 B2.40 45*
Circ, and Axial S/G supports 1-RC-E-11B Seam 1 6465-035 B2.40 60*
Cire and Axial Tubesheet to lower head. *[
78%
S/G supports 1-RC-E-11C Seam 1 6465-036 B2.40 0*
0*
Tubesheet to lower head. */
78%
S/G supports 1-RC-E-11C Scam 1 6465-028 B2.40 45*
Circ. and Axial Tubesheet to lower head. '#[
78%
S/G supports 1-RC-E-11C Seam 1 6465-029 B2.40 60*
Cire. and Axial Tubesheet to lower head. X[
78%
S/G supports 1-RC-E-11D Seam 1 6465-020 B2.40 0*
0*
Tubesheet to lower head. K[
78%
S/G supports 1-RC-E-11D Seam 1 6465-036 B2.40 45 Cire. and Axial Tubesheet to lower head. **[
78%
S/G supports 1-RC-E-11D Seam 1 6465-021 B2.40 60*
Circ. and Axial Tubesheet to lower head. *[
78%
S/G supports 1.
Data sheet number refers to. lata sheet corttaining limited scan.
f. ; ;,- ' *
^;
SBN-1110-J-
Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice-Inspection Requirements Relief Request: PR-4 Component Identification:.
EClass 1 Piping Welds and Safe End Welds Code Class:
1 Examination Category:
B-J and B-F Code Requirement:
i For Seabrook Unit No. 1, volumetric (ultrasonic) and surface examination of 100 percent of the length of each weld in the main coolant piping system shall be conducted in accordance with the ASME, B&PV Code 1977 Edition through the
-Summer 1978 Addendum, Subarticle IWB-2500.
Code Relief Request:
Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portions'of the welds
[
listed in Table 1 attached.
Basis for Request:
Geometric configuration, permanent obstructions, and structural inter-4 ferences prohibit 100 percent volumetric exam coverage of the Code required examination volume. Relief is, therefore, requested from performing pre-l' service examinations on the inaccessible portions of the volume. required as noted in Table 1.
It should be noted that the Westinghouse developed-UT technology for cast stainless steel piping was utilized in performing all exams on the cast -
portions of the main-coolant piping. This technique was developed as a best i
effort method of examining cast stainless steel, which is a generic problem encountered in Westinghouse plants of similar design. In doing so, the i
alternate examination provisions of ASME'Section XI, Subsubarticle IWA-2240 and ASHE Section XI, Paragraph T-110(c).were evoked.
A 0* longitudinal beam examination was conducted on all cast stainless steel welds to map ID geometry contours.. This was done in addition to Section XI
~
j requirements to aid in the performance and evaluation of angle beam examina-e tion results.
Complete examinations which met the requirements of ASME Section XI were performed on welds of.similar configuration using the same inspection tech-niques, equipment and procedures as those partially. inspected or uninspected welds. Since the partially inspected or uninspected welds will see the same operating and environmental conditions as the inspected welds, a reasonable assurance of the structural integrity of the welds for which relief is re-L quested has been attained.
I i
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---v e-+.*mee
- - ~ *
-<y~~v 1,
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Ralisf Riquzst: PR-4 Paga 2 of 7 Proposed Alternative Examinations:
A.
The subject welds received both volumetric examination by radiography and surface examinations during fabrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject welds is provided.
B.
A preoperational cold hydrostatic test was conducted successfully on the Class 1 Pressure Boundary, of which these welds are a part thereof, per the requirements of ASME Section III.
C.
In-service system leakage tests will be performed per Category B-P, IWB-2500-1 as well as surface and volumetric exans on the accessible portions of the welds shown on Table 1, as required by Section XI selection criteria. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage and results and applied where deemed appropriate by New Hampshire Yankee.
