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=Text=
=Text=
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4; UNITED STATES O
4; UNITED STATES O
              %o                                                                                                    NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 u              <i g N Docket Nos.: 50-424 50-425 APPLICANT:                                       Georgia Power Company FACILITY:                                       Vogtle, Units 1 and 2
NUCLEAR REGULATORY COMMISSION o
u
<i WASHINGTON, D. C. 20555 N
g Docket Nos.: 50-424 50-425 APPLICANT:
Georgia Power Company FACILITY:
Vogtle, Units 1 and 2


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF MEETING HELD JUNE 4, 1986, ON V0GTLE ARBITRARY INTERMEDIATE PIPE BREAKS The staff met with the applicant and its representatives on June 4, 1986, to discuss the Vogtle arbitrary intermediate pipe break issue. Participants are listed in Enclosure 1.
OF MEETING HELD JUNE 4, 1986, ON V0GTLE ARBITRARY INTERMEDIATE PIPE BREAKS The staff met with the applicant and its representatives on June 4, 1986, to discuss the Vogtle arbitrary intermediate pipe break issue.
The current issue with Vogtle arbitrary intemediate pipe breaks (AIPBs) arose out of the staff's review of one of the applicant's readiness review modules which indicated that the applicant did not have a procedure to ensure that welded attachments would not be located within 5 pipe diameters of an AIPB location. Further, as stated in a {{letter dated|date=May 9, 1986|text=May 9,1986 letter}} from the applicant, six locations were identified which have welded attachments within 5 pipe dia-meters. The lack of a procedure and the six locations conflict with the staff's interpretation of attachment e to the applicant's {{letter dated|date=April 26, 1984|text=April 26, 1984 letter}} which indicated that no welded attachments were within 5 pipe diameters of an AIPB location. The applicant's {{letter dated|date=May 9, 1986|text=May 9,1986, letter}} discussed its analytical treat-ment of the six welded attachments. The meeting then clarified and expanded on the applicant's submittal.
Participants are listed in Enclosure 1.
In its presentation, the applicant explained that welded attachments at Vogtle were of five types: (1) lugs, (2)~ pipe stanchion dummy stub), (3) pipe stan-chion with reinforcing pad, (4) anchor strap, and 5) bearing pad. The applicant indicated that a review of 182 break locations (requested in their {{letter dated|date=November 11, 1983|text=letter dated November 11,1983}}) using piping and instrumentation drawings was conducted in March 1984. In July 1984, the applicant identified six break locations with welded attachments within 5 pipe diameters. The applicant analyzed these six locations per ASME Code NC/ND 3645 which it believed to be in accor-dance with the staff's evaluation dated June 28, 1984.                                                                                                                                                             In April 1986 the applicant again reviewed the break locations for welded attachments within 5 pipe diameters using stress isometric drawings and basing distance from the centerline of the welded attachments. This review identified six welded attachments within 5 pipe diameters of an AIPB. These six attachments were addressed in the applicant's {{letter dated|date=May 9, 1986|text=May 9, 1986, letter}}. Subsequently, the applicant again used stress isometric drawings to review welded attachment locations but also considered construction tolerances. The drawing review identified 37 potential attachments within 5 pipe diameters. The applicant conducted a plant walkdown of these 37 locations and found 14 attachments within 5 pipe diameters.
The current issue with Vogtle arbitrary intemediate pipe breaks (AIPBs) arose out of the staff's review of one of the applicant's readiness review modules which indicated that the applicant did not have a procedure to ensure that welded attachments would not be located within 5 pipe diameters of an AIPB location.
The applicant presented updated information at the meeting regarding these 14 welded attachments. Of these 14, four were voided dummy stubs with snubbers removed, and another durmly stub was enveloped by another attachment. Therefore, 8607090541 860702 PDR       ADOCK 05000424 A                                                                       PDR                                                                   _
Further, as stated in a {{letter dated|date=May 9, 1986|text=May 9,1986 letter}} from the applicant, six locations were identified which have welded attachments within 5 pipe dia-meters. The lack of a procedure and the six locations conflict with the staff's interpretation of attachment e to the applicant's {{letter dated|date=April 26, 1984|text=April 26, 1984 letter}} which indicated that no welded attachments were within 5 pipe diameters of an AIPB location. The applicant's {{letter dated|date=May 9, 1986|text=May 9,1986, letter}} discussed its analytical treat-ment of the six welded attachments. The meeting then clarified and expanded on the applicant's submittal.
In its presentation, the applicant explained that welded attachments at Vogtle were of five types:
(1) lugs, (2)~ pipe stanchion dummy stub), (3) pipe stan-chion with reinforcing pad, (4) anchor strap, and 5) bearing pad. The applicant indicated that a review of 182 break locations (requested in their {{letter dated|date=November 11, 1983|text=letter dated November 11,1983}}) using piping and instrumentation drawings was conducted in March 1984.
In July 1984, the applicant identified six break locations with welded attachments within 5 pipe diameters. The applicant analyzed these six locations per ASME Code NC/ND 3645 which it believed to be in accor-dance with the staff's evaluation dated June 28, 1984.
In April 1986 the applicant again reviewed the break locations for welded attachments within 5 pipe diameters using stress isometric drawings and basing distance from the centerline of the welded attachments. This review identified six welded attachments within 5 pipe diameters of an AIPB. These six attachments were addressed in the applicant's {{letter dated|date=May 9, 1986|text=May 9, 1986, letter}}. Subsequently, the applicant again used stress isometric drawings to review welded attachment locations but also considered construction tolerances. The drawing review identified 37 potential attachments within 5 pipe diameters. The applicant conducted a plant walkdown of these 37 locations and found 14 attachments within 5 pipe diameters.
The applicant presented updated information at the meeting regarding these 14 welded attachments. Of these 14, four were voided dummy stubs with snubbers removed, and another durmly stub was enveloped by another attachment. Therefore, 8607090541 860702 PDR ADOCK 05000424 A
PDR


