ML18152A268: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:; *
{{#Wiki_filter:;
* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 23, 1996 United States Nuclear Regulatory Commission Attention:
* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
Document Control Desk Washington, D.C.
* April 23, 1996 United States Nuclear Regulatory Commission                       Serial No.      96-138 Attention: Document Control Desk                                   NL&OS/EJW Washington, D.C. *20555                                           Docket No. 50-280 License No. DPR-32 Gentlemen:
* 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the recent refueling outage, Surry Power Station Unit 1 completed examinations in the first period of its third ten year inservice inspection (ISi) interval. The component examination program is conducted in accordance with ASME Section XI 1989 Edition.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS Serial No. 96-138 NL&OS/EJW Docket No. 50-280 License No. DPR-32 During the recent refueling outage, Surry Power Station Unit 1 completed examinations in the first period of its third ten year inservice inspection (ISi) interval.
Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from certain requirements of the ASME Section XI Code associated with partial examinations conducted during the 1995 Surry Unit 1 refueling outage. Relief Requests SR-009 through SR-017 (attached) provide the basis for the requested relief.
The component examination program is conducted in accordance with ASME Section XI 1989 Edition. Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from certain requirements of the ASME Section XI Code associated with partial examinations conducted during the 1995 Surry Unit 1 refueling outage. Relief Requests SR-009 through SR-017 (attached) provide the basis for the requested relief. These relief requests have been approved by the Surry Station Nuclear Safety and Operating Committee.
These relief requests have been approved by the Surry Station Nuclear Safety and Operating Committee.
If you have any questions concerning these requests, please contact us. Very truly yours, James P. O'Hanlon Senior Vice President  
If you have any questions concerning these requests, please contact us.
-Nuclear Attachments  
Very truly yours, James P. O'Hanlon Senior Vice President - Nuclear Attachments
--9604250440 9604-23 PDR ADOCK 05000280 PDR
          -   -
9604250440 9604-23 PDR ADOCK 05000280
      ~                      PDR
 
                                                      \ ..
'
'
* J
      *J
* cc: United States Nuclear Regulatory Commission Region II 101 Marietta Street, N.W. Suite 2900 Atlanta, GA 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station \ .. * 
                        *
*
* cc:   United States Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
* RELIEF REQUEST SR-009 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 1-12 27 1/2"-RC-9-2501 R II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-0102AZ-1 Class 1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number 89.11 does not allow any limitations to the required volumetric or surface examinations.
Suite 2900 Atlanta, GA 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due* to the configuration of the weld (pipe to reactor coolant pump) and a 1" x 5" identification tag. Coverage of the volumetric examinations are detailed in Table SR-009-1.
 
Figure SR-009-1 is provided as graphic detail of the limitations experienced.
                    *
This weld is a terminal end weld and, as such, all welds of this type are scheduled for examination.
* RELIEF REQUEST SR-009 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                         Drawing#                      Class Weld 1-12         27 1/2"-RC-9-2501 R           11448-WMKS-0102AZ-1             1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number 89.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.
Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due* to the configuration of the weld (pipe to reactor coolant pump) and a 1" x 5" identification tag.
Coverage of the volumetric examinations are detailed in Table SR-009-1. Figure SR-009-1 is provided as graphic detail of the limitations experienced. This weld is a terminal end weld and, as such, all welds of this type are scheduled for examination.
Therefore, substitution with another weld is not feasible.
Therefore, substitution with another weld is not feasible.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
UT Scan Coverage Weld No. 1-12 96.2 UT Scan Direction Definitions 0 1 100 .8. 100 Table SR-009-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-0102AZ-1 Category B-J, Item B9.11 Surface Coverage%
 
100 Reason For Partial Pipe to reactor coolant pump configuration prevented scanning from the 5 side. A l" x 5" welded tag prevented full coverage, (76% coverage obtained) for the 5" of weld circumference on the 2 side. The use of alternate angles would not have improved volumetric coverage.
Table SR-009-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-0102AZ-1 Category B-J, Item B9.11 UT Scan Coverage
Because of the use of the longitudinal wave form only Yz node examinations were possible.
* Surface Weld No.                                  1        .8.        Coverage%             Reason For Partial 1-12                  96.2      0        100      100            100                Pipe to reactor coolant pump configuration prevented scanning from the 5 side. A l" x 5" welded tag prevented full coverage, (76% coverage obtained) for the 5" of weld circumference on the 2 side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yz node examinations were possible.
2 -Axial scan, 180 degrees from Isometric flow direction 5 -Axial scan, the same direction as the isometric flow 7 -Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 -Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow *
UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction
* Figure SR-009-1 Search Unit
* 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
* 5 Side A ~1
 
* Exam. Volume Exam. Volume Hatched area (in examination volume) shows extent of coverage due to the I.D. Tag. Seventy-six (76) percent of the volume was not examined for five (5) inches.
Figure SR-009-1 Search Unit
{ EL. II'* 'I 15/16" ------V/ ; REACTOR VESSEL l*RC-...... R*l ..... INOTE 71 11448-WMKS-0102AZ-l REACTOR COOLANT PUMP .... *r*1tc ....... ::... .... P-u£ .. .> INOTE 'II ,-* x GE~OR ..... E*IC ... INOTE 111 ... **" ** .. \*** ~, =s*--R-c--:--,-.,-5-.,2---1 SEE DE TAIL 'A' ON 'J 448*WHk5*1llll2Alj
* 5 Side A
('""") I I I I I I I I I I I I I I COLD LEG HOT l~G ~E DETAIL 'O"OH 'J ' L_4411-1tHKS*lllll2Alj JI'* 2'1' 'Ill" RED Ell * * 
              ~1 Exam. Volume                                   Exam. Volume
*
* Hatched area (in examination volume) shows extent of coverage due to the I.D. Tag.
* RELIEF REQUEST SR-010 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 1-11 31 "-RC-8-2501 R II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-0102AZ-1 Class 1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations.
Seventy-six (76) percent of the volume was not examined for five (5) inches.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full coverage could not be achieved due to the configuration of the weld (pipe to reactor coolant pump) and a support. Coverage of the examinations are detailed in Table SR-010-1.
 
Figure SR-010-1 is provided as graphic detail of the limitations experienced, where the weld could be examined.
11448-WMKS-0102AZ-l
Figure SR-010-2 is provided to show the closeness of the support in relation to weld 1-11. The support is a massive welded and bolted structure that supports the reactor coolant pump and, as such, cannot be removed to allow access to weld 1-11. This weld is a terminal end and, as such, all welds of this type are scheduled for examination.
('""")
Therefore, substitution with another weld is not feasible.
REACTOR COOLANT                                                           I    I PUMP                         GE~OR                          I    I
                                                      ....*r*1tc.......                                                   I    I
: . ..... P-u£ . .>                           l*RC-                  I    I
* I    I INOTE 'II
                                                                                              .....E*IC ...               I    I INOTE 111               I    I COLD      HOT LEG      l~G
                                                                                                                                    ~ E DETAIL 'O"OH
                                                                                                                                    '
                                                                                                                                                        'J L_4411-1tHKS*lllll2Alj JI'* 2'1'
                                                                                                                                        'Ill" RED Ell
                                                                        ,-* ...x
                                                                                                                                                            *
{ EL. II'* 'I 15/16" ------V/
                        ;
REACTOR VESSEL
                                                                        ~          **"
                                                                          ** .. \ * * * ~,=s*--R-c--:--,-.,-5-.,2---1 l*RC-
                            ......R*l .....                                          SEE DE TAIL 'A' ON 448*WHk5*1llll2Alj
                                                                                                                  'J INOTE 71
 
                      *
* RELIEF REQUEST SR-010 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                         Drawing#                      Class Weld 1-11         31 "-RC-8-2501 R             11448-WMKS-0102AZ-1           1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.
Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full coverage could not be achieved due to the configuration of the weld (pipe to reactor coolant pump) and a support. Coverage of the examinations are detailed in Table SR-010-1. Figure SR-010-1 is provided as graphic detail of the limitations experienced, where the weld could be examined. Figure SR-010-2 is provided to show the closeness of the support in relation to weld 1-11. The support is a massive welded and bolted structure that supports the reactor coolant pump and, as such, cannot be removed to allow access to weld 1-11. This weld is a terminal end and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
UT Scan Coverage Table SR-010-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WM KS-0102AZ-1 Category 8-J, Item 89.11 Surface Coverage%
 
