ML18153B285: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:e                                     e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 11, 1993 United States Nuclear Regulatory Commission                             Serial No. 93-419 Attention: Document Control Desk                                         SPS/ETS Washington, D. C. 20555                                                 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
{{#Wiki_filter:.,,,.----
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 SECOND TEN YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUESTS Surry Power Station Units 1 and 2 are currently in the third period of their second ten year intervals. Second interval inspection requirements are scheduled to be completed in the refueling outages currently scheduled to start in February 1994 and September 1994 for Surry Units 1 and 2, respectively. Previously by letter dated January 26, 1993 (Serial No. 93-002), relief requests were submitted to close out the second ten year interval. Pursuant to 1O CFR 50.55a(g)(5), additional relief from specific Code requirements for Surry Units 1 and 2 is being requested. The basis for each relief request is provided in the Attachments to this letter.
L e
In addition, Relief Request 24 for Surry Unit 2 is being resubmitted to incorporate components not included in the January 26, 1993 letter, that were replaced during the recent Unit 2 refueling outage.
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 11, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 SECOND TEN YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUESTS Serial No.
SPS/ETS Docket Nos.
License Nos.
93-419 50-280 50-281 DPR-32 DPR-37 Surry Power Station Units 1 and 2 are currently in the third period of their second ten year intervals. Second interval inspection requirements are scheduled to be completed in the refueling outages currently scheduled to start in February 1994 and September 1994 for Surry Units 1 and 2, respectively. Previously by {{letter dated|date=January 26, 1993|text=letter dated January 26, 1993}} (Serial No. 93-002), relief requests were submitted to close out the second ten year interval.
Pursuant to 1 O CFR 50.55a(g)(5), additional relief from specific Code requirements for Surry Units 1 and 2 is being requested. The basis for each relief request is provided in the Attachments to this letter.
In addition, Relief Request 24 for Surry Unit 2 is being resubmitted to incorporate components not included in the {{letter dated|date=January 26, 1993|text=January 26, 1993 letter}}, that were replaced during the recent Unit 2 refueling outage.
These requests have been reviewed by the Station Nuclear Safety and Operating Committee.
These requests have been reviewed by the Station Nuclear Safety and Operating Committee.
If you have questions regarding this information, please contact us.
If you have questions regarding this information, please contact us.
Very truly )'?u\s,
Very truly )'?u\\s,  
              .\ j t L,. 9:J*'
. j,., 9:J*' )_1
              .               )_1*~,--~-
' '/ _'-.... \\ *~,--~-
                          *'\"'QJ.~j<:\
\\ t L * \\"'QJ.~j <:\\ ---*~---...
                                '/ _'-....\
W. L. Stewart Senior Vice President - Nuclear Attachments 1 r.: n l0 0,.. i
                                                ---*~--- ...
.... (J I,' \\
W. L. Stewart Senior Vice President - Nuclear Attachments 1 r.: n l0 0
' ~~
                                  .... (J I ,' \ -'
9308160215 93osii n1*.,-
                                                      ,..~~i
PDR ADOCK 05000280 u*\\
                                                      '
Q PDR  
.,,,.----
9308160215       93osii                   n*.,-
PDR   ADOCK 05000280                       1u*\
Q                             PDR


cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
cc:
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Surry Unit 1 ISi Relief Requests


Attachment 1 Surry Unit 1 ISi Relief Requests
RELJ:EF REQUEST 28 I.
IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II.
IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded repairs or installation of replacement items by welding.
III.
BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME Section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundaryg These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the* approval in Regulatory Guide 1.147, Code Case N-498, 11 Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.
IV.
ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative requirements shall be applied:
: 1)
NDE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.


RELJ:EF REQUEST 28 I. IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II. IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded repairs or installation of replacement items by welding.
L RELIEF REQUEST 28 (COlf 1 T)
III. BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME Section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundaryg These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the* approval in Regulatory Guide 1.147, Code Case N-498, 11 Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.
. 2)
IV. ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative requirements shall be applied:
Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.
: 1)  NDE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no          .
: 3)
construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.
Use of this alternative shall be documented on the NIS-2 Form.
If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing *have been met.  


RELIEF REQUEST 28 (COlf 1 T)
RELIEF REQUEST 29 I.
  . 2)  Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.
IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:
: 3)  Use of this alternative shall be documented on the NIS-2 Form.
11448-CBM-89B 1-SI-79 1-SI-82 1-SI-85 1-SI-88 1-SI-91 1-SI-94 AND AND AND AND AND AND 1-SI-235, 1-SI-241 1-SI-236, 1-SI-242 1-SI-237, 1-SI-243 1-SI-238 1-SI-239 1-SI-240 (Drawings Attached)
If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing *have been met.
Function Class
L
: Safety Injection System
: 1 II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.
III.
BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.
IV.
ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure.
The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.
This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.


RELIEF REQUEST 29 I. IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:
- --.-*..a,te 8?80*H8J-81>"11 "Oolo.llAIIIIICI CCI.DL!GLID'Z  
11448-CBM-89B 1-SI-79  AND  1-SI-235, 1-SI-241 1-SI-82  AND  1-SI-236, 1-SI-242 1-SI-85  AND  1-SI-237, 1-SI-243 1-SI-88  AND  1-SI-238 1-SI-91  AND  1-SI-239 1-SI-94  AND  1-SI-240 (Drawings Attached)
&#xa9; UU&-FM~Slt.1 21*5D'*l'"1... **'5 ll}!jof~,11USIIIS'l64fff*ITI
Function    : Safety Injection System Class        : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.
&#xa3; G:) G:)
III. BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.
IV. ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure. The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.
This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.
 
- --.-*..a,te
  .,,.          8?80*H8J-81>"11 "Oolo.llAIIIIICI 5                                                  2 L.FatlCITt9.SUSl&#xa3;Tlr1TH1SDQ.lwUC,        =
1n,.a, 71 CCI.DL!GLID'Z         &#xa9; UU&-FM~Slt.1 nn..                                      i El 0
I. IIU&-QlM-08'19. SH. <I    151 ClollSSIFICJl,JlCN IOHWIT P'IAWING Z.114484"1-"8'16..SH.<I      ISIHTDROSTlllli~TICl'ft[SSlJ'IETESJl~DRAlfN 1 IIUl!-SPM41'16, SH. <I      ISi Sr5!'EM Pl'&#xa3;S'SI.R TES TOO IJ'l,IIIIIPC,
                                                                                                                                                                      ~
l"IJRII~ OF TH&#xa3;  s.vcn    JNJ[CTICN '.ilSt[M T)M,f ME    ,iwn    01' TH&#xa3; RCPB IIIS D&#xa3;f1'ED llOI IBCF~VIHAY BEEM QJl,SSIFIED ISi CUSS L S&#xa3;f lta"AS8.'55e!~II AS RCFCAEIUO 9T RCll&ATCIRl WU LA f(W>TICIT[ l fOR IIIOOITU)W,. lf,f"Clll'lllfllk
                                              &#xa3; G:)     G:)
CT,....::F.
CT,....::F.
                                                                                      @
INSIDE MISSILE OUTSIDE MISSILE BARRIER BARRIER 5
0 INSIDE REACTOR CONTAINMENT OUTSIDE REACTOR CONTAINMENT R(VISICND[SCllll'flCll,I nos aTPRa:U:I 010 1&.Sa.EJ KIit Mfl1!.0IIIClfUlll-'YOIIIDlaGIM fl.Clll-'YOIIIDMl'INJICI,                 111:,.
1n,.a, 71 INSIDE REACTOR OUTSIDE REACTOR CONTAINMENT CONTAINMENT 0
11448-FH -0aqa                 Ta 0
0 0
VIRGINIA POWER
0 0
* NORTH CAROLI NA POWER fl.CLEM El<<ill&#xa3;&#xa3;RIIG SERVICES RIOtO<<lo VIRGINIA INSIDE MISSILE OUTSIDE MISSILE  0 BARRIER    BARRIER                                                          ISi CLASSIFICATION BOUNDARY DRAWING 0 0                                                                SAFETY INJECTION SYSTEM SURRY POWER STATION UNIT I VIRGINIA POWER
2
                                                                                                                                ---IJSllNSl.ftJWO 015"1. DG1 - -             DMIUG 1111.                              ,u.
=
ll448*CBH*08'18                 2 U&..tSSDTl&#xa3;RIISt:1C1fED       &H*CJF <I 2
L.FatlCITt9.SUSl&#xa3;Tlr1TH1SDQ.lwUC, nn..
21*5D'*l'"1 ...**'5 ll}!jof~,11USIIIS'l64fff*ITI
I. IIU&-QlM-08'19. SH. <I 151 ClollSSIFICJl,JlCN IOHWIT P'IAWING Z.114484"1-"8'16..SH.<I ISIHTDROSTlllli~TICl'ft[SSlJ'IETESJl~DRAlfN 1 IIUl!-SPM41'16, SH. <I ISi Sr5!'EM Pl'&#xa3;S'SI.R TES TOO IJ'l,IIIIIPC,
~
l"IJRII~ OF TH&#xa3; s.vcn JNJ[CTICN '.ilSt[M T)M,f ME,iwn 01' TH&#xa3; RCPB IIIS D&#xa3;f1'ED llOI IBCF~VIHAY BEEM QJl,SSIFIED ISi CUSS L S&#xa3;f lta"AS8.'55e!~II AS RCFCAEIUO 9T RCll&ATCIRl WU LA f(W>TICIT[ l fOR IIIOOITU)W,. lf,f"Clll'lllfllk R(VISICND[SCllll'flCll,I nos aTPRa:U:I 010 1&.Sa.EJ KIit Mfl1!.0IIIClfUlll-'YOIIIDlaGIM fl.Clll-'YOIIIDMl'INJICI, 111:,.
11448-FH -0aqa Ta VIRGINIA POWER NORTH CAROLI NA POWER fl.CLEM El<<ill&#xa3;&#xa3;RIIG SERVICES RIOtO<<lo VIRGINIA ISi CLASSIFICATION BOUNDARY DRAWING SAFETY INJECTION SYSTEM SURRY POWER STATION UNIT I VIRGINIA POWER  
---IJSllNSl.ftJWO 015"1. DG1 --
DMIUG 1111.
ll448*CBH*08'18  
,u.
2 U&..tSSDTl&#xa3;RIISt:1C1fED &H*CJF <I 2
i El 0
Surry Unit 2 ISi Relief Requests e