l                                                                                             l the total locations evaluated was nine. The applicant indicated that it re-calculated the information contained in Attachment 1 to its {{letter dated|date=May 9, 1986|text=May 9,1986, letter}} for the nine attachments. The recalculation reduced conservatisms in the initial submittal. The three welded attachments additional to those in the May 9 letter are on the main feedwater, main steam, and chemical and volume control system lines. The applicant also discussed its proposal for considering local stresses within the zone of influence around a weld. The applicant stated that the contribution of local stresses from a welded attachment to general pipe stress will reduce to zero at a distance of 3 /RT, where R equals the pipe radius and T equals the nominal pipe thickness. Within that distance, the
l l the total locations evaluated was nine. The applicant indicated that it re-calculated the information contained in Attachment 1 to its {{letter dated|date=May 9, 1986|text=May 9,1986, letter}} for the nine attachments. The recalculation reduced conservatisms in the initial submittal. The three welded attachments additional to those in the May 9 letter are on the main feedwater, main steam, and chemical and volume control system lines. The applicant also discussed its proposal for considering local stresses within the zone of influence around a weld. The applicant stated that the contribution of local stresses from a welded attachment to general pipe stress will reduce to zero at a distance of 3 /RT, where R equals the pipe radius and T equals the nominal pipe thickness. Within that distance, the applicant proposes to add local stresses to general pipe stress. The staff i
  ;            applicant proposes to add local stresses to general pipe stress. The staff i             deemphasized this analysis criteria primarily because the staff concern with i             welded attachments on the main steam and feedwater lines involves unanticipated
deemphasized this analysis criteria primarily because the staff concern with i
:            loading conditions. Enclosure 3 contains the applicant's summary of total stresses at eliminated AIPB locations which have welded attachments within 5 l               pipe diameters.
welded attachments on the main steam and feedwater lines involves unanticipated loading conditions. Enclosure 3 contains the applicant's summary of total stresses at eliminated AIPB locations which have welded attachments within 5 l
The staff asked the applicant what would need to be done if welded attachments
pipe diameters.
;              had to be removed for cases 5 and 6 ({{letter dated|date=May 9, 1986|text=May 9,1986, letter}}) on the main steamline.
The staff asked the applicant what would need to be done if welded attachments had to be removed for cases 5 and 6 ({{letter dated|date=May 9, 1986|text=May 9,1986, letter}}) on the main steamline.
l             The applicant stated that insulation would have to be removed around the line l
l The applicant stated that insulation would have to be removed around the line l
and that energy absorbing material would need to be installed.
and that energy absorbing material would need to be installed.
Following a brief evaluation of the applicant's analytical consideration of the welded attachments within 5 pipe diameters of an AIPB location, the staff dis-cussed alternate guidelines to be used for welded attachments which would provide an equivalent level of safety to those provided in SRP Section 3.6.2 when elimination of AIPB's is implemented. The staff indicated that all cases of welded attachments within 5 pipe diameters of the AIPB location should be evaluated the same as those cases in Attachment 1 to the {{letter dated|date=May 9, 1986|text=May 9,1986, letter}}.
Following a brief evaluation of the applicant's analytical consideration of the welded attachments within 5 pipe diameters of an AIPB location, the staff dis-cussed alternate guidelines to be used for welded attachments which would provide an equivalent level of safety to those provided in SRP Section 3.6.2 when elimination of AIPB's is implemented.
In addition, because of the potential loading uncertainties which exist for the steam lines and main feedwater lines the applicant needs to assess the weak link in the pipe-to-pipe support load path. The weak link is defined as the point where the least design margin to design load allowables occurs. If the weak link is found to occur at the connection to the pipe, the applicant must consider the effects of a break at that location or redesign the load path.
The staff indicated that all cases of welded attachments within 5 pipe diameters of the AIPB location should be evaluated the same as those cases in Attachment 1 to the {{letter dated|date=May 9, 1986|text=May 9,1986, letter}}.
3               The applicant stated that it would submit information regarding the nine welded
In addition, because of the potential loading uncertainties which exist for the steam lines and main feedwater lines the applicant needs to assess the weak link in the pipe-to-pipe support load path.
!              attachments of concern including calculations in light of the staff's guidelines
The weak link is defined as the point where the least design margin to design load allowables occurs.
;              discussed above within about one ironth. The applicant also stated that it would submit the details of its proposal for considering local stresses from welded attachments based on the 3 /RT criteria presented at the meeting. The staff in-
If the weak link is found to occur at the connection to the pipe, the applicant must consider the effects of a break at that location or redesign the load path.
:              dicated that the applicant also needs to respond in writing to staff questions
3 The applicant stated that it would submit information regarding the nine welded attachments of concern including calculations in light of the staff's guidelines discussed above within about one ironth. The applicant also stated that it would submit the details of its proposal for considering local stresses from welded attachments based on the 3 /RT criteria presented at the meeting. The staff in-dicated that the applicant also needs to respond in writing to staff questions discussed with the applicant on May 20 and 22,1986. These questions are con-tained in Enclosure 2.
:              discussed with the applicant on May 20 and 22,1986. These questions are con-tained in Enclosure 2.
At the applicant's requests, seismic interaction of comodities was also discussed. The applicant stated that it has a gap criteria for interaction between safety-related equipment. The applicant further indicated that a sep-aration criteria does not exist between passive comodities (e.g., conduits, cable trays, pipe, ducts) but that structural integrity must be maintained.
At the applicant's requests, seismic interaction of comodities was also discussed. The applicant stated that it has a gap criteria for interaction between safety-related equipment. The applicant further indicated that a sep-aration criteria does not exist between passive comodities (e.g., conduits, cable trays, pipe, ducts) but that structural integrity must be maintained.
:              The staff indicated that possible interaction between such comodities is best determined by a plant walkdown of sefety-related systems by appropriate people.
The staff indicated that possible interaction between such comodities is best determined by a plant walkdown of sefety-related systems by appropriate people.
i f
i f


      ~
~
JUL 0 2 1926 The applicant described an analysis of potential worst case interactions which showed that components would still be able to perfom their functions. The staff requested the applicant to submit for staff review information describing in detail the analysis and justifying why the analysis is acceptable to replace plant walkdowns.
JUL 0 2 1926 The applicant described an analysis of potential worst case interactions which showed that components would still be able to perfom their functions. The staff requested the applicant to submit for staff review information describing in detail the analysis and justifying why the analysis is acceptable to replace plant walkdowns.
[
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Line 54: Line 63:
As stated l
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[4hPWR-A EBQ/[
Tler:lr         JBramer                                                                                                 DTerao         G agchi       BJYoungblood 7/ f /86               7/ / /86                                                                                                 7/ ) /86       7/ /E6         7/ Z /86
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Mr. R. E. Conway Georgia Power Company                   Vogtle Electric Generating Plant cc:
Mr. R. E. Conway Georgia Power Company Vogtle Electric Generating Plant cc:
Mr. L. T. Gucwa                         Resident Inspector Chief Nuclear Engineer                   Nuclear Regulatory Commission Georgia Power Company                   P. O. Box 572 P.O. Box 4545                           Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr. Ruble A. Thomas                     Deppish Kirkland, III, Counsel Vice President - Licensing               Office of the Consumers' Utility Vogtle Project                             Council Georgia Power Company /                 Suite 225 Southern Company Services, Inc.         32 Peachtree Street, N.W.
Mr. L. T. Gucwa Resident Inspector Chief Nuclear Engineer Nuclear Regulatory Commission Georgia Power Company P. O. Box 572 P.O. Box 4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr. Ruble A. Thomas Deppish Kirkland, III, Counsel Vice President - Licensing Office of the Consumers' Utility Vogtle Project Council Georgia Power Company /
P.O. Box 2625                           Atlanta, Georgia 30303 Birmingham, Alabama 35202 James E. Joiner Mr. Donald 0. Foster                     Troutman, Sanders, Lockerman, Vice President & Project General Manager   & Ashmore Georgia Power Company                   Candler Building Post Office Box 299A, Route 2           127 Peachtree Street, N.E.
Suite 225 Southern Company Services, Inc.
Waynesboro, Georgia 30830               Atlanta, Georgia 30303 Douglas C. Teper Mr. J. A. Bailey                         Georgians Against Nuclear Energy Project Licensing Manager               1253 Lenox Circle
32 Peachtree Street, N.W.
,      Southern Company Services, Inc.         Atlanta, Georgia 30306 P.O. Box 2625 Birmingham, Alabama 35202               Billie Pirner Garde Citizens Clinic Director Ernest L. Blake, Jr.                     Government Accountability Project Bruce W. Churchill, Esq.                 303 10th Street Shaw, Pittman, Potts and Trowbridge     Augusta, Georgia 30901 1800 M Street, N.W.
P.O. Box 2625 Atlanta, Georgia 30303 Birmingham, Alabama 35202 James E. Joiner Mr. Donald 0. Foster Troutman, Sanders, Lockerman, Vice President & Project General Manager
Washington, D. C. 20036 Mr. G. Bockhold, Jr.
& Ashmore Georgia Power Company Candler Building Post Office Box 299A, Route 2 127 Peachtree Street, N.E.
Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. , Suite 2900 Atlanta, Georgia 30323
Waynesboro, Georgia 30830 Atlanta, Georgia 30303 Douglas C. Teper Mr. J. A. Bailey Georgians Against Nuclear Energy Project Licensing Manager 1253 Lenox Circle Southern Company Services, Inc.
Atlanta, Georgia 30306 P.O. Box 2625 Birmingham, Alabama 35202 Billie Pirner Garde Citizens Clinic Director Ernest L. Blake, Jr.
Government Accountability Project Bruce W. Churchill, Esq.
303 10th Street Shaw, Pittman, Potts and Trowbridge Augusta, Georgia 30901 1800 M Street, N.W.
Washington, D. C.
20036 Mr. G. Bockhold, Jr.
Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323