Reason For Partial .;. Weld No. 1-11 0 49 46.5 50 50 Pipe to reactor coolant pump configuration prevented scanning from the 2 side. A pipe support covering the weld from 270° to 90°, (9 O'clock to 3. O'clock) prevented examination, both volumetric and surface, in this area. The use of alternate angles would not have improved volumetric coverage.
Table SR-010-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WM KS-0102AZ-1                                                                             .;.
Because of the use of the longitudinal wave form only 1/2 node UT Scan Direction Definitions 2 -Axial scan, 180 degrees from Isometric flow direction 5 -Axial scan, the same direction as the isometric flow
Category 8-J, Item 89.11 UT Scan Coverage Surface Weld No.
1-11                 0     49     46.5     50 Coverage%
50 Reason For Partial Pipe to reactor coolant pump configuration prevented scanning from the 2 side. A pipe support covering the weld from 270° to 90°, (9 O'clock to   3.
O'clock) prevented examination, both volumetric and surface, in this area.
The use of alternate angles would not have improved volumetric coverage.
Because of the use of the longitudinal wave form only 1/2 node
* examinations were possible.
* examinations were possible.
7 -Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 -Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
* Figure SR-010-1 Search Unit Search Unit 5 Side ~I 2 Side I V Exam. Volume Hatched area (in examination volume) shows lack of coverage due to configuration, i.e., six (6) percent of the examination volume was not examined.  
                                                                                                                                                            *
* *
* Figure SR-010-1 Search Unit                             Search Unit
* Reactor coolant Pump ~--+-Weld 1-11 Pipe support--.
* 5 Side                                                                                 2 Side I
Side View Figure SR-010-2 Component Su art 31"-RC-8-2501R at \.leld 1-11 Top View *
V
* i EL, II"* 'I l!lil&'y/
                                                                      ~I
' REACTOR VESSEL I-RC-. ...... R*l ..... INOTE 71 11448-WMKS-0102AZ-l REACTOR COOLANT fYB.P ****r1te**  
* Exam. Volume Hatched area (in examination volume) shows lack of coverage due to configuration, i.e., six (6) percent of the examination volume was not examined.
.... . \ .... P-1c* ... > IIIOTE 'II TD 11441 *Wl<<S*IUl3A7 OE~OR "'i-Rt*"" .... E-IC .... INIJJE II * ......... \ 'rl""&"&deg;*.~RC~-~:"-l*-15_0_2_*_1 SEE OET AIL 'A' ON "] 448*WHk5*BIB2AZj (MH .... I I I I I I I I I I I I I I CIJ..D LEG SEE llETAIL '&'ON j ll4411*WHKS*Bll2AZj HOT LEG * ~E DETAIL 'D'CIN j ' L4411*11NCS*lll2AZ~r-ll'* zqo 'Ill' RED ELL * 
 
* ** RELIEF REQUEST SR-011 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 1-20 31 "-RC-8-2501 R II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-0102AZ-1 Class 1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category 8-J, item number 89.12 does not allow any limitations to the required volumetric or surface examinations.
Figure SR-010-2 Reactor coolant Pump
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Code Case N524 (b), (1) modifies Table IWB-2500-1, Note (4) and only requires that examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential examination volume. Ill. BASIS FOR RELIEF The component listed above is inaccessible for both surface and volumetric examination.
                  ~--+-Weld 1-11 Component Su art
Examination could not be achieved due to the configuration of the support. A reactor coolant pump support/pipe support completely covers this longitudinal weld. The circumferential weld (1-11) that intersects with this longitudinal weld is a terminal end and, as such, all welds of this type are scheduled for examination.
* 31"-RC-8-2501R at \.leld 1-11 Pipe support--.
Therefore, substitution with another weld is not feasible.
Top View
The adjacent longitudinal weld 1-21 (shown on drawing 11448-WMKS-0102AZ-1 and Figure SR-011-1) was examined 100%, at weld 1-11, per Code Case N-524, with no reportable indications (NRI). IV. ALTERNATE PROVISIONS It is proposed that the system leakage test be substituted for the Code surface and volumetric examination.
* Side View
_J Weld 1-20 .... (longitudinal weld) is under component support. Reactor coolant Pump Figure SR-011-1 Weld 1-11 (circumferential weld) Weld 1-21 (longitudinal weld) Pipe support .... Side View Component Su ort 31"-RC-8-2501R at Weld 1-11 Top View # !. *
 
* l EL, II'* 'I 15/16' y/ ' REACTOR VESSEL I-RC-., ...... R*l ..... INOTE 71 11448-lrl4KS-0102AZ-1 REACTOR COOLANT POMP ., .. *r1tc*** .. . \ .... P*IC-... > INOTE 'II GE~OR l*RC-..... E*IC ..... !NOTE Ill (_ ...... \_ .. \ I &'*RC*:'1-15112*
11448-WMKS-0102AZ-l (MH....
I SEE DETAIL 'A' ON 448*WHKS*B1ll2AZj
REACTOR COOLANT                                                                         I    I fYB.P                         OE~OR                                            I    I
,~ .... ) I I I I I I I I I I I I I I CDl.0
                                              ****r1te**.....                         "'i-Rt*""
* NOT LEG L!EG SEE DETAIL '8' ON -::1 114411*WHKS*lllll2AZj
I I
~E DETAIL 'O'ON '] ' L44ll*WHICS*1112AZ:J ll'X 2<r 'II' RED ELL !. * *
I I
*
                                              \ .... P-1c* ... >
* RELIEF REQUEST SR-012 I. IDENTIFICATION OF COMPONENT Weld No. Line # Weld 1-05DM 29 11-RC-1-2501 R Weld 1-06DM 31"-RC-2-2501R II. IMPRACTICABLE CODE REQUIREMENTS D.rawing # 11448-WMKS-O 1 OOAZ-1 11448-WMKS-01 OOAZ-1 Class 1 1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-F, item number 85.70 does not allow any limitations to the required volumetric or surface examinations.
* I    I IIIOTE 'II
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Ill. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. However, due to the configuration of the weld (pipe to steam generator nozzle to safe end butt weld) full volumetric coverage could not be achieved.
                                                                                        .... E-IC....                               I    I INIJJE II                               I    I CIJ..D    HOT LEG      LEG
Coverage of the volumetric examinations are detailed in Table SR-012-1.
                                                                                                                                              ~ E DETAIL 'D'CIN  j
Figure SR-012-1 is provided as graphic detail of the limitations experienced.
                                                                                                                                              ' L4411*11NCS*lll2AZ~r-ll'* zqo
All welds of this type are scheduled for examination.
                                                                                                                                                  'Ill' RED ELL i EL, II"* 'I l!lil&'y/
Therefore, substitution with other welds is not feasible.
TD 11441
                                              *Wl<<S*IUl3A7
                                                                                                                                                                      *
                    ' REACTOR                                    *.........~                                  SEE llETAIL '&'ON j ll4411*WHKS*Bll2AZj
                                                                              'rl""&"&deg;*.~RC~-~:"-l*-15_0_2_*_1 VESSEL I-RC- .
                      ......R*l .....                                      SEE OET AIL 'A' ON "]
INOTE 71                                            448*WHk5*BIB2AZj
                                                                    \
 
                    *                                     **
RELIEF REQUEST SR-011 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                         Drawing#                        Class Weld 1-20         31 "-RC-8-2501 R             11448-WMKS-0102AZ-1             1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category 8-J, item number 89.12 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Code Case N524 (b), (1) modifies Table IWB-2500-1, Note (4) and only requires that examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential examination volume.
Ill. BASIS FOR RELIEF The component listed above is inaccessible for both surface and volumetric examination. Examination could not be achieved due to the configuration of the support. A reactor coolant pump support/pipe support completely covers this longitudinal weld. The circumferential weld (1-11) that intersects with this longitudinal weld is a terminal end and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible. The adjacent longitudinal weld 1-21 (shown on drawing 11448-WMKS-0102AZ-1 and Figure SR-011-
: 1) was examined 100%, at weld 1-11, per Code Case N-524, with no reportable indications (NRI).
IV. ALTERNATE PROVISIONS It is proposed that the system leakage test be substituted for the Code surface and volumetric examination.
_J
 
                                                                                            #
Figure SR-011-1                             !.
Reactor coolant Pump
                                                                                            *
                                  ~ Weld 1-11 (circumferential weld)
Weld 1-20 ....                    ~ Weld 1-21 (longitudinal weld)   Component (longitudinal weld)                                                  Su ort is under component support.
31"-RC-8-2501R at Weld 1-11 Pipe support ....
Top View
* Side View
 