e Attachment 2 Surry Unit 2 ISi Relief Requests
e Relief Request 24 I.
 
IDENTIFICATION OF COMPONENTS system:
e Relief Request 24 I. IDENTIFICATION OF COMPONENTS system:         Main Steam Feedwater Components:    Valves listed:
Components:
Component            Mark#           Line#              SIG Class Valve                2-FW-30*         3 11 -WAPD-109-601 A    2 Valve                2-MS-84.         6"-SHP-145-601     A    2*
Component Valve Valve Valve Valve Valve Main Steam Feedwater Valves listed:
Valve                2-MS-119        4 11 -SHP-138-601   B    2 Valve                2-FW-61*          3 11 -WAPD-111-601 B    2 Valve                2-MS-155          6 -SHP-147-601 11 C   2 (Drawings attached)
Mark#
    * - Downstream weld only II. IMPRACTICAL CODE REQUIREMENTS Surry Unit 2 utilized Code Case N-416, Alternate Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping Section XI, Division 1, on the components identified above. This Code Case defers the hydrostatic test required by IWA-4400 of ASME Section XI until the next regularly scheduled system hydrostatic test (IWC-5000) for that system.
2-FW-30*
III. BASIS OF RELIEF The identified component was replaced under the rules of ASME Section XI. IWA-4400 of the Code requires that a hydrostatic test be conducted on certain welded repairs or replacements.
2-MS-84.
2-MS-119 2-FW-61*
2-MS-155 (Drawings attached)
* - Downstream weld only II.
IMPRACTICAL CODE REQUIREMENTS Line#
3 11-WAPD-109-601 6"-SHP-145-601 4 11-SHP-138-601 3 11-WAPD-111-601 6 11-SHP-147-601 SIG A
A B
B C
Class 2
2*
2 2
2 Surry Unit 2 utilized Code Case N-416, Alternate Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping Section XI, Division 1, on the components identified above. This Code Case defers the hydrostatic test required by IWA-4400 of ASME Section XI until the next regularly scheduled system hydrostatic test (IWC-5000) for that system.
III.
BASIS OF RELIEF The identified component was replaced under the rules of ASME Section XI. IWA-4400 of the Code requires that a hydrostatic test be conducted on certain welded repairs or replacements.
This replacement cannot be hydrostatically tested without hydrostatically testing the connecting steam generator, as no intermediate isolation exists.
This replacement cannot be hydrostatically tested without hydrostatically testing the connecting steam generator, as no intermediate isolation exists.
Prior to NRC and Code approval of Code Case N-416, relief requests were routinely written and approved for this type situation. The relief requests were based upon the difficulties associated with steam generator hydrostatic testing. The test cannot be conducted at ambient conditions due to fracture prevention concerns associated with the Surry steam generators, which results in difficult monitoring and controlling requirements. The Surry steam generators are required to be a minimum of 150 degrees F. on the secondary side and a minimum of 180 degrees F. on the primary side. Additionally normal problems, such as test boundary isolation, internal boundary leakage, placing spring hanger stops for dead weight loading concerns, and test pump size requirements further increase the difficulties associated with this particular test.
Prior to NRC and Code approval of Code Case N-416, relief requests were routinely written and approved for this type situation. The relief requests were based upon the difficulties associated with steam generator hydrostatic testing. The test cannot be conducted at ambient conditions due to fracture prevention concerns associated with the Surry steam generators, which results in difficult monitoring and controlling requirements. The Surry steam generators are required to be a minimum of 150 degrees F. on the secondary side and a minimum of 180 degrees F. on the primary side. Additionally normal problems, such as test boundary isolation, internal boundary leakage, placing spring hanger stops for dead weight loading concerns, and test pump size requirements further increase the difficulties associated with this particular test.  


e
e Relief Request 24 (CON 1T)
*'                      Relief Request 24 (CON 1 T)
The test pressure of 1356 psig also requires gaging or removal of the Main Steam Safety valves, which initially lift at 1085 psig. Some examples of previous correspondence requesting relief and approval follow:
The test pressure of 1356 psig also requires gaging or removal of the Main Steam Safety valves, which initially lift at 1085 psig. Some examples of previous correspondence requesting relief and approval follow:
VEPCO Letter/ Date              NRC Letter/ Date Serial# 88-725/ 1/9/89           Serial# 89-278/ 4/7/89 Serial# 89-636/ 8/29/89          Serial# 89-734/10/2/89 Serial# 87-056/ 2/13/87          Serial# 88-419/6/17/88
VEPCO Letter/ Date Serial# 88-725/ 1/9/89 Serial# 89-636/ 8/29/89 Serial# 87-056/ 2/13/87 NRC Letter/ Date Serial# 89-278/ 4/7/89 Serial# 89-734/10/2/89 Serial# 88-419/6/17/88
* When Code Case N-416 was incorporated into Regulatory guide 1.147, "Inservice Inspection Code Case Acceptability-ASME Section XI Division 1, relief requests were no longer needed, since the hydrostatic test was deferred to the end of the interval hydrostatic test described in table IWC-2500-1. This appeared to be the minimum hydrostatic testing that could be achieved for the steam generators. Recently in Revision 9 of Regulatory Guide 1.147, you approved Code Case N-498, Alternative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and 2 Systems Section XI, Division 1. This Code Case allows testing of the class 2 steam generators at nominal operating pressure. As a result, no hydrostatic test is now required by ASME Section XI on these components under normal circumstances, when incorporating Code Case N-498. The hydrostatic test of Code Case N-416 is still required to be performed, however. As described before, the component identified above can only be hydrostatically tested by additionally testing the connecting steam generator. Requiring a full steam generator test only for this replacement activity is considered impractical, due to the difficulties of the test described previously.
* When Code Case N-416 was incorporated into Regulatory guide 1.147, "Inservice Inspection Code Case Acceptability-ASME Section XI Division 1, relief requests were no longer needed, since the hydrostatic test was deferred to the end of the interval hydrostatic test described in table IWC-2500-1. This appeared to be the minimum hydrostatic testing that could be achieved for the steam generators. Recently in Revision 9 of Regulatory Guide 1.147, you approved Code Case N-498, Alternative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and 2 Systems Section XI, Division 1. This Code Case allows testing of the class 2 steam generators at nominal operating pressure. As a result, no hydrostatic test is now required by ASME Section XI on these components under normal circumstances, when incorporating Code Case N-498. The hydrostatic test of Code Case N-416 is still required to be performed, however. As described before, the component identified above can only be hydrostatically tested by additionally testing the connecting steam generator. Requiring a full steam generator test only for this replacement activity is considered impractical, due to the difficulties of the test described previously.
IV. ALTERNATE TESTING The alternative requirements described in Code Case N-416, a volumetric examination of the full penetration welds and a visual examination (VT-2) at nominal operating pressure was previously performed and deemed acceptable.
IV.
ALTERNATE TESTING The alternative requirements described in Code Case N-416, a volumetric examination of the full penetration welds and a visual examination (VT-2) at nominal operating pressure was previously performed and deemed acceptable.  