ENCLOSURE 1                       ,
ENCLOSURE 1 PARTICIPANTS NRC Bechtel ITT~ Miller
PARTICIPANTS NRC                                                               Bechtel ITT~ Miller                                                       5. cereghino R. Bosnak                                                           D. Jagannathan G. Bagchi                                                         0. Gurbuz E. Girard                                                         G. Wang J. Brammer                                                         D. Capito D. Terao Georgia Power Company D. Hudson V. Hartka Southern Company Services
: 5. cereghino R. Bosnak D. Jagannathan G. Bagchi
: 0. Gurbuz E. Girard G. Wang J. Brammer D. Capito D. Terao Georgia Power Company D. Hudson V. Hartka Southern Company Services
: 0. Batum J. Bailey
: 0. Batum J. Bailey


Enclosure 2 Staff Questions Related to May 9, 1986, Letter
Staff Questions Related to May 9, 1986, Letter 1.
: 1. Identify the 6 systems in which the welded attachments in Attachment I are located. Are any of these systems subject to thermal cycling?
Identify the 6 systems in which the welded attachments in Attachment I are located. Are any of these systems subject to thermal cycling?
: 2. Identify the ASME Code Case which was used to calculate the " Code Case Method" stress in Attachment 1.
2.
: 3. Describe the type of attachr,ents in question, i.e., shear lugs, trunion, etc.
Identify the ASME Code Case which was used to calculate the " Code Case Method" stress in Attachment 1.
: 4. Do dummy stubs have potential to carry load? If so, is the support welded directly to the pipe or is there a saddle welded between the support and the pipe?
3.
Describe the type of attachr,ents in question, i.e., shear lugs, trunion, etc.
4.
Do dummy stubs have potential to carry load? If so, is the support welded directly to the pipe or is there a saddle welded between the support and the pipe?
l
l


                -                                                Enclosure 3
WE_JEJ ATTACHMENT REVIEW SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7001A ISOMETRIC.................
      .          WE_JEJ ATTACHMENT REVIEW SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7001A ISOMETRIC................. 1K3-1208-066-01 CURRENT HIGH STRESS POINT (CHSP)....... 26A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
1K3-1208-066-01 CURRENT HIGH STRESS POINT (CHSP).......
WITHIN 50 OF CHSP..........V1-1208-066-H006 PIPE SUPPCRT DATA POINT... 26A LOCATION................... AUX BLOG             LEVEL A STRESS DATA EOUATION 9+10           LOCAL STRESS                 9+10+ LOCAL STRESS
26A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
                                              ^       '      "      "        "
WITHIN 50 OF CHSP..........V1-1208-066-H006 PIPE SUPPCRT DATA POINT... 26A LOCATION................... AUX BLOG LEVEL A STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS
c OP 2GA     C DP 26A                     CODE CASE        W.R.C. CODE CASE W. R. C.
^
(CH3P)       (W/A)     METHOD           METHOD         METHOD       METHOD 8,363       8.363     4,910           6,620         13.273=       14.983=
c OP 2GA C DP 26A W. R. C.
                                                        '~
CODE CASE W.R.C.
                                      . 8( 1. 2 Sh + Sa )   -        32,752 PIPE BREAK THRESHOLD 3]rt 1. 79" 3/4" X 1/2" X 2"                                     26A LUG     XL)                     ,
CODE CASE (CH3P)
El Q   1
(W/A)
(         i9, 97                         9 ,0=
METHOD METHOD METHOD METHOD 8,363 8.363 4,910 6,620 13.273=
3, 5
14.983=
2" OIA PREVIOUS HIGHEST                 , ,
'~
STRESS LOCATION (RELOCATED DUE                             3" DIA TO FCR)
32,752 PIPE BREAK THRESHOLD
      = THE STRESS VALUES PREVr0USLY SUBMITTED WERE CONSERVATIVELY CALCU THESTRESSVALUESSHbWNREFLECTTHEACTUALAPPLICABLELOADCOMBINATIONS.
. 8( 1. 2 Sh + Sa )
3]rt
: 1. 79" 3/4" X 1/2" X 2" 26A LUG XL)
El Q
(
i9, 97 9,0=
1 3,
5 2"
OIA PREVIOUS HIGHEST STRESS LOCATION (RELOCATED DUE 3"
DIA TO FCR)
= THE STRESS VALUES PREVr0USLY SUBMITTED WERE CONSERVATIVELY CALCU THESTRESSVALUESSHbWNREFLECTTHEACTUALAPPLICABLELOADCOMBINATIONS.


WE_DEJ ATTACHMENT REVIEW 2               _
WE_DEJ ATTACHMENT REVIEW 2
SYSTEM.....................VASTE                 EVAPORATOR STEAM STRESS CALCULATION........ 70634 ISOMETRIC................. 1K3-1314-084-03 CURRENT HIGH STRESS POINT (CHSP)....... 800 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
SYSTEM.....................VASTE EVAPORATOR STEAM STRESS CALCULATION........ 70634 ISOMETRIC.................
WITHIN 5D OF CHSP..........V1-1314-084-H013 PIPE SUPPORT DATA POINT... 160 LOCATION................... AUX BLDG                   LEVEL A STRESS DATA EQUATION 9+10               LOCAL STRESS                   9+10+ LOCAL STRESS e DP 800     0 DP 160         W. R. C.       CODE CASE         W.R.C. CODE CASE       I (CHSP)         (W/A)       METHOD           METHOD         METHOD       METHOD 21,974       4.187       1,500           1,734           21,974       21,974     ,
1K3-1314-084-03 CURRENT HIGH STRESS POINT (CHSP).......
32,400              i' PIPE BREAK THRESHOLD             . 8( 1. 2 Sh + Sa )     .
800 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
WITHIN 5D OF CHSP..........V1-1314-084-H013 PIPE SUPPORT DATA POINT... 160 LOCATION................... AUX BLDG LEVEL A STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS e DP 800 0 DP 160 W. R. C.
CODE CASE W.R.C.
CODE CASE I
(CHSP)
(W/A)
METHOD METHOD METHOD METHOD 21,974 4.187 1,500 1,734 21,974 21,974 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
32,400 i'
l 34rt -3. 47 '
l 34rt -3. 47 '
160                   800 i
160 800 i
I l' X l'   X 3' LUG (HXWXL)
I l'
(TYP)
X l'
                                                    \
X 3' LUG (HXWXL)
                                                                ,,e PREVIOUS HIGHEST                   8'   DIA 3,
\\
STRESS LOCATION (RELOCATED OUE TO FCR)                               ,,g'
,,e (TYP)
          = PER WALKDOWN     .
PREVIOUS HIGHEST 8'
DIA 3,
STRESS LOCATION (RELOCATED OUE TO FCR)
,,g'
= PER WALKDOWN