                                                                                                                                                              !.
11448-lrl4KS-0102AZ-1 REACTOR COOLANT
                                                                                                                          ,~....
I
                                                                                                                                )
I POMP                       GE~OR                                  I      I
                                                  .,..*r1tc***.. .                                                         I      I
                                                \ .... P*IC-... >                       l*RC-                           I      I
* I      I
                                                                                      .....E*IC.....                       I       I INOTE 'II                                                          I       I
                                                                                          !NOTE Ill CDl.0
* NOT LEG         L!EG
                                                                                                                                      ~ E DETAIL 'O'ON ' ]
                                                                                                                                      ' L44ll*WHICS*1112AZ:J ll'X 2<r
                                                                                                                                            'II' RED ELL l EL, II'* 'I 15/16' y/
                                                                                                                                                              *
                      ' REACTOR
(_ ......\_          ..          SEE DETAIL '8' ON -::1 114411*WHKS*lllll2AZj VESSEL                                                I &'*RC*:'1-15112* I I-RC-
              .,      ...... R*l .....                                    SEE DETAIL 'A' ON INOTE 71                                            448*WHKS*B1ll2AZj
                                                                    \
 
                    *
* RELIEF REQUEST SR-012 I. IDENTIFICATION OF COMPONENT Weld No.         Line #                         D.rawing #                  Class Weld 1-05DM     29 11 -RC-1-2501 R             11448-WMKS-O 1OOAZ-1          1 Weld 1-06DM     31"-RC-2-2501R                 11448-WMKS-01 OOAZ-1           1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-F, item number 85.70 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.
Ill. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. However, due to the configuration of the weld (pipe to steam generator nozzle to safe end butt weld) full volumetric coverage could not be achieved. Coverage of the volumetric examinations are detailed in Table SR-012-1. Figure SR-012-1 is provided as graphic detail of the limitations experienced. All welds of this type are scheduled for examination. Therefore, substitution with other welds is not feasible.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code*requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code*requirements.
UT Scan Coverage Weld No. l-05DM l-06DM 0 80 UT Scan Direction Definitions 80 0 1 50 50 .8. 50 50 Table SR-012-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-01 OOAZ-1 Category B-F, Item BS.70 Surface Coverage%
 
100 100 Reason For Partial Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage.
Table SR-012-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-01 OOAZ-1 Category B-F, Item BS.70 UT Scan Coverage
Because of the use of the longitudinal wave form only Yi node examinations were possible.
* Surface Weld No.                                  1        .8.        Coverage%             Reason For Partial l-05DM                0        80      50      50              100                Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yi node examinations were possible.
Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage.
l-06DM                80        0        50      50              100                Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yi node examinations were possible
Because of the use of the longitudinal wave form only Yi node examinations were possible 2 -Axial scan, 180 degrees from Isometric flow direction 5 -Axial scan, the same direction as the isometric flow 7 -Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 -Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow *
* UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
* Figure SR-012-1
 
* Search Unit Nozzle Side Elbow Side ..... 43&deg; Beam Angle
Figure SR-012-1 Search Unit
* t .,_ Exam. Volume Hatched area (in examination volume) shows extent of coverage due to configuration, i.e., 20% of the examination volllne was not examined.
* Nozzle Side Elbow Side
I*. CO'o" *,**, I . .:, ' .... ., ,' :,*;: I ~--; :-:~., I C-===:J 1 ... :,,., ..... ,I tlL,U 'I l'l*iC.' ,, &&#xa3;1:Ill!l
                                                                            ..... 43&deg; Beam Angle
~EJ;ill, *l*RC; .. Rel / / t ll,11'*'1 I'.:<:.' ;/ REACTOR COOLANf PJMP l*RC* r*IA CJ [,;," .. "., .. , .. I 11,~.J ..... J.:, ........ " ..:*',I _J cif;L CJ CE~OR l*RC* E*IA 'til .-.. -Ll<lLl ,.. ..*.. , I I I I I I I I I I I I I I e! :.**,*-(, ***'-!:* . .':*-* .*.:* *-*!.Ul'..*,,.:**I'>**,*
                                                                      .,_ Exam. Volume t
1J ,II .'l '.' .. , i ,I ,;,, ' -l ~.r.: .. ' . .; . . . ., ..... *-*-:. .. .,;, .:,:;,,,:*"*  
* Hatched area (in examination volume) shows extent of coverage due to configuration, i.e., 20% of the examination volllne was not examined.
*"* ,*: *,' I .. *****.:**.
 
l .... ; < ',*'.l i :~ '' .:.:-* **,, II ;;11!**"'*:-;**f,** ,r .. -1,:,*J ::::e ~~:~:*.i:.!)'" ll I !f~_;/:~t}ff:r,*;~,~.i1H .... ;~ IIUd f'!!I IIH,111',.:",.)
                                                                                                                ,....*..
,:r:*.-;:  
I
....... 1 ~:P;*,,; ~1 .-..;*,G VIRGINIA POWER NORTH CAROLI NA POWER NUCLEAA EMH~[RINO SERVICES RICitHO~.O.VIRCil,.IA
                                                                                                                        ,I I        I REACTOR COOLANf                                      I        I I        I PJMP                                CE~OR      I        I I       I
* INSERVICE INSPECTION ISOMETRIC RC SYS: LOOP A REACTOR COOLANT PIPE SURRY POWER STATION Ut,,!T I VIRGINIA POWER
                                ~                             l*RC*                                 l*RC*     I        I
* ** RELIEF REQUEST SR-013 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 0-07 3"-CH-113-1503 II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-1105B3 Class 2 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category C-F-1, item number C5.21 does not allow any limitations to the required volumetric or surface examinations.
                                ~                              r*IA                                 E*IA
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less thari 10 percent. Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to the configuration of the weld (pipe to valve) and a welded pipe support. Coverage of the volumetric examinations are detailed in Table SR-013-1.
[,;,"   ..".,..,. I I
Figure SR-013-1 is provided as graphic detail of the limitations experienced.
  *.    .... .,
Substitution with another weld of the same size would not necessarily improve the examination coverage since similar. geometric conditions are expected.
  . .:, 'CO'o"    ,'*,**,
:,*;:  ~
I                         CJ 11,~.J ..... ~ J.:,........ "
                                                                      ..:*',I                   _J cif;L I ~--; :- :~., I C-===:J 1...:,,., . . . ,I                                    CJ                                      'til .-..-
e!
:.**,*-(,
      ~                                                                                                Ll<lLl              ***'- !:*. .':*-* .*.:*                                       ..  .,;,
                                                                                                                                                                                                        *-*-:.
                                                                                                                                                                                        .:,:;,,,:*"*
      ~
                                                                                                                            *-*!.Ul'..*,,.:**I'>**,*
1J ,II .'l '.'.. , i ,I ,;,, ' -l
                                                                                                                              ~.r.: .. ' . .;     ~  . . . ., .....
l . . . . ; < ',*'.l i :~ '' .:.:- *             **,,
                                                                                                                                                                                        . *****.:**.
II
                                                                                                                                                                                          *"* ,*: *,' ~  I
                                                                                                                                                                                            ;;11!**"'*:-;**f,**
tlL,U 'I l'l*iC.' , ,
                                      /
                      &&#xa3;1:Ill!l    /
                      ~EJ;ill,
                      *l*RC;
                        .. Rel                                                                                            ,r .. -1,:,*J
::::e ~~:~:*.i:.!)'"           ll I
                                                                                                                                                                      !f~_;/:~t}ff:r,*;~,~.i1H t~~              ....; ~
IIUd f'!!I                               ,:r:*.-;: .......1 IIH,111',.:",.)                          ~:P;*,,; ~1 .-..;*,G t  ll,11'*'1 I'.:<:.' ;/
                                                                                                                                                                                                                *
                                                                                                                                ~~~                VIRGINIA POWER
                                                                                                                                ~\~ NORTH CAROLI NA POWER NUCLEAA EMH~[RINO SERVICES RICitHO~.O.VIRCil,.IA INSERVICE INSPECTION ISOMETRIC RC SYS: LOOP A REACTOR COOLANT PIPE SURRY POWER STATION Ut,,!T I VIRGINIA POWER
 
                    *                                     **
RELIEF REQUEST SR-013 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                         Drawing#                      Class Weld 0-07         3"-CH-113-1503               11448-WMKS-1105B3               2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category C-F-1, item number C5.21 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less thari 10 percent.
Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to the configuration of the weld (pipe to valve) and a welded pipe support. Coverage of the volumetric examinations are detailed in Table SR-013-1. Figure SR-013-1 is provided as graphic detail of the limitations experienced. Substitution with another weld of the same size would not necessarily improve the examination coverage since similar.
geometric conditions are expected.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
UT Scan Coverage Table SR-013-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WM KS-110583 Category C-F-1, Item CS.21 Surface Coverage%
 