1 t
I
Relicf Requgat: PR-4
\\*
P g2 3 of 7 Table 1 Pips R21d Sctn Limit.ctions Table IWB-2500-1, Category B-J. B-F Data Code Weld Sheet Item Technique Configuration / Limitation
^"E "
Identification Number (1)
Number REACTOR COOLANT MAIN LOOP PIPING Loop-1 1-RC-1-1-1 None B9.11 65 RL 1/2 Vee Axial-Safe End-to-Pipe / Metallurgy 75%
1 Direction (Safe End Side) 1/2 Vee Cire.
1-RC-2-1-2 None B9.11 40*RL Vee Elbow Side Elbow-to4 Pipe / Structural Steel 95%
Axial and Cire.
1-RC-2-1-5 None B9.11 42*RL Vee Elbow Side Pipe-to-Elbow / Structural Steel 95%
Axial and Cire.
1-RC-2-1-6 None B9.11 41*RL Vee Elbow Side Elbow-to-Pump / Surface Indentation 99%
Axial and Cire.
' "C 2 1 I "r-
"0.!!
'!*"L
( Vmm "....y Cid,
"... e tu "irc/:' tall.
3, O!
' Ci _ ; _
1-RC-3-1-3 None B9.11 40*RL Vee Elbow Side Elbow-to-Safe End/ Surface Geometry 1%
Axial and Circ.
(Elbow Side) 1-RC-3-1-3 None B9.11 None Elbow-to-Safe End/ Metallurgy 0%
(Safe End Side)
Loop-2 1-RC 1-1 None B9.11 65 RL l Vee Axial-Safe End-to-Pipe / Metallurgy 75%
1 Direction (Safe End Side) i Vee Cire.
1-RC-5-1-2 None B9.11 40*RL Vee Elbow Side Elbow-to-Pipe / Structural Steel 93%
Axial and Cire.
1-RC-5-1-5 None B9.11 40*RL h Vee Elbow Side Pipe-to-Elbow / Structural Steel 95%
Axial and Circ.
' "C C I "0.'!
'2*"'
( V
"_..c Cid;
" c.p :: "ip:/":: nil-rgy av
'..1::'"::.
1-RC-6-1-3 None B9.11 40*RL Vee Elbow Side Elbow-to-Safe End/ Surface Geometry 1%
Txial and Cire.
(Elbow Side)
R211;f Request: PR-4
'~
P ga 4 cf 7 Table 1 Pipe Weld Scan Limitations Table IWB-2500-1, Category B-J B-F Data Code CRV Weld Sheet Item Technique Configuration / Limitation Coverage An Identification Number Number I
I 0%
Loop 2 Cont.
Elbow-to-Safe End/ Metallurgy None 1-RC-6-1-3 None B9.11 (Safe End Side) l l
75%
Loop 3 Safe End-to-Pipe / Metallurgy 0 RL 3 Vee Axial-(Safe End Side) l 1-RC-7-1-1 None B9.11 65 1 Direction 3 Vee Cire.
Elbow-to-Pipe / Structural Steel 94%
1-RC-8-1-2 None 39.11 41*RL Vee Elbow Side Axial and Circ.
n'
.-;;- ^
- ~...
- ^.1
'2*;L
$ "- 7
...e ;;d-P_,. to rip:/M::all_.gy
!: i' : ' CL:.
1%
1-RC-9-1-3 None B9.11 40*RL h Vee Elbow Side Elbow-to-Safe End/ Surface Geometry Axial and Cire.
(Elbow Side) 0%
Elbow-to-Safe End/ Metallurgy None 1-RC-9-1-3 None B9.11 (Safe End Side)
Loop 4 Safe End-to-Pipe / Metallurgy 75%
1-RC-10-1-1 None B9.11 65 RL 1 Vee Axial.
(Safe End Side) 1 Direction
} Vee Cire.
9I
- ~...
- ^..
' 1 " RL i -
i=~e ;Iu-E=~e iv Tie /M Lull Joe
/_. _
_ 2 Cf..
1%
Elbow-to-Safe End/ Surface Geometry 1-RC-12-1-3 None B9.11 40*RL Vee Elbow Side Axial and Circ.