WE_JEJ ATTACHMENT REVIEW
WE_JEJ ATTACHMENT REVIEW 23
                  -~
-~
23 SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7092 ISOMETRIC................. 1K4-1208-005-02 CURRENT HIGH STRESS POINT (CHSP)....... 88 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7092 ISOMETRIC.................
WITHIN 5D OF CHSP..........V1-1208-005-H006 PIPE SUPPORT DATA POINT... 90 LOCATION...................CONTMT BLOG               LEVEL 8 STRESS DATA EOUATION 9+10             LOCAL STRESS             9+10+ LOCAL     TRESS e DP 88     o DP 90         W.R.C.       CODE CASE     W.R.C.       CODE CASE (CHSP)         (w/A)     METHOD         METHOD     METHOD         METHOD   l 8.806       2.420         4.840       23,301        23 301 23 301
1K4-1208-005-02 CURRENT HIGH STRESS POINT (CHSP).......
                                    . 8( 1. 2 Sh + Sa ) -      32,126 PIPE BREAK THRESHOLD 3Jrt 2. 45" 90 3" X 2"     RED''                                   -
88 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
2' DIA                             3" DIA 88             e
WITHIN 5D OF CHSP..........V1-1208-005-H006 PIPE SUPPORT DATA POINT... 90 LOCATION...................CONTMT BLOG LEVEL 8 STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL TRESS e DP 88 o DP 90 W.R.C.
                                            'r'e.,
CODE CASE W.R.C.
CODE CASE (CHSP)
(w/A)
METHOD METHOD METHOD METHOD l
23 301 8.806 2.420 4.840 23,301 23 301 32,126 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
3Jrt 2. 45" 90 3"
X 2" RED''
2' DIA 3"
DIA 88 e
'r'e.,
3/4' X 1/2" X 2' LUG (HXWXL)
3/4' X 1/2" X 2' LUG (HXWXL)
(TYP)
(TYP)
    =  INACCESSIBLE DUE TO INSULATION.
INACCESSIBLE DUE TO INSULATION.
=
DIMENSION FROM Ac~ BUILT USED
DIMENSION FROM Ac~ BUILT USED


7 WE_DED ATTACHMENT REVIEW SYSTEM..................... CHEMICAL & VOLUME CONTROL, STRESS CALCULATION........ 7092 ISOMETRIC.................             1K4-1208'-005-02 CURRENT HIGH STRESS POINT ( CHSP ) . . . . . . . 156 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
WE_DED ATTACHMENT REVIEW 7
WITHIN 5D OF CHSP..........V1-1208-255-H001 PIPE SUPPORT DATA POINT... 155 LOCATION...................CONTMT BLDG                 LEVEL B             l STRESS DATA EOUATION 9+10             LOCAL STRESS                 9+10+ LOCAL STRESS
SYSTEM..................... CHEMICAL & VOLUME CONTROL, STRESS CALCULATION........ 7092 ISOMETRIC.................
* 1          #^'       "^ " ^ IU" 8 O DP 15S     o DP 155       W.R.C.       CODE CASE         W.R.C. CODE CASE (CHSP)       (W/A)       METHOD.           METHOD       METHOD       METHOD 24,297     8.997       2,420             4,840       24,297       24,297
1K4-1208'-005-02 CURRENT HIGH STRESS POINT ( CHSP )....... 156 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
                                      . 8( 1. 2 Sh + Sa )     -      32.126 PIPE BREAK THRESHOLD 3Jrt -2. 45' 3'   X 2' RED 155 2'   DIA s'                                                    3' DIA O               b Q
WITHIN 5D OF CHSP..........V1-1208-255-H001 PIPE SUPPORT DATA POINT... 155 LOCATION...................CONTMT BLDG LEVEL B STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS 1
Gr.*
#^'
3/4" X 1/2' X 2'
"^
        =  INACCESSIBLE DUE TO INSULATION                                 (T P l
^
ESTIMATED DIMENSION FROM FIELD WALKDOWN IS SLIGHTLY LARGER DIMENSIn" PAGM A9-BljILT USED         ,
IU" 8 O DP 15S o DP 155 W.R.C.
l t
CODE CASE W.R.C.
i
CODE CASE (CHSP)
(W/A)
METHOD.
METHOD METHOD METHOD 24,297 8.997 2,420 4,840 24,297 24,297 32.126 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
3Jrt -2. 45' 3'
X 2' RED 155 2'
DIA 3' DIA s'
O b Q Gr.
3/4" X 1/2' X 2' INACCESSIBLE DUE TO INSULATION (T P
=
ESTIMATED DIMENSION FROM FIELD l
WALKDOWN IS SLIGHTLY LARGER DIMENSIn" PAGM A9-BljILT USED l
t i


WELDED ATTACHMENT REVIEW 5               SvSTss.....................sA1N           STEAn STRESS CALCULATION........ 7073/74 ISOMETRIC................. 1K5-1301-001-01 CURRENT HIGH STRESS POINT ( CHSP ) . . . . . . . 68 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
WELDED ATTACHMENT REVIEW 5
WITHIN 5D OF CHSP..........V1-1301-008-H052 PIPE SUPPORT DATA POINT... 148 LOCATION................... AUX BLDG             LEVEL 1 STRESS DATA E
SvSTss.....................sA1N STEAn STRESS CALCULATION........ 7073/74 ISOMETRIC.................
EOUATION 9+10             LOCAL STRESS               q.1g. LOCAL STRESS c DP 148         (W/A)     MAX INTERACTION STRESS V. R. C.     CODE CASE       W.R.C. CODE CASE (CHSP)         W/       METHOD-         METHOD       METHOD       METHOD 10.487     12,410         13,691         33.541     33,541 33 541
1K5-1301-001-01 CURRENT HIGH STRESS POINT ( CHSP )....... 68 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
                                    . 8( 1. 2 Sh + Sa )   -        37,800 PIPE BREAK THRESHOLD 34rt - 10. 72" 148 12" DIA SCH DUMMY  STUB  80s \
WITHIN 5D OF CHSP..........V1-1301-008-H052 PIPE SUPPORT DATA POINT... 148 LOCATION................... AUX BLDG LEVEL 1 STRESS DATA E
68 1 1/4" THK                               38" X 26" RED REINFORCING PAD 3%
EOUATION 9+10 LOCAL STRESS q.1g. LOCAL STRESS c DP 148 (W/A)
SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD                     HIGHEST STRESS VALKDOWN. DIMENSION FROM AS-BUILT USED.                   LOATION
MAX INTERACTION STRESS V. R. C.
CODE CASE W.R.C.
CODE CASE (CHSP)
W/
METHOD-METHOD METHOD METHOD 33 541 10.487 12,410 13,691 33.541 33,541 37,800 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
34rt - 10. 72" 148 DIA SCH 80s \\
12" DUMMY STUB 68 38" X 26" RED 1 1/4" THK REINFORCING PAD 3%
SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD HIGHEST STRESS VALKDOWN. DIMENSION FROM AS-BUILT USED.
LOATION