Reason For Partial .. Weld No. 0-07 59 59 z 100 .a 100 100 Pipe to valve configuration prevented scanning from the 2 side (valve side). Welded support prevented 100% coverage from the elbow side. A 4T calibration was used to scan from the elbow side of the weld, where. accessible.
Table SR-013-1 Surry Unit 1                                                                             .
* UT Scan Direction Definitions 2 -Axial scan, 180 degrees from Isometric flow direction 5 -Axial scan, the same direction as the isometric flow 7 -Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 -Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
Examination Coverage Estimates (Piping) 11448-WM KS-110583 Category C-F-1, Item CS.21 UT Scan Coverage Surface Weld No.                              z      .a        Coverage%             Reason For Partial 0-07                 59     59     100     100             100               Pipe to valve configuration prevented scanning from the 2 side (valve side).
* Figure SR-013-1 1-CH-MOV-1373  
Welded support prevented 100% coverage from the elbow side. A 4T calibration was used to scan from the elbow side of the weld, where.
\ _____ _,, 0.400 11 distance from trunion to toe of weld. Trunion diameter is 3.2 11 lleld 0-07 l t *
accessible.
* e 7 6 5 4 3 l \\ NOTES, L~1!\~~~?[~~.~:1:::(gw~~~-i z.*1LL*1*r,c1,mtLII\SZA 11f:[C) ... f[II:._ !NIC .. ,US'/7 l'll[C,ll""-"IIAC""'"'I*
* UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
REFERENCE ORAWti-lGS1 11**1*,.S*Ur..lJ IIUl*CII' le!l*J5"..Z 11u1*"*au 11,.,.,,.z,~
* Figure SR-013-1 lleld 0-07 l
Pl'lllGSTll';Ho;.i,(Tt14 Ill Q.olSiifJCAIIO'I BC,.~\* c,u11,a,G Pl*IJroGCJ1*111:11G l'IP'l>G CJl**l"IC  
* 1-CH-MOV-1373
)-I '-> *
\ _____                             _,,       t 0.40011 distance from trunion to
* VIRGINIA POWER NORTH CAROLI NA POWER kJCLEAR E~lf.EERlhO SER'IICES RICH<<Jf<<JoYIRulHI" INSERVICE INSPECTION ISOMETRIC CHEMICAL ANO VOLUME CDNTfiJL SURRY POWER STATION UNIT I VIRGINIA POWER CAO"'* 1c.,,,,.,,.a1111121~q11.1so ll44IS*WMl(S*IIB'!1Bl  
* toe of weld. Trunion diameter is 3.2 11
....
 
e 7 6 5 4 3         l
                                                                                          )-
                                                                            \\             I
                                                                                          '->
NOTES, L~1!\~~~?[~~.~:1:::(gw~~~-i z.*1LL*1*r,c1,mtLII\SZA 11f:[C) ... f[II:._ !NIC..,US'/7 l'll[C,ll""-"IIAC""'"'I*
REFERENCE ORAWti-lGS1 11**1*,.S*Ur..lJ                 Pl'lllGSTll';Ho;.i,(Tt14 IIUl*CII' le!l*J5"..Z             Ill Q.olSiifJCAIIO'I BC,.~\* c,u11,a,G 11u1*"*au                        Pl*IJroGCJ1*111:11G 11,.,.,,.z,~                      l'IP'l>G CJl**l"IC
                                                                                        *
* VIRGINIA POWER NORTH CAROLI NA POWER kJCLEAR E~lf.EERlhO SER'IICES RICH<<Jf<<JoYIRulHI" INSERVICE INSPECTION ISOMETRIC CHEMICAL ANO VOLUME CDNTfiJL SURRY POWER STATION UNIT I VIRGINIA POWER CAO"'* 1c.,,,,.,,.a1111121~q11.1so ll44IS*WMl(S*IIB'!1Bl
                                                                                                ....
 
                    *
* RELIEF REQUEST SR-014 I. IDENTIFICATION OF COMPONENT Weld No.        Line#                          Drawing#                      Class Weld 1-01        1 1/2"-CH-97-1502              11448-WMKS-01 OOA 1Z          1 Weld 1-01        1 1/2"-CH-95-1502              11448-WMKS-0101 A 1Z          1 Weld 1-01        1 1/2"-CH-93-1502              11448-WMKS-0102A 1Z            1 II. IMPRACTICABLE CODE REQUIREMENTS For Surry Unit 1, Relief Request SR-008 was used for weld selection of Class 1 pressure retaining welds in piping in lieu of ASME Section XI, 1989 Edition, Table IWB-2500-1, Notes 1 (b) and 2 of Category B-J. Relief Request SR-008 was approved by NRC letter 95-404, dated 7-19-95. The relief request requires that all terminal ends of piping runs connected to vessels and pumps be examined.
Ill. BASIS FOR RELIEF The components listed above are terminal ends on seal injection piping connected to the reactor coolant pumps. The welds are completely inaccessible due to their closeness to the pump flange, i.e., they are underneath the flange. The attached picture shows the configuration on the "A" loop. However, when the reactor coolant pump main flange is disassembled, the weld is accessible for examination. All terminal end welds are scheduled for examination. Therefore, substitution with another weld is not feasible. However, another weld will be selected for examination in order to ensure that 25% of examination Category B-J welds will be examined.
IV. ALTERNATE PROVISIONS It is proposed that the system leakage test and the primary loop leakage monitoring performed by the station be substituted for the Code surface examination. If a reactor coolant pump main flange is disassembled, thereby making the weld accessible for examination, the weld will be examined consistent with Code requirements.          *
 
*
*
* RELIEF REQUEST SR-014 I. IDENTIFICATION OF COMPONENT Weld No. Weld 1-01 Weld 1-01 Weld 1-01 Line# 1 1/2"-CH-97-1502 1 1/2"-CH-95-1502 1 1/2"-CH-93-1502 II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-01 OOA 1 Z 11448-WMKS-0101 A 1 Z 11448-WMKS-0102A 1 Z Class 1 1 1 For Surry Unit 1, Relief Request SR-008 was used for weld selection of Class 1 pressure retaining welds in piping in lieu of ASME Section XI, 1989 Edition, Table IWB-2500-1, Notes 1 (b) and 2 of Category B-J. Relief Request SR-008 was approved by N RC letter 95-404, dated 7-19-95. The relief request requires that all terminal ends of piping runs connected to vessels and pumps be examined.
* SR-014-PICTURE
Ill. BASIS FOR RELIEF The components listed above are terminal ends on seal injection piping connected to the reactor coolant pumps. The welds are completely inaccessible due to their closeness to the pump flange, i.e., they are underneath the flange. The attached picture shows the configuration on the "A" loop. However, when the reactor coolant pump main flange is disassembled, the weld is accessible for examination.
* 11448-WMKS-OlOOAlZ
All terminal end welds are scheduled for examination.
* CEEJ" EL.16'-e* --..
Therefore, substitution with another weld is not feasible.
              ""'- ..........   \
However, another weld will be selected for examination in order to ensure that 25% of examination Category B-J welds will be examined.
CEtr.:                     CTE]
IV. ALTERNATE PROVISIONS It is proposed that the system leakage test and the primary loop leakage monitoring performed by the station be substituted for the Code surface examination.
I 1/2&deg; X 3/4* /
If a reactor coolant pump main flange is disassembled, thereby making the weld accessible for examination, the weld will be examined consistent with Code requirements.
REO
                              'le* LR ELL 2* JC J,4*
*
RED
* SR-014-PICTURE 
 