(Elbow Side) 0%
Elbow-to-Safe End/ Metallurgy 1-RC-12-1-3 None B9.11 None (Safe End Side)
Relicf R qu at PR.-'
.... ' ~
Pigm 5 of 7 Table 1 Pipe Weld Scan Limitations Table IWB-2500-1 Category B-J, B-F Data Me "RV Weld Exam Technique Configuration / Limitation Angle Covera 8e Identification Number Number Branch Piping 1-SI-203 2 6462-229 B9.11 45'S 1 Vee Axial Valve-to-Pipe / Permanent Obstruction 84%
1 Vee Cire.
1-RH-158-5-19 6462-203 39.11 45*RL Vee Axial Pipe-to-Reducer /
e ometry 75S.
45 S h Vee Cire.
- "#EY 73%
Pipt-to-Pipe / "# 8'" 6* **'#Y 1-RH-158-5-20 6462-203 B9.11 45*RL Vee Axial 8
45*S h Vee Cire.
50%
1-Ril-160-17-2 6462-340 B9.11 45*RL h Vee Axial Pipe-to-Tec/
f e ome m 45 S Vee Circ.
urgy 50%
1-RC-48-2-2 6462-358 B9.11 45*RL h Vee Axial Pipe-to-Tec/ "e a 45*S Vee Cire.
- * **E#Y Limited by 1-RC-1-1-5B 6462-131 B9.3 1 45' Full Vee Axial only 12" Branch Connection / Weld 1-RC 33%
1-2 and sur-6462-132 face contour 1-RC-3-1-5B 6462-137 B9.31 45*
Full Vee Axial only 10" B m h -
I 50%
/ c t scan y su ce 1-RC-4-1-5B 6462-130 B9.31 45*
Full Vee Axial only 6" B anch f
g9 g 50%
scan Limited by surface 50%
10" Branch 1-RC-6-1-3B 6462-132 B9.31 45' Full Vee Axial only Connection j contour on Cire, scan 1-RC-7-1-5B 6462-137 B9.31 45' Full Vee Axial only 14" Branch Limited by surface 50%
j Connection contour on Circ.
scan
Reli1f Requ:1tg PR-4
,,U T,
P ge 6 cf 7
T ble 1 Pipe Weld Scin Limitction:
Table IWB-2500-1, Category B-J, B-F Sheet em Technique Configuration / Limitation Wald
"*#8E" 8*
Identification Number Number l-RC-7-1-6B 6462-132 B9.31 45*
Full Vee Axial only 6 Branch
/
r 50%
scan 7
1-RC-9-1-4B 6462-125 B9.31 45*
Full Vee Axial only 10" Branch j
g 50%
scan by ce 1-RC-10-1-5B 6462-137 B9.31 45' Full Vee Axial only 12" Br h
f g
50%
scan 1-RC-12-1-4B 6462-130 B9.31 45*
Full Vee Axial only 10" Br m h
/
t o
50%
scan Safe End Welds-Reactar Vessel 1-SB-RV-301-121-D None B5.10 Composite Vee Nozzle-to-Safe End/ID Geometry 97%
Axial and Cire.
Safe End Welds-Steam 3enerator 1-RC-1-1-3 6463-120 B5.30 45*
Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial only (Nozzle Side)
One Direction (Carbon Steel Only) 1-RC-2-1-1 6463-129 B5.30 45*
Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial only (Nozzle Side)
One Direction (Carbon Steel only) 1-RC-4-1-3 6463-125 B5.30 45*
Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only (Nozzle Side)
(Carbon Steel only)
Reli1.f Requent: PR-4 a.
s +
..-g Tzbla 1 P;gn 7 cf 7 Pipe Weld Scin Limitctions Table IWB-2500-1, Categoty B-J, B-F aa Code CRV Weld Exam Technique Configuration / Limitation ldentification Angle N
r 1-RC-5-1-1 6463-124 B5.30 45"
\\ Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only (Nozzle Side One Direction Carbon Steel Only) 1-RC-7-1-3 6463-124 B5.30 45' Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only (Nozzle Side Carbon Steel Only)
One Direction I
1-RC-8-129 6463-81 B5.30 45" Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only One Direction to-\\
1-RC-3UL-3 6463-127 B5.30 45' Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only One Direction I
1-RC-11-1-+
6463-56 BS.30 45' Vee Nozzle-to-Elbow / Surface Geometry 25%
Axial Only One Direction 1.