WE_DED ATTACHMENT REVIEW 6               SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7073/74 ISOMETRIC................. 1K5-1301-001-01 CURRENT HIGH STRESS PDINT ( C H S P ) . . . . . . . . lji PIPE SUPPORT WITH WELDED ATTACHMENT ( W/A)
WE_DED ATTACHMENT REVIEW 6
WITHIN 5D OF CHSP..........V1-1301-008-H055 PIPE SUPPORT DATA POINT... 147 LOCATION................... AUX BLOG                 LEVEL 1 STRESS DATA EQUATION 9+10           LOCAL STRESS                       9+10+L CAL STRESS 4           A)         M   N         ION   Ess e DP 75       o DP 147     W.R.C.       CODE CASE               W.R.C.     CODE CASE (CHSP)       (W/A)     METHDD.           METHOD             METHDD         METHOD 24,646       14,326     8,850             8,368             24,646         24,646
SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7073/74 ISOMETRIC.................
                                  . 8( 1. 2 Sh + Sa )         -      37,800 PIPE BREAK THRESHOLD 26' DIA 75 O                   j I                               147
1K5-1301-001-01 CURRENT HIGH STRESS PDINT ( C H S P )........ lji PIPE SUPPORT WITH WELDED ATTACHMENT ( W/A)
                                        ,-          Jg
WITHIN 5D OF CHSP..........V1-1301-008-H055 PIPE SUPPORT DATA POINT... 147 LOCATION................... AUX BLOG LEVEL 1 STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+L CAL STRESS 4
                                      $b,)                               - 147A ENVELOPED 38' X 26' RED         ,        s
A)
                                                                =    -18'   DIA SCH 80 N                 DUMMY STUB (TYP)       l 38' DIA PIPE BREAK                                                                   l P-1055C SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD                         HIGHEST STRESS WALKDOWN. DIMENSION FROM AS-BUILT USED.                         LOCATION
M N
ION Ess e DP 75 o DP 147 W.R.C.
CODE CASE W.R.C.
CODE CASE (CHSP)
(W/A)
METHDD.
METHOD METHDD METHOD 24,646 14,326 8,850 8,368 24,646 24,646 37,800 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
26' DIA 75 O
j I
147 Jg
$b,)
- 147A ENVELOPED 38' X 26' RED s
-18' DIA SCH 80
=
N DUMMY STUB (TYP) 38' DIA PIPE BREAK P-1055C SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD HIGHEST STRESS WALKDOWN. DIMENSION FROM AS-BUILT USED.
LOCATION


I WELDEJ ATTACHMENT REVIEW 7               SysTes.....................sn1n seeOwATen STRESS CALCULATION........ 7072C ISOMETRIC................. 1K3-1305-154-01 CURRENT HIGH STRESS POINT (CHSP).......         11A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
I WELDEJ ATTACHMENT REVIEW 7
WITHIN 5D OF CHSP..........V1-1302-107-H001 PIPE SUPPORT DATA POINT... 11A LOCATION................... AUX BLDG             LEVEL A STRESS DATA EQUATION 9+10         BEARING STRESS                 9+10+ LOCAL STRESS eD                                                                 ^     "
SysTes.....................sn1n seeOwATen STRESS CALCULATION........ 7072C ISOMETRIC.................
(CHSP)       (W/A) 23,434       23,434             3.550                       26,984
1K3-1305-154-01 CURRENT HIGH STRESS POINT (CHSP).......
                                  . 8 ( 1. 2 Sh + Sa )     -        32,400 PIPE BREAK THRESHOLD 3J r- t - 3 . 92''
11A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
                                                  /
WITHIN 5D OF CHSP..........V1-1302-107-H001 PIPE SUPPORT DATA POINT... 11A LOCATION................... AUX BLDG LEVEL A STRESS DATA EQUATION 9+10 BEARING STRESS 9+10+ LOCAL STRESS eD
                                                      /
^
                                      / /
(CHSP)
(W/A) 23,434 23,434 3.550 26,984 32,400 PIPE BREAK THRESHOLD
. 8 ( 1. 2 Sh + Sa )
3J r-t - 3. 92''
/
/
/ /
1/2' TAK REINFORCING
1/2' TAK REINFORCING
                            //                                   PAD 1
/ /
PAD


WELDED ATTACHMENT REVIEW 8               SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7075 ISOMETRIC................. 1K5-1301-012-01                           l CURRENT HIGH STRESS POINT (CHSP)....... 255 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
WELDED ATTACHMENT REVIEW 8
WITHIN 5D OF CHSP..........V1-1301-012-H026 PIPE SUPPORT DATA POINT... 252 LOCATION................... TUNNEL IT68             LEVEL A I
SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7075 ISOMETRIC.................
STRESS DATA EOUATION 9+10           LOCAL STRESS               9+10+ LOCAL STRESS e DP 255     e DP 252     W. R. C. CODE CASE         W.R.C. CODE CASE (CHSP)         (W/A)     METHOD'         METHOD       METHOD         METHOD 27,716       15,917       680             837         27,716       27.716
1K5-1301-012-01 CURRENT HIGH STRESS POINT (CHSP).......
                                      . 8( 1. 2 Sh + Sa )   -          32,400 PIPE BREAK THRESHOLD 3ht - 2. 52" 55 1 ,
255 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
2 2, 1
WITHIN 5D OF CHSP..........V1-1301-012-H026 PIPE SUPPORT DATA POINT... 252 LOCATION................... TUNNEL IT68 LEVEL A I
                                                      'O.
STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS e DP 255 e DP 252 W. R. C.
t d                                           -
CODE CASE W.R.C.
CODE CASE (CHSP)
(W/A)
METHOD' METHOD METHOD METHOD 27,716 15,917 680 837 27,716 27.716 32,400 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
3ht - 2. 52" 55 22, 1
1
'O.
t d
p
p
                            <        /( N 3/4" X 1/2' X 2 1/2'
/(
                          /_'
N 3/4" X 1/2' X 2 1/2'
o 6'                        LUG ( HXWXL )
/_'
o 6
LUG ( HXWXL )
(TYP)
(TYP)
A                                                                 !
A 252 4'
252       ,,
DIA INACCESSIBLE FOR FIELD VALKDOWN
4' DIA
=
          =  INACCESSIBLE FOR FIELD VALKDOWN WORST CASE CONST.RUCTION TOLERANCE ASSUMED.
WORST CASE CONST.RUCTION TOLERANCE ASSUMED.