*
  *.,.
* CEEJ" EL.16'-e*  
11448~WMKS-0101A1Z
--.. ""'-..........
                                                                                                  ---
CEtr.: I 1/2&deg; X 3/4* / REO 11448-WMKS-OlOOAlZ
i.
\ CTE] 'le* LR ELL 2* JC J,4* RED
REACT~R ~OOLANT u p
*.,. i. 11448~WMKS-0101A1Z  
                            ,,,..'.
,,,..'. 2" X 1 112" RED / / / [IE] I 1 112" X JI~" r;rn/ 'l0" SW ELL '" REACT~R ~OOLANT u p *, \ .OJI] *, '* 'l0" SW ELL 'lJ:li] ' SCH. 160 [I]O / FLOOR SLEEVE FL ELl-13'-6" '-.J 2"-CH-94-1503-
2" X 1 112" RED /     /
! ISi CLAS~ 28 ISi CLASS IA ORIENTATION LOOKING EAST ---
                              /
I "-J *
[IE]
* 11448-WMKS-0102A1Z  
                                                                                  *,
'!0" SW ELL""* [J]D I 1/2" X 3/4" RED./ [IE] / (--l--,CH--"'35,..,,0""')  
                                                                                  \ .OJI]
/"/ ' / / mo / REACTOR COOLANT Eill:1e .... ***1-RC-** .. /*** ....... e::.lC ..... / JilD / / '!0" SW ELL ,FLANGE BOL T!NJ '.4 STUOS I 9 NUT~ ~OTE~ OJI] / [8D .I 2" X 3/4' RED. '!0" SW ELL 2"-(H*<!J-1502-" f z*-CH-'i2-!503-j ISi CLASS 28 151 CLASS IA ORIENTATION LOOKING NORTHWEST
                                                                              *,   '* 'l0" SW ELL
* RELIEF REQUEST SR-015 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 2-05 1-RS-P-2A II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-RS-P-2A Class 2 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.
                                                                                'lJ:li]
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is forty (40) percent. Figure SR-015-1 is provided as graphic detail of the limitations experienced.
                                      'l0" SW ELL I
Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.
1 112" X JI~" r;rn/
                                                    '" [I]O
                                                      '            SCH. 160 FLOOR SLEEVE FL ELl-13'-6"
                                                  /
                                                            '-.J 2"-CH-94-1503-     !
ISi CLAS~ 28 ISi CLASS IA ORIENTATION LOOKING EAST
 
I "-J
* 11448-WMKS-0102A1Z
* REACTOR COOLANT
[IE]
              '!0" SW ELL""*       /       (--l--,CH--"'35,..,,0""')                 Eill:1e
                                          /                                  .... ***1-RC- **..
[J]D
                                '
                                        / / mo                        /***.......e::.lC..... /
                                                          /"/
JilD
                                                                                    /   /   '!0" SW ELL OJI]
                                                    ,FLANGE BOL
                                                    '.4 STUOS T!NJ          /
I 9 NUT~
                                                    ~OTE~
                                                                                              '!0" SW ELL I 1/2" X 3/4" RED./
2"-(H*<!J-1502-
[8D
                                                .I "f   z*-CH-'i2-!503- j ISi CLASS 28 151 CLASS IA 2" X 3/4' RED.
ORIENTATION LOOKING NORTHWEST
* RELIEF REQUEST SR-015 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                             Drawing#                    Class Weld 2-05       1-RS-P-2A                         11448-WMKS-RS-P-2A           2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.
Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is forty (40) percent. Figure SR-015-1 is provided as graphic detail of the limitations experienced. Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
1-RS-P-2A Wall Side View Figure SR-015-1 <--Weld 2-05 ... 2 11 x 1 h 11 Ring Welded To Casing Inaccessible (Buried) ! 3V, 11 x3 11 xV, 11 THK Angle Iron 3 11 x3 11 xV, 11 THK Angle Iron Top View Wall <-Support/ Vibration Plate Circumference is 75 11* Starting at 0 11 , going clockwise, support extends from 23" to 53 11 , and makes this area inaccessible for surface examination. ( *I
 
* 11448-WMKS-RS-P-2A D D VS LC (&sect;I) D .* '-, < ~~.;) OUTS I DE REC I RC SPRAY PUMP TO 11448 -WMKS-0123N1 . t !0--Rs-q-15J3 --.Ji. _Q!SCH_~Q!;
Figure SR-015-1                                                                       (
1-RS-P-2A 3V, 11 x3 11 xV, 11 THK Angle Iron
                                                                                      <- Support/
Vibration Plate
                                                                                                          *I 3 11 x3 11 xV, 11 THK Angle Iron
              <-- Weld 2-05 Top View
                    ... 211 x1h11 Ring  Wall
* Welded To Casing Inaccessible (Buried)
                  !
Wall Side View Circumference is 75 11
* Starting at 011 , going clockwise, support extends from 23" to 53 11 , and makes           this   area   inaccessible for     surface examination.
 
11448-WMKS-RS-P-2A D                               <~~.;)
OUTS I DE REC I RC SPRAY PUMP D          D TO 11448
                                                                          -WMKS-0123N1
                                                                    . t !0--Rs-q-15J3 ~
                                                            --.Ji. _Q!SCH_~Q!;
GAUGE CONNECTION CAN DRAIN 1t'PIPE1
GAUGE CONNECTION CAN DRAIN 1t'PIPE1
* DETAIL E ---;o~~IJ~!~~~~v~~!T'fE6Ef~IL  
                                            .* '-,
,. 2'Xl/2'THK RING -::,,2:'.:!=~~=~  
VS LC
----'WELDED ro CASING ACCESS!BL~  
* DETAIL E
**. 12'-0' INACCESSIBLE FROM I 1448 -WMKS-1101AS DETAIL B
(&sect;I)
                                            ---;o~~IJ~!~~~~v~~!T'fE6Ef~IL
                                                      ,. 2'Xl/2'THK RING
                            -::,,2:'.:!=~~=~ ---- 'WELDED           ro CASING ACCESS!BL~ **. ~~ 12'-0' INACCESSIBLE JETAIL D FROM I 1448
-WMKS-1101AS
                                              . -..... DETAIL A 20 - 1 318' DETAIL B
* OET~IL C-...___,.
* OET~IL C-...___,.
JETAIL D . -..... DETAIL A 20 -1 318' 
 
' ' *
''
* RELIEF REQUEST SR-016 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 2-05 1-SI-P-1A II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-SI-P-1A Class 2 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.
                        *
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1 O percent. Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is thirty-seven (37) percent. Figure SR-016-1 is provided as graphic detail of the limitations experienced.
* RELIEF REQUEST SR-016 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                             Drawing#                Class Weld 2-05       1-SI-P-1A                         11448-WMKS-SI-P-1A         2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1O percent.
Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is thirty-seven (37) percent.
Figure SR-016-1 is provided as graphic detail of the limitations experienced.
Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.
Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
*
 
* Wall .., / ', 1-SI-P-1A Figure SR-016-1 .. Weld 2-05 .. 2 11 xY, 11 Ring Welded To Casing ,-----'--------!  
Figure SR-016-1 3'1,11 x3 11 x'l, 11 THK Angle Iron
\ Inaccessible (Buried) Side View 3'1, 11 x3 11 x'l, 11 THK Angle Iron Top View Wall .. Support/ Vibration Plate 0" Circumference is 75 11* Starting at 0 11 , going clockwise, support extends from 3 11 to 31", and makes this area inaccessible for surface examination .
* 1-SI-P-1A
' ' ". ** . .*. 11448-WMKS-SI-P-lA ITEi CSEE NOTE Jl TO 11448 -WM~S-0127CI 10'*51*84*152*  
                                                                                                      .. Support/
! VS LC @D STIFFENING RIB CTYP 41 12'*SH*l5J-
Vibration Plate 0"
! ITEi SEE DETAIL B ")TOR ' I COVER mTI . < ~:i~ ) LOWHEAD SAFETY INJECTION PUMP ISEE NOTE JI .__ SEE DETAIL E
                              .. Weld 2-05 Top View
                                    .. 211 xY, 11 Ring Wall Welded To Casing
* Inaccessible (Buried)
                      ,-----'--------!
Wall        \
Side View Circumference is 75 11
* Starting at 011 , going clockwise, support extends from 3 11 to 31", and makes             this   area   inaccessible   for   surface examination .
    ..,
  /
',
 