  ..,, .            ""90-HBJ-81-Stl
""90-HBJ-81-Stl B
                                                                                                                                                                    . *:.:,:,,i ~~ .. '
F E
B                                  7                                                                                    II                                    4
D C
                                                                                                                                                                        \
B Z4-illfllll*l"'2141..
                                                                                                                                                                  ~:..:-: '
tm1Cl!ll,Lll1~t1N.n1 STEAM GENERATOR 7
                                                                                                                                                                                              .,
n WALL OF REACTOR CONTAJN:!fNJ II I I i I I e
F
e e
                                                                                                                                                                ,
e e
1'* siI aI      i
. *:.:,:,,i ~~.. '  
                                                                                                                                                                                                '*
\\  
                                                                                                                                                                                                                                                                &
~:..:-: '
                                                                                                                                                                                                                                                                ~t~.=a~=... ..
1'i
                                                                                                                                                                                                                                                                '~:ar::L~.~~ctN'UTD
* s I a I i 4
                                                                                                                                                                                                                                                                                                    ----
<D
,. r-SlflEl.O WALL i
I i i i J. ---
(:
C
C
* IIIDUUC fflll.
* IIIDUUC fflll.  
I I i I I e            e          e            e            e
~t~.=a~=.....
                                                                                                                                                                            @
'~:ar::L~.~~ctN'UTD
: 17. U51H'M-l1911U7A au...,.*a.
L~91.I tlla.J159'1CATDl...._,CNWDG
(.,
(.,
E
2........._9LI IIIHYUIIDSTAntlMI.Nlta:: l'IU3.II[ 1DTIG DWiNJ
                          ,-,
                                                                                                                                                              **                                            <D
                                                                                                                                                                                                                          ,.
i r-SlflEl.O WALL
(:
                                                                                                                                                                                                                                                            ... _
                                                                                                                                                                                                                                                            .._
                                                                                                                                                                                                                                                            ._
__
                                                                                                                                                                                                                                                            .._ , _ _
                                                                                                                                                                                                                                                            .,,..,..__,,.
: 17. U51H'M-l1911U7A au...,.*a.
                                                                                                                                                                                                                                                                                            ......... - """
E
                                                                                                                                                                                                                          !
J.
I i
i i    ---
D                                                                                                                                                                                                                                                                                                                                            D STEAM GENERATOR
                                                      ...,..n.......
L~91.I 2........._9LI
                                                                                                                                                                                                                                                                                          -*-
tlla.J159'1CATDl...._,CNWDG IIIHYUIIDSTAntlMI.Nlta:: l'IU3.II[ 1DTIG DWiNJ
:1.~*1mlT'llDIPNESS1JE'ft:slDII....,.
:1.~*1mlT'llDIPNESS1JE'ft:slDII....,.
CD~~2.~~-:n.~~~~a11m1             """""'"""
CD~~2.~~-:n.~~~~a11m1 C!:) ~ =-==. fi'L a, Im! Stal ODDIIUII II MIT r, M IU&
C                                                                                                                                                                                                                                                                                                                                          C WALL OF REACTOR CONTAJN:!fNJ                                                                                                                                                                                                C!:) ~ =-==. fi'L a, Im! Stal ODDIIUII II MIT r, M                   IU&
n.Gll'ftllDIIIIIIGIG.
                                                                                                  --.
11548-FH -064A 31 I~ *~
B
' h VIRGrnlA POWER e
                                                                                                                                                                                                                                                                                                                                  ....
NORTH CAROLINA POWER
n.Gll'ftllDIIIIIIGIG.                ...
: I 1\\1  
11548-FH -064A                 31 I~' *h~ e i
&sect; i A II.a.EM EIClltGIIIICJ 6DIVICU i~i,i11----------"'~DIINl~~**-*m_1*~**--------1 ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 11191. DOI 11111' wo.-
: I 1\1 &sect; A
IJNIIGIG.
* VIRGrnlA POWER NORTH CAROLINA POWER II.a.EM EIClltGIIIICJ 6DIVICU i~i ,i11----------"'~DIINl~~**-*m_1*~**--------1
ll114B*CBM*1!64A I
___    ISi CLASSIFICATION BOUNDARY DRAWING
LIi.iii OT>EIII* 11111D.. I i.'
                                                                                                                                                                                                                                                                            ...,
* 2 E
MAIN STEAM SYSTEM
D C
                                                                                                                                                                                                                                                                                  ....
A
SURRY POWER STATION UNIT 2
* ***-* * *------------------i ----------------------- 1 ------*-*r**----------**
                                                                                                                                                                                                                                                                                        .,,,
04*--------------------. **-----------------------------------------------------------------------------------------------------------------------------------------*  
VIRGINIA 11191. DOI 11111' POWER IJNIIGIG.                            ....
A wo.-                          ll114B*CBM*1!64A                 I
                                                                                                                                                                                                                                                                            ......                    LIi.iii OT>EIII* 11111D . . I i.'
* 2 Z4-illfllll*l"'2141 . .
tm1Cl!ll,Lll1~t1N.n1
                                                                    * ***-* **------------------i ----------------------- ------*-*r**----------**
1 04
                                                                                                                                                    *--------------------. **-----------------------------------------------------------------------------------------------------------------------------------------*