Data sheet number, where given, refers to d ita sheet containing incomplete sce n.
2.
S = Shear RL = Refracted Lo 1gitudinal
s..
,g SBN-1110; Seabrook Nuclear Power Station Unit.No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-5 Component Identification:
Pump and Valve Internal Pressure Boundary Surfaces Code Class:
1 Examination Category:
B-L-2 and B-M-2 Code Requirement:
-t For Seabrook Unit No. 1, a visual examination.(VTH0$ of the internal surfaces shall be conducted for the following items in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum.
Item Description.
B12.40 Valve bodies exceeding 4" NPS B12.20 Pump casings Notes Examinations are limited to:
A.
One valve within each group of valves that are of the same design, manu-facturing method, and are performing similar functions in the system.
B.
One pump per group performing similar functions.
Code Relief Request:
Pursuant to 10CFR50-55(a)(g)5(iii), relief is requested from performing a preservice visual examination (VTJ30 g
Support for Relief / Alternate Examinations:
For the reactor coolant pump casings and 33 valve bodies (see Table 1 attached) in the reactor coolant, pressurizer, safety injection, and residual heat re -
mova1' systems, relief is requested from disassembly.of an operable valve or pump for the performing a preservice visual examination (VTdSO.
d Therequirementtodisassembleanoperab,(evalveorpumpforthesolepurpose of performing a visual examination (VT-Sy of the internal pressure retaining boundary is impractical and not commensurate to the increased assurance of safety achieved by this inspection. Class'1 valves and pumps are installed in their respective systems and all active valves completed functional testing in accordance with ASME Section XI, Article IWV. To disassemble these items would provide a very small potential'for increasing plant safety margins with a disproportionate impact on expenditures of plant manpower and resources.
R211sf R quict: PR-5 Pzga 2 of 3 The manufacturer's test data will be used in lieu of a preservice visual examination (VT-y). This includes documentation of examinations performed during fabricatibn and installation of the subject valves. The examina-tions performed may include volumetric, surface, and visual examinations, as required by ASME Section II, Material Specifications for Ferrous and Nonferrous Materials, and ASME Section III, Construction and Installation Requirements.
Class 1 valves and pumps are subjected to numerous types of nondestructive testing and a rigorous quality assurance program during all stages of fab-rication, storage, and installation. These valves and pumps have been found acceptable by the manufacturer, the ASME Authorized Nuclear Inspector, and New Hampshire Yankee's Quality Assurance. During maintenance of Class 1 pumps, a visual examination (VT-3) will be performed during in-service.
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R;11sf Riquist: PR-5 Pagn 3 of 3 Table 1 Class 1 Pumps and Valves Subject to Internals Visuals per IWB-2500-1 Cat. B-L-2, B-M-2 Group
- Valve I.D.
System Description Manufacturer 1.
1-RC-V22 Reactor Coolant 12" Gate
-Westinghouse 4
1-RC-V23 Reactor Coolant 12" Gate Westinghouse 1-RC-V87 Reactor Coolant 12" Gate Westinghouse 1-RC-V88 Reactor Coolant 12" Cate Westinghouse 2.
1-RC-V115 Reactor Coolant 6" Relief Crosby 1-RC-V116 Reactor Coolant 6" Relief Crosby 1-RC-V117 Reactor Coolant 6" Relief Crosby 3.
1-RH-V15 Residual Heat Removal 6" Check Westinghouse 1-RH-V29 Residual Heat Removal 6" Check Westinghouse 1-RH-V30 Residual Heat Removal 6" Check Westinghouse 1-RH-V31 Residual Heat Removal 6" Check Westinghouse 1-RH-V52 Residual Heat Removal 6" Check Westinghouse 1-RH-V53 Residual Heat Removal 6" Check Westinghouse 1-RH-V50 Residual Heat Removal 8" Check Westinghouse 1-RH-V51 Residual Heat Removal 8" Check Westinghouse 4.
1-RH-V59 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V61 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V63 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V65 Residual Heat Removal 6" Gate Valve
' Westinghouse 5.