''
  ".
          **                                                                       . .*.     ~
11448-WMKS-SI-P-lA
                                                                                      .<~:i~
LOWHEAD SAFETY
                                                                                                      )
INJECTION PUMP
                                                      ")TOR ITEi CSEE NOTE Jl TO 11448                                     COVER
      -WM~S-0127CI 10'*51*84*152* !                                             mTI ISEE NOTE JI
                                                    'I
                                                                        .__ SEE DETAIL E VS LC
* SEE 11448*FV*5A CCET El
* SEE 11448*FV*5A CCET El
* FOR VIBRATION PLATE DETAJ. . . 2"Xll2'THK RING .. ., WELDED TO CASINO ACCESSIBLE  
                    @D                                                  *FOR VIBRATION PLATE DETAJ..
*. ~I, _12*~~-. iNACCESSIBLE  
                                                                              . 2"Xll2'THK RING
.. -Jtll'W<>I I_ Ti11CKNESS . SEE DETAIL D ,-l~~=SE!"!!!!I."--'--, -.-1 L--,,.--~SE---.ir-~-, '** -i u -~ SEE OETAIL A *---1:BLJ SEE DETAIL c ..___,'
                                                                        .. .,WELDED TO CASINO ACCESSIBLE *. ~I, _12*~~-.
" ... *
iNACCESSIBLE
* RELIEF REQUEST SR-017 I. IDENTIFICATION OF COMPONENT Weld No. Line# Weld 3-07BC 3"-RC-35-1502 II. IMPRACTICABLE CODE REQUIREMENTS Drawing# 11448-WMKS-0124A 1-1 Class. 1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category 8-J, item number 89.32 does not allow any limitations to the required surface examinations.
                                                                  .. -     Jtll'W<>I   I_ Ti11CKNESS STIFFENING RIB CTYP 41                                . SEE DETAIL D
Code Case N:..460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1 O percent. Ill. BASIS FOR RELIEF The weld listed above is covered by a reinforcement pad/saddle weld, which totally covers the examination area described in the Code. Therefore, examination coverage cannot be achieved due to the configuration of the piping. This weld is a branch connection and, as such, all welds of this type are scheduled for examination.
                                              ,-l~~=SE!"!!!!I."--'--,
L--,,.--~SE---.ir-~-,
                                                                                -.-1
                                                            '**
                                                                -i
                                                                ~u 12'*SH*l5J- !                                  -~ SEE OETAIL A ITEi                                *---1:BLJ SEE DETAIL B SEE DETAIL  c ..___,'
 
...
    "
                          *
* RELIEF REQUEST SR-017 I. IDENTIFICATION OF COMPONENT Weld No.         Line#                             Drawing#                Class.
Weld 3-07BC     3"-RC-35-1502                     11448-WMKS-0124A1-1       1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category 8-J, item number 89.32 does not allow any limitations to the required surface examinations.
Code Case N:..460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1O percent.
Ill. BASIS FOR RELIEF The weld listed above is covered by a reinforcement pad/saddle weld, which totally covers the examination area described in the Code. Therefore, examination coverage cannot be achieved due to the configuration of the piping. This weld is a branch connection and, as such, all welds of this type are scheduled for examination.
Therefore, substitution with another weld is not feasible.
Therefore, substitution with another weld is not feasible.
IV. ALTERNATE PROVISIONS It is proposed that a surface examination performed on the fillet weld of the reinforcement pad, and the system leakage test be substituted for the Code surface examination.
IV. ALTERNATE PROVISIONS It is proposed that a surface examination performed on the fillet weld of the reinforcement pad, and the system leakage test be substituted for the Code surface examination.
( l*RC*IJJ)
* 11448-WMKS-0124Al-1
:~: r:~: Bill Tll<<i 8 NJTS
    ~~
* 11 INOTE 41 ISi CLASS IA 3/4' NON CLASSED 11448-WMKS-0124Al-1 p i'*RC-42*682-SCH. 169 PRESSURIZER E-2 4'-RC*34*1592*
( l*RC*IJJ)               3/4' 4'-RC*34*1592*
SCH.129 ISi CLASS IA PRESSURIZER E-2 NON CLASSED . PRESSURIZER E-2 NON CLASSED 6'*RC*l7*'51l2*
SCH.129
SCH.128 1 &-*Rt-49*692*  
                                                                                                                                              *
! / SCH.169 i * * *}}
:~:r:~:
ISi CLASS IA NON CLASSED p                                          ISi CLASS IA NON CLASSED . PRESSURIZER I-RC-
* Bill Tll<<i                                                                                  E-2       NON 6'*RC*l7*'51l2*
8 NJTS
* 11                                                                                                                    SCH.128 CLASSED INOTE 41 i'*RC-42*682-                  PRESSURIZER SCH. 169                        l-RC-E-2 1&-*Rt-49*692* !
                                                                                                                            /   SCH.169 i
PRESSURIZER I-RC-E-2}}

Revision as of 01:14, 21 October 2019

Forwards Relief Requests SR-009 Through SR-017 Re Inservice Insp Program
ML18152A268
Person / Time
Site: Surry Dominion icon.png
Issue date: 04/23/1996
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-138, NUDOCS 9604250440
Download: ML18152A268 (35)


Text

  • April 23, 1996 United States Nuclear Regulatory Commission Serial No.96-138 Attention: Document Control Desk NL&OS/EJW Washington, D.C. *20555 Docket No. 50-280 License No. DPR-32 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the recent refueling outage, Surry Power Station Unit 1 completed examinations in the first period of its third ten year inservice inspection (ISi) interval. The component examination program is conducted in accordance with ASME Section XI 1989 Edition.

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from certain requirements of the ASME Section XI Code associated with partial examinations conducted during the 1995 Surry Unit 1 refueling outage. Relief Requests SR-009 through SR-017 (attached) provide the basis for the requested relief.

These relief requests have been approved by the Surry Station Nuclear Safety and Operating Committee.

If you have any questions concerning these requests, please contact us.

Very truly yours, James P. O'Hanlon Senior Vice President - Nuclear Attachments

- -

9604250440 9604-23 PDR ADOCK 05000280

~ PDR

\ ..

'

  • J
  • cc: United States Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

  • RELIEF REQUEST SR-009 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 1-12 27 1/2"-RC-9-2501 R 11448-WMKS-0102AZ-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number 89.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due* to the configuration of the weld (pipe to reactor coolant pump) and a 1" x 5" identification tag.

Coverage of the volumetric examinations are detailed in Table SR-009-1. Figure SR-009-1 is provided as graphic detail of the limitations experienced. This weld is a terminal end weld and, as such, all welds of this type are scheduled for examination.

Therefore, substitution with another weld is not feasible.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

Table SR-009-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-0102AZ-1 Category B-J, Item B9.11 UT Scan Coverage

  • Surface Weld No. 1 .8. Coverage% Reason For Partial 1-12 96.2 0 100 100 100 Pipe to reactor coolant pump configuration prevented scanning from the 5 side. A l" x 5" welded tag prevented full coverage, (76% coverage obtained) for the 5" of weld circumference on the 2 side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yz node examinations were possible.

UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction

  • 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow

Figure SR-009-1 Search Unit

  • 5 Side A

~1 Exam. Volume Exam. Volume

  • Hatched area (in examination volume) shows extent of coverage due to the I.D. Tag.

Seventy-six (76) percent of the volume was not examined for five (5) inches.

11448-WMKS-0102AZ-l

('""")

REACTOR COOLANT I I PUMP GE~OR I I

....*r*1tc....... I I

. ..... P-u£ . .> l*RC- I I
  • I I INOTE 'II

.....E*IC ... I I INOTE 111 I I COLD HOT LEG l~G

~ E DETAIL 'O"OH

'

'J L_4411-1tHKS*lllll2Alj JI'* 2'1'

'Ill" RED Ell

,-* ...x

{ EL. II'* 'I 15/16" ------V/

REACTOR VESSEL

~ **"

    • .. \ * * * ~,=s*--R-c--:--,-.,-5-.,2---1 l*RC-

......R*l ..... SEE DE TAIL 'A' ON 448*WHk5*1llll2Alj

'J INOTE 71

  • RELIEF REQUEST SR-010 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 1-11 31 "-RC-8-2501 R 11448-WMKS-0102AZ-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full coverage could not be achieved due to the configuration of the weld (pipe to reactor coolant pump) and a support. Coverage of the examinations are detailed in Table SR-010-1. Figure SR-010-1 is provided as graphic detail of the limitations experienced, where the weld could be examined. Figure SR-010-2 is provided to show the closeness of the support in relation to weld 1-11. The support is a massive welded and bolted structure that supports the reactor coolant pump and, as such, cannot be removed to allow access to weld 1-11. This weld is a terminal end and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

Table SR-010-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WM KS-0102AZ-1 .;.

Category 8-J, Item 89.11 UT Scan Coverage Surface Weld No.

1-11 0 49 46.5 50 Coverage%

50 Reason For Partial Pipe to reactor coolant pump configuration prevented scanning from the 2 side. A pipe support covering the weld from 270° to 90°, (9 O'clock to 3.

O'clock) prevented examination, both volumetric and surface, in this area.

The use of alternate angles would not have improved volumetric coverage.

Because of the use of the longitudinal wave form only 1/2 node

  • examinations were possible.

UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow

  • Figure SR-010-1 Search Unit Search Unit
  • 5 Side 2 Side I

V

~I

  • Exam. Volume Hatched area (in examination volume) shows lack of coverage due to configuration, i.e., six (6) percent of the examination volume was not examined.

Figure SR-010-2 Reactor coolant Pump

~--+-Weld 1-11 Component Su art

  • 31"-RC-8-2501R at \.leld 1-11 Pipe support--.