....
r 9
9            '1890-H8J-8*!ill 6 !5   3                             2
'1890-H8J-8*!ill E
                                                                                                            !!!!!!.
C B
                                      \
lt*.ll.H*l'HZll,46 ZC51[J58.121lS2eieAIFM.8TI 6  
LLIUC St(Mtllf ~ CCNf,, NltClltllWII.CDN.IG.-COG 1M1 IIM*U'2rflllblf-lWlll.                                 '          ~
!5 3  
\\
11'54(1-t'M~SK.2 2
LLIUC St(Mtllf ~
CCNf,, NltClltllWII.CDN.IG.-COG 1M1 IIM*U'2rflllblf-lWlll.  
~
1."llelllllCOIT"1JeCNff'OCl'IIUllJG~*SI.
1."llelllllCOIT"1JeCNff'OCl'IIUllJG~*SI.
S.IIIU.l'IIIE'IStll[~TOlt:11.-,
S.IIIU.l'IIIE'IStll[~TOlt:11.-,
4.,U TDftN,fl.11! a..ClUJIS TO It I VZ'Rt#C tQ.L
4.,U TDftN,fl.11! a..ClUJIS TO It I VZ'Rt#C tQ.L  
                                                            ~-DlltcAtl'S       ""'""&deg;.,~WW.
~-DlltcAtl'S ""'""&deg;.,~WW.
L&ooa:.ns ClM'UTP POJNT, r,,&sa     lrOCDLl'tam.llf'II!.
L&ooa:.ns ClM'UTP POJNT, r,,&sa lrOCDLl'tam.llf'II!.
LP'Olfflt'NS a, UM1-1M-1e I -             ~ f'llhal.1!1.1'
LP'Olfflt'NS a, UM1-1M-1e I -
                                                              ~ITCllD&deg;""'IJGU4t&............
~
                                                            ._lltOlllUDIIDaIITOTNISICJTLMUD'll.lll.tlCUSllacl'l'NI.
f'llhal.1!1.1'  
                                                                                                  ........,_
~ITCllD&deg;""'IJGU4t&............  
mu
._lltOlllUDIIDaIITOTNISICJTLMUD'll.lll.tlCUSllacl'l'NI.  
                                                            &U<<I~                            f\.Dlll"t(>lll'l,IOIM,F'QDIMTDISJSffN E                                                        R.11~71 13,,11~
&U<<I~
F\.OlfrfflillD!IIIQll#\f"~l'AOT[trtc,,S'BTtN F\.OlfrttJ\101.IIOll#(,STDlrl~tCllkl~
R.11~71 13,,11~
M,l!'!M8-nHIS711                F\.Olf/\'tN OIOIIM,COUMSo\Tt S111D4 m,U'41~71                        nownc.       ~aNJD611rt: snTEN
M,l!'!M8-nHIS711 m,U'41~71
                                                            -.11~821111                      l'l.Dlll'l'!lt~So99'1.DGSTSTOI 17,ll'!MO..,.Jllll,              f'Lnlfl'fOI CLIGWC,DOlC,111. JUD STSTDI 0
-.11~821111 17,ll'!MO..,.Jllll, mu f\\.Dlll"t(>lll'l,IOIM,F'QDIMTDISJSffN F\\.OlfrfflillD!IIIQll#\\f"~l'AOT[trtc,,S'BTtN F\\.OlfrttJ\\101.IIOll#(,STDlrl~tCllkl~
ll'F'AODt.Cft,l4wtlGS 1.11'41-<Dt--.SH.1           mcu,sstnt.\t~~CJWtllel 2.U'!M8*~SH.lts.lS1'S!Dll'ACS9.JEtESTPCIQRilWDG 11'54(1-t'M~SK.2
F\\.Olf/\\'tN OIOIIM,COUMSo\\Tt S111D4 nownc. ~aNJD611rt: snTEN l'l.Dlll'l'!lt~So99'1.DGSTSTOI f'Lnlfl'fOI CLIGWC,DOlC,111. JUD STSTDI ll'F'AODt.Cft,l4wtlGS 1.11'41-<Dt--.SH.1 mcu,sstnt.\\t~~CJWtllel 2.U'!M8*~SH.lts.lS1'S!Dll'ACS9.JEtESTPCIQRilWDG  
                                                                                                      ~
~  
C                                                          <DraH?sr~11 ~~l'fttfl\'Cl~~~'=~~-
<DraH?sr~11 ~~l'fttfl\\'Cl~~~'=~~-
CD~~u:elJIOl'~l1'/fov~~~
CD~~u:elJIOl'~l1'/fov~~~ ~~~~~
                                                                      ~lllfNR&#xa3;CU,JllltJITOJtll[U&,.MTIQLc..i...
~  
                                                            ~ T M ! n.a; i,,tll'WmS!D[ t:,
~lllfNR&#xa3;CU,JllltJITOJtll[U&,.MTIQLc..i...  
                                                            ~ S t t 11548-Fl'l -etl6,l,.
~TM! n.a; i,,tll'WmS!D[ t:, [IOI lft#II OO<<:A1"1'0A IS r-iiiir a, fH[-
C[)sun....-.-.,SK.lf'Ollt.Nr 11lJiC1T
~Stt 11548-Fl'l -etl6,l,.
[IOI
C[)sun.... -.-.,SK.lf'Ollt.Nr 11lJiC1T :r11J.KWtr.
                                                                                                                      ~~~~~ ~
lft#II OO<<:A1"1'0A IS r-iiiir a,
:r11J.KWtr.
fH[-
CD~d:'s~~~~~"::SETrf"~~~~t'i.~
CD~d:'s~~~~~"::SETrf"~~~~t'i.~
lllt!:..:c,rro.,.
lllt!:..:c,rro.,.
CDfft>ur,no.
CDfft>ur,no. -nc _.....-r11,a"' c:,i F9 ---
                                                                ~Sl'OCl1-.;1 CUISSll'l~f!QO,I ~
~Sl'OCl1-.;1 CUISSll'l~f!QO,I ~  
m,a-1,ca llr _,ururt>G c.o DOI c a ~ no 1111     -IJCl9
-IJCl9 CC-OIi ~
                                                                                - n c _ . . ...-r11 ,a"' c:,i F9CC-        ---
CMI.
                                                                                                                              ..._OIi ~ CMI.
m,a-1,ca llr _,ururt>G c.o DOI ca~ no 1111..._
CAUTION, B                                                            ~ir~iZl:~~~~~~~*-=n..                                                                       B !
: CAUTION, 0
R[VIS[Oi1DESCJl!1'TIQIII TN1Slfl'IIICDrlOWOIS9.ElPEK T>C FQ.LOIIINJ fl.Olln(Jt DIIGWI
~ir~iZl:~~~~~~~*-=n..
                                                                                                                '1.0IJ'VOrtt,l,WINJND, 11546-FM -068A                 "'*
B !
41 VIRGINIA POWER
R[VIS[Oi1DESCJl!1'TIQIII TN1Slfl'IIICDrlOWOIS9.ElPEK T>C FQ.LOIIINJ fl.Olln(Jt DIIGWI  
* NORTH CAROLI NA POWER ltJCLEM ENJIIEERIHO SERVta;s RIOMJNJoYIROINIA ISi CLASSIFICATIOM BOUNDARY DRAWING FEEDWATER SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER IH.ESS QUR'f1SE NJtEO       S>I l rs*
'1.0IJ'VOrtt,l,WINJND, 11546-FM -068A VIRGINIA POWER NORTH CAROLI NA POWER ltJCLEM ENJIIEERIHO SERVta;s RIOMJNJoYIROINIA ISi CLASSIFICATIOM BOUNDARY DRAWING FEEDWATER SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 41 IH.ESS QUR'f1SE NJtEO S>I l rs*  
lt*.ll.H*l'HZll,46 ZC51[J58.121lS2eieAIFM.8TI


ldlr90-HSJ-e*sn 8                             7    B        15  4 3                  2
ldlr90-HSJ-e*sn 8
                                                                                                                            !!!!!!
F E
F
D C
                                                    *-.            h
:,7~1'"214112 IGl!l11211,IZU~.11'1 2-RC-
                                                                                \
                                                                          '*It I*
                                                                                -i F
                                                          ......
                                                            "'
CD E                                                                                 :: :.=-
                                                                                              ....
JUOPa ...::-
                                                                                                                    .........  -  mu:
                                                                                                                          ~ * . : _ ~"::o. ma mrrN                            E D                                                                                                                                                                            D 2-RC-
                                                                                    ,_
                                                                                    ~-...
                                                                                    &-DU
                                                                                                      ...      -~1DI.....,_
                                                                                                                .flS'IDI .....
m lfflllllOSTa~nc N'SUll 1D1N ma,,m TDTlll!allG
__&#xa3;!!!.._
__&#xa3;!!!.._
STEAH GENERATOR C                                                                                                                                                                            C CDPdllfbd
STEAH GENERATOR WALL OF REACTOR CONTAINMENT 7
                                                                                              ...........
B CD 15 4
r,,,. . . . .
h 3
CUSSUllD tsl WIGS Z
\\
* l(.IN STSTEN N 111690C14TID no9G Ml'I[ IIDI CCXIII.a: VJJH IEUATUrr Q,Q L&
'* I*
WALL OF REACTOR CONTAINMENT                                                                ...
It - i 2
C!:),,. na l'RDWt'f'I sa: r,         M SftM   aDEWt,TIIJI 11....r mr nc IIICl'IL
F mu:
                                                                                      -~-..__.._,..TOP'MCllll,._na
:: :.=- JUOPa
                                                                                      -~111*..._.._._.Cllll~CM*
...::-~
                                                                                      ~ . . . . .TINQCC91Cllllc::al'UIIP'MCIIII,._
*.:_~ "::o. ma mrrN E
                                                                                      ~~ PCIIQCllrl TtCll ---.cT- ESPDII -                                 Oil.Yo
&-DU
                                                                                      =-~~~~-5.;:,._i&:mc" .. ~ e
~-... -~1DI.....,_
                                                                                  ....................
m lfflllllOSTa~nc N'SUll 1D1N ma,,m
RJlll'IIIIIIIIIIIIIGIG.                   IIIY.
.flS'IDI..... TDTlll!allG CDPdllfbd r,,,.....
11548-FH -064A                       31
l(.IN STSTEN N 111690C14TID no9G Ml'I[ IIDI CUSSUllD tsl WIGS Z
                                                                                                                                                            *zmr         1 VIRGINIA POVER
* CCXIII.a: VJJH IEUATUrr Q,Q L&
* NORTH CAROi. lNA POVER IIJCLbA EtCJIJ&#xa3;DIIIII SEIVICO lltlOICJIJoVIIIIINIA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM                                                   A SURRY POWER STATION UNIT 2 VIRGINIA POWER DI.._ DCII WIIENR - -
C!:),,. na l'RDWt'f'I sa: r, M SftM aDEWt,TIIJI 11....r mr nc IIICl'IL  
N'        DMIIIIG 1G.
-~-..__.._,..TOP'MCllll,._na  
11!148-tllH*ll64A
-~111*..._.._._.Cllll~CM*  
                                                                                                                                                                        ....
~
I 2
TINQCC91Cllllc::al'UIIP'MCIIII,._  
:,7~1'"214112 IGl!l11211,IZU~.11'1
~~
PCIIQCllrl TtCll ---.cT-ESPDII -
Oil.Yo D
C
=-~~~~-5.;:,._i&:mc".. ~ e RJlll'IIIIIIIIIIIIIGIG.
IIIY.
11548-FH -064A 31  
*zmr 1 VIRGINIA POVER NORTH CAROi. lNA POVER IIJCLbA EtCJIJ&#xa3;DIIIII SEIVICO lltlOICJIJoVIIIIINIA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM A
2 SURRY POWER STATION UNIT 2 VIRGINIA POWER DI.._ DCII N' WIIENR --
DMIIIIG 1G.
11!148-tllH*ll64A I  