WELDED ATTACHMENT REVIEW 9                 SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7003A ISOMETRIC................. 1K7-1208-044-01 CURRENT HIGH STRESS POINT (CHSP).......           19 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
WELDED ATTACHMENT REVIEW 9
WITHIN 5D OF CHSP..........V1-1208-044-H015 PIPE SUPPORT DATA POINT... 17A LOCATION................... FUEL HDLG BLDG                                         LEVEL A STRESS DATA EQUATION 9+10               LOCAL STRESS                       9+10+ LOCAL STRESS
SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7003A ISOMETRIC.................
                                        *          ^     ' #^'             "    " ^ 0" e DP 19         c DP 17A                                               W.R.C.
1K7-1208-044-01 CURRENT HIGH STRESS POINT (CHSP).......
(CHSP)           (W/A)       W.R.C.        CODE CASE                                            CODE CASE METHOD.         METHOD               METHOD                         METHOD 18,783       7,219         4,070           8.877                 18,783                         18,783 PIPE BREAK THRESHOLD               . 8( 1. 2 Sh + Sa )           -        33,680 34rt - 1. 77 '
19 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)
1 1/2' DIA         18 9.
WITHIN 5D OF CHSP..........V1-1208-044-H015 PIPE SUPPORT DATA POINT... 17A LOCATION................... FUEL HDLG BLDG LEVEL A STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS
1 1/2' X l' SWG        /                                  3/4' X 1/2' X 1 1/4' 2' X l'   SWG                                                     (T P l
^
l             j 2' DIA 17A
#^'
          =  PER FIELD WALKDOWN
^
0" e DP 19 c DP 17A W.R.C.
CODE CASE W.R.C.
CODE CASE (CHSP)
(W/A)
METHOD.
METHOD METHOD METHOD 18,783 7,219 4,070 8.877 18,783 18,783 33,680 PIPE BREAK THRESHOLD
. 8( 1. 2 Sh + Sa )
34rt - 1. 77 '
1 1/2' DIA 18 9.
/
3/4' X 1/2' X 1 1/4' 1 1/2' X l' SWG 2'
X l' SWG (T P l
l j 2' DIA 17A PER FIELD WALKDOWN
=


F                                                                               l MEETING  
F l
MEETING  


==SUMMARY==
==SUMMARY==
DISTRIBUTION
DISTRIBUTION
            <MP                                       NRC Participants NRC PDR                                 R. Bosnak L PDR                                   G. Bagchi NSIC                                     E. Girard PRC System                               J. Brammer PWRf4 Reading File                       D. Terao M. Miller M. Duncan Attorney, OELD J. Partlow E. Jordan B. Grimes ACRS (10)
<MP NRC Participants NRC PDR R. Bosnak L PDR G. Bagchi NSIC E. Girard PRC System J. Brammer PWRf4 Reading File D. Terao M. Miller M. Duncan Attorney, OELD J. Partlow E. Jordan B. Grimes ACRS (10)
OTHERS bec: Licensee & Service List I
OTHERS bec: Licensee & Service List I
I t
I t
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        .-          _}}
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Latest revision as of 03:49, 8 December 2024

Summary of 860604 Meeting W/Util & Bechtel to Discuss Arbitrary Intermediate Pipe Break Issue.Attendance List, Staff Questions Re & Diagrams Encls
ML20199L667
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/02/1986
From: Mark Miller
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8607090541
Download: ML20199L667 (16)
v • d • e


Text

._

4; UNITED STATES O

NUCLEAR REGULATORY COMMISSION o

u

<i WASHINGTON, D. C. 20555 N

g Docket Nos.: 50-424 50-425 APPLICANT:

Georgia Power Company FACILITY:

Vogtle, Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING HELD JUNE 4, 1986, ON V0GTLE ARBITRARY INTERMEDIATE PIPE BREAKS The staff met with the applicant and its representatives on June 4, 1986, to discuss the Vogtle arbitrary intermediate pipe break issue.

Participants are listed in Enclosure 1.

The current issue with Vogtle arbitrary intemediate pipe breaks (AIPBs) arose out of the staff's review of one of the applicant's readiness review modules which indicated that the applicant did not have a procedure to ensure that welded attachments would not be located within 5 pipe diameters of an AIPB location.

Further, as stated in a May 9,1986 letter from the applicant, six locations were identified which have welded attachments within 5 pipe dia-meters. The lack of a procedure and the six locations conflict with the staff's interpretation of attachment e to the applicant's April 26, 1984 letter which indicated that no welded attachments were within 5 pipe diameters of an AIPB location. The applicant's May 9,1986, letter discussed its analytical treat-ment of the six welded attachments. The meeting then clarified and expanded on the applicant's submittal.

In its presentation, the applicant explained that welded attachments at Vogtle were of five types:

(1) lugs, (2)~ pipe stanchion dummy stub), (3) pipe stan-chion with reinforcing pad, (4) anchor strap, and 5) bearing pad. The applicant indicated that a review of 182 break locations (requested in their letter dated November 11,1983) using piping and instrumentation drawings was conducted in March 1984.

In July 1984, the applicant identified six break locations with welded attachments within 5 pipe diameters. The applicant analyzed these six locations per ASME Code NC/ND 3645 which it believed to be in accor-dance with the staff's evaluation dated June 28, 1984.

In April 1986 the applicant again reviewed the break locations for welded attachments within 5 pipe diameters using stress isometric drawings and basing distance from the centerline of the welded attachments. This review identified six welded attachments within 5 pipe diameters of an AIPB. These six attachments were addressed in the applicant's May 9, 1986, letter. Subsequently, the applicant again used stress isometric drawings to review welded attachment locations but also considered construction tolerances. The drawing review identified 37 potential attachments within 5 pipe diameters. The applicant conducted a plant walkdown of these 37 locations and found 14 attachments within 5 pipe diameters.

The applicant presented updated information at the meeting regarding these 14 welded attachments. Of these 14, four were voided dummy stubs with snubbers removed, and another durmly stub was enveloped by another attachment. Therefore, 8607090541 860702 PDR ADOCK 05000424 A

PDR

l l the total locations evaluated was nine. The applicant indicated that it re-calculated the information contained in Attachment 1 to its May 9,1986, letter for the nine attachments. The recalculation reduced conservatisms in the initial submittal. The three welded attachments additional to those in the May 9 letter are on the main feedwater, main steam, and chemical and volume control system lines. The applicant also discussed its proposal for considering local stresses within the zone of influence around a weld. The applicant stated that the contribution of local stresses from a welded attachment to general pipe stress will reduce to zero at a distance of 3 /RT, where R equals the pipe radius and T equals the nominal pipe thickness. Within that distance, the applicant proposes to add local stresses to general pipe stress. The staff i

deemphasized this analysis criteria primarily because the staff concern with i

welded attachments on the main steam and feedwater lines involves unanticipated loading conditions. Enclosure 3 contains the applicant's summary of total stresses at eliminated AIPB locations which have welded attachments within 5 l

pipe diameters.

The staff asked the applicant what would need to be done if welded attachments had to be removed for cases 5 and 6 (May 9,1986, letter) on the main steamline.

l The applicant stated that insulation would have to be removed around the line l

and that energy absorbing material would need to be installed.