Top View

  • Side View

11448-WMKS-0102AZ-l (MH....

REACTOR COOLANT I I fYB.P OE~OR I I

        • r1te**..... "'i-Rt*""

I I

I I

\ .... P-1c* ... >

  • I I IIIOTE 'II

.... E-IC.... I I INIJJE II I I CIJ..D HOT LEG LEG

~ E DETAIL 'D'CIN j

' L4411*11NCS*lll2AZ~r-ll'* zqo

'Ill' RED ELL i EL, II"* 'I l!lil&'y/

TD 11441

  • Wl<<S*IUl3A7

' REACTOR *.........~ SEE llETAIL '&'ON j ll4411*WHKS*Bll2AZj

'rl""&"°*.~RC~-~:"-l*-15_0_2_*_1 VESSEL I-RC- .

......R*l ..... SEE OET AIL 'A' ON "]

INOTE 71 448*WHk5*BIB2AZj

\

  • **

RELIEF REQUEST SR-011 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 1-20 31 "-RC-8-2501 R 11448-WMKS-0102AZ-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category 8-J, item number 89.12 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent. Code Case N524 (b), (1) modifies Table IWB-2500-1, Note (4) and only requires that examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential examination volume.

Ill. BASIS FOR RELIEF The component listed above is inaccessible for both surface and volumetric examination. Examination could not be achieved due to the configuration of the support. A reactor coolant pump support/pipe support completely covers this longitudinal weld. The circumferential weld (1-11) that intersects with this longitudinal weld is a terminal end and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible. The adjacent longitudinal weld 1-21 (shown on drawing 11448-WMKS-0102AZ-1 and Figure SR-011-

1) was examined 100%, at weld 1-11, per Code Case N-524, with no reportable indications (NRI).

IV. ALTERNATE PROVISIONS It is proposed that the system leakage test be substituted for the Code surface and volumetric examination.

_J

Figure SR-011-1  !.

Reactor coolant Pump

~ Weld 1-11 (circumferential weld)

Weld 1-20 .... ~ Weld 1-21 (longitudinal weld) Component (longitudinal weld) Su ort is under component support.

31"-RC-8-2501R at Weld 1-11 Pipe support ....

Top View

  • Side View

!.

11448-lrl4KS-0102AZ-1 REACTOR COOLANT

,~....

I

)

I POMP GE~OR I I

.,..*r1tc***.. . I I

\ .... P*IC-... > l*RC- I I

  • I I

.....E*IC..... I I INOTE 'II I I

!NOTE Ill CDl.0

  • NOT LEG L!EG

~ E DETAIL 'O'ON ' ]

' L44ll*WHICS*1112AZ:J ll'X 2<r

'II' RED ELL l EL, II'* 'I 15/16' y/

' REACTOR

(_ ......\_ .. SEE DETAIL '8' ON -::1 114411*WHKS*lllll2AZj VESSEL I &'*RC*:'1-15112* I I-RC-

., ...... R*l ..... SEE DETAIL 'A' ON INOTE 71 448*WHKS*B1ll2AZj

\

  • RELIEF REQUEST SR-012 I. IDENTIFICATION OF COMPONENT Weld No. Line # D.rawing # Class Weld 1-05DM 29 11 -RC-1-2501 R 11448-WMKS-O 1OOAZ-1 1 Weld 1-06DM 31"-RC-2-2501R 11448-WMKS-01 OOAZ-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-F, item number 85.70 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. However, due to the configuration of the weld (pipe to steam generator nozzle to safe end butt weld) full volumetric coverage could not be achieved. Coverage of the volumetric examinations are detailed in Table SR-012-1. Figure SR-012-1 is provided as graphic detail of the limitations experienced. All welds of this type are scheduled for examination. Therefore, substitution with other welds is not feasible.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code*requirements.

Table SR-012-1 Surry Unit 1 Examination Coverage Estimates (Piping) 11448-WMKS-01 OOAZ-1 Category B-F, Item BS.70 UT Scan Coverage

  • Surface Weld No. 1 .8. Coverage% Reason For Partial l-05DM 0 80 50 50 100 Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yi node examinations were possible.

l-06DM 80 0 50 50 100 Pipe to steam generator nozzle to safe-end configuration prevented scanning from the nozzle side, and also prevented full scanning from the elbow side. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only Yi node examinations were possible

  • UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow

Figure SR-012-1 Search Unit

  • Nozzle Side Elbow Side

..... 43° Beam Angle

.,_ Exam. Volume t

  • Hatched area (in examination volume) shows extent of coverage due to configuration, i.e., 20% of the examination volllne was not examined.

,....*..

I

,I I I REACTOR COOLANf I I I I PJMP CE~OR I I I I

~ l*RC* l*RC* I I

~ r*IA E*IA

[,;," ..".,..,. I I

  • . .... .,

. .:, 'CO'o" ,'*,**,

,*;: ~

I CJ 11,~.J ..... ~ J.:,........ "

..:*',I _J cif;L I ~--; :- :~., I C-===:J 1...:,,., . . . ,I CJ 'til .-..-

e!

.**,*-(,

~ Ll<lLl ***'- !:*. .':*-* .*.:* .. .,;,

  • -*-:.

.:,:;,,,:*"*

~

  • -*!.Ul'..*,,.:**I'>**,*

1J ,II .'l '.'.. , i ,I ,;,, ' -l

~.r.: .. ' . .; ~ . . . ., .....

l . . . . ; < ',*'.l i :~ .:.:- * **,,

. *****.:**.

II

  • "* ,*: *,' ~ I
11!**"'*
-;**f,**

tlL,U 'I l'l*iC.' , ,

/

&£1:Ill!l /

~EJ;ill,

  • l*RC;