1-SI-V3 Safety Injection 10" Gate Valve Westinghouse 1-SI-V17 Safety Injection 10" Gate Valve Westinghouse 1-SI-V32 Safety injection 10" Gate Valve Westinghouse 1-SI-V47 Safety Injection 10" Gate Valve Westinghouse 6.
1-SI-V5 Safety Injection 10" check Valve Westinghouse 1-SI-V6 Safety Injection 10" Check Valve Westinghouse 1-SI-V20 Safety Injection 10" Check Valve Westinghouse 1-SI-V21 Safety Injection 10" Check Valve Westinghouse 1-SI-V35 Safety Injection 10" Check Valve Westinghouse 1-SI-V36 Safety Injection 10" Check Valve Westinghouse 1-SI-V50 Safety Injection 10" Check Valve Westinghouse 1-SI-V51 Safety Injection 10" check Valve Westinghouse 1-SI-V82 Safety Injection 6" Check Valve Westinghouse 1-SI-V87 Safety Injection 6" Check Valve Westinghouse
. Group
- Pump I.D.
System Description Manufacturer 1.
1-RC-P-1A Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1B Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1C Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1D Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse
- Examinations required are limited to one (1) pump or valve in each group.
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SBN-1110 a,
Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-6 Component Identification:
Steam Generator, Residual Heat Removal and Excess Letdown Heat Exchanger Welds Code Class: 2 Examination Category:
C-A and C-B Code Requirement:
For Seabrook Unit No. 1, a volumetric (ultrasonic) examination of 100 percent of the weld length and 100% of the nozzle inner radius areas shall be conducted for the following items in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum, Subarticle IWC-2500:
Item Description C-1.10 Shell circumferential welds C-1.20 Head circumferential welds C-1.30 Tubesheet-to-Shell weld C-2.20 Nozzle to shell welds Code Relief Request:
Purusant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portion of the subject vessel welds.
Basis for Relief:
Geometric configuration and permanent obstructions prohibit the performance of a 100 percent volumetric examination of each of the subject welds. The PSI limitations and the specific relief, as they apply to each weld, are noted in the attached table for each component.
Support for Relief / Alternate Examinations:
A.
The subject welds received both volumetric examination by radiography and surface examinations during fabrication in accordance with ASME Section III requirements which provide adequate assurance of the struc-tural integrity of the welds.
B.
A construction hydrostatic test was conducted successfully on the Class 1 pressure boundary, of which these welds are a part thereof, in accordance with the requiremetns of ASME Section III.
C.
In-service system leakage tests will be performed per Category C-H Table IWC-2500-1 each refueling outage.
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Rali%f R:qu2et:.PR-6
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Pags 2 of-5 Table 1 Steam Generator Limitations h et Technique Configuration / Limitation h
Ident ation Number (1)
Number 1-RC-E-11A Seam 8 6465-005 C1.20 0*
O' Upper shell to head. 4 plates 98%
1-RC-E-11A Scam 8 6465-011 C1.20 45' Circ. and Axial Upper shell to head. 4 plates 98%
l-RC-E-11A Seam 8 6465 Q y.
C1.20 60*
Cire. and Axial Upper shell to head.'4 plates 80%
and surface contour.
1-RC-E-IIA Seam 6 6465-006 C1.10 0*
0*
Shell to transition. 2 plates and 96%
4 instrumentation lines 1-RC-E-11A Seam 6 6465-002 C1.10 45' Cire, and Axial Shell to transition. 2 plated and 96%.
4 instrumentation lines 1-RC-E-11A Seam 6 6465-003 C1.10 60*
Cire. and Axial Shell to transition. 2 plates and 82%
4 instrumentation lines, also surface contour of weld 1-RC-E-11A Seam 5 6465-012 C1.10 60*
Cire. and Axial Transition to shell. Surface 80%
contour.
1-RC-E-11A Seam 3 6465-010 C1.10 0*
0*
Shell to stub barrel. Surface 99%
gouge.