Following a brief evaluation of the applicant's analytical consideration of the welded attachments within 5 pipe diameters of an AIPB location, the staff dis-cussed alternate guidelines to be used for welded attachments which would provide an equivalent level of safety to those provided in SRP Section 3.6.2 when elimination of AIPB's is implemented.

The staff indicated that all cases of welded attachments within 5 pipe diameters of the AIPB location should be evaluated the same as those cases in Attachment 1 to the May 9,1986, letter.

In addition, because of the potential loading uncertainties which exist for the steam lines and main feedwater lines the applicant needs to assess the weak link in the pipe-to-pipe support load path.

The weak link is defined as the point where the least design margin to design load allowables occurs.

If the weak link is found to occur at the connection to the pipe, the applicant must consider the effects of a break at that location or redesign the load path.

3 The applicant stated that it would submit information regarding the nine welded attachments of concern including calculations in light of the staff's guidelines discussed above within about one ironth. The applicant also stated that it would submit the details of its proposal for considering local stresses from welded attachments based on the 3 /RT criteria presented at the meeting. The staff in-dicated that the applicant also needs to respond in writing to staff questions discussed with the applicant on May 20 and 22,1986. These questions are con-tained in Enclosure 2.

At the applicant's requests, seismic interaction of comodities was also discussed. The applicant stated that it has a gap criteria for interaction between safety-related equipment. The applicant further indicated that a sep-aration criteria does not exist between passive comodities (e.g., conduits, cable trays, pipe, ducts) but that structural integrity must be maintained.

The staff indicated that possible interaction between such comodities is best determined by a plant walkdown of sefety-related systems by appropriate people.

i f

~

JUL 0 2 1926 The applicant described an analysis of potential worst case interactions which showed that components would still be able to perfom their functions. The staff requested the applicant to submit for staff review information describing in detail the analysis and justifying why the analysis is acceptable to replace plant walkdowns.

[

Melanie A. Miller, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A

Enclosures:

As stated l

l l

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W EB PWR#4/DPWR-A Tler:lr JBramer DTerao G agchi BJYoungblood 7/ f /86 7/ / /86 7/ ) /86 7/

/E6 7/ Z /86

Mr. R. E. Conway Georgia Power Company Vogtle Electric Generating Plant cc:

Mr. L. T. Gucwa Resident Inspector Chief Nuclear Engineer Nuclear Regulatory Commission Georgia Power Company P. O. Box 572 P.O. Box 4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr. Ruble A. Thomas Deppish Kirkland, III, Counsel Vice President - Licensing Office of the Consumers' Utility Vogtle Project Council Georgia Power Company /

Suite 225 Southern Company Services, Inc.

32 Peachtree Street, N.W.

P.O. Box 2625 Atlanta, Georgia 30303 Birmingham, Alabama 35202 James E. Joiner Mr. Donald 0. Foster Troutman, Sanders, Lockerman, Vice President & Project General Manager

& Ashmore Georgia Power Company Candler Building Post Office Box 299A, Route 2 127 Peachtree Street, N.E.

Waynesboro, Georgia 30830 Atlanta, Georgia 30303 Douglas C. Teper Mr. J. A. Bailey Georgians Against Nuclear Energy Project Licensing Manager 1253 Lenox Circle Southern Company Services, Inc.

Atlanta, Georgia 30306 P.O. Box 2625 Birmingham, Alabama 35202 Billie Pirner Garde Citizens Clinic Director Ernest L. Blake, Jr.

Government Accountability Project Bruce W. Churchill, Esq.

303 10th Street Shaw, Pittman, Potts and Trowbridge Augusta, Georgia 30901 1800 M Street, N.W.

Washington, D. C.

20036 Mr. G. Bockhold, Jr.

Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323

ENCLOSURE 1 PARTICIPANTS NRC Bechtel ITT~ Miller

5. cereghino R. Bosnak D. Jagannathan G. Bagchi
0. Gurbuz E. Girard G. Wang J. Brammer D. Capito D. Terao Georgia Power Company D. Hudson V. Hartka Southern Company Services
0. Batum J. Bailey

Staff Questions Related to May 9, 1986, Letter 1.

Identify the 6 systems in which the welded attachments in Attachment I are located. Are any of these systems subject to thermal cycling?

2.

Identify the ASME Code Case which was used to calculate the " Code Case Method" stress in Attachment 1.

3.

Describe the type of attachr,ents in question, i.e., shear lugs, trunion, etc.

4.

Do dummy stubs have potential to carry load? If so, is the support welded directly to the pipe or is there a saddle welded between the support and the pipe?

l

WE_JEJ ATTACHMENT REVIEW SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7001A ISOMETRIC.................

1K3-1208-066-01 CURRENT HIGH STRESS POINT (CHSP).......

26A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 50 OF CHSP..........V1-1208-066-H006 PIPE SUPPCRT DATA POINT... 26A LOCATION................... AUX BLOG LEVEL A STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS

^

c OP 2GA C DP 26A W. R. C.

CODE CASE W.R.C.

CODE CASE (CH3P)

(W/A)

METHOD METHOD METHOD METHOD 8,363 8.363 4,910 6,620 13.273=

14.983=

'~

32,752 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

3]rt

1. 79" 3/4" X 1/2" X 2" 26A LUG XL)

El Q

(

i9, 97 9,0=

1 3,

5 2"

OIA PREVIOUS HIGHEST STRESS LOCATION (RELOCATED DUE 3"

DIA TO FCR)

= THE STRESS VALUES PREVr0USLY SUBMITTED WERE CONSERVATIVELY CALCU THESTRESSVALUESSHbWNREFLECTTHEACTUALAPPLICABLELOADCOMBINATIONS.

WE_DEJ ATTACHMENT REVIEW 2

SYSTEM.....................VASTE EVAPORATOR STEAM STRESS CALCULATION........ 70634 ISOMETRIC.................

1K3-1314-084-03 CURRENT HIGH STRESS POINT (CHSP).......

800 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1314-084-H013 PIPE SUPPORT DATA POINT... 160 LOCATION................... AUX BLDG LEVEL A STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS e DP 800 0 DP 160 W. R. C.

CODE CASE W.R.C.

CODE CASE I

(CHSP)

(W/A)

METHOD METHOD METHOD METHOD 21,974 4.187 1,500 1,734 21,974 21,974 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

32,400 i'

l 34rt -3. 47 '

160 800 i

I l'

X l'

X 3' LUG (HXWXL)

\\

,,e (TYP)

PREVIOUS HIGHEST 8'

DIA 3,

STRESS LOCATION (RELOCATED OUE TO FCR)

,,g'

= PER WALKDOWN

WE_JEJ ATTACHMENT REVIEW 23

-~

SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7092 ISOMETRIC.................

1K4-1208-005-02 CURRENT HIGH STRESS POINT (CHSP).......

88 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1208-005-H006 PIPE SUPPORT DATA POINT... 90 LOCATION...................CONTMT BLOG LEVEL 8 STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL TRESS e DP 88 o DP 90 W.R.C.

CODE CASE W.R.C.