.. Rel ,r .. -1,:,*J

e ~~:~:*.i:.!)'" ll I

!f~_;/:~t}ff:r,*;~,~.i1H t~~ ....; ~

IIUd f'!!I ,:r:*.-;: .......1 IIH,111',.:",.) ~:P;*,,; ~1 .-..;*,G t ll,11'*'1 I'.:<:.' ;/

~~~ VIRGINIA POWER

~\~ NORTH CAROLI NA POWER NUCLEAA EMH~[RINO SERVICES RICitHO~.O.VIRCil,.IA INSERVICE INSPECTION ISOMETRIC RC SYS: LOOP A REACTOR COOLANT PIPE SURRY POWER STATION Ut,,!T I VIRGINIA POWER

  • **

RELIEF REQUEST SR-013 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 0-07 3"-CH-113-1503 11448-WMKS-1105B3 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category C-F-1, item number C5.21 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less thari 10 percent.

Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to the configuration of the weld (pipe to valve) and a welded pipe support. Coverage of the volumetric examinations are detailed in Table SR-013-1. Figure SR-013-1 is provided as graphic detail of the limitations experienced. Substitution with another weld of the same size would not necessarily improve the examination coverage since similar.

geometric conditions are expected.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

Table SR-013-1 Surry Unit 1 .

Examination Coverage Estimates (Piping) 11448-WM KS-110583 Category C-F-1, Item CS.21 UT Scan Coverage Surface Weld No. z .a Coverage% Reason For Partial 0-07 59 59 100 100 100 Pipe to valve configuration prevented scanning from the 2 side (valve side).

Welded support prevented 100% coverage from the elbow side. A 4T calibration was used to scan from the elbow side of the weld, where.

accessible.

  • UT Scan Direction Definitions 2 - Axial scan, 180 degrees from Isometric flow direction 5 - Axial scan, the same direction as the isometric flow 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow 8 - Circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow
  • Figure SR-013-1 lleld 0-07 l
  • 1-CH-MOV-1373

\ _____ _,, t 0.40011 distance from trunion to

  • toe of weld. Trunion diameter is 3.2 11

e 7 6 5 4 3 l

)-

\\ I

'->

NOTES, L~1!\~~~?[~~.~:1:::(gw~~~-i z.*1LL*1*r,c1,mtLII\SZA 11f:[C) ... f[II:._ !NIC..,US'/7 l'll[C,ll""-"IIAC""'"'I*

REFERENCE ORAWti-lGS1 11**1*,.S*Ur..lJ Pl'lllGSTll';Ho;.i,(Tt14 IIUl*CII' le!l*J5"..Z Ill Q.olSiifJCAIIO'I BC,.~\* c,u11,a,G 11u1*"*au Pl*IJroGCJ1*111:11G 11,.,.,,.z,~ l'IP'l>G CJl**l"IC

  • VIRGINIA POWER NORTH CAROLI NA POWER kJCLEAR E~lf.EERlhO SER'IICES RICH<<Jf<<JoYIRulHI" INSERVICE INSPECTION ISOMETRIC CHEMICAL ANO VOLUME CDNTfiJL SURRY POWER STATION UNIT I VIRGINIA POWER CAO"'* 1c.,,,,.,,.a1111121~q11.1so ll44IS*WMl(S*IIB'!1Bl

....

  • RELIEF REQUEST SR-014 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 1-01 1 1/2"-CH-97-1502 11448-WMKS-01 OOA 1Z 1 Weld 1-01 1 1/2"-CH-95-1502 11448-WMKS-0101 A 1Z 1 Weld 1-01 1 1/2"-CH-93-1502 11448-WMKS-0102A 1Z 1 II. IMPRACTICABLE CODE REQUIREMENTS For Surry Unit 1, Relief Request SR-008 was used for weld selection of Class 1 pressure retaining welds in piping in lieu of ASME Section XI, 1989 Edition, Table IWB-2500-1, Notes 1 (b) and 2 of Category B-J. Relief Request SR-008 was approved by NRC letter 95-404, dated 7-19-95. The relief request requires that all terminal ends of piping runs connected to vessels and pumps be examined.

Ill. BASIS FOR RELIEF The components listed above are terminal ends on seal injection piping connected to the reactor coolant pumps. The welds are completely inaccessible due to their closeness to the pump flange, i.e., they are underneath the flange. The attached picture shows the configuration on the "A" loop. However, when the reactor coolant pump main flange is disassembled, the weld is accessible for examination. All terminal end welds are scheduled for examination. Therefore, substitution with another weld is not feasible. However, another weld will be selected for examination in order to ensure that 25% of examination Category B-J welds will be examined.

IV. ALTERNATE PROVISIONS It is proposed that the system leakage test and the primary loop leakage monitoring performed by the station be substituted for the Code surface examination. If a reactor coolant pump main flange is disassembled, thereby making the weld accessible for examination, the weld will be examined consistent with Code requirements. *

  • SR-014-PICTURE
  • 11448-WMKS-OlOOAlZ
  • CEEJ" EL.16'-e* --..

""'- .......... \

CEtr.: CTE]

I 1/2° X 3/4* /

REO

'le* LR ELL 2* JC J,4*

RED

  • .,.

11448~WMKS-0101A1Z

---

i.

REACT~R ~OOLANT u p

,,,..'.

2" X 1 112" RED / /

/

[IE]

  • ,

\ .OJI]

  • , '* 'l0" SW ELL

'lJ:li]

'l0" SW ELL I

1 112" X JI~" r;rn/

'" [I]O

' SCH. 160 FLOOR SLEEVE FL ELl-13'-6"

/

'-.J 2"-CH-94-1503-  !

ISi CLAS~ 28 ISi CLASS IA ORIENTATION LOOKING EAST

I "-J

  • 11448-WMKS-0102A1Z

[IE]

'!0" SW ELL""* / (--l--,CH--"'35,..,,0""') Eill:1e

/ .... ***1-RC- **..

[J]D

'

/ / mo /***.......e::.lC..... /

/"/

JilD

/ / '!0" SW ELL OJI]

,FLANGE BOL

'.4 STUOS T!NJ /

I 9 NUT~

~OTE~

'!0" SW ELL I 1/2" X 3/4" RED./

2"-(H*<!J-1502-

[8D

.I "f z*-CH-'i2-!503- j ISi CLASS 28 151 CLASS IA 2" X 3/4' RED.

ORIENTATION LOOKING NORTHWEST

  • RELIEF REQUEST SR-015 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 2-05 1-RS-P-2A 11448-WMKS-RS-P-2A 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is forty (40) percent. Figure SR-015-1 is provided as graphic detail of the limitations experienced. Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

Figure SR-015-1 (

1-RS-P-2A 3V, 11 x3 11 xV, 11 THK Angle Iron

<- Support/

Vibration Plate

  • I 3 11 x3 11 xV, 11 THK Angle Iron

<-- Weld 2-05 Top View

... 211 x1h11 Ring Wall

  • Welded To Casing Inaccessible (Buried)

!

Wall Side View Circumference is 75 11

  • Starting at 011 , going clockwise, support extends from 23" to 53 11 , and makes this area inaccessible for surface examination.

11448-WMKS-RS-P-2A D <~~.;)

OUTS I DE REC I RC SPRAY PUMP D D TO 11448

-WMKS-0123N1

. t !0--Rs-q-15J3 ~

--.Ji. _Q!SCH_~Q!;

GAUGE CONNECTION CAN DRAIN 1t'PIPE1

.* '-,

VS LC

  • DETAIL E

(§I)

---;o~~IJ~!~~~~v~~!T'fE6Ef~IL

,. 2'Xl/2'THK RING

-::,,2:'.:!=~~=~ ---- 'WELDED ro CASING ACCESS!BL~ **. ~~ 12'-0' INACCESSIBLE JETAIL D FROM I 1448

-WMKS-1101AS

. -..... DETAIL A 20 - 1 318' DETAIL B

  • OET~IL C-...___,.

  • RELIEF REQUEST SR-016 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class Weld 2-05 1-SI-P-1A 11448-WMKS-SI-P-1A 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category C-G, item number C6.10 does not allow any limitations to the required surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1O percent.

Ill. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from a pump casing support. The reduction in coverage is thirty-seven (37) percent.

Figure SR-016-1 is provided as graphic detail of the limitations experienced.

Substitution with another weld is not feasible because the 11 8 11 pump has the same limitation.

IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

Figure SR-016-1 3'1,11 x3 11 x'l, 11 THK Angle Iron

  • 1-SI-P-1A

.. Support/

Vibration Plate 0"

.. Weld 2-05 Top View

.. 211 xY, 11 Ring Wall Welded To Casing

  • Inaccessible (Buried)

,-----'--------!

Wall \

Side View Circumference is 75 11

  • Starting at 011 , going clockwise, support extends from 3 11 to 31", and makes this area inaccessible for surface examination .

..,

/

',

".

    • . .*. ~

11448-WMKS-SI-P-lA

.<~:i~

LOWHEAD SAFETY

)

INJECTION PUMP

")TOR ITEi CSEE NOTE Jl TO 11448 COVER

-WM~S-0127CI 10'*51*84*152* ! mTI ISEE NOTE JI

'I

.__ SEE DETAIL E VS LC

  • SEE 11448*FV*5A CCET El

@D *FOR VIBRATION PLATE DETAJ..

. 2"Xll2'THK RING

.. .,WELDED TO CASINO ACCESSIBLE *. ~I, _12*~~-.

iNACCESSIBLE

.. - Jtll'W<>I I_ Ti11CKNESS STIFFENING RIB CTYP 41 . SEE DETAIL D

,-l~~=SE!"!!!!I."--'--,

L--,,.--~SE---.ir-~-,

-.-1

'**

-i

~u 12'*SH*l5J- ! -~ SEE OETAIL A ITEi *---1:BLJ SEE DETAIL B SEE DETAIL c ..___,'

...

"

  • RELIEF REQUEST SR-017 I. IDENTIFICATION OF COMPONENT Weld No. Line# Drawing# Class.

Weld 3-07BC 3"-RC-35-1502 11448-WMKS-0124A1-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWB-2500-1, examination Category 8-J, item number 89.32 does not allow any limitations to the required surface examinations.

Code Case N:..460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1O percent.

Ill. BASIS FOR RELIEF The weld listed above is covered by a reinforcement pad/saddle weld, which totally covers the examination area described in the Code. Therefore, examination coverage cannot be achieved due to the configuration of the piping. This weld is a branch connection and, as such, all welds of this type are scheduled for examination.

Therefore, substitution with another weld is not feasible.

IV. ALTERNATE PROVISIONS It is proposed that a surface examination performed on the fillet weld of the reinforcement pad, and the system leakage test be substituted for the Code surface examination.

  • 11448-WMKS-0124Al-1

~~

( l*RC*IJJ) 3/4' 4'-RC*34*1592*

SCH.129

~:r:~:

ISi CLASS IA NON CLASSED p ISi CLASS IA NON CLASSED . PRESSURIZER I-RC-

  • Bill Tll<<i E-2 NON 6'*RC*l7*'51l2*

8 NJTS

  • 11 SCH.128 CLASSED INOTE 41 i'*RC-42*682- PRESSURIZER SCH. 169 l-RC-E-2 1&-*Rt-49*692* !

/ SCH.169 i

PRESSURIZER I-RC-E-2