              -,,,9'!1-HSJ-81>!:itt
-,,,9'!1-HSJ-81>!:itt  
*qa                         "'INOIIIIIIIII 8                            7        6    II 4              3          2
*qa  
                                                                                                                              !!!!!!
"'INOIIIIIIIII F
LftllacTD.U9Ullrlna .......
E D
F                                                                                                                                                                       F I I I                          '
C 8
e  e e h h
7
                                                                                  ---
~JD' i
SHIELD WALL---;
i r-- WALL CF REACTOR CONTAINMENT~
                                                                                        !
i i
i E                                                                                     I                                                                              E
i t
                                                                                        !
D                                                                                                                                                                      D
                                                                                                                        .........,_
L~-31              mD..16!1UDTDIIIIIIIWITDIIMfllll 1.~-3              lllN'l'IJIISTAntmENTICPIIIESSUIIIIISBG-3 . ~ ... l        mmTDl~lUTtlGl*dG
                                                  ~JD'   i i
C r--
i WALL CF REACTOR CONTAINMENT~
                                                          !
                                                                                                                          ~
CD ~m'1.:ras:-'.J:.:~-=:.'l&rt"'ll.=:rc..w.                              C i                                           !
* i                                             t i                                            !
i                                            !
i
            *
                                                          !I i
i i
i i
A.a.Mlil CIIIIWIIIJ ID.          IIIY.
i I
11548-FH -064A                31
i i i
* la, I VIRGINIA POWER
* NORTH CAROL INA POWER IULEM EtGIJ&ltUII liERYICEI "lotDII, YIIGDUA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM                                        A SURRY POWER STATION UNIT 2 VIRGINIA POWER
                                                                                                          .... ,_ --
D19'LDCIII  IIIF      DMIIJG JG.
ll!548-t814*1164A            ""*I
                                                                                                                                    .US ll'TtCJIII. tGTID 9' :I l:F I 2
27-,0-1'9'12 14*1*
27-,0-1'9'12 14*1*
ZIZl*l~.1111~.*n
ZIZl*l~.1111~.*n I
e 6
II 4
I I e
e 3
SHIELD WALL---;
i ! I !
h h 2
LftllacTD.U9Ullrlna.......
L~-31 mD..16!1UDTDIIIIIIIWITDIIMfllll 1.~-3 lllN'l'IJIISTAntmENTICPIIIESSUIIIIISBG-3.~
... l mmTDl~lUTtlGl*dG
~
CD ~m'1.:ras:-'.J:.:~ -=:.'l&rt"'ll.=:rc..w.
A.a.Mlil CIIIIWIIIJ ID.
IIIY.
11548-FH -064A 31
* la, I VIRGINIA POWER NORTH CAROL INA POWER IULEM EtGIJ&ltUII liERYICEI "lotDII, YIIGDUA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER D19'LDCIII IIIF DMIIJG JG.
ll!548-t814*1164A I
.US ll'TtCJIII. tGTID 9' :I l:F I 2
F E
D C
A


Relief Request 25 I. IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II. IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded-repairs or installation of replacement items by welding.
Relief Request 25 I.
III. BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundary. These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the approval in Regulatory Guide 1.147, Code Case N-498,"
IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II.
IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded-repairs or installation of replacement items by welding.
III.
BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundary. These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the approval in Regulatory Guide 1.147, Code Case N-498,"
Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.
Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.
IV. ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative require~ents shall be applied:
IV.
: 1) NOE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.
ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative require~ents shall be applied:
: 1)
NOE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.  


e                         e Relief Request 25 (CON'T)
l
: 2)  Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.
: 2)
: 3)  Use of this alternative shall be documented on the NIS-2 Form.
: 3) e e
If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing have been met.
Relief Request 25 (CON'T)
Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.
Use of this alternative shall be documented on the NIS-2 Form.
If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing have been met.  


*'
RELIEF REQUEST 26 I.
RELIEF REQUEST 26
IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:
* I. IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:
Function Class 11548-CBM-89B 2-SI-79 2-SI-82 2-SI-85 2-SI-88 2-SI-91 2-SI-94 AND AND AND
11548-CBM-89B 2-SI-79 AND  2-SI-235, 2-SI-241 2-SI-82 AND  2-SI-236, 2-SI-242 2-SI-85 AND  2-SI-237, 2-SI-243 2-SI-88 ,AND  2-SI-226, 2-SI-227 AND 2-SI-238 2-SI-91 AND  2-SI-226, 2-SI-227 AND 2-SI-239 2-SI-94 AND   2-SI-226, 2-SI-227 AND 2-SI-240 (Drawings Attached)
,AND AND AND 2-SI-235, 2-SI-236, 2-SI-237, 2-SI-226, 2-SI-226, 2-SI-226, (Drawings Attached)
Function    : Safety Injection System Class        : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.
: Safety Injection System
III. BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.
: 1 II.
IV. ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure. The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.
IMPRACTICAL CODE REQUIREMENTS 2-SI-241 2-SI-242 2-SI-243 2-SI-227 AND 2-SI-238 2-SI-227 AND 2-SI-239 2-SI-227 AND 2-SI-240 Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.
This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.
III.
BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.
IV.
ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure.
The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.
This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.  