CODE CASE (CHSP)

(w/A)

METHOD METHOD METHOD METHOD l

23 301 8.806 2.420 4.840 23,301 23 301 32,126 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

3Jrt 2. 45" 90 3"

X 2" RED

2' DIA 3"

DIA 88 e

'r'e.,

3/4' X 1/2" X 2' LUG (HXWXL)

(TYP)

INACCESSIBLE DUE TO INSULATION.

=

DIMENSION FROM Ac~ BUILT USED

WE_DED ATTACHMENT REVIEW 7

SYSTEM..................... CHEMICAL & VOLUME CONTROL, STRESS CALCULATION........ 7092 ISOMETRIC.................

1K4-1208'-005-02 CURRENT HIGH STRESS POINT ( CHSP )....... 156 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1208-255-H001 PIPE SUPPORT DATA POINT... 155 LOCATION...................CONTMT BLDG LEVEL B STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS 1

  1. ^'

"^

^

IU" 8 O DP 15S o DP 155 W.R.C.

CODE CASE W.R.C.

CODE CASE (CHSP)

(W/A)

METHOD.

METHOD METHOD METHOD 24,297 8.997 2,420 4,840 24,297 24,297 32.126 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

3Jrt -2. 45' 3'

X 2' RED 155 2'

DIA 3' DIA s'

O b Q Gr.

3/4" X 1/2' X 2' INACCESSIBLE DUE TO INSULATION (T P

=

ESTIMATED DIMENSION FROM FIELD l

WALKDOWN IS SLIGHTLY LARGER DIMENSIn" PAGM A9-BljILT USED l

t i

WELDED ATTACHMENT REVIEW 5

SvSTss.....................sA1N STEAn STRESS CALCULATION........ 7073/74 ISOMETRIC.................

1K5-1301-001-01 CURRENT HIGH STRESS POINT ( CHSP )....... 68 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1301-008-H052 PIPE SUPPORT DATA POINT... 148 LOCATION................... AUX BLDG LEVEL 1 STRESS DATA E

EOUATION 9+10 LOCAL STRESS q.1g. LOCAL STRESS c DP 148 (W/A)

MAX INTERACTION STRESS V. R. C.

CODE CASE W.R.C.

CODE CASE (CHSP)

W/

METHOD-METHOD METHOD METHOD 33 541 10.487 12,410 13,691 33.541 33,541 37,800 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

34rt - 10. 72" 148 DIA SCH 80s \\

12" DUMMY STUB 68 38" X 26" RED 1 1/4" THK REINFORCING PAD 3%

SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD HIGHEST STRESS VALKDOWN. DIMENSION FROM AS-BUILT USED.

LOATION

WE_DED ATTACHMENT REVIEW 6

SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7073/74 ISOMETRIC.................

1K5-1301-001-01 CURRENT HIGH STRESS PDINT ( C H S P )........ lji PIPE SUPPORT WITH WELDED ATTACHMENT ( W/A)

WITHIN 5D OF CHSP..........V1-1301-008-H055 PIPE SUPPORT DATA POINT... 147 LOCATION................... AUX BLOG LEVEL 1 STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+L CAL STRESS 4

A)

M N

ION Ess e DP 75 o DP 147 W.R.C.

CODE CASE W.R.C.

CODE CASE (CHSP)

(W/A)

METHDD.

METHOD METHDD METHOD 24,646 14,326 8,850 8,368 24,646 24,646 37,800 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

26' DIA 75 O

j I

147 Jg

$b,)

- 147A ENVELOPED 38' X 26' RED s

-18' DIA SCH 80

=

N DUMMY STUB (TYP) 38' DIA PIPE BREAK P-1055C SAME AS PREVIOUS INACCESSIBLE DUE TO INSULATION PER FIELD HIGHEST STRESS WALKDOWN. DIMENSION FROM AS-BUILT USED.

LOCATION

I WELDEJ ATTACHMENT REVIEW 7

SysTes.....................sn1n seeOwATen STRESS CALCULATION........ 7072C ISOMETRIC.................

1K3-1305-154-01 CURRENT HIGH STRESS POINT (CHSP).......

11A PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1302-107-H001 PIPE SUPPORT DATA POINT... 11A LOCATION................... AUX BLDG LEVEL A STRESS DATA EQUATION 9+10 BEARING STRESS 9+10+ LOCAL STRESS eD

^

(CHSP)

(W/A) 23,434 23,434 3.550 26,984 32,400 PIPE BREAK THRESHOLD

. 8 ( 1. 2 Sh + Sa )

3J r-t - 3. 92

/

/

/ /

1/2' TAK REINFORCING

/ /

PAD

WELDED ATTACHMENT REVIEW 8

SYSTEM..................... MAIN STEAM STRESS CALCULATION........ 7075 ISOMETRIC.................

1K5-1301-012-01 CURRENT HIGH STRESS POINT (CHSP).......

255 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1301-012-H026 PIPE SUPPORT DATA POINT... 252 LOCATION................... TUNNEL IT68 LEVEL A I

STRESS DATA EOUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS e DP 255 e DP 252 W. R. C.

CODE CASE W.R.C.

CODE CASE (CHSP)

(W/A)

METHOD' METHOD METHOD METHOD 27,716 15,917 680 837 27,716 27.716 32,400 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

3ht - 2. 52" 55 22, 1

1

'O.

t d

p

/(

N 3/4" X 1/2' X 2 1/2'

/_'

o 6

LUG ( HXWXL )

(TYP)

A 252 4'

DIA INACCESSIBLE FOR FIELD VALKDOWN

=

WORST CASE CONST.RUCTION TOLERANCE ASSUMED.

WELDED ATTACHMENT REVIEW 9

SYSTEM..................... CHEMICAL & VOLUME CONTROL STRESS CALCULATION........ 7003A ISOMETRIC.................

1K7-1208-044-01 CURRENT HIGH STRESS POINT (CHSP).......

19 PIPE SUPPORT WITH WELDED ATTACHMENT (W/A)

WITHIN 5D OF CHSP..........V1-1208-044-H015 PIPE SUPPORT DATA POINT... 17A LOCATION................... FUEL HDLG BLDG LEVEL A STRESS DATA EQUATION 9+10 LOCAL STRESS 9+10+ LOCAL STRESS

^

  1. ^'

^

0" e DP 19 c DP 17A W.R.C.

CODE CASE W.R.C.

CODE CASE (CHSP)

(W/A)

METHOD.

METHOD METHOD METHOD 18,783 7,219 4,070 8.877 18,783 18,783 33,680 PIPE BREAK THRESHOLD

. 8( 1. 2 Sh + Sa )

34rt - 1. 77 '

1 1/2' DIA 18 9.

/

3/4' X 1/2' X 1 1/4' 1 1/2' X l' SWG 2'

X l' SWG (T P l

l j 2' DIA 17A PER FIELD WALKDOWN

=

F l

MEETING

SUMMARY

DISTRIBUTION

<MP NRC Participants NRC PDR R. Bosnak L PDR G. Bagchi NSIC E. Girard PRC System J. Brammer PWRf4 Reading File D. Terao M. Miller M. Duncan Attorney, OELD J. Partlow E. Jordan B. Grimes ACRS (10)

OTHERS bec: Licensee & Service List I

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i I

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