1-RC-E-11A Seam 3 6465-009 C1.10 45*
Circ, and Axial Shell to stub barrel. Surface 99%
- gouge, 1-RC-E-11A Seam 3 6465-013 C1.10 60*
Cire and Axial Shell to stub barrel. Surface 91%
gouge.
1-RC-E-IIA Seam 2 6465-014 C1.30 45' Axial Stub barrel to tubesheet. Tube-86%
sheet flange, and hand way.
1-RC-E-IIA Seam 2 6465-015 C1.30 60*
Axial Stub barrel to tubesheet. Tube-80%
sheet flange and handway.
1-RC-E-11A-161R None C2.20 None None Steam outlet nozzle inner 0%
radius /ID geometry 1-RC-E-11B-161R None C2.20 None None Steam outlet nozzle inner 0%
radius /ID geometry 1-RC-E-11C-16IR None C2.20 None None Steam outlet nozzle inner 0%
radius /ID geometry 1-RC-E-11D-16IR None C2.20 None None Steam outlet nozzle inner 0%
radius /ID geometry
-up Relief R:que;ts PR-6:
Pzg3 3 of 5 Table 1 Steam Cenerator Limitations Data Code Weld Sheet Item Technique Configuration / Limitation Identification
^"E Number (1)
Number 1-RC-E-11B Seam 6 6465-040 C1.10 0*
0*
Transition to shell. 6 pads 95%
3 1-RC-E-11B Seam 6 6465$
C1.10 45' Axial Transition to shell. 6 pads
'95%
6465-6b C1.10 60*
Axial Transition to shell. 6 pads 95%
1-RC-E-11B Scam 6 o 31 1-RC-E-11B Seam 5 6465-ete-C1.10 0*
0*
Shell to transition. Surface 72%
Contour.
1-RC-E-11B Seam 5 6465-030 C1.10 45' Cire. and Axial Shell to transition. Surface 75%
contour.
1-RC-E-11B Seam 5 6465-032 C1.10 60*
Cire. and Axial Shell to transition. Surface 79%
Contour.
1-RC-E-11B Seam 3 6465-031 C1.10 0*
0*
Shell to stub barrel. Surface 71%
contour.
1-RC-E-11B Seam 3 6465-033 C1.10 45*
Circ. and Axial Shell to stub barrel. Surface 79%
contour.
1-RC-E-11B Seam 3 64650-032 C1.10 60*
Circ. and Axial Shell to stub barrel. Surface 80%
Contour.
1-RC-E-11B-11NZ 6465-037 C2.20 0*
0*
Nozzle to shell. Nozzel and 99%
surface contour.
1-RC-E-11B-11NZ 6465-038 C2.20 45' Circ. and Axial Nozzle to shell. Nozzle and-89%
curface contour.
1-RC-E-11B-11NZ 6465-039 C2.20 60*
Cire. and Axial Nozzle to shell. Nozzle and 84%
surface contour.
1-RC-E-11C Seam 6 6465-040 C1.10 0*
0*
Transition to shell. 6 pads 95%
1-RC-E-11C Seam 6 6465-039 C1.10 45*
Axial Transition to shell. 6 pads 95%
1-RC-E-11C Seam 6 6465-041 C1.10 60*
Axial fransition to shell. 6 pads 95%
1-RC-E-11C Seam 5 6465-031 C1.10 0*
0*
shell to transition. Surface 77%
- entour.
R;11;f Reque::.t: PR-6 P g2 4 cf 5 ~
Table 1-Steam Cenerator Limitations
- " "I "*
E"#* '"
9 Cov rage 6 **E Ang Ident fication Number (g)
Number C33C) 1-RC-E-11C Seam 5 6465-e94-C1.10 45' Circ and Axial Shell to transition. Surface 78%
contour.
1-RC-E-11C Seam 5 6465-032 C1'.10 60*
Circ. and Axial Shell to transition. Surface 78%
Contour.
1-RC-E-11C I ll 6467-8 C2.20 70*
Skew (inner radius)
Nozzle to shell. Surface contour 0%
1-RC-E-11D Seam 6 6465-017 C1.10 0*
0*
Transition to shell. Surface 88%
contour and 6 pads.