  !            Bb80*H8J-8t>SII i-"'-"~------*"'-"'-"-""---,------------;-------------,-------------------------~-----------~------------~---*---**----
Bb80*H8J-8t>SII i-"'-"~------*"'-"'-"-""---,------------;-------------,-------------------------~-----------~------------~---*---**----
6                                       5                                                                                                             2
D C
                                                                                                                                                                                                                                                                            !!!!ll L.f0AICJT[S.S0:5"1:[Tl~DMWIIC,US4a..,.,.....,
B TOKlllEGLOCl'I 11,'llofM *98&4.511.1 17-SP'*l'l'Vll,*
                                                                                                                                                                                                                                                                                    ,)
.taltf~.JZIJ~"-B'I lNSJDE MISSILE BARRIER 6
                                                                                                                                                                                                                                                                                        ,c*
5 l/4'-51*3'54*1'82*
l/4'-51*3'54*1'82*
JNSIDE REACTOR OUTS[DE REACTOR CONTAINMENT CONTAINMENT 2  
D                                                                                                                                                                                                                                                                                                                      D, L 115-1e-o,,i-t1S'18.SH.4     rs1a.*ss1nuir1DN BO.NJ,l,Rf CRAwPG Z.ll~*Sf'l'I-M'IO.SH.4         l'StS1SIDIPAESSl.lllTEUNillRAwPG
!!!!ll L.f0AICJT[S.S0:5"1:[Tl~DMWIIC,US4a..,.,.....,  
                                                                                                                                                                                                                                                                    ~
,)  
G::>~         1:S~1~ f:'f~~~'~:s~ ~s~'Tl1g:.J~L C                                                                                                                                                                                                                                      $&#xa3;&#xa3; L8FRC5&'l5*g1111as A(fER[ICEO 81' lllt:GU..AIOIT GuIDE U6,,
,c*
L 115-1e-o,,i-t1S'18.SH.4 rs1a.*ss1nuir1DN BO.NJ,l,Rf CRAwPG Z.ll~*Sf'l'I-M'IO.SH.4 l'StS1SIDIPAESSl.lllTEUNillRAwPG  
~
G::>~1:S~1~ f:'f~~~'~:s~ ~s~'Tl1g:.J~L  
$&#xa3;&#xa3; L8FRC5&'l5*g1111as A(fER[ICEO 81' lllt:GU..AIOIT GuIDE U6,,
FOOINJT[ JfOA JGJIT!lhll. lWIJIMAIUl'f.
FOOINJT[ JfOA JGJIT!lhll. lWIJIMAIUl'f.
TOKlllEGLOCl'I 11,'llofM *98&4.511.1 JNSIDE REACTOR OUTS[DE REACTOR    ctlOlt-"IJ<f~*l"&deg;-'""'"ATOf'MOll'81)111*wlt,C;S.IIC C:OJIR&#xa3;5"GCII"&deg; CLA551flC*Tlc.o -
ctlOlt-"IJ<f~*l"&deg;-'""'"ATOf'MOll'81)111*wlt,C;S.IIC C:OJIR&#xa3;5"GCII"&deg; CLA551flC*Tlc.o -*
* OAAW/,c;;I OC.., OIi CN1 CM! -
OAAW/,c;;I OC.., OIi CN1 CM! -
CONTAINMENT  CONTAINMENT        MTlAM!. .011 -SJITUIINCiC-OlllcalfOlllr" DIii ....
MTlAM!.. 011 -SJITUIINCiC-OlllcalfOlllr" DIii....
CAUTION, JH1!&,,,c,rr.,tCUGl'Ol.rfi.,,O,n,isa,-.c,Clll4Vl>oallrCIIIIIIP"(Jll!><Cll:0-...Y.
: CAUTION, JH1!&,,,c,rr.,tCUGl'Ol.rfi.,,O,n,isa,-.c,Clll4Vl>oallrCIIIIIIP"(Jll!><Cll:0-...Y.
B                                                                                                                                                                                                                              ~~=:iT:.~~tiir~~=-:r.~~1.1c* ,cYUOL                                        ,,c         8 RfY/5](J,jll&#xa3;5CRll'JJDN THII 11'11'AD.CT DWO ISSlLD PEA THE ftl.l.c.lNl Ft.OW/~ DIIIIQIMI FUIWIVCNDIWIIIJJGtCI.                 ~,.
D,
115'48-FH *0898                 23 VIRGINIA POVER
~~=:iT:.~~tiir~~=-:r.~~1.1c*,,c,cYUOL 8
* NORTH CAROL I NA PD VER N.CI.EAR EN'.HNEEAINO SERVICES Rloeo<<>,YIRGINIA lNSJDE MISSILE BARRIER                                                                                                                                                                                      ISi CLASSIFICATION BOUNDARY DRAWING SAFETY INJECTION SYSTEM
RfY/5](J,jll&#xa3;5CRll'JJDN THII 11'11'AD.CT DWO ISSlLD PEA THE ftl.l.c.lNl Ft.OW/~ DIIIIQIMI FUIWIVCNDIWIIIJJGtCI.  
                                                                                                                                                                                                                              ---- .... -
~,.
SURRY POWER STATION UNIT 2 VIRGINIA POWER OISP'L. DO:
115'48-FH *0898 23 VIRGINIA POVER NORTH CAROL I NA PD VER N.CI.EAR EN'.HNEEAINO SERVICES Rloeo<<>,YIRGINIA ISi CLASSIFICATION BOUNDARY DRAWING SAFETY INJECTION SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 2
                                                                                                                                                                                                                                                  ""'"&deg;'--
OISP'L. DO:
1111(      DVIIIIII~.
1111(
1154B-CBH-0B'l8
""'"&deg;'--
                                                                                                                                                                                                                                                                                                                    . ..
DVIIIIII~.
2 17-SP'*l'l'Vll,*
1154B-CBH-0B'l8  
.taltf~.JZIJ~"-B'I
....}}
:--------------------:-------------------*----.----------.------------------------*----------,------------***-*-***--*---*-**--*--******}}

Latest revision as of 19:15, 5 January 2025

Forwards Second 10-yr ISI Interval Relief Requests 28,29,24, 25 & 26.Second Interval Insp Requirements Scheduled to Be Completed in Refueling Outages Currently Scheduled to Start in Feb 1994 & Sept 1994 for Units 1 & 2,respectively
ML18153B285
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/11/1993
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-419, NUDOCS 9308160215
Download: ML18153B285 (18)


Text

.,,,.----

L e

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 11, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 SECOND TEN YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUESTS Serial No.

SPS/ETS Docket Nos.

License Nos.93-419 50-280 50-281 DPR-32 DPR-37 Surry Power Station Units 1 and 2 are currently in the third period of their second ten year intervals. Second interval inspection requirements are scheduled to be completed in the refueling outages currently scheduled to start in February 1994 and September 1994 for Surry Units 1 and 2, respectively. Previously by letter dated January 26, 1993 (Serial No.93-002), relief requests were submitted to close out the second ten year interval.

Pursuant to 1 O CFR 50.55a(g)(5), additional relief from specific Code requirements for Surry Units 1 and 2 is being requested. The basis for each relief request is provided in the Attachments to this letter.

In addition, Relief Request 24 for Surry Unit 2 is being resubmitted to incorporate components not included in the January 26, 1993 letter, that were replaced during the recent Unit 2 refueling outage.

These requests have been reviewed by the Station Nuclear Safety and Operating Committee.

If you have questions regarding this information, please contact us.

Very truly )'?u\\s,

. j,., 9:J*' )_1

' '/ _'-.... \\ *~,--~-

\\ t L * \\"'QJ.~j <:\\ ---*~---...

W. L. Stewart Senior Vice President - Nuclear Attachments 1 r.: n l0 0,.. i

.... (J I,' \\

' ~~

9308160215 93osii n1*.,-

PDR ADOCK 05000280 u*\\

Q PDR

cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Surry Unit 1 ISi Relief Requests

RELJ:EF REQUEST 28 I.

IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II.

IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded repairs or installation of replacement items by welding.

III.

BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME Section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundaryg These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the* approval in Regulatory Guide 1.147, Code Case N-498, 11 Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems,Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.

IV.

ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative requirements shall be applied:

1)

NDE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.

L RELIEF REQUEST 28 (COlf 1 T)

. 2)

Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.

3)

Use of this alternative shall be documented on the NIS-2 Form.

If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing *have been met.

RELIEF REQUEST 29 I.

IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:

11448-CBM-89B 1-SI-79 1-SI-82 1-SI-85 1-SI-88 1-SI-91 1-SI-94 AND AND AND AND AND AND 1-SI-235, 1-SI-241 1-SI-236, 1-SI-242 1-SI-237, 1-SI-243 1-SI-238 1-SI-239 1-SI-240 (Drawings Attached)

Function Class

Safety Injection System
1 II.

IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.

III.

BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.

IV.

ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure.

The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.

This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.

- --.-*..a,te 8?80*H8J-81>"11 "Oolo.llAIIIIICI CCI.DL!GLID'Z

© UU&-FM~Slt.1 21*5D'*l'"1... **'5 ll}!jof~,11USIIIS'l64fff*ITI

£ G:) G:)

CT,....::F.

INSIDE MISSILE OUTSIDE MISSILE BARRIER BARRIER 5

1n,.a, 71 INSIDE REACTOR OUTSIDE REACTOR CONTAINMENT CONTAINMENT 0

0 0

0 0

2

=

L.FatlCITt9.SUSl£Tlr1TH1SDQ.lwUC, nn..

I. IIU&-QlM-08'19. SH. <I 151 ClollSSIFICJl,JlCN IOHWIT P'IAWING Z.114484"1-"8'16..SH.<I ISIHTDROSTlllli~TICl'ft[SSlJ'IETESJl~DRAlfN 1 IIUl!-SPM41'16, SH. TICIT[ l fOR IIIOOITU)W,. lf,f"Clll'lllfllk R(VISICND[SCllll'flCll,I nos aTPRa:U:I 010 1&.Sa.EJ KIit Mfl1!.0IIIClfUlll-'YOIIIDlaGIM fl.Clll-'YOIIIDMl'INJICI, 111:,.

11448-FH -0aqa Ta VIRGINIA POWER NORTH CAROLI NA POWER fl.CLEM El<<ill££RIIG SERVICES RIOtO<<lo VIRGINIA ISi CLASSIFICATION BOUNDARY DRAWING SAFETY INJECTION SYSTEM SURRY POWER STATION UNIT I VIRGINIA POWER

---IJSllNSl.ftJWO 015"1. DG1 --

DMIUG 1111.

ll448*CBH*08'18

,u.

2 U&..tSSDTl£RIISt:1C1fED &H*CJF <I 2

i El 0

Surry Unit 2 ISi Relief Requests e

e Relief Request 24 I.

IDENTIFICATION OF COMPONENTS system:

Components:

Component Valve Valve Valve Valve Valve Main Steam Feedwater Valves listed:

Mark#

2-FW-30*

2-MS-84.

2-MS-119 2-FW-61*

2-MS-155 (Drawings attached)

  • - Downstream weld only II.

IMPRACTICAL CODE REQUIREMENTS Line#

3 11-WAPD-109-601 6"-SHP-145-601 4 11-SHP-138-601 3 11-WAPD-111-601 6 11-SHP-147-601 SIG A

A B

B C

Class 2

2*

2 2

2 Surry Unit 2 utilized Code Case N-416, Alternate Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping Section XI, Division 1, on the components identified above. This Code Case defers the hydrostatic test required by IWA-4400 of ASME Section XI until the next regularly scheduled system hydrostatic test (IWC-5000) for that system.

III.

BASIS OF RELIEF The identified component was replaced under the rules of ASME Section XI. IWA-4400 of the Code requires that a hydrostatic test be conducted on certain welded repairs or replacements.

This replacement cannot be hydrostatically tested without hydrostatically testing the connecting steam generator, as no intermediate isolation exists.

Prior to NRC and Code approval of Code Case N-416, relief requests were routinely written and approved for this type situation. The relief requests were based upon the difficulties associated with steam generator hydrostatic testing. The test cannot be conducted at ambient conditions due to fracture prevention concerns associated with the Surry steam generators, which results in difficult monitoring and controlling requirements. The Surry steam generators are required to be a minimum of 150 degrees F. on the secondary side and a minimum of 180 degrees F. on the primary side. Additionally normal problems, such as test boundary isolation, internal boundary leakage, placing spring hanger stops for dead weight loading concerns, and test pump size requirements further increase the difficulties associated with this particular test.

e Relief Request 24 (CON 1T)

The test pressure of 1356 psig also requires gaging or removal of the Main Steam Safety valves, which initially lift at 1085 psig. Some examples of previous correspondence requesting relief and approval follow:

VEPCO Letter/ Date Serial# 88-725/ 1/9/89 Serial# 89-636/ 8/29/89 Serial# 87-056/ 2/13/87 NRC Letter/ Date Serial# 89-278/ 4/7/89 Serial# 89-734/10/2/89 Serial# 88-419/6/17/88

IV.

ALTERNATE TESTING The alternative requirements described in Code Case N-416, a volumetric examination of the full penetration welds and a visual examination (VT-2) at nominal operating pressure was previously performed and deemed acceptable.

""90-HBJ-81-Stl B

F E

D C

B Z4-illfllll*l"'2141..

tm1Cl!ll,Lll1~t1N.n1 STEAM GENERATOR 7

n WALL OF REACTOR CONTAJN:!fNJ II I I i I I e

e e

e e

. *:.:,:,,i ~~.. '

\\

~:..:-: '

1'i

  • s I a I i 4

<D

,. r-SlflEl.O WALL i

I i i i J. ---

(:

C

  • IIIDUUC fflll.

~t~.=a~=.....

'~:ar::L~.~~ctN'UTD

17. U51H'M-l1911U7A au...,.*a.

L~91.I tlla.J159'1CATDl...._,CNWDG

(.,

2........._9LI IIIHYUIIDSTAntlMI.Nlta:: l'IU3.II[ 1DTIG DWiNJ

1.~*1mlT'llDIPNESS1JE'ft:slDII....,.

CD~~2.~~-:n.~~~~a11m1 C!:) ~ =-==. fi'L a, Im! Stal ODDIIUII II MIT r, M IU&

n.Gll'ftllDIIIIIIGIG.

11548-FH -064A 31 I~ *~

' h VIRGrnlA POWER e

NORTH CAROLINA POWER

I 1\\1

§ i A II.a.EM EIClltGIIIICJ 6DIVICU i~i,i11----------"'~DIINl~~**-*m_1*~**--------1 ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 11191. DOI 11111' wo.-

IJNIIGIG.

ll114B*CBM*1!64A I

LIi.iii OT>EIII* 11111D.. I i.'

  • 2 E

D C

A

  • ***-* * *------------------i ----------------------- 1 ------*-*r**----------**

04*--------------------. **-----------------------------------------------------------------------------------------------------------------------------------------*

r 9

'1890-H8J-8*!ill E

C B

lt*.ll.H*l'HZll,46 ZC51[J58.121lS2eieAIFM.8TI 6

!5 3

\\

11'54(1-t'M~SK.2 2

LLIUC St(Mtllf ~

CCNf,, NltClltllWII.CDN.IG.-COG 1M1 IIM*U'2rflllblf-lWlll.

~

1."llelllllCOIT"1JeCNff'OCl'IIUllJG~*SI.

S.IIIU.l'IIIE'IStll[~TOlt:11.-,

4.,U TDftN,fl.11! a..ClUJIS TO It I VZ'Rt#C tQ.L

~-DlltcAtl'S ""'""°.,~WW.

L&ooa:.ns ClM'UTP POJNT, r,,&sa lrOCDLl'tam.llf'II!.

LP'Olfflt'NS a, UM1-1M-1e I -

~

f'llhal.1!1.1'

~ITCllD°""'IJGU4t&............

._lltOlllUDIIDaIITOTNISICJTLMUD'll.lll.tlCUSllacl'l'NI.

&U<<I~

R.11~71 13,,11~

M,l!'!M8-nHIS711 m,U'41~71

-.11~821111 17,ll'!MO..,.Jllll, mu f\\.Dlll"t(>lll'l,IOIM,F'QDIMTDISJSffN F\\.OlfrfflillD!IIIQll#\\f"~l'AOT[trtc,,S'BTtN F\\.OlfrttJ\\101.IIOll#(,STDlrl~tCllkl~

F\\.Olf/\\'tN OIOIIM,COUMSo\\Tt S111D4 nownc. ~aNJD611rt: snTEN l'l.Dlll'l'!lt~So99'1.DGSTSTOI f'Lnlfl'fOI CLIGWC,DOlC,111. JUD STSTDI ll'F'AODt.Cft,l4wtlGS 1.11'41-<Dt--.SH.1 mcu,sstnt.\\t~~CJWtllel 2.U'!M8*~SH.lts.lS1'S!Dll'ACS9.JEtESTPCIQRilWDG

~

<DraH?sr~11 ~~l'fttfl\\'Cl~~~'=~~-

CD~~u:elJIOl'~l1'/fov~~~ ~~~~~

~

~lllfNR£CU,JllltJITOJtll[U&,.MTIQLc..i...

~TM! n.a; i,,tll'WmS!D[ t:, [IOI lft#II OO<<:A1"1'0A IS r-iiiir a, fH[-

~Stt 11548-Fl'l -etl6,l,.

C[)sun.... -.-.,SK.lf'Ollt.Nr 11lJiC1T :r11J.KWtr.

CD~d:'s~~~~~"::SETrf"~~~~t'i.~

lllt!:..:c,rro.,.

CDfft>ur,no. -nc _.....-r11,a"' c:,i F9 ---

~Sl'OCl1-.;1 CUISSll'l~f!QO,I ~

-IJCl9 CC-OIi ~

CMI.

m,a-1,ca llr _,ururt>G c.o DOI ca~ no 1111..._

CAUTION, 0

~ir~iZl:~~~~~~~*-=n..

B !