1-RC-E-11D Seam 6 6465-019 C1.10 45*
Cire. and Axial Transition to shell. Surface 91%
contour and 6 pads.
1-RC-E-11D Seam 6 6465-018 C1.10 60*
Circ. and Axial Transition _to shell. Surface-92%
contour and 6 pads.
1-RC-E-11D Seam 5 6465-017 C1.10 0'
0*
Shell to transition. Surface 85%
contour for a 5" square area and weld contour.
1-RC-E-11D Seam 5 6465-022 C1.10 45*
Circ. and Axial Shell to transition. Surface 83%
contour for a 5" square area and weld contour.
1-RC-E-11D Seam 5 6465-018 C1.10 60*
Circ. and Axial Shell to transition. Surface 79%
contour for a 5" square area and weld contour.
1-RC-E-11D 16NZ 6465-020 C2.20 0*
O' Nozzle to shell. Nozzle and 57%
and surface contour.
1-RC-E-11D 16NZ 6465-036 C2.20 45*
Circ. and Axial Nozzle to shell. Nozzle and 57%
and surface contour.
1-RC-E-11D 16NZ 6465-021 C2.20 60*
Cire. and Axial Nozzle to shell. Nozzle and 57%
surface contour.
1.
Data sheet number refers to da :a sheet cont. tining imcomplete scan.
Relisf Reque:tt PR _g.
4 Piga 5 ef 5 J
Table 2 Excess Letdown HX and Regenerative HX Limitations echnique n igura n/ Limitation Cov age Angl Ident fi ation Number (1)
Number Permanent ee Ax a f
Head-to-Flange / Obstruct'on 46.4%-
1-CS-E-3C 6487-4 C1.20 45 Surface Geometry 1-REG-4A 6487-7 C1.10 45*
b Vee Axial and Cire. Shell-to-Bonnet / Permanent'
. 70.'4%
Channel Obstruction 1-REG-4B 6487-7 C1.10 45' Vee Axial and Cire. Shell-to-Bonnet / Permanent 70.4%
Channel Obstruction 1.
Data sheet numbe : refers to data sheet con
- aining incoinplete scan.
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SBN-1110 i
a-Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief' Request: PR-7 i
i Component Identification-RHR Heat Exchanger sozzles Code Class: 2 Examination Category:
C-B Code Item No.: C2.20 Code Requirement:
For Seabrook Unit No. 1. volumetric and surface examinations of the nozzle-to-shell welds (C2.20) for the residual heat removal heat exchangers shall be conducted in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum, Subarticle IWC-2500.
Code Relief Request:
Pursuant to 10CFR50.55(a)(g)S(iii), relief is requested from performing the preservice ultrasonic examination of the nozzle to vessel welds on the tube side waterbox of the RHR Heat exchangers.
Reason for Relief:
Table IWC-2500-1, Category C-B, requires a volumetric examination of nozzle welds in vessels whose thickness exceeds 1/2" nominal.
In the case of the Seabrook RHR Heat Exchangers, the weld geometry for the inlet and outlet nozzles do not have a configuration (Figure 1) which can be examined with ultrasonic techniques. The Pre-Service volumetric requirements will be fulfilled by the construction radiography.
Ultrasonic examination techniques will be developed, such that maximum i
coverage will be achieved at the first refueling outage.
Proposed Alternate Examinations:
1.
Since the weld thickness is ( 1/2" nominal. PSI examinations were per-formed in accordance with the requirements of Code Item Number C2.10 and Examination Requirements Figure IWC-2520-3 for nozzles in vessels 1/2" or less in nominal thickness.
2.
The subject welds received both volumetric examination by radiography and surface examination during fabrication in accordance with the requirements of ASME Section III which provides adequate assurance of the structural integrity of the welds.
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R211sf R:quast: PR-7 l
P ga 2 of 3 3.
A preservice hydrostatic test was successfully conducted on the Class 2 portion of the heat exchanger, which includes the nozzle-to-shell welds, in accordance with ASME Section III.
4.
Regular system pressure tests will be performed inservice in accordance with the requirements of Table IWC-2500-1. Category C-B.
g 5.
At the first refueling outage, the welds will be ultrasonically examined from the nozzle side using techniques developed on the Unit 2 beat ex-changers.
l i
R2113f Riqu2:ts PR-7 Pass 3 of 3
- e Seabrook Station Unit 1 Figure 1 1
1 40Nr. 8840 SEE OEVAN
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/
II.
ae so-
=
.k,
. 'g In L
b'/d a
d
(( i
- fd z. g
(
- '4 g
To Ta&y.nm E
=V
=43 4c o, m
DETAtt 'WW MOZZS. 'A' sf W gruu scate 4
RHR Nozzle-to-Shell Welds, 2 Heat Exchangers i
two nozzles each.
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s.
SBN-1110 Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request:
PR-9 Component Identification:
Class 2 Piping Welds Code Class: 2 Examination Category:
C-F Code Requirement:
For Seabrook Unit No. 1, volumetric (ultrasonic) and surface examinations of 100 percent of the length of each weld requiring examination shall be conducted in accordance with the ASME B&PV Code,Section XI,1977 Edition through the Summer 1978 Addendum.
Code Relief Request:
Purusant to 10CFR50.55(a)(g)S(iii), relief is requested from performing the preservice volumetric and/or surface examinations on the inaccessible portions of the welds listed in Table 1 (attached).
Basis for Relief:
Geometric configuration, permanent obstructions and/or structural inter-ferences, prohibit 100 percent examination coverage of the Code required volume. Relief, is, therefore, requested from performing preservice exam-inations on the inaccessP21e portions of certain circumferential welds as noted in Table 1 (attached).
Proposed Alternative Examinations:
A.
The subject welds received volumetric examination by radiography durinF fabrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject welds is provided.
B.
A Section III hyc.ostatic test was conducted successfully on the Class 2 Pressure Boundary, of which these welds are a part thereof.
C.
In-service system leakage tests will be performed per Category C-H, Table IWC-2500-1 as well as surface and volumetric exams on the accessible por-tions of the welds shown on Table 1, as required by Section XI selection criteria. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage and results and applied where deemed appropriate by New Hampphire Yankee.
Ttbla 1 PR-9 Pipa Wald Sccn Lioitaticas Table IWC-2500-1 Cstegory C-F Pags 2 cf 3.
I Wald Data Code Exam Technique Configuration / Limitation CRV Id:;n t i fic a t ion Sheet Item Angle (2)
Coverage Number (1)
Number 1-RH-158-4-2 6462-294 C5.21 45*RL l Vee Axial Pipe-to-Flange / Metallurgy 50%
45*S lVee Cire.
Surface Geometry 1-MS-4002 *H4h 6463-067 C5.22 45*S Il Vee Axial Pipe Longitudinal Surface LU-7 i Vee Circ.
Weld Seam Contour 99.6%
MS-4000-41-4B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent i Vee Circ.
Connection Obstruction 70%
MS-4000-41-13B 6463-038 C5.31 45'S Full Vee Axial 6" Branch Permanent i Vee Circ.
Connection Obstructions 59%
MS-4001-41-4B 6463-038 C5.31 45'S Full Vee Axial 6" Branch Permanent lVee Circ.
Connection Obstruction 70%
MS-4003-37-33 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent
} Vee Cire.
Connection Obstruction 95%
MS-4001-41-3B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent 65%
IVee Cire.
Connection Obstruction i
Toblo 1 PR-9 Pips Wald Secn Liuitaticns Paga 3 of 3 Table IWC-2500-1 Cetegory C-F I
Wald Data Code Exam Technique Configuration / Limitation CRV Idantification Sheet Item Angle (2)
Coverage Number (1)
Number MS-4002-37-3B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent i Vee Cire.
Connection Obstruction 9 5 '.
MS-4001-41-138 6463-038 C 5.31 45'S Full Vee Axial 6" Branch Permanent 7 0 *.
- 1. Vee Cire.
Connection Obstruction
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i (1) Data sheet number,where given, refers to data s h e e t-containing incomplete scan.
Shear Wa ve (2) S
=
'RL= Refracted Longitudi nal Wave
_