R[VIS[Oi1DESCJl!1'TIQIII TN1Slfl'IIICDrlOWOIS9.ElPEK T>C FQ.LOIIINJ fl.Olln(Jt DIIGWI

'1.0IJ'VOrtt,l,WINJND, 11546-FM -068A VIRGINIA POWER NORTH CAROLI NA POWER ltJCLEM ENJIIEERIHO SERVta;s RIOMJNJoYIROINIA ISi CLASSIFICATIOM BOUNDARY DRAWING FEEDWATER SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 41 IH.ESS QUR'f1SE NJtEO S>I l rs*

ldlr90-HSJ-e*sn 8

F E

D C

,7~1'"214112 IGl!l11211,IZU~.11'1 2-RC-

__£!!!.._

STEAH GENERATOR WALL OF REACTOR CONTAINMENT 7

B CD 15 4

h 3

\\

'* I*

It - i 2

F mu:

:.=- JUOPa

...::-~

  • .:_~ "::o. ma mrrN E

&-DU

~-... -~1DI.....,_

m lfflllllOSTa~nc N'SUll 1D1N ma,,m

.flS'IDI..... TDTlll!allG CDPdllfbd r,,,.....

l(.IN STSTEN N 111690C14TID no9G Ml'I[ IIDI CUSSUllD tsl WIGS Z

  • CCXIII.a: VJJH IEUATUrr Q,Q L&

C!:),,. na l'RDWt'f'I sa: r, M SftM aDEWt,TIIJI 11....r mr nc IIICl'IL

-~-..__.._,..TOP'MCllll,._na

-~111*..._.._._.Cllll~CM*

~

TINQCC91Cllllc::al'UIIP'MCIIII,._

~~

PCIIQCllrl TtCll ---.cT-ESPDII -

Oil.Yo D

C

=-~~~~-5.;:,._i&:mc".. ~ e RJlll'IIIIIIIIIIIIIGIG.

IIIY.

11548-FH -064A 31

  • zmr 1 VIRGINIA POVER NORTH CAROi. lNA POVER IIJCLbA EtCJIJ£DIIIII SEIVICO lltlOICJIJoVIIIIINIA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM A

2 SURRY POWER STATION UNIT 2 VIRGINIA POWER DI.._ DCII N' WIIENR --

DMIIIIG 1G.

11!148-tllH*ll64A I

-,,,9'!1-HSJ-81>!:itt

  • qa

"'INOIIIIIIIII F

E D

C 8

7

~JD' i

i r-- WALL CF REACTOR CONTAINMENT~

i i

i t

i i

i I

i i i

27-,0-1'9'12 14*1*

ZIZl*l~.1111~.*n I

e 6

II 4

I I e

e 3

SHIELD WALL---;

i ! I !

h h 2

LftllacTD.U9Ullrlna.......

L~-31 mD..16!1UDTDIIIIIIIWITDIIMfllll 1.~-3 lllN'l'IJIISTAntmENTICPIIIESSUIIIIISBG-3.~

... l mmTDl~lUTtlGl*dG

~

CD ~m'1.:ras:-'.J:.:~ -=:.'l&rt"'ll.=:rc..w.

A.a.Mlil CIIIIWIIIJ ID.

IIIY.

11548-FH -064A 31

  • la, I VIRGINIA POWER NORTH CAROL INA POWER IULEM EtGIJ&ltUII liERYICEI "lotDII, YIIGDUA ISi CLASSIFICATION BOUNDARY DRAWING MAIN STEAM SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER D19'LDCIII IIIF DMIIJG JG.

ll!548-t814*1164A I

.US ll'TtCJIII. tGTID 9' :I l:F I 2

F E

D C

A

Relief Request 25 I.

IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 components II.

IMPRACTICAL CODE REQUIREMENTS IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, IWC-5000, or IWD-5000 following welded-repairs or installation of replacement items by welding.

III.

BASIS FOR RELIEF In past situations our utility has been required to defer or ask relief from ASME section XI hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis of impracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundary. These situations have necessitated in some cases immediate communication with and approval from the NRC, so that start-up delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems with the approval in Regulatory Guide 1.147, Code Case N-498,"

Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems,Section XI, Division 1. 11 The Code has recognized that alternative rules should be available to hydrostatic testing to allow an option to the owner. They have developed Code Case N-416-1, "Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code Case as of this writing has been passed by Section XI and has been sent up to Main Committee for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option.

IV.

ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following alternative require~ents shall be applied:

1)

NOE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no construction NDE is required on partial and full penetration welds greater than 1 inch nominal pipe size, these welds shall receive a surface examination as a minimum.

l

2)
3) e e

Relief Request 25 (CON'T)

Prior to or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with a system pressure test, using the 1989 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.

Use of this alternative shall be documented on the NIS-2 Form.

If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this alternative testing have been met.

RELIEF REQUEST 26 I.

IDENTIFICATION OF COMPONENTS Component(s): Piping between following check valves located on station prints:

Function Class 11548-CBM-89B 2-SI-79 2-SI-82 2-SI-85 2-SI-88 2-SI-91 2-SI-94 AND AND AND

,AND AND AND 2-SI-235, 2-SI-236, 2-SI-237, 2-SI-226, 2-SI-226, 2-SI-226, (Drawings Attached)

Safety Injection System
1 II.

IMPRACTICAL CODE REQUIREMENTS 2-SI-241 2-SI-242 2-SI-243 2-SI-227 AND 2-SI-238 2-SI-227 AND 2-SI-239 2-SI-227 AND 2-SI-240 Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.

III.

BASIS FOR RELIEF The double check valve combination prevents pressurization of the area in between the check valves when conducting pressure tests on the primary system.

IV.

ALTERNATE TESTING During the performance of the Class 1 Code Case N-498 pressure test, the area described above will be tested at a pressure 100 psig less than the RCS normal operating pressure.

The establishment of a 100 psig differential pressure across the affected valves would prevent any uncontrollable dilution of the primary during testing.

This alternative test would replace the provisions listed in the current Relief Request 1 of our ISI program.

Bb80*H8J-8t>SII i-"'-"~------*"'-"'-"-""---,------------;-------------,-------------------------~-----------~------------~---*---**----

D C

B TOKlllEGLOCl'I 11,'llofM *98&4.511.1 17-SP'*l'l'Vll,*

.taltf~.JZIJ~"-B'I lNSJDE MISSILE BARRIER 6

5 l/4'-51*3'54*1'82*

JNSIDE REACTOR OUTS[DE REACTOR CONTAINMENT CONTAINMENT 2

!!!!ll L.f0AICJT[S.S0:5"1:[Tl~DMWIIC,US4a..,.,.....,

,)

,c*

L 115-1e-o,,i-t1S'18.SH.4 rs1a.*ss1nuir1DN BO.NJ,l,Rf CRAwPG Z.ll~*Sf'l'I-M'IO.SH.4 l'StS1SIDIPAESSl.lllTEUNillRAwPG

~

G::>~1:S~1~ f:'f~~~'~:s~ ~s~'Tl1g:.J~L

$££ L8FRC5&'l5*g1111as A(fER[ICEO 81' lllt:GU..AIOIT GuIDE U6,,

FOOINJT[ JfOA JGJIT!lhll. lWIJIMAIUl'f.

ctlOlt-"IJ<f~*l"°-'""'"ATOf'MOll'81)111*wlt,C;S.IIC C:OJIR£5"GCII"° CLA551flC*Tlc.o -*

OAAW/,c;;I OC.., OIi CN1 CM! -

MTlAM!.. 011 -SJITUIINCiC-OlllcalfOlllr" DIii....

CAUTION, JH1!&,,,c,rr.,tCUGl'Ol.rfi.,,O,n,isa,-.c,Clll4Vl>oallrCIIIIIIP"(Jll!><Cll:0-...Y.

D,

~~=:iT:.~~tiir~~=-:r.~~1.1c*,,c,cYUOL 8

RfY/5](J,jll£5CRll'JJDN THII 11'11'AD.CT DWO ISSlLD PEA THE ftl.l.c.lNl Ft.OW/~ DIIIIQIMI FUIWIVCNDIWIIIJJGtCI.

~,.

115'48-FH *0898 23 VIRGINIA POVER NORTH CAROL I NA PD VER N.CI.EAR EN'.HNEEAINO SERVICES Rloeo<<>,YIRGINIA ISi CLASSIFICATION BOUNDARY DRAWING SAFETY INJECTION SYSTEM SURRY POWER STATION UNIT 2 VIRGINIA POWER 2

OISP'L. DO:

1111(

""'"°'--

DVIIIIII~.

1154B-CBH-0B'l